NUREG-1123

Revision 2 |

Knowledge and Abilities Catalog

for Nuclear Power Plant Operators:

Boiling Water Reactors

Manuscript Completed: June 5, 1998 |

Date Published: 

Operator Licensing and Human Performance Branch

Division of Reactor Controls and Human Factors

U.S. Nuclear Regulatory Commission

Washington, DC 20555
Back of cover
iii NUREG-1123, Rev. 2 |

ABSTRACT

The Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling Water Reactors

(BWRs) (NUREG-1123, Revision 2) provides the basis for the development of content-valid |

licensing examinations for reactor operators (ROs) and senior reactor operators (SROs). The

examinations developed using the BWR Catalog along with the Operator Licensing Examination |

Standards for Power Reactors (NUREG-1021, Rev. 8) will sample the topics listed under Title 10, |

Code of Federal Regulations, Part 55 (10 CFR 55).

The BWR Catalog contains approximately 7,000 knowledge and ability (K/A) statements for ROs and

SROs at BWRs. The catalog is organized into six major sections: Organization of the Catalog,

Generic Knowledge and Ability Statements, Plant Systems grouped by Safety Functions, Emergency

and Abnormal Plant Evolutions, Components, and Theory.

Revision 1 to the BWR Catalog modified the form and content of the original catalog. The K/As were |

linked to their applicable 10 CFR 55 item numbers. SRO level K/As were identified by 10 CFR

55.43 item numbers. The plant-wide generic and system generic K/As were combined in one section

with approximately one hundred new K/As. Component Cooing Water and Instrument Air Systems

were added to the Systems Section. Finally, High Containment Hydrogen Concentration and Plant

Fire On Site evolutions added to the Emergency and Abnormal Plant Evolutions section.

Revision 2 incorporates corrections to the Rev. 1 catalog that were identified during a pilot testing |

program associated with revision of 10 CFR 55 and implementation of NUREG-1021, Interim Rev. |

8, “ Operator Licensing Examination Standards for Power Reactors.” Corrections to the catalog |

include: |

1. addition of 7 K/As that had been omitted in Rev. 1. |

2. correction of typographical errors. |

3. addition of importance value modifiers that had been omitted in Rev. 1. |

Corrections and additions are identified by “redline” marking in the margins. |
NUREG-1123, Rev. 2 iv |

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v NUREG-1123, Rev. 2 |

TABLE OF CONTENTS page

ABSTRACT iii

SUMMARY OF SIGNIFICANT CHANGES xi

1 ORGANIZATION OF THE CATALOG

1.1 Introduction 1-1

1.2 Part 55 of Title 10 of the Code of Federal Regulations 1-1

1.3 RO Written Examination 1-1

1.4 SRO Written Examination 1-2

1.5 RO and SRO Operating Test Items 1-3 |

1.6 Senior Operators Limited to Fuel Handling 1-4

1.7 Organization of the BWR Catalog 1-4

1.8 Generic Knowledge and Abilities 1-5

1.9 Plant Systems 1-6

1.10 Emergency And Abnormal Plant Evolutions 1-10

1.11 Components 1-12

1.12 Theory 1-13 |

1.13 Importance Ratings 1-13 |

1.14 Acronyms And Terms 1-14 |

2 GENERIC KNOWLEDGE AND ABILITIES (132)

2.1 Conduct Of Operations 2-1

2.2 Equipment Control 2-5

2.3 Radiation Control 2-9

2.4 Emergency Procedures / Plan 2-10

3 PLANT SYSTEMS

3.1 Reactivity Control 3.1-1

Control Rod Drive Hydraulic System 3.1-3

Control Rod and Drive Mechanism 3.1-7

Reactor Manual Control System 3.1-10

Recirculation Flow Control System 3.1-13

Recirculation System 3.1-17

Rod Control and Information System 3.1-22

Standby Liquid Control System 3.1-25
NUREG-1123, Rev. 2 vi |

TABLE OF CONTENTS (Continued) page

3. 2 Reactor Water Inventory Control 3.2-1

High Pressure Coolant Injection System 3.2-3

High Pressure Core Spray System 3.2-8

Low Pressure Core Spray System 3.2-12

Reactor Condensate System 3.2-16

Reactor Core Isolation Cooling System 3.2-21

Reactor Feedwater System 3.2-25

Reactor Water Cleanup System 3.2-29

Reactor Water Level Control System 3.2-33

Residual Heat Removal /Low Pressure Coolant Injection: Injection Mode

(Plant Specific)

3.2-38

3.3 Reactor Pressure Control 3.3-1

Automatic Depressurization System 3.3-3

Main and Reheat Steam System 3.3-6

Reactor/Turbine Pressure Regulating System 3.3-11

Relief/Safety Valves 3.3-18

3. 4 Heat Removal From Reactor Core 3.4-1

High Pressure Coolant Injection System 3.4-3

High Pressure Core Spray System 3.4-8

Isolation (Emergency) Condenser 3.4-12

Low Pressure Core Spray System 3.4-16

Main and Reheat Steam System 3.4-20

Main Turbine Generator and Auxiliary Systems 3.4-25

Reactor Core Isolation Cooling System 3.4-29

Recirculation System 3.4-33

Residual Heat Removal /Low Pressure Coolant Injection: Injection Mode 3.4-38

Shutdown Cooling System (RHR Shutdown Cooling Mode) 3.4-42

3.5 Containment Integrity 3.5-1

Primary Containment System and Auxiliaries 3.5-3

Primary Containment Isolation System /Nuclear Steam Supply Shut-Off 3.5-8

Reactor Vessel Internals 3.5-12

RHR/LPCI: Torus/Suppression Pool Cooling Mode 3.5-15

RHR/LPCI: Containment Spray System Mode 3.5-19

RHR/LPCI: Torus/Suppression Pool Spray Mode 3.5-23

Secondary Containment 3.5-28

3.6 Electrical 3.6-1

A.C. Electrical Distribution 3.6-3

D.C. Electrical Distribution 3.6-6

Emergency Generators (Diesel/Jet) 3.6-9
vii NUREG-1123, Rev. 2 |

TABLE OF CONTENTS (Continued) page

Uninterruptable Power Supply (A.C. /D.C.) 3.6-13

3.7 Instrumentation 3.7-1

Average Power Range Monitor/Local Power Range Monitor System 3.7-3

Intermediate Range Monitor System 3.7-7

Nuclear Boiler Instrumentation 3.7-10

Radiation Monitoring System 3.7-15

Reactor Protection System 3.7-19

Rod Block Monitor System 3.7-24

Rod Control and Information System 3.7-27

Rod Position Information System 3.7-30

Rod Sequence Control System (Plant Specific) 3.7-33

Rod Worth Minimizer System (Plant Specific) 3.7-35

Source Range Monitor System 3.7-38

Traversing In-Core Probe 3.7-41

3.8 Plant Service Systems 3.8-1

Fire Protection System 3.8-3

Fuel Handling 3.8-7

Instrument Air System 3.8-10

Component Cooling Water System 3.8-13

3.9 Radioactivity Release 3.9-1

Main Steam Isolation Valve Leakage Control System 3.9-3

Offgas System 3.9-7

Plant Ventilation Systems 3.9-11

Radiation Monitoring System 3.9-14

Radwaste 3.9-18

Reactor Vessel Internals 3.9-21

Fuel Pool Cooling and Clean-up 3.9-24

Standby Gas Treatment System 3.9-29

Control Room Heating, Ventilation and Air Conditioning 3.9-33

4 EMERGENCY AND ABNORMAL PLANT EVOLUTIONS

4.1 Generic Emergency Plant Evolutions 4.1-1

High Drywell Pressure 4.1-3

High Reactor Pressure 4.1-5

Suppression Pool High Water Temperature 4.1-7

High Containment Temperature 4.1-8

High Drywell Temperature 4.1-9

High Suppression Pool Water Level 4.1-11
NUREG-1123, Rev. 2 viii |

TABLE OF CONTENTS (Continued) page

Low Suppression Pool Water Level 4.1-12

Reactor Low Water Level 4.1-14

High Secondary Containment Area Temperature 4.1-16

High Secondary Containment Area Radiation Levels 4.1-18

Secondary Containment Ventilation High Radiation 4.1-20

Secondary Containment High Differential Pressure 4.1-22

Secondary Containment High Sump / Area Water Level 4.1-23

SCRAM Condition Present and Reactor Power Above APRM Downscale or

unknown

4.1-24

High Off-Site Release Rate 4.1-26

High Containment Hydrogen Concentration. 4.1-28

4.2 GENERIC Abnormal Plant Evolutions 4.2-1

Partial or Complete Loss of Forced Core Flow Circulation 4.2-3

Loss of Main Condenser Vacuum 4.2-5

Partial or Complete Loss of A.C. Power 4.2-7

Partial or Complete Loss of D.C. Power 4.2-9

Main Turbine Generator Trip 4.2-10

SCRAM 4.2-12

High Reactor Pressure 4.2-14

High Reactor Water Level 4.2-16

Low Reactor Water Level 4.2-18

High Drywell Pressure 4.2-19

High Containment Temperature (Mark III Containment Only) 4.2-21

High Drywell Temperature 4.2-22

High Suppression Pool Temperature 4.2-23

Inadvertent Reactivity Addition 4.2-24

Incomplete SCRAM 4.2-26

Control Room Abandonment 4.2-28

High Off-Site Release Rate 4.2-29

Partial or Complete Loss of Component Cooling Water 4.2-31

Partial or Complete Loss of Instrument Air 4.2-33

Inadvertent Containment Isolation 4.2-35

Loss of Shutdown Cooling 4.2-37

Loss of Control Rod Drive Pumps 4.2-39

Refueling Accidents 4.2-40

Plant Fire On Site 4.2-42
ix NUREG-1123, Rev. 2 |

TABLE OF CONTENTS (Continued) page

5 COMPONENTS 5-1

Valves 5-3

Sensors and Detectors 5-4

Controllers and positioners 5-6

Pumps 5-7

Motors and Generators 5-9

Heat Exchangers and Condensers 5-10

Demineralizers and Ion Exchangers 5-11

Breakers, Relays and Disconnects 5-12

6 THEORY 6.1-1

REACTOR THEORY 6.1-3

Neutrons 6.1-3

Neutron Life Cycle 6.1-4

Reactor Kinetics and Neutron Sources 6.1-5

Reactivity Coefficients 6.1-6

Control rods 6.1-7

Fission Product Poisons 6.1-8

Fuel Depletion and Burnable Poisons 6.1-10

Reactor Operational Physics 6.1-11

THERMODYNAMICS 6.2-1

Thermodynamic Units and Properties 6.2-1

Basic Energy Concepts 6.2-2

Steam 6.2-3

Thermodynamic Processes 6.2-4

Thermodynamic Cycles 6.2-5

Fluid Statics 6.2-6

Heat Transfer and Heat Exchanges 6.2-8

Thermal Hydraulics 6.2-9

Core Thermal Limits 6.2-12

Brittle Fracture and Vessel Thermal Stress 6.2-15
NUREG-1123, Rev. 2 x |

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xi NUREG-1123, Rev. 2 |

SUMMARY OF SIGNIFICANT CHANGES

The changes described in paragraphs 1 through 6, below, were incorporated in Revision 1 of |

the catalog in August, 1995. Paragraph 7 describes changes that are incorporated with |

Revision 2 of the catalog. |

1 ORGANIZATION OF THE BWR CATALOG

1.1 The 10 CFR 55 items listed.

The content of the written examinations and operating licensing tests is dictated by Sections 55.41, |

55.43, and 55.45 of Title 10 of the Code of Federal Regulations (10 CFR). The thirty four (34)

items listed in 10 CFR 55 are listed in the catalog to reduce the need for cross referencing. |

1.2 Knowledge and Abilities linked to 10 CFR 55

The linkage of K/As to the 10 CFR 55.41, 43 and 45 requirements was done to help ensure that the

examinations include a representative sample from among the applicable items. Throughout the |

catalog, 10 CFR 55 section references are shown in parentheses following the appropriate K/A |

statement, such as (CFR: 41.x / 43.x / 45.x). |

1.3 Senior Reactor Operator (SRO) K/As identified

NUREG-1021, Rev. 8, "Operator Licensing Examination Standards for Power Reactors," Section |

ES-401, requires at least 25% of the site-specific written examination for SROs to evaluate K/As |

required for the higher license level. The original catalogs did not explicitly identify the K/As that |

represented the higher license level. Differences in RO and SRO importance ratings were

sometimes used, but, the rating differences were not linked to the 10 CFR 55.43 SRO items. In this

catalog revision, SRO license level K/As were linked to the items associated with the 10 CFR

55.43 SRO items. This is intended to remove subjectivity from selection of higher license level

K/As.

1.4 Senior Reactor Operator Limited to Fuel Handling (LSRO) examination 

 specifications added.

NUREG-1021, Rev. 8 , Section 701 refers to the K/A catalog. In an effort to assure consistency |

between the Examination Standards and the catalog, a brief discussion of the use of the catalog for |

LSRO examinations was included.
NUREG-1123, Rev. 2 xii |

1.5 An updated catalog organization was implemented.

1. ORGANIZATION OF BWR CATALOG

1. Added 10 CFR information

2 Generic Knowledge and Abilities

1. Combined old plant-wide and system generic K/As in one section.

2. Eliminated duplicate generic K/As.

3. Organized the section into 4 topic areas.

4. Added about 100 new generic K/As.

3 Plant Systems

1. Moved System Generic K/As to new generic section

2. Added Instrument Air System

3. Added Component Cooling Water System

4 Emergency & Abnormal Plant Evolution Section

1. Moved Generic K/As to Section 2

2. Added High Containment Hydrogen Concentration

3. Added Plant Fire On Site

5 Components

No change

6 Theory Section

No change
xiii NUREG-1123, Rev. 2 |

2 GENERIC KNOWLEDGE AND ABILITIES (132)

2.1 The System Generic K/As were combined with the Plant-Wide Generic K/As.

Many of the old system generic K/As had plant-wide applicability as well as local applicability.

In addition, the old plant-wide generic section had relatively few K/As to draw upon to make up

13% of the RO examination or 17% of the SRO examination, per NUREG-1021. As a result, all |

generic K/As were merged into one section.

||

OLD SYSTEM |

GENERIC K/A |

NEW K/A

 1 2.1.2 |

 2 2.1.14 |

 3 2.4.30 |

 4 2.1.27 |

 5 2.2.22 |

 6 2.2.25 |

 7 2.1.28 |

 8 2.4.31 |

 9 2.1.30 |

 10 2.1.32 |

 11 2.1.33 |

 12 2.4.50 |

 13 2.1.23 |

 14 2.4.49 |

 15 2.4.4 |

These are generally administrative knowledge and abilities with broad application across systems

and operations. The four (4) topic areas listed below.

2.1 Conduct of Operations K/As

2.2 Equipment Control K/As

2.3 Radiation Control K/As

2.4 Emergency Procedures /Plan K/As

The generic K/As for "Conduct of Operations," are used to evaluate the applicant's |

knowledge of the daily operation of the facility. The types of information covered under this

category may include for example, shift turnover or temporary modification procedures.
NUREG-1123, Rev. 2 xiv |

| The generic K/As for "Equipment Control " are used to evaluate the administrative issues

associated with the management and control of plant systems and equipment. Examples of the types

of information evaluated under this topic include maintenance and temporary modifications of

systems. Fuel handling and refueling K/As were also organized into this topic area because of the

equipment control aspect of fuel handling.

| The generic K/As for "Radiation Control," are used to evaluate the applicant's knowledge and

abilities with respect to radiation hazards and protection (personnel and public). Examples of the

types of information that should be evaluated under this topic are knowledge of significant

radiation hazards or radiation work permits.

| The generic K/As for "Emergency Procedures / Plan" are used to evaluate the applicant's general

knowledge of emergency operations. The K/As are designed to evaluate knowledge of the

emergency procedures use. The emergency plan K/As may be used to evaluate the applicant's

knowledge of the plan, including, as appropriate, the RO's or SRO's responsibility to decide

whether it should be executed and the duties assigned under the plan.

2.2 Approximately one hundred (100) new generic K/As were added to the catalog.

The new K/As were identified through license examiner surveys and an independent review of the

catalog, NUREG-1021, licensee event reports and inspection reports. All new K/As were directly

linked to the applicable 10 CFR 55 requirements.

3 PLANT SYSTEMS (56) WITHIN 9 SAFETY FUNCTIONS

3.1 The old system generic K/As were combined with plant wide generic K/As in Section 

2, Generic K/As.

3.2 Two systems were added because they were covered in the Abnormal Evolutions.

1. Instrument Air System

2. Component Cooling Water System

3.3 K/A stem statement K5, changed “operational applications” to “operational 

implications”

4 EMERGENCY & ABNORMAL PLANT EVOLUTIONS (40)

| 4.1 The original system generic K/As were combined with plant wide generic K/As in

Section 2, Generic K/As. Duplicate generic K/As were combined into single K/As where

applicable.

4.2. High Containment Hydrogen Concentration was added to reflect Revision 4 changes

to BWROG Emergency Procedures Guidelines (EPGs).

4.3 Plant Fire On Site was added as an abnormal plant evolution to achieve consistency

with the Fire Protection System section.
xv NUREG-1123, Rev. 2 |

4.4 Emergency and Abnormal Evolution K/As were linked to 10 CFR 55 item numbers at |

the stem statement level.

5 COMPONENTS

5.1 All component K/As were linked to 10 CFR 55 item numbers. |

6 THEORY

6.1 Reactor Theory and Thermodynamics theory K/As were linked to 10 CFR, 55 item |

numbers.

7 REVISION 2 CHANGES |

|

7.1 Approximately 7 K/As that had been omitted in Rev. 1 were added. |

7.2 Typographical errors were corrected. |

7.3 Importance value modifiers that had been omitted in Rev. 1 were added. |

Corrections and additions are identified by “redline” marking in the margins. |

|
1.1 NUREG-1123, Rev. 2 |

1 ORGANIZATION OF THE 

 CATALOG

1.1 INTRODUCTION

The Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling Water Reactors

(BWR) NUREG-1123, Revision 2, provides the basis for development of content-valid written |

and operating licensing examinations for reactor operators (ROs) and senior reactor operators

(SROs). The Catalog is designed to ensure equitable and consistent examinations.

1.2 PART 55 OF TITLE 10 OF THE CODE OF FEDERAL REGULATIONS

The catalog is used in conjunction with NUREG-1021, Revision 8 "Operator Licensing |

Examination Standards for Power Reactors." NUREG-1021 provides policy and guidance and |

establishes the procedures and practices for examining licensees and applicants for RO and SRO

licenses pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). All

knowledge and abilities (K/As) in this catalog are directly linked by item number to 10 CFR 55.

1.3 RO WRITTEN EXAMINATION

The items for RO written examinations are specified in 10 CFR 55.41(b). The RO written

examination questions should be generated from a representative sample of K/As derived from

among the 10 CFR 55.41(b) items listed below:

(1) Fundamentals of reactor theory, including fission process, neutron multiplication, source

effects, control rod effects, criticality indications, reactivity coefficients, and poison

effects.

(2) General design features of the core, including core structure, fuel elements, control rods,

core instrumentation, and coolant flow.

(3) Mechanical components and design features of reactor primary system.

(4) Secondary coolant and auxiliary systems that affect the facility.
NUREG-1123, Rev. 2 1.2 |

(5) Facility operating characteristics during steady state and transient conditions, including

coolant chemistry, causes and effects of temperature, pressure and reactivity changes,

effects of load changes, and operating limitations and reasons for these operating

characteristics.

(6) Design, components, and function of reactivity control mechanisms and instrumentation.

(7) Design, components, and function of control and safety systems, including instrumentation,

signals, interlocks, failure modes, and automatic and manual features.

(8) Components, capacity, and functions of emergency systems.

(9) Shielding, isolation, and containment design features, including access limitations.

(10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

(11) Purpose and operation of radiation monitoring systems, including alarms and survey

equipment.

(12) Radiological safety principles and procedures.

(13) Procedures and equipment available for handling and disposal of radioactive materials and

effluents.

(14) Principals of heat transfer, thermodynamics and fluid mechanics.

The RO written examination is administered in two sections, a generic fundamentals examination

| (GFE) section and a site-specific examination. The GFE covers those knowledge items that do not

| vary significantly among reactors of the same type (refer to NUREG-1021, ES-205). The GFE

covers components, reactor theory, and thermodynamics knowledge. The component knowledge

items are derived from 10 CFR 55.41(b) items 3 and 7. Reactor theory knowledge items are

derived from 10 CFR 55.41(b)1. Thermodynamic knowledge items are derived from 10 CFR

55.41(b)14.

The site-specific RO written examination covers K/As that vary among reactors of the same type. 

| The guidance for preparation of RO written examination is presented in NUREG-1021, ES-401. 

The RO examination includes a balanced mix of generic K/As, plant systems K/As, and

emergency/abnormal evolution K/As. The K/As associated with the RO site-specific written

examinations are derived from 10 CFR 55.41(b) items 2 through 13.

1.4 SRO WRITTEN EXAMINATION

The items for SRO written examinations are presented in 10 CFR 55.43(b). The guidance for 
1.3 NUREG-1123, Rev. 2 |

preparation of the SRO written examination is presented in NUREG-1021, ES-401. The

examination for SRO should include at least 25 percent (25%) higher license level K/As from the |

7 items listed under 10 CFR 55.43(b). No more than 75 percent (75%) of the SRO K/As may be |

derived from the 10 CFR 55.41(b) RO K/As. The 7 SRO items listed under 10 CFR 55.43(b)

include:

(1) Conditions and limitations in the facility license.

(2) Facility operating limitations in the technical specifications and their bases.

(3) Facility licensee procedures required to obtain authority for design and operating changes

in the facility.

(4) Radiation hazards that may arise during normal and abnormal situations, including

maintenance activities and various contamination conditions.

(5) Assessment of facility conditions and selection of appropriate procedures during normal,

abnormal, and emergency situations.

(6) Procedures and limitations involved in initial core loading, alterations in core

configuration, control rod programming, and determination of various internal and external

effects on core reactivity.

(7) Fuel handling facilities and procedures.

1.5 RO AND SRO OPERATING TEST ITEMS |

The items for operating tests for ROs and SROs are presented in 10 CFR 55.45(a). The guidance

for preparation of the operating tests is presented in NUREG-1021, ES-301. The operating test |

should include a representative selection of K/As derived from 13 items listed in 10 CFR |

55.45(a). The 13 items listed in 10 CFR 55.45(a) are: |

(1) Perform pre-startup procedures for the facility, including operating of those controls

associated with plant equipment that could affect reactivity.

(2) Manipulate the console controls as required to operate the facility between shutdown and

designated power levels.

(3) Identify enunciators and condition-indicating signals and perform appropriate remedial

actions where appropriate.

(4) Identify the instrumentation systems and the significance of facility instrument readings.

(5) Observe and safely control the operating behavior characteristics of the facility.
NUREG-1123, Rev. 2 1.4 |

(6) Perform control manipulations required to obtain desired operating results during normal,

abnormal, and emergency situations.

(7) Safely operate the facility's heat removal systems, including primary coolant, emergency

coolant, and decay heat removal systems, and identify the relations of proper operation of

these systems to the operation of the facility.

(8) Safety operate the facility's auxiliary and emergency systems, including operation of those

controls associated with plant equipment that could affect reactivity or the release of

radioactive materials to the environment 

(9) Demonstrate or describe the use and function of the facility's radiation monitoring systems,

including fixed radiation monitors and alarms, portable survey instruments, and personnel

monitoring equipment.

(10) Demonstrate a knowledge of significant radiation hazards, including permissible levels in

excess of those authorized, and ability to perform other procedures to reduce excessive

levels of radiation and to guard against personnel exposure.

(11) Demonstrate knowledge of the emergency plan for the facility, including, as appropriate,

the operator's or senior operator's responsibility to decide when the plan should be

executed and the duties under the plan assigned.

(12) Demonstrate the knowledge and ability as appropriate to the assigned position to assume

the responsibilities associated with the safe operation of the facility.

(13) Demonstrate the applicant's ability to function within the control room team as appropriate

to the assigned position, in such a way that the facility licensee’s procedures are adhered to

and that the limitations in its license and amendments are not violated.

1.6 SENIOR OPERATORS LIMITED TO FUEL HANDLING 

The specifications for examinations for Senior Operators Limited to Fuel Handling (LSRO) are

| provided in Examination Standard, NUREG 1021, Section ES-701. The LSRO examination

| process includes both a written examination and an operating test. This examination and test

| include, but are not limited to, items associated with 10 CFR 55.43(b) items 5 through 7, and 10

CFR 55.45(a) items 5 and 6.

1.7 ORGANIZATION OF THE BWR CATALOG

The Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling Water Reactors

| is organized into 6 major sections. Knowledge and ability statements (K/As) are grouped

according to the major section to which they pertain. This organization is shown schematically

below.
1.5 NUREG-1123, Rev. 2 |

1 ORGANIZATION OF THE BWR CATALOG

2 GENERIC KNOWLEDGE AND ABILITIES (132)

Conduct of Operations K/As

Equipment Control K/As

Radiation Control K/As

Emergency Procedures / Plan K/As

3 PLANT SYSTEMS (56) WITHIN 9 SAFETY FUNCTIONS

Knowledge Categories (K1 - K6)

Ability Categories (A1 - A4)

4 EMERGENCY & ABNORMAL PLANT EVOLUTIONS (40)

Knowledge Categories (E/A K1 - E/A K3)

Ability Categories (E/A A1 - E/A - A2)

5 COMPONENTS

Component Knowledge Categories (8)

6 THEORY

Reactor Theory Knowledge Categories (8)

Thermodynamics Knowledge Categories (10)

1.8 GENERIC KNOWLEDGE AND ABILITIES

Generic knowledge and abilities are generally administrative knowledges and abilities with broad |

application across systems and operations. They are listed in Section 2 of the catalog. The four

(4) categories of generic K/As are listed below:

1 Conduct of Operations K/As

2 Equipment Control K/As

3 Radiation Control K/As

4 Emergency Procedures /Plan K/As

The generic K/As for "Conduct of Operations," are used to evaluate the applicant's |

knowledge of the daily operation of the facility. The types of information covered under this

category may include for example, shift turnover or temporary modification procedures.

The generic K/As for "Equipment Control " are used to evaluate the administrative requirements |

associated with the management and control of plant systems and equipment. Examples of the types

of information evaluated under this topic include maintenance and temporary modifications of

systems.

The generic K/As for "Radiation Control" are used to evaluate the applicant's knowledge and |

abilities with respect to radiation hazards and protection (personnel and public). Examples of
NUREG-1123, Rev. 2 1.6 |

 the types of information that should be evaluated under this topic are knowledge of significant

radiation hazards or radiation work permits.

| The generic K/As for "Emergency Procedures / Plan" are used to evaluate the applicant's general

knowledge of emergency operations. The K/As are designed to evaluate knowledge of the

emergency procedures use. The emergency plan K/As may be used to evaluate the applicant's

knowledge of the plan, including, as appropriate, the RO's or SRO's responsibility to decide

whether it should be executed and the duties assigned under the plan.

1.9 PLANT SYSTEMS

| 1.9.1 Plant System Organization by Safety Function

| Nine (9) major safety functions must be maintained to ensure safe BWR nuclear power plant

| operation. The safety functions groups are:

1. Reactivity Control

2. Reactor Water Inventory Control

3. Reactor Pressure Control

4. Heat Removal From the Core

5. Containment Integrity

6. Electrical

7. Instrumentation

8. Plant Service Systems

9. Radioactivity Release.

Fifty six (56) plant systems have been included in the BWR Catalog based on their relationship

and importance to safety functions. Table 1 contains a list of these plant systems, arranged within

safety function. It should be noted that some plant systems contribute to more than one safety

function. 

Each plant system has a 6-digit code number. The words "Plant Specific" following the system

title, indicates that the knowledge or ability does not apply to all plants. 

See Section 3 of the BWR catalog for the delineation of K/As for the plant systems.

Table 1

Plant Systems by Safety Functions

________________________________________________________________________

Safety Function 1: Reactivity Control

201001 Control Rod Drive Hydraulic System

201003 Control Rod and Drive Mechanism

201002 Reactor Manual Control System
1.7 NUREG-1123, Rev. 2 |

202002 Recirculation flow Control System

202001 Recirculation System

201005 Rod Control and Information System

211000 Standby Liquid Control System

Safety Function 2: Reactor Water Inventory Control

206000 High Pressure Coolant Injection System

209002 High Pressure Core Spray System

209001 Low Pressure Core Spray System

256000 Reactor Condensate System

217000 Reactor Core Isolation Cooling System

259001 Reactor Feedwater System

204000 Reactor Water Cleanup System

259002 Reactor Water Level Control System

203000 Residual Heat Removal /Low Pressure Coolant Injection: Injection Mode

(Plant Specific)

Safety Function 3: Reactor Pressure Control

218000 Automatic Depressurization System

239001 Main and Reheat Steam System

241000 Reactor/Turbine Pressure Regulating System

239002 Safety Relief Valves

Safety Function 4: Heat Removal From Reactor Core

206000 High Pressure Coolant Injection System

209002 High Pressure Core Spray System

207000 Isolation (Emergency) Condenser

209001 Low Pressure Core Spray System

239001 Main and Reheat Steam System

245000 Main Turbine Generator and Auxiliary Systems

217000 Reactor Core Isolation Cooling System

202001 Recirculation System

203000 Residual Heat Removal /Low Pressure Coolant Injection: Injection Mode

205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)

Safety Function 5: Containment Integrity

223001 Primary Containment System and Auxiliaries

223002 Primary Containment Isolation System /Nuclear Steam Supply Shut-Off

290002 Reactor Vessel Internals

219000 RHR/LPCI: Torus/Suppression Pool Cooling Mode

226001 RHR/LPCI: Containment Spray System Mode
NUREG-1123, Rev. 2 1.8 |

230000 RHR/LPCI: Torus/Suppression Pool Spray Mode

290001 Secondary Containment

Safety Function 6: Electrical

262001 A.C. Electrical Distribution

263000 D.C. Electrical Distribution

264000 Emergency Generators (Diesel/Jet)

262002 Uninterruptable Power Supply (A.C. /D.C.)

Safety Function 7: Instrumentation

215005 Average Power Range Monitor/Local Power Range Monitor

215003 Intermediate Range Monitor System

216000 Nuclear Boiler Instrumentation

272000 Radiation Monitoring System

212000 Reactor Protection System

215002 Rod Block Monitor System

201005 Rod Control and Information System

214000 Rod Position Information System

201004 Rod Sequence Control System (Plant Specific)

201006 Rod Worth Minimizer System (Plant Specific)

215004 Source Range Monitor System

215001 Traversing In-Core Probe

Safety Function 8: Plant Service Systems

286000 Fire Protection System

234000 Fuel Handling

300000 Instrument Air System

400000 Component Cooling Water System

Safety Function 9: Radioactivity Release

239003 Main Steam Isolation Valve Leakage Control System

271000 Offgas System

288000 Plant Ventilation Systems

272000 Radiation Monitoring System

268000 Radwaste

290002 Reactor Vessel Internals

233000 Fuel Pool Cooling and Clean-up

261000 Standby Gas Treatment System

290003 Control Room Heating, Ventilation and Air Conditioning
1.9 NUREG-1123, Rev. 2 |

1.9.2 Knowledge and Ability Stem Statements for Plant Systems |

The information delineated within each plant system is organized into 6 different types of

knowledge and 4 different types of ability. If there are no knowledge or ability statements

following a stem statement there is no applicable K/A.

The applicable 10 CFR 55.41 / 43 / and 45 item numbers are included with each stem statement. 

In most cases the K/As associated with the stem statements can be used for both the written

examination and the operating test. See Table 2 below: |

Table 2

Knowledge and Ability Stem Statements for Plant Systems

K1. Knowledge of the physical connections and/or cause-effect relationships

between (SYSTEM) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K2. Knowledge of electrical power supplies to the following:

(CFR: 41.7)

K3. Knowledge of the effect that a loss or malfunction of the (SYSTEM) will

have on the following:

(CFR: 41.7 / 45.4)

K4. Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide

for the following:

(CFR: 41.7)

K5. Knowledge of the operational implications of the following concepts as

they apply to the (SYSTEM):

(CFR: 41.5 / 45.3)

K6 Knowledge of the effect that a loss or malfunction of the following will

have on the (SYSTEM):

(CFR: 41.7 / 45.7)

A1. Ability to predict and/or monitor changes in parameters associated with

operating the (SYSTEM) controls including:

(CFR: 41.5 / 45.5)

A2. Ability to (a) predict the impacts of the following on the (SYSTEM) and

(b) based on those predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal operation:

(CFR: 41.5 / 45.6)
NUREG-1123, Rev. 2 1.10 |

A3. Ability to monitor automatic operations of the (SYSTEM) including:

(CFR: 41.7 / 45.7)

A4. Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

1.10 EMERGENCY & ABNORMAL PLANT EVOLUTIONS 

| Section 4 of the BWR catalog contains emergency plant evolutions (EPEs) and abnormal plant

| evolutions (APEs). An emergency plant evolution is any condition, event or symptom which leads

| to entry into the plant-specific emergency operating procedures (EOPs). An abnormal plant

| evolution is any degraded condition, event or symptom not directly leading to an EOP entry

| condition, but, nontheless, adversely affecting a safety function. The listing of EPEs and APEs

| was developed to include those integrative situations crossing several plant systems and/or safety

| functions. 

The emergency plant evolution strategies described in Revision 4 to the Boiling Water Reactor

Owners Group Emergency Procedures Guidelines, cover five broad areas:

1) Reactor Pressure Vessel Control

2) Reactor Pressure Vessel Control With SCRAM Condition Present and Reactor

Power Above APRM Downscale or Unknown.

3) Primary Containment Control

4) Secondary Containment Control

5) Radioactivity Release Control.

If the operator controls the five broad areas of emergency plant evolutions listed above, the plant

| safety functions will be safely maintained. Table 3, below, contains a numerical list of the 16

| emergency plant evolutions and the 24 abnormal plant evolutions covered by this catalog.

| Table 3

| Emergency and Abnormal Plant Evolutions

| EPEs

295024 High Drywell Pressure

295025 High Reactor Pressure

295026 Suppression Pool High Water Temperature

295027 High Containment Temperature (Mark III Containment Only)

295028 High Drywell Temperature

295029 High Suppression Pool Water Level

295030 Low Suppression Pool Water Level

295031 Reactor Low Water Level

295032 High Secondary Containment Area Temperature
1.11 NUREG-1123, Rev. 2 |

295033 High Secondary Containment Area Radiation Levels

295034 Secondary Containment Ventilation High Radiation

295035 Secondary Containment High Differential Pressure

295036 Secondary Containment High Sump / Area Water Level

295037 SCRAM Condition Present and Reactor Power Above APRM Downscale

or unknown

295038 High Off-Site Release Rate

500000 High Containment Hydrogen Concentration.

APEs |

295001 Partial or Complete Loss of Forced Core Flow Circulation

295002 Loss of Main Condenser Vacuum

295003 Partial or Complete Loss of A.C. Power

295004 Partial or Complete Loss of D.C. Power

295005 Main Turbine Trip

295006 SCRAM

295007 High Reactor Pressure

295008 High Reactor Water Level

295009 Low Reactor Water Level

295010 High Drywell Pressure

295011 High Containment Temperature (Mark III Containment Only)

295012 High Drywell Temperature

295013 High Suppression Pool Water Temperature

295014 Inadvertent Reactivity Addition

295015 Incomplete SCRAM

295016 Control Room Abandonment

295017 High Off-Site Release Rate

295018 Partial or Complete Loss of Component Cooling Water

295019 Partial or Complete Loss of Instrument Air

295020 Inadvertent Containment Isolation

295021 Loss of Shutdown Cooling

295022 Loss of Control Rod Drive Pumps

295023 Refueling Accidents

600000 Plant Fire On Site

1.10.1 Knowledge and Ability Stem Statements for Emergency and Abnormal

 Plant Evolutions

The information delineated within each emergency or abnormal evolution is organized into three

(3)different types of knowledge and two (2) different types of ability. If there are no knowledge or

ability statements following a stem statement there is no applicable K/A.

The applicable 10 CFR 55.41, 43, and 45 item numbers are included with each stem statement. In

most cases the K/As associated with the stem statements can be used for both 
NUREG-1123, Rev. 2 1.12 |

the written and operating examinations. See Table 4, below: 

Table 4

 Knowledge and Ability Stem Statements for

 Emergency and Abnormal Plant Evolutions

E/AK1 Knowledge of the operational applications of the following concepts as they apply

to the (EMERGENCY OR ABNORMAL PLANT EVOLUTION): (CFR: 41.8 to

41.10)

E/AK2 Knowledge of the interrelations between (EMERGENCY OR ABNORMAL 

PLANT EVOLUTION) and the following: 

(CFR: 41.7 / 45.8) 

E/AK3 Knowledge of the reasons for the following responses as they apply to

(EMERGENCY OR ABNORMAL PLANT EVOLUTION): 

(CFR: 41.5 / 45.6)

E/AA1 Ability to operate and / or monitor the following as they apply to (EMERGENCY 

AND ABNORMAL PLANT EVOLUTION): 

(CFR: 41.7 / 45.6)

E/AA2 Ability to determine and interpret the following as they apply to 

(EMERGENCY AND ABNORMAL PLANT EVOLUTION): 

(CFR: 41.10 / 43.5 / 45.13)

1.11 COMPONENTS

| Basic components such as valves and pumps are found in many systems. NUREG-1021, section

| ES-205, “General Fundamentals Examination,” lists 8 categories of components. The following

eight (8) categories of components, for which additional knowledge statements are necessary are

listed below and delineated in Section 5 of the BWR catalog. 

The component knowledge statements are more detailed than those provided in the system listing,

yet at the same time they are generic to the component types. Each component has a unique six (6)

digit code number and 10 CFR 55.41 (b) item number. See Table 5, below. 

Table 5

 Components

291001 Valves (CFR: 41.3)

291002 Sensors and Detectors ( CFR: 41.7)

291003 Controllers and positioners (CFR: 41.7)

291004 Pumps(CFR: 41.3)
1.13 NUREG-1123, Rev. 2 |

291005 Motors and Generators (CFR: 41.7)

291006 Heat Exchangers and Condensers (CFR: 41.4) |

291007 Demineralizers and Ion Exchangers ( CFR: 41.3) |

291008 Breakers, Relays and Disconnects (CFR: 41.7) |

1.12 THEORY

NUREG-1021, Section ES-205, “General Fundamentals Examination,” lists |

 theory items. General fundamental knowledge which underlies safe performance on the job is |

delineated in Section 6 of the BWR Catalog. These theory topics represent general fundamental

concepts related to plant operation. Each theory topic has a unique six (6) digit code number. The

applicable 10 CFR 41(b) item number is provided for Reactor Theory and Thermodynamics

Theory.

Reactor Theory (CFR: 41.1)

292001 Neutrons

292002 Neutron Life Cycle

292003 Reactor Kinetics and Neutron Sources

292004 Reactivity Coefficients

292005 Control rods

292006 Fission Product Poisons

292007 Fuel Depletion and Burnable Poisons

292008 Reactor Operational Physics

Thermodynamics Theory (CFR: 41.14)

293001 Thermodynamic Units and Properties

293002 Basic Energy Concepts

293003 Steam

293004 Thermodynamic Process

293005 Thermodynamic Cycles

293006 Fluid Statics

293007 Heat Transfer and Heat Exchangers

293008 Thermal Hydraulics

293009 Core Thermal Limits

293010 Brittle Fracture and Vessel Thermal Stress

1.13 IMPORTANCE RATINGS

Importance, in this context, considers direct and indirect impact of the K/A on safe plant operation |

in a manner ensuring personnel and public health and safety. Importance Ratings of the K/As are

given for Reactor Operators and Senior Reactor Operators next to each knowledge and ability in

the catalog. These ratings reflect average ratings of individual NRC and utility panel members. 

The rating scale is presented in Table 6, below. |
NUREG-1123, Rev. 2 1.14 |

| Table 6

 RO and SRO Importance Ratings

Rating Importance for safe operation

5 Essential

4 Very important

3 Fairly important

2 Of limited importance

1 Insignificant Importance

* Indicates variability in the responses

Therefore, the rating of 2.0 or below represents a statement of limited or insignificant importance

for the safe operation of a plant. Such statements are generally considered as inappropriate

content for NRC licensing examinations. (See below for qualifications of importance ratings

related to variability of the ratings and plant specific data.)

1.13.1 Asterisk and Question Ratings

Some importance ratings are followed by an asterisk (*) or question mark (?). These marks

indicate variability in the rating responses. An asterisk indicates that the rating spread was very

broad. An asterisk can also signify that more than 15 percent of the raters indicated that the

knowledge or ability is not required for the RO/SRO position at their plant, either because it refers

to an inapplicable design feature or because it is the responsibility of someone else (e.g. SRO vs.

RO). A question mark indicates that more than 15 percent of the raters felt that they were not

familiar with the knowledge or ability as related to the particular system or design feature. These

| marks indicate a need for examination developers to review plant-specific materials to determine

whether or not that knowledge or ability is indeed appropriate for inclusion in any given

examination.

1.13.2 Difference Ratings

A dagger (†) to the left of an individual knowledge or ability statement indicates that more than 20

percent of the raters indicated that the level of knowledge or ability required by an SRO is

different than the level of knowledge or ability required by an RO. 

1.14 ACRONYMS AND TERMS

ADS automatic depressurization system

APE abnormal plant evolution

AFW auxiliary feedwater system

APRM average power range monitor

ARI alternate rod insertion system

ARM area radiation monitoring system
1.15 NUREG-1123, Rev. 2 |

ACRONYMS AND TERMS (continued)

ATWS anticipated transient without scram

CFR code of federal regulations

CRD control rod drive

D/G diesel generator

ECCS emergency core cooling system

EPE emergency plant evolution

HPCS high pressure core spray

HVAC heating, ventilation and air conditioning

IAS instrument air system

IRM intermediate range monitor

K/A knowledge and ability

LCO limiting condition for operation

LPCI low pressure coolant injection

LPCS low pressure core spray

LSRO senior reactor operator limited to fuel handling

MFW main feedwater

M/G motor generator

MSIV main steam isolation valve

RCIC reactor coolant isolation system

RCS reactor coolant system

RHR residual heat removal

RO reactor operator

RPS reactor protection system

RPV reactor pressure vessel

SRO senior reactor operator

SRV safety relief valve
2-1 NUREG-1123, Rev. 2 |

2.0 GENERIC KNOWLEDGES AND

 ABILITIES

2.1 Conduct of Operations

2.1.1 Knowledge of conduct of operations requirements.

 (CFR: 41.10 / 45.13)

IMPORTANCE RO 3.7 SRO 3.8 

2.1.2 Knowledge of operator responsibilities during all modes of plant operation.

 (CFR: 41.10 / 45.13)

IMPORTANCE RO 3.0 SRO 4.0

2.1.3 Knowledge of shift turnover practices. 

 (CFR: 41.10 / 45.13)

IMPORTANCE RO 3.0 SRO 3.4

2.1.4 Knowledge of shift staffing requirements.

 (CFR: 41.10 / 43.2)

IMPORTANCE RO 2.3 SRO 3.4

2.1.5 Ability to locate and use procedures and directives related to shift staffing and 

 activities.

 (CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE RO 2.3 SRO 3.4

2.1.6 Ability to supervise and assume a management role during plant transients and

 upset conditions.

 (CFR: 43.5 / 45.12 / 45.13)

IMPORTANCE RO 2.1 SRO 4.3

2.1.7 Ability to evaluate plant performance and make operational judgments based on 

 operating characteristics / reactor behavior / and instrument interpretation.

 (CFR: 43.5 / 45.12 / 45.13)

IMPORTANCE RO 3.7 SRO 4.4

2.1.8 Ability to coordinate personnel activities outside the control room. 

 (CFR: 45.5 / 45.12 / 45.13)

IMPORTANCE RO 3.8 SRO 3.6
NUREG-1123, Rev. 2 2-2 |

2.1 Conduct of Operations (continued)

2.1.9 Ability to direct personnel activities inside the control room.

 (CFR: 45.5 / 45.12 / 45.13)

IMPORTANCE RO 2.5 SRO 4.0

2.1.10 Knowledge of conditions and limitations in the facility license.

 (CFR: 43.1 / 45.13)

IMPORTANCE RO 2.7 SRO 3.9

2.1.11 Knowledge of less than one hour technical specification action statements for

 systems.

 (CFR: 43.2 / 45.13)

IMPORTANCE RO 3.0 SRO 3.8

2.1.12 Ability to apply technical specifications for a system.

 (CFR: 43.2 / 43.5 / 45.3)

IMPORTANCE RO 2.9 SRO 4.0

2.1.13 Knowledge of facility requirements for controlling vital / controlled access.

 (CFR: 41.10 / 43.5 / 45.9 / 45.10)

IMPORTANCE RO 2.0 SRO 2.9

2.1.14 Knowledge of system status criteria which require the notification of plant

 personnel.

 (CFR: 43.5 / 45.12)

IMPORTANCE RO 2.5 SRO 3.3

2.1.15 Ability to manage short-term information such as night and standing orders.

 (CFR: 45.12)

IMPORTANCE RO 2.3 SRO 3.0

2.1.16 Ability to operate plant phone / paging system / and two-way radio.

 (CFR: 41.10 / 45.12)

IMPORTANCE RO 2.9 SRO 2.8

2.1.17 Ability to make accurate / clear and concise verbal reports.

 (CFR: 45.12 / 45.13)

IMPORTANCE RO 3.5 SRO 3.6

2.1.18 Ability to make accurate / clear and concise logs / records / status boards / and

 reports.

 (CFR: 45.12 / 45.13)

IMPORTANCE RO 2.9 SRO 3.0
2-3 NUREG-1123, Rev. 2 |

2.1 Conduct of Operations (continued)

2.1.19 Ability to use plant computer to obtain and evaluate parametric information on 

 system or component status.

 (CFR: 45.12)

IMPORTANCE RO 3.0 SRO 3.0

2.1.20 Ability to execute procedure steps.

 (CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE RO 4.3 SRO 4.2

2.1.21 Ability to obtain and verify controlled procedure copy.

 (CFR: 45.10 / 45.13)

IMPORTANCE RO 3.1 SRO 3.2

2.1.22 Ability to determine Mode of Operation. 

 (CFR: 43.5 / 45.13)

IMPORTANCE RO 2.8 SRO 3.3

2.1.23 Ability to perform specific system and integrated plant procedures during

 different modes of plant operation.

 (CFR: 45.2 / 45.6)

IMPORTANCE RO 3.9 SRO 4.0

2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.

 (CFR: 45.12 / 45.13)

IMPORTANCE RO 2.8 SRO 3.1

2.1.25 Ability to obtain and interpret station reference materials such as graphs / 

 monographs / and tables which contain performance data.

 (CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE RO 2.8 SRO 3.1

2.1.26 Knowledge of non-nuclear safety procedures (e.g. rotating equipment / electrical /

 high temperature / high pressure / caustic / chlorine / oxygen and hydrogen).

 (CFR: 41.10 / 45.12)

IMPORTANCE RO 2.2 SRO 2.6
NUREG-1123, Rev. 2 2-4 |

2.1 Conduct of Operations (continued)

2.1.27 Knowledge of system purpose and or function.

 (CFR: 41.7)

IMPORTANCE RO 2.8 SRO 2.9

2.1.28 Knowledge of the purpose and function of major system components and controls.

 (CFR: 41.7)

IMPORTANCE RO 3.2 SRO 3.3

2.1.29 Knowledge of how to conduct and verify valve lineups.

 (CFR: 41.10 / 45.1 / 45.12)

IMPORTANCE RO 3.4 SRO 3.3

2.1.30 Ability to locate and operate components / including local controls.

 (CFR: 41.7 / 45.7)

IMPORTANCE RO 3.9 SRO 3.4

2.1.31 Ability to locate control room switches / controls and indications and to determine

 that they are correctly reflecting the desired plant lineup.

 (CFR: 45.12)

IMPORTANCE RO 4.2 SRO 3.9

2.1.32 Ability to explain and apply system limits and precautions.

 (CFR: 41.10 / 43.2 / 45.12)

IMPORTANCE RO 3.4 SRO 3.8

2.1.33 Ability to recognize indications for system operating parameters which are

 entry-level conditions for technical specifications.

 (CFR: 43.2 / 43.3 / 45.3)

IMPORTANCE RO 3.4 SRO 4.0

2.1.34 Ability to maintain primary and secondary plant chemistry within allowable

 limits.

 (CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE RO 2.3 SRO 2.9
2-5 NUREG-1123, Rev. 2 |

2.2 Equipment Control

2.2.1 Ability to perform pre-startup procedures for the facility / including operating those 

controls associated with plant equipment that could affect reactivity.

 (CFR: 45.1)

IMPORTANCE RO 3.7 SRO 3.6

2.2.2 Ability to manipulate the console controls as required to operate the facility

 between shutdown and designated power levels.

 (CFR: 45.2)

IMPORTANCE RO 4.0 SRO 3.5

2.2.3 (multi-unit) Knowledge of the design / procedural / and operational differences

 between units.

 (CFR: 41 / 43 / 45)

IMPORTANCE RO 3.1 SRO 3.3

2.2.4 (multi-unit) Ability to explain the variations in control board layouts / systems /

 instrumentation and procedural actions between units at a facility.

 (CFR: 45.1-45.13)

IMPORTANCE RO 2.8 SRO 3.0*

2.2.5 Knowledge of the process for making changes in the facility as described in 

 the safety analysis report.

 (CFR: 43.3 / 45.13)

IMPORTANCE RO 1.6 SRO 2.7

2.2.6 Knowledge of the process for making changes in procedures as described in the

 safety analysis report.

 (CFR: 43.3 / 45.13)

IMPORTANCE RO 2.3 SRO 3.3

2.2.7 Knowledge of the process for conducting tests or experiments not described in the

 safety analysis report.

 (CFR: 43.3 / 45.13)

IMPORTANCE RO 2.0 SRO 3.2

2.2.8 Knowledge of the process for determining if the proposed change / test / or

 experiment involves an unreviewed safety question.

 (CFR: 43.3 / 45.13)

IMPORTANCE RO 1.8 SRO 3.3
NUREG-1123, Rev. 2 2-6 |

2.2 Equipment Control (Continued)

2.2.9 Knowledge of the process for determining if the proposed change / test or

 experiment increases the probability of occurrence or consequences of an accident

 during the change / test or experiment.

 (CFR: 43.3 / 45.13)

IMPORTANCE RO 2.0 SRO 3.3

2.2.10 Knowledge of the process for determining if the margin of safety / as defined in the

 basis of any technical specification is reduced by a proposed change / test or

 experiment.

 (CFR: 43.3 / 45.13)

IMPORTANCE RO 1.9 SRO 3.3

2.2.11 Knowledge of the process for controlling temporary changes.

 (CFR: 41.10 / 43.3 / 45.13)

IMPORTANCE RO 2.5 SRO 3.4 *

2.2.12 Knowledge of surveillance procedures.

 (CFR: 41.10 / 45.13)

IMPORTANCE RO 3.0 SRO 3.4

2.2.13 Knowledge of tagging and clearance procedures.

 (CFR: 41.10 / 45.13)

IMPORTANCE RO 3.6 SRO 3.8

2.2.14 Knowledge of the process for making configuration changes.

 (CFR: 43.3 / 45.13)

IMPORTANCE RO 2.1 SRO 3.0

2.2.15 Ability to identify and utilize as-built design and configuration change

 documentation to ascertain expected current plant configuration and operate

 the plant.

 (CFR: 43.3 / 45.13)

IMPORTANCE RO 2.2 SRO 2.9

2.2.16 Knowledge of the process for making of field changes.

 (CFR: 41.10 / 45.13)

IMPORTANCE RO 1.9 SRO 2.6*
2-7 NUREG-1123, Rev. 2 |

2.2 Equipment Control (Continued)

2.2.17 Knowledge of the process for managing maintenance activities during power

 operations.

 (CFR: 43.5 / 45.13)

IMPORTANCE RO 2.3 SRO 3.5

2.2.18 Knowledge of the process for managing maintenance activities during shutdown

 operations.

 (CFR: 43.5 / 45.13)

IMPORTANCE RO 2.3 SRO 3.6

2.2.19 Knowledge of maintenance work order requirements.

 (CFR: 43.5 / 45.13)

IMPORTANCE RO 2.1 SRO 3.1

2.2.20 Knowledge of the process for managing troubleshooting activities.

 (CFR: 43.5 / 45.13)

IMPORTANCE RO 2.2 SRO 3.3

2.2.21 Knowledge of pre and post maintenance operability requirements.

 (CFR: 43.2)

IMPORTANCE RO 2.3 SRO 3.5

2.2.22 Knowledge of limiting conditions for operations and safety limits.

 (CFR: 43.2 / 45.2)

IMPORTANCE RO 3.4 SRO 4.1

2.2.23 Ability to track limiting conditions for operations.

 (CFR: 43.2 / 45.13)

IMPORTANCE RO 2.6 SRO 3.8

2.2.24 Ability to analyze the affect of maintenance activities on LCO status.

 (CFR: 43.2 / 45.13)

IMPORTANCE RO 2.6 SRO 3.8

2.2.25 Knowledge of bases in technical specifications for limiting conditions for

 operations and safety limits.

 (CFR: 43.2)

IMPORTANCE RO 2.5 SRO 3.7
NUREG-1123, Rev. 2 2-8 |

2.2 Equipment Control (Continued)

2.2.26 Knowledge of refueling administrative requirements. 

 (CFR: 43.5 / 45.13)

IMPORTANCE RO 2.5 SRO 3.7

2.2.27 Knowledge of the refueling process.

 (CFR: 43.6 / 45.13)

IMPORTANCE RO 2.6 SRO 3.5

| 2.2.28 Knowledge of new and spent fuel movement procedures.

 (CFR: 43.7 / 45.13)

IMPORTANCE RO 2.6 SRO 3.5

| 2.2.29 Knowledge of SRO fuel handling responsibilities.

 (CFR: 43.6 / 45.12)

IMPORTANCE RO 1.6 SRO 3.8

| 2.2.30 Knowledge of RO duties in the control room during fuel handling such as alarms

 from fuel handling area / communication with fuel storage facility / systems operated

 from the control room in support of fueling operations / and supporting

 instrumentation.

 (CFR: 45.12)

IMPORTANCE RO 3.5 SRO 3.3

| 2.2.31 Knowledge of procedures and limitations involved in initial core loading.

 (CFR: 43.6)

IMPORTANCE RO 2.2 SRO 2.9*

| 2.2.32 Knowledge of the effects of alterations on core configuration.

 (CFR: 43.6)

IMPORTANCE RO 2.3 SRO 3.3

| 2.2.33 Knowledge of control rod programming.

 (CFR: 43.6)

IMPORTANCE RO 2.5 SRO 2.9

| 2.2.34 Knowledge of the process for determining the internal and external effects on core

reactivity.

 (CFR: 43.6)

IMPORTANCE RO 2.8 SRO 3.2*
2-9 NUREG-1123, Rev. 2 |

2.3 Radiation Control

2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements.

 (CFR: 41.12 / 43.4. 45.9 / 45.10)

IMPORTANCE RO 2.6 SRO 3.0

2.3.2 Knowledge of facility ALARA program.

 (CFR: 41.12 / 43.4 / 45.9 / 45.10)

IMPORTANCE RO 2.5 SRO 2.9

2.3.3 Knowledge of SRO responsibilities for auxiliary systems that are outside the control

 room (e.g. / waste disposal and handling systems).

 (CFR: 43.4 / 45.10)

IMPORTANCE RO 1.8 SRO 2.9

2.3.4 Knowledge of radiation exposure limits and contamination control / including

 permissible levels in excess of those authorized.

 (CFR: 43.4 / 45.10)

IMPORTANCE RO 2.5 SRO 3.1

2.3.5 Knowledge of use and function of personnel monitoring equipment.

 (CFR: 41.11 / 45.9)

IMPORTANCE RO 2.3 SRO 2.5

2.3.6 Knowledge of the requirements for reviewing and approving release permits.

 (CFR: 43.4 / 45.10)

IMPORTANCE RO 2.1 SRO 3.1

2.3.7 Knowledge of the process for preparing a radiation work permit.

 (CFR: 41.10 / 45.12)

IMPORTANCE RO 2.0 SRO 3.3

2.3.8 Knowledge of the process for performing a planned gaseous radioactive release.

 (CFR: 43.4 / 45.10)

IMPORTANCE RO 2.3 SRO 3.2
NUREG-1123, Rev. 2 2-10 |

2.3 Radiation Control (Continued)

2.3.9 Knowledge of the process for performing a containment purge.

 (CFR: 43.4 / 45.10)

IMPORTANCE RO 2.5 SRO 3.4

2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard

 against personnel exposure.

 (CFR: 43.4 / 45.10)

IMPORTANCE RO 2.9 SRO 3.3

2.3.11 Ability to control radiation releases.

 (CFR: 45.9 / 45.10)

IMPORTANCE RO 2.7 SRO 3.2

2.4 Emergency Procedures /Plan

2.4.1 Knowledge of EOP entry conditions and immediate action steps.

 (CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 4.3 SRO 4.6

2.4.2 Knowledge of system set points / interlocks and automatic actions associated with

 EOP entry conditions.

 (CFR: 41.7 / 45.7 / 45.8)

Note: The issue of setpoints and automatic safety features is not specifically 

covered in the systems sections).

IMPORTANCE RO 3.9 SRO 4.1

2.4.3 Ability to identify post-accident instrumentation. 

 (CFR: 41.6 / 45.4)

IMPORTANCE RO 3.5 SRO 3.8

2.4.4 Ability to recognize abnormal indications for system operating parameters

 which are entry-level conditions for emergency and abnormal operating procedures.

 (CFR: 41.10 / 43.2 / 45.6)

IMPORTANCE RO 4.0 SRO 4.3

2.4.5 Knowledge of the organization of the operating procedures network for normal /

 abnormal / and emergency evolutions.

 (CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 2.9 SRO 3.6
2-11 NUREG-1123, Rev. 2 |

2.4 Emergency Procedures /Plan (Continued)

2.4.6 Knowledge symptom based EOP mitigation strategies.

 (CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3.1 SRO 4.0

2.4.7 Knowledge of event based EOP mitigation strategies.

 (CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3.1 SRO 3.8

2.4.8 Knowledge of how the event-based emergency/abnormal operating procedures are

 used in conjunction with the symptom-based EOPs.

 (CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3.0 SRO 3.7

2.4.9 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of

 RHR) mitigation strategies.

 (CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3.3 SRO 3.9

2.4.10 Knowledge of annunciator response procedures.

 (CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3.0 SRO 3.1

2.4.11 Knowledge of abnormal condition procedures. 

 (CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3.4 SRO 3.6

2.4.12 Knowledge of general operating crew responsibilities during emergency 

 operations. 

 (CFR: 41.10 / 45.12)

IMPORTANCE RO 3.4 SRO 3.9

2.4.13 Knowledge of crew roles and responsibilities during EOP flowchart use.

 (CFR: 41.10 / 45.12)

IMPORTANCE RO 3.3 SRO 3.9

2.4.14 Knowledge of general guidelines for EOP flowchart use.

 (CFR: 41.10 / 45.13 )

IMPORTANCE RO 3.0 SRO 3.9
NUREG-1123, Rev. 2 2-12 |

2.4 Emergency Procedures /Plan (Continued)

2.4.15 Knowledge of communications procedures associated with EOP implementation.

 (CFR: 41.10 / 45.13)

IMPORTANCE RO 3.0 SRO 3.5

2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support 

procedures.

 (CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3.0 SRO 4.0

2.4.17 Knowledge of EOP terms and definitions.

 (CFR: 41.10 / 45.13)

IMPORTANCE RO 3.1 SRO 3.8

2.4.18 Knowledge of the specific bases for EOPs.

 (CFR: 41.10 / 45.13)

IMPORTANCE RO 2.7 SRO 3.6

2.4.19 Knowledge of EOP layout / symbols / and icons.

 (CFR: 41.10 / 45.13)

IMPORTANCE RO 2.7 SRO 3.7

2.4.20 Knowledge of operational implications of EOP warnings / cautions / and notes.

 (CFR: 41.10 / 45.13)

IMPORTANCE RO 3.3 SRO 4.0

2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions

 including:

1. Reactivity control

2. Core cooling and heat removal

3. Reactor coolant system integrity

4. Containment conditions

5. Radioactivity release control.

 (CFR: 43.5 / 45.12)

IMPORTANCE RO 3.7 SRO 4.3

2.4.22 Knowledge of the bases for prioritizing safety functions during

 abnormal/emergency operations.

 (CFR: 43.5 / 45.12)

IMPORTANCE RO 3.0 SRO 4.0
2-13 NUREG-1123, Rev. 2 |

2.4 Emergency Procedures /Plan (Continued)

2.4.23 Knowledge of the bases for prioritizing emergency procedure implementation 

 during emergency operations.

 (CFR: 41.10 / 45.13)

IMPORTANCE RO 2.8 SRO 3.8

2.4.24 Knowledge of loss of cooling water procedures.

 (CFR: 41.10 / 45.13)

IMPORTANCE RO 3.3 SRO 3.7

2.4.25 Knowledge of fire protection procedures.

 (CFR: 41.10 / 45.13)

IMPORTANCE RO 2.9 SRO 3.4

2.4.26 Knowledge of facility protection requirements including fire brigade and portable

 fire fighting equipment usage.

 (CFR: 43.5 / 45.12)

IMPORTANCE RO 2.9 SRO 3.3

2.4.27 Knowledge of fire in the plant procedure.

 (CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3.0 SRO 3.5

2.4.28 Knowledge of procedures relating to emergency response to sabotage.

 (CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 2.3 SRO 3.3

2.4.29 Knowledge of the emergency plan.

 (CFR: 43.5 / 45.11)

IMPORTANCE RO 2.6 SRO 4.0

2.4.30 Knowledge of which events related to system operations/status should be

 reported to outside agencies.

 (CFR: 43.5 / 45.11)

IMPORTANCE RO 2.2 SRO 3.6

2.4.31 Knowledge of annunciators alarms and indications / and use of the response 

 instructions.

 (CFR: 41.10 / 45.3)

IMPORTANCE RO 3.3 SRO 3.4
NUREG-1123, Rev. 2 2-14 |

2.4 Emergency Procedures /Plan (Continued)

2.4.32 Knowledge of operator response to loss of all annunciators.

 (CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3.3 SRO 3.5

2.4.33 Knowledge of the process used track inoperable alarms.

 (CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 2.4 SRO 2.8

2.4.34 Knowledge of RO tasks performed outside the main control room

 during emergency operations including system geography and system implications.

 (CFR: 43.5 / 45.13)

IMPORTANCE RO 3.8 SRO 3.6

2.4.35 Knowledge of local auxiliary operator tasks during emergency operations 

 including system geography and system implications.

 (CFR: 43.5 / 45.13)

IMPORTANCE RO 3.3 SRO 3.5

2.4.36 Knowledge of chemistry / health physics tasks during emergency operations.

 (CFR: 43.5)

IMPORTANCE RO 2.0 SRO 2.8

2.4.37 Knowledge of the lines of authority during an emergency.

 (CFR: 45.13)

IMPORTANCE RO 2.0 SRO 3.5

2.4.38 Ability to take actions called for in the facility emergency plan / including (if 

 required)supporting or acting as emergency coordinator.

 (CFR: 43.5 / 45.11)

IMPORTANCE RO 2.2 SRO 4.0

2.4.39 Knowledge of the RO's responsibilities in emergency plan implementation.

 (CFR: 45.11)

IMPORTANCE RO 3.3 SRO 3.1

2.4.40 Knowledge of the SRO's responsibilities in emergency plan implementation.

 (CFR: 45.11)

IMPORTANCE RO 2.3 SRO 4.0

2.4.41 Knowledge of the emergency action level thresholds and classifications.

 (CFR: 43.5 / 45.11)

IMPORTANCE RO 2.3 SRO 4.1
2-15 NUREG-1123, Rev. 2 |

2.4 Emergency Procedures /Plan (Continued)

2.4.42 Knowledge of emergency response facilities.

 (CFR: 45.11)

IMPORTANCE RO 2.3 SRO 3.7

2.4.43 Knowledge of emergency communications systems and techniques.

 (CFR: 45.13)

IMPORTANCE RO 2.8 SRO 3.5

2.4.44 Knowledge of emergency plan protective action recommendations.

 (CFR: 43.5 / 45.11)

IMPORTANCE RO 2.1 SRO 4.0

2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.

 (CFR: 43.5 / 45.3 / 45.12)

IMPORTANCE RO 3.3 SRO 3.6

2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

 (CFR: 43.5 / 45.3 / 45.12)

IMPORTANCE RO 3.5 SRO 3.6

2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner

 utilizing the appropriate control room reference material.

 (CFR: : 41.10 /43.5 / 45.12)

IMPORTANCE RO 3.4 SRO 3.7

2.4.48 Ability to interpret control room indications to verify the status and operation of

 system / and understand how operator action s and directives affect plant and

 system conditions.

 (CFR: 43.5 / 45.12)

IMPORTANCE RO 3.5 SRO 3.8

2.4.49 Ability to perform without reference to procedures those actions that require 

 immediate operation of system components and controls.

 (CFR: 41.10 / 43.2 / 45.6)

IMPORTANCE RO 4.0 SRO 4.0

2.4.50 Ability to verify system alarm setpoints and operate controls identified in the

 alarm response manual.

 (CFR: 45.3)

IMPORTANCE RO 3.3 SRO 3.3
NUREG-1123, Rev. 2 2-16 |

This page left blank
3.1-1 NUREG-1123, Rev. 2 |

3.1 Reactivity Control page

201001 Control Rod Drive Hydraulic System 3.1-3

201003 Control Rod and Drive Mechanism 3.1-7

201002 Reactor Manual Control System 3.1-10

202002 Recirculation flow Control System 3.1-13

202001 Recirculation System 3.1-17

201005 Rod Control and Information System 3.1-22

211000 Standby Liquid Control System 3.1-25
NUREG-1123, Rev. 2 3.1-2 |

This page left blank
3.1-3 NUREG-1123, Rev. 2 |

SYSTEM: 201001 Control Rod Drive Hydraulic System

TASK: Perform lineups on the CRD hydraulic system

Place the control rod drive system in service

Monitor the control rod Drive System

Remove Control Rod Drive System From Service

Vent the control rod drive system (write in)

Conduct CRD hydraulics valve testing during cold shutdown

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between CONTROL ROD DRIVE

HYDRAULIC SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Condensate system ...................................................... 3.1 3.1

K1.02 Condensate storage tanks ................................................. 3.0 3.0

K1.03 Recirculation pumps (seal purge): Plant-Specific ............................ 3.1 3.1

K1.04 Head spray: BWR-3 .................................................... 2.7 2.7

K1.05 Feedwater (or reactor water cleanup)-CRD return to

vessel: Plant-Specific ................................................... 2.7 2.7

K1.06 Component cooling water systems: Plant-Specific ........................... 2.8 2.8

K1.07 Reactor protection system ............................................... 3.4 3.4

K1.08 Reactor manual control system ............................................ 3.4 3.4

K1.09 Plant air systems ....................................................... 3.1 3.2

K1.10 Control rod drive mechanisms ............................................ 2.8 2.8

K1.11 Reactor water cleanup pumps: Plant-Specific ............................... 2.8 2.8

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Pumps ................................................................ 2.9 3.1

K2.02 Scram valve solenoids ................................................... 3.6* 3.7

K2.03 Backup SCRAM valve solenoids ........................................... 3.5* 3.6*

K2.04 Scram discharge volume vent and drain valve solenoids. ....................... 3.2 3.3

K2.05 Alternate rod insertion valve solenoids: Plant-Specific ....................... 4.5* 4.5*

K2.06 Motor operated valves ................................................... 2.1* 2.3*

K2.07 Breaker control ......................................................... 2.0* 2.1*

K3. Knowledge of the effect that a loss or malfunction of

the CONTROL ROD DRIVE HYDRAULIC SYSTEM will have on

following:

(CFR: 41.7 / 45.4)

K3.01 Recirculation pumps: Plant-Specific ....................................... 3.0 3.1

K3.02 Reactor water level ..................................................... 2.6 2.6

K3.03 Control rod drive mechanisms ............................................ 3.1 3.2

K3.04 Head spray: BWR-3 .................................................... 2.7 2.7

K3.05 Reactor water cleanup pumps: Plant-Specific ............................... 2.3 2.3
NUREG-1123, Rev. 2 3.1-4 |

SYSTEM: 201001 Control Rod Drive Hydraulic System

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4. Knowledge of CONTROL ROD DRIVE HYDRAULIC SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR 41.7)

K4.01 Protection against pump runout during SCRAM conditions

(location of the CRD system flow element and a

restricting orifice in the accumulator charging water line) ..................... 2.5 2.6

K4.02 Stable system flow when moving control rods

(stabilizing valves) ...................................................... 2.6 2.6

K4.03 Control rod drive mechanism cooling water flow ............................. 2.7 2.7

K4.04 Scramming control rods with inoperative SCRAM solenoid

valves (back-up SCRAM valves) ........................................... 3.6 3.6

K4.05 Control rod SCRAM .................................................... 3.8 3.8

| K4.06 Isolation of the SCRAM discharge volumes during SCRAM

conditions ............................................................. 3.8 3.9

K4.07 Testing SCRAM discharge volume isolation valves ........................... 2.8 2.8

K4.08 Controlling control rod drive header pressure ............................... 3.1 3.0

K4.09 Controlling control rod drive cooling header pressure ........................ 2.9 2.8 

K4.10 Control of rod movement (HCU directional control valves) .................... 3.1 3.0

K4.11 Protection against filling the SDV during non-SCRAM conditions .............. 3.6 3.6

K4.12 Controlling CRD system flow............................................. 2.9 2.9

K4.13 Motor cooling .......................................................... 2.3 2.3

K5. Knowledge of the operational implications of the

following concepts as they apply to CONTROL ROD DRIVE

HYDRAULIC SYSTEM :

(CFR: : : 41.5 / 45.3)

K5.01 Pump operation ......................................................... 2.4 2.4

K5.02 Flow indication ......................................................... 2.6 2.6

K5.03 Pressure indication ...................................................... 2.7 2.7

K5.04 Indications of pump cavitation ............................................ 2.4 2.4

K5.05 Indications of pump runout: Plant-Specific ................................. 2.7 2.7

K5.06 Differential pressure indication ........................................... 2.5 2.6

K5.07 Air operated control valves ............................................... 2.3 2.4

K5.08 Solenoid operated valves ................................................. 2.5 2.6

K5.09 System venting ......................................................... 2.2* 2.2*

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the CONTROL ROD DRIVE

HYDRAULIC System :

(CFR: 41.7 / 45.7)

K6.01 Condensate system ...................................................... 2.8 2.8

K6.02 Condensate storage tanks ................................................. 3.0 3.1
3.1-5 NUREG-1123, Rev. 2 |

SYSTEM: 201001 Control Rod Drive Hydraulic System

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6.03 Plant air systems ........................................................ 3.0 2.9

K6.04 RPS .................................................................. 3.6 3.7 |

K6.05 A.C. power ............................................................. 3.3 3.3

K6.06 Component cooling water systems: Plant-Specific ........................... 2.8 2.8

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the CONTROL ROD

DRIVE HYDRAULIC SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 CRD drive water header pressure .......................................... 3.1 2.9

A1.02 CRD cooling water header pressure ........................................ 2.9 2.9

A1.03 CRD system flow ....................................................... 2.9 2.8

A1.04 Head spray flow: BWR-3 ................................................ 2.7 2.7

A1.05 SDV isolation valve position .............................................. 3.5 3.4

A1.06 HCU pressure/level ..................................................... 3.4 3.4

A1.07 Reactor water level ...................................................... 3.3 3.2

A1.08 Pump amps ............................................................ 2.3 2.2

A1.09 CRD drive water flow.................................................... 2.9 2.8

A1.10 CRD cooling water flow ................................................. 2.8 2.6

A2. Ability to (a) predict the impacts of the following on

the CONTROL ROD DRIVE HYDRAULIC SYSTEM ; and (b) based

on those predictions, use procedures to correct,

control, or mitigate the consequences of those

abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Pumps trips ............................................................ 3.2 3.3

A2.02 Valve closures .......................................................... 3.2 3.3

A2.03 Power supply failures .................................................... 3.0 3.1

A2.04 †Scram conditions ...................................................... 3.8 3.9*

A2.05 Discharge strainer(s) becoming plugged .................................... 2.9 2.9

A2 06 Suction strainer(s) becoming plugged ...................................... 2.9 2.9

A2.07 Flow control valve failure ................................................ 3.2 3.1

A2.08 Inadequate system flow .................................................. 2.8 2.8

A2.09 Loss of applicable plant air systems ........................................ 3.2 3.1

A2.10 †Low HCU accumulator pressure/high level ................................. 3.5 3.6

A2 11 Valve openings ......................................................... 2.6 2.7

A2.12 High cooling water flow ................................................. 2.8 2.9

A2.13 Low cooling water flow .................................................. 2.7 2.8

A2.14 Low drive header pressure ................................................ 2.8 2.8
NUREG-1123, Rev. 2 3.1-6 |

SYSTEM: 201001 Control Rod Drive Hydraulic System

Tasks as noted previously

A3. Ability to monitor automatic operations of the CONTROL

ROD DRIVE HYDRAULIC SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation ......................................................... 3.0 3.0

A3.02 Pump start: Plant-Specific ............................................... 2.8 2.8

A3.03 System pressure ........................................................ 2.7 2.7

A3.04 System flow ........................................................... 2.8 2.7

A3.05 Reactor water level ...................................................... 2.8 2.8

A3.06 Reactor power .......................................................... 2.8 2.8

A3.07 HCU accumulator pressure/level .......................................... 3.3 3.3

A3.08 Drive water flow ........................................................ 3.0 2.9

A3.09 Cooling water flow ...................................................... 2.8 2.8

A3.10 Lights and alarms ....................................................... 3.0 2.9

A3.11 SDV level ............................................................. 3.5 3.5

A4. Ability to manually operate and/or monitor in the

control room:

CFR: 41.7 / 45.5 to 45.8)

A4.01 CRD pumps ............................................................ 3.1 3.1

A4.02 CRD pump discharge valve ............................................... 2.6 2.6

A4.03 CRD system flow control valve ........................................... 2.9 2.8

A4.04 Drive water header pressure control valve ................................... 3.1 3.0

A4.05 Cooling water header pressure control valve ................................. 2.7 2.8

A4.06 SDV isolation valve test switch ............................................ 2.8 2.7

A4.07 Stabilizing valve selector switch ........................................... 2.2* 2.1*
3.1-7 NUREG-1123, Rev. 2 |

SYSTEM: 201003 Control Rod and Drive Mechanism

TASK: Flush a CRD mechanism

Conduct Control Rod Operability Test

Conduct Control Rod Coupling Integrity Test

Perform Control Rod Drive Stall Flow Testing (CRD 18-Month Accumulator Operability Test)

Perform control rod drive accumulator piston seal exercising

Perform the control rod drive timing test (write in)

Perform friction testing

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between CONTROL ROD AND DRIVE

MECHANISM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Control rod drive hydraulic system ........................................ 3.2 3.3

K1.02 Reactor water .......................................................... 2.9 3.0

K1.03 RPIS ................................................................. 3.1 3.1

K1.04 Reactor vessel ......................................................... 2.9 2.9

K1.05 CRD mechanism temperature monitor ..................................... 2.6 2.6

K2. Knowledge of electrical power supplies to the

following:

 (CFR: 41.7)

None |

K3. Knowledge of the effect that a loss or malfunction of

the CONTROL ROD AND DRIVE MECHANISM will have on

following:

(CFR: 41.7 / 45.4)

K3.01 Reactor power ......................................................... 3.2 3.4

K3.02 †Flux shaping .......................................................... 2.8 3.1

K3.03 †Shutdown margin ...................................................... 3.2 3.8

K4. Knowledge of CONTROL ROD AND DRIVE MECHANISM design

feature(s) and/or interlocks which provide for the

following: (CFR: 41.7)

K4.01 Limiting control rod speed in the event of a rod drop ......................... 2.9* 3.0*

K4.02 Detection of an uncoupled rod ............................................ 3.8 3.9

K4.03 Slowing the drive mechanism near the end of its travel

following a SCRAM: Plant-Specific ...................................... 2.1* 2.1*

K4.04 The use of either accumulator or reactor water to

SCRAM the control rod ................................................. 3.6 3.7

K4.05 Rod position indication .................................................. 3.2 3.3

K4.06 Uncoupling the control rod from the drive mechanism ........................ 2.4 2.6

K4.07 Maintaining the control rod at a given location .............................. 3.2 3.2

K4.08 Monitoring CRD mechanism temperature .................................. 2.6 2.7
NUREG-1123, Rev. 2 3.1-8 |

SYSTEM: 201003 Control Rod and Drive Mechanism

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K5. Knowledge of the operational implications of the

following concepts as they apply to CONTROL ROD AND

DRIVE MECHANISM :

(CFR: 41.5 / 45.3)

K5.01 Hydraulics ............................................................ 2.6 2.7

K5.02 †Flux shaping .......................................................... 2.8 3.3

K5.03 Reactor power control .................................................. 3.3 3.4

K5.04 †Rod sequence patterns ................................................. 3.1 3.4

K5.05 Reverse power effect ................................................... 3.0 3.1

K5.06 How control rod worth varies with moderator

temperature and voids ................................................... 2.7 2.9

K5.07 How control rod movements affect core reactivity ........................... 3.3 3.6

K5.08 How control rods affect shutdown margin .................................. 3.1 3.5

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the CONTROL ROD AND DRIVE

MECHANISM :

(CFR: 41.7 / 45.7)

K6.01 Control rod drive hydraulic system ........................................ 3.3 3.3

K6.02 Reactor pressure ....................................................... 3.0 3.0

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the CONTROL ROD

AND DRIVE MECHANISM controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor power ......................................................... 3.7 3.8

| A1.02 CRD drive pressure ..................................................... 2.8 2.8

A1.03 CRD drive water flow ................................................... 2.9 2.9

A2. Ability to (a) predict the impacts of the following on

the CONTROL ROD AND DRIVE MECHANISM ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 ^Stuck rod ............................................................ 3.4 3.6

A2.02 Uncoupled rod ......................................................... 3.7 3.8

A2.03 †Drifting rod .......................................................... 3.4 3.7

A2.04 Single control rod SCRAM .............................................. 3.5 3.6

A2.05 Reactor Scram ......................................................... 4.1* 4.1

A2.06 Loss of CRD cooling water flow .......................................... 3.0 3.1

A2.07 Loss of CRD drive water flow ............................................ 3.1 3.2
3.1-9 NUREG-1123, Rev. 2 |

SYSTEM: 201003 Control Rod and Drive Mechanism

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A2.08 Low HCU accumulator pressure/high level 3.8 3.7

A2.09 Low reactor pressure 3.2 3.4

A2.10 †Excessive SCRAM time for a given drive mechanism ........................ 3.0 3.4

A3. Ability to monitor automatic operations of the CONTROL

ROD AND DRIVE MECHANISM including:

(CFR: 41.7 / 45.7)

A3.01 Control rod position .................................................... 3.7 3.6

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 CRD mechanism temperature ............................................ 2.6* 2.6*

A4.02 CRD mechanism position: Plant-Specific .................................. 3.5 3.5
NUREG-1123, Rev. 2 3.1-10 |

SYSTEM: 201002 Reactor Manual Control System

TASK: Operate Control Rods Using "Single Notch" Mode 

Operate Control Rods Using "Notch Override" 

Conduct "Emergency Rod In" Control Rode Insertion 

Operate The Control Rod Drive System To Bring The Reactor Critical

Operate the Control Rod Drive Manually At Power 

Operate the Control Rod Drive System To Shutdown The Reactor 

Conduct Refueling Interlocks Functional Test/Control Rod Drive

Maintenance Test 

What if rod drift alarm occurs?

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between REACTOR MANUAL CONTROL

SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Control rod drive hydraulic system ........................................ 3.2 3.2

K1.02 Control rod and drive mechanism ......................................... 3.0 2.9

Kl.03 Control rod block interlocks/power operation 

refueling .............................................................. 3.4 3.6

K1.04 Rod block monitor: Plant-Specific ........................................ 3.5 3.6

K1.05 Rod worth minimizer: Plant-Specific ...................................... 3.4 3.5

K1.06 Rod sequence control system: Plant-Specific ............................... 3.2 3.3

K1.07 Process computer: Plant-Specific ........................................ 2.8 2.9

K1.08 †Refueling interlocks: Plant-Specific ..................................... 3.2 3.6

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

| K2.01 Select matrix .......................................................... 2.1* 2.3*

| K2.02 CRD HCU directional control valves ...................................... 2.1* 2.3*

K3. Knowledge of the effect that a loss or malfunction of

the REACTOR MANUAL CONTROL SYSTEM will have on

following:

(CFR: 41.7 / 45.4)

K3.01 Ability to move control rods ............................................. 3.4 3.4

K3.02 ^Rod block monitor: Plant-Specific ....................................... 2.9 3.2

K3.03 Ability to process rod block signals ....................................... 2.9 3.0

K4. Knowledge of REACTOR MANUAL CONTROL SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Detection of sequence timer malfunction .................................. 2.7 2.7

K4.02 Control rod blocks ..................................................... 3.5 3.5

K4.03 Detection of drifting control rods ......................................... 3.6 3.6
3.1-11 NUREG-1123, Rev. 2 |

SYSTEM: 201002 Reactor Manual Control System

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.04 "Single notch" rod withdrawal and insertion .................................. 3.3 3.3

K4.05 "Notch override" rod withdrawal .......................................... 3.3 3.3

K4.06 "Emergency In" rod insertion ............................................. 3.5 3.5

K4.07 Timing of rod insert and withdrawal cycles (rod

movement sequence timer) .............................................. 2.5* 2.5* |

K4.08 "Continuous In" rod insertion ............................................. 3.2 3.2

K5. Knowledge of the operational implications of the

following concepts as they apply to REACTOR MANUAL

CONTROL SYSTEM :

(CFR: 41.5 / 45.3)

|

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the REACTOR MANUAL CONTROL

SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 Select matrix power .................................................... 2.5 2.6

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the REACTOR

MANUAL CONTROL SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 CRD drive water flow ................................................... 2.8 2.8

A1.02 Control rod position .................................................... 3.4 3.3

A1.03 Rod movement sequence lights ........................................... 3.0 2.9

A1.04 Overall reactor power ................................................... 3.6 3.5

A1.05 Local reactor power .................................................... 3.4 3.6

A2. Ability to (a) predict the impacts of the following on

the REACTOR MANUAL CONTROL SYSTEM ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Rod movement sequence timer malfunctions ................................ 2.7 2.8

A2.02 Rod drift alarm ......................................................... 3.2 3.3

A2.03 Select block ........................................................... 2.9 2.8

A2.04 Control rod block ...................................................... 3.2 3.1
NUREG-1123, Rev. 2 3.1-12 |

SYSTEM: 201002 Reactor Manual Control System

Tasks as noted previously

IMPORTANCE 

K/A NO. ABILITY RO SRO

A3. Ability to monitor automatic operations of the REACTOR

MANUAL CONTROL SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Control rod block actuation .............................................. 3.2 3.1

A3.02 Rod movement sequence lights ........................................... 2.8 2.7

A3.03 Rod drift alarm ......................................................... 3.2 3.2

A3.04 Rod movement sequence timer malfunction alarm:

Plant-Specific ......................................................... 2.8 2.8

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Rod movement control switch ............................................ 3.5 3.4

A4.02 Emergency in/notch override switch ....................................... 3.5 3.5

A4.03 Rod drift test switch .................................................... 2.8 2.8

A4.04 Timer malfunction test switch: Plant-Specific .............................. 2.8 2.8

A4.05 Rod select matrix ...................................................... 3.1 3.0

A4.06 Rod select matrix power switch ........................................... 2.8 2.8
3.1-13 NUREG-1123, Rev. 2 |

SYSTEM: 202002 Recirculation Flow Control System

TASK: Adjust the recirculation flow using manual control

Operate recirculation pumps in various control modes (adjust the recirculation flow using "master manual"

control)

What if flow mismatch exceeds limits of daily surveillance log

What if power to flow is not in specified range?

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between RECIRCULATION FLOW

CONTROL SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Recirculation system ................................................... 3.5 3.6

K1.02 Reactor power ......................................................... 4.2* 4.2

K1.03 Reactor core flow ...................................................... 3.7 3.7

K1.04 Reactor/turbine pressure regulating system: PlantSpecific .............................................................. 3.1 3.1

K1.05 Recirculation MG set: Plant-Specific ..................................... 3.5 3.5

K1.06 A.C. electrical ......................................................... 2.9 3.0

K1.07 D.C. electrical ......................................................... 2.6 2.8

K1.08 Feedwater flow ........................................................ 3.1 3.2

K1.09 Reactor water level ..................................................... 3.1 3.2

Kl.10 Rod pattern ............................................................ 2.5 2.6

K1.11 APRM system ......................................................... 3.4 3.4

K1.12 Recirculation flow control valves: Plant-Specific ........................... 3.7 3.9

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Recirculation flow control system ........................................ 2.4* 2.4* |

K2.02 Hydraulic power unit: Plant-Specific ...................................... 2.6 2.6

K3. Knowledge of the effect that a loss or malfunction of

the RECIRCULATION FLOW CONTROL SYSTEM will have on

following:

(CFR: 41.7 / 45.4)

K3.01 Core flow ............................................................. 3.5 3.5

K3.02 Reactor power ......................................................... 4.0 4.0

K3.03 Reactor water level ..................................................... 3.3 3.4

K3.04 Reactor/turbine pressure regulation system ................................. 2.9 3.1

K3.05 Recirculation pump speed: Plant-Specific .................................. 3.2 3.3

K3.06 Recirculation flow control valve position: Plant-

 Specific .............................................................. 3.7 3.7
NUREG-1123, Rev. 2 3.1-14 |

SYSTEM: 202002 Recirculation Flow Control System

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4. Knowledge of RECIRCULATION FLOW CONTROL SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Scoop tube break: Plant-Specific ......................................... 3.1 3.1

K4.02 Recirculation pump speed control: Plant-Specific ........................... 3.0 3.0

K4.03 Signal failure detection: Plant-Specific .................................... 3.0 3.0

| K4.04 Automatic load following: Plant-Specific .................................. 2.4* 2.4*

K4.05 Limiting recirculation pump speed mismatch: PlantSpecific .............................................................. 3.1 3.4

K4.06 Recirculation pump adequate NPSH: Plant-Specific ......................... 3.1 3.1

K4.07 Minimum and maximum pump speed setpoints .............................. 2.9 2.9

K4.08 Automatic flow control valve positioning: BWR-5,6 ......................... 3.3 3.4

K4.09 Minimum and maximum flow control valve position

setpoints: BWR-5,6 .................................................... 3.3 3.4

K5. Knowledge of the operational implications of the

following concepts as they apply to RECIRCULATION FLOW

CONTROL SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Fluid coupling: BWR-3,4 ............................................... 2.8 2.8

K5.02 Feedback signals ....................................................... 2.6 2.6

K5.03 Error signals ........................................................... 2.4 2.4

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the RECIRCULATION FLOW

CONTROL SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 A.C. power ............................................................ 2.8 2.9

K6.02 D.C. power ............................................................ 2.6 2.6

K6.03 Recirculation system ................................................... 2.8 2.8

K6.04 Feedwater flow inputs: BWR-3,4,5,6 ...................................... 3.5 3.5

| K6.05 Reactor water level ..................................................... 3.1 3.1

K6.06 Reactor/turbine pressure regulating system: PlantSpecific .............................................................. 2.9 2.9

K6.07 APRM signal input: BWR-5,6 ............................................ 3.6 3.7
3.1-15 NUREG-1123, Rev. 2 |

SYSTEM: 202002 Recirculation Flow Control System

Tasks as noted previously

IMPORTANCE 

K/A NO. ABILITY RO SRO

A1. Ability to predict and/or monitor changes in

parameters associated with operating the RECIRCULATION

FLOW CONTROL SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Recirculation pump speed: BWR-2,3,4,5,6 ................................. 3.2 3.2

A1.02 MG set drive motor amps: Plant-Specific .................................. 2.7 2.7

A1.03 MG set generator current, power, voltage ................................... 2.5* 2.4*

A1.04 Reactor water level ..................................................... 2.9 2.9

A1.05 Reactor power ......................................................... 3.6 3.6

A1.06 Reactor core flow ...................................................... 3.4 3.3

A1.07 Recirculation loop flow: Plant-Specific ................................... 3.1 3.1

A1.08 Recirculation FCV position: BWR-5,6 .................................... 3.4 3.4

A2. Ability to (a) predict the impacts of the following on

the RECIRCULATION FLOW CONTROL SYSTEM ; and (b) based

on those predictions, use procedures to correct,

control, or mitigate the consequences of those

abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Recirculation pump trip ................................................. 3.4 3.4

A2.02 Loss of A.C. ........................................................... 2.9 3.0

A2.03 Loss of D.C. ........................................................... 2.6 2.7

A2.04 Recirculation pump speed mismatch between loops:

Plant-Specific ......................................................... 3.0 3.2

A2.05 Scoop tube lockup: BWR-2,3,4 .......................................... 3.1 3.1

A2.06 Low reactor water level: Plant-Specific .................................... 3.3 3.3

A2.07 Loss of feedwater signal inputs: Plant-Specific ............................. 3.3 3.3

A2.08 FCV lockup: BWR-5,6 .................................................. 3.3 3.3

A2.09 †Recirculation flow mismatch: Plant-Specific .............................. 3.1 3.3

A3. Ability to monitor automatic operations of the

RECIRCULATION FLOW CONTROL SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Flow control valve operation: BWR-5,6 ................................... 3.6 3.4

A3.02 Lights and alarms ....................................................... 3.4 3.4

A3.03 Scoop tube operation: BWR-2,3,4 ........................................ 3.1 3.0

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 MG sets ............................................................... 3.3 3.1

A4.02 Hydraulic power unit: BWR-5,6 ........................................... 2.8 2.8

A4.03 Lights and alarms ........................................................ 3.1 3.1
NUREG-1123, Rev. 2 3.1-16 |

A4.04 Reactor power .......................................................... 3.8 3.8

A4.05 Reactor level ........................................................... 3.4 3.4

A4.06 Scoop tube power: BWR-2,3,4 ............................................ 2.7 2.6

A4.07 Recirculation pump speed: BWR-2,3,4,5,6 .................................. 3.3 3.2

A4.08 Recirculation system flow ................................................ 3.3 3.3

A4.09 Core flow .............................................................. 3.2 3.3
3.1-17 NUREG-1123, Rev. 2 |

SYSTEM: 202001 Recirculation System

TASK: Perform lineups on the recirculation system 

Vent recirculation pump seals 

Startup a recirculation pump (startup a second recirculation pump)

Operate recirculation pumps in various control modes (adjust the recirculation flow using "master manual"

control) 

Monitor recirculation pumps in operation 

Monitor jet pump operation 

Secure a recirculation pump 

Perform jet pump operability test 

Conduct heatup and cooldown temperature checks 

Conduct recirculation pump startup check of the delta temperature between the reactor coolant in the idle

loop to the reactor vessel

Conduct recirculation pump trip logic system functional test 

Conduct recirculation loop valve operability test 

Conduct recirculation system valve testing 

What if jet pumps not operating within required operating band

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between RECIRCULATION SYSTEM and

the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Core flow .............................................................. 3.6 3.7

K1.02 Reactor power .......................................................... 4.1 4.1

K1.03 Reactor moderator temperature ............................................ 3.2 3.3

K1.04 Reactor/turbine pressure regulating system: PlantSpecific ............................................................... 3.3 3.3

K1.05 Reactor pressure ........................................................ 3.4 3.4

K1.06 Jet pumps .............................................................. 3.6 3.6

K1.07 Component cooling water systems ......................................... 3.1 3.2

K1.08 A.C. electrical .......................................................... 3.1 3.2

K1.09 D.C. electrical .......................................................... 2.7 2.9

K1.10 Control rod drive system: Plant-Specific ................................... 2.8 2.8

K1.11 Drywell equipment drain sump ............................................. 2.7 2.8

K1.12 Recirculation system motor-generator sets: PlantSpecific ............................................................... 3.6 3.6

K1.13 Jet pump ring header and risers: Plant-Specific .............................. 3.1 3.2

K1.14 Rod block monitor: Plant-Specific ......................................... 3.0 3.2

K1.15 Nuclear boiler instrumentation (reactor water

level/pressure) .......................................................... 3.2 3.2

K1.16 Low pressure coolant injection logic: Plant-Specific .......................... 3.9 3.9

K1.17 Vessel bottom head drain temperature ...................................... 3.1 3.3

K1.18 RHR shutdown cooling mode .............................................. 3.3 3.3

K1.19 Feedwater flow ......................................................... 3.2 3.2

K1.20 Plant air systems: Plant-Specific .......................................... 2.4 2.5

K1.21 Reactor water cleanup system ............................................. 2.6 2.6
NUREG-1123, Rev. 2 3.1-18 |

SYSTEM: 202001 Recirculation System

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.22 Reactor water level ..................................................... 3.5 3.6

K1.23 Average power range monitor flow converters: PlantSpecific .............................................................. 3.4 3.5

K1.24 Isolation condenser: Plant-Specific ....................................... 3.4 3.4

K1.25 Reactor water sampling system ............................................ 2.6 2.7

| K1.26 Recirculation flow control system: Plant-Specific ........................... 3.6 3.6

| K1.27 ATWS circuitry: Plant-Specific .......................................... 4.1 4.3*

K1.28 End-of-cycle recirculation pump trip circuitry:

Plant-Specific ......................................................... 3.9 4.1

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Recirculation pumps: Plant-Specific ...................................... 3.2* 3.2

K2.02 MG sets: Plant-Specific ................................................ 3.2 3.3

K2.03 Recirculation system valves .............................................. 2.7* 2.8*

K2.04 Hydraulic power unit oil pumps: Plant-Specific ............................. 2.5* 2.5*

K2.05 MG set oil pumps: Plant-Specific ........................................ 2.3* 2.3*

K3. Knowledge of the effect that a loss or malfunction of

the RECIRCULATION SYSTEM will have on following:

(CFR: 41.7 / 45.4)

K3.01 Core flow ............................................................. 3.6 3.6

K3.02 Load following capabilities: Plant-Specific ................................ 2.8 2.8

K3.03 Reactor power ......................................................... 3.9 3.9

K3.04 Reactor water level ..................................................... 3.7 3.7

K3.05 Recirculation system MG sets: Plant-Specific .............................. 3.3 3.3

K3.06 Low pressure coolant injection logic: Plant-Specific ......................... 3.7 3.9

K3.07 Vessel bottom head drain temperature ...................................... 2.9 2.9

K3.08 Shutdown cooling system ................................................ 2.8 2.9

K3.09 Reactor water cleanup system ............................................ 2.4* 2.5*

K3.10 Average power range monitor flow converters ............................... 3.3 3.4

K3.11 Component cooling water systems ........................................ 2.3* 2.3*

K3.12 Isolation condenser: Plant-Specific ....................................... 3.0 3.0

K3.13 Reactor water sampling system ........................................... 2.5 2.5

K3.14 Primary containment integrity: Plant-Specific .............................. 3.5 3.5

K4. Knowledge of RECIRCULATION System design feature(s)

and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 2/3 core coverage: Plant-Specific ........................................ 3.9 3.9

K4.02 Adequate recirculation pump NPSH ....................................... 3.1 3.2

K4.03 Recirculation pump motor cooling ........................................ 2.8 2.8

K4.04 Controlled seal flow .................................................... 3.0 3.1

K4.05 Seal cooling ........................................................... 2.9 2.9
3.1-19 NUREG-1123, Rev. 2 |

SYSTEM: 202001 Recirculation System

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.06 Automatic voltage/frequency regulation: PlantSpecific .............................................................. 2.6* 2.7

K4.07 Motor generator set trips: Plant-Specific .................................. 2.8 2.9

K4.08 Oil pump automatic starts: Plant-Specific .................................. 2.8 2.9

K4.09 Pump minimum flow limit: Plant-Specific ................................. 2.7 2.9

K4.10 Pump start permissives: Plant-Specific .................................... 3.3 3.4

K4.11 Limitation of recirculation pumps flow mismatch:

Plant-Specific ......................................................... 3.1 3.5

K4.12 Minimization of reactor vessel bottom head temperature

gradients: Plant-Specific ................................................ 3.2 3.5

K4.13 †End of cycle recirculation pump trip: Plant-Specific ........................ 3.7 4.0*

K4.14 ATWS: Plant-Specific .................................................. 4.0 4.1*

K4.15 Slow speed pump start: Plant-Specific ..................................... 3.1 3.4

K4.16 Recirculation pump downshift/runback: Plant-Specific ....................... 3.3 3.6

K4.17 Fast speed pump start: Plant-Specific ..................................... 3.3 3.5

K4.18 Automatic MG set start sequencing: Plant-Specific .......................... 2.8 3.0

K5. Knowledge of the operational implications of the

following concepts as they apply to RECIRCULATION

SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Indications of pump cavitation ............................................ 2.7 2.8

K5.02 Jet pump operation: BWR-3,4,5,6 ........................................ 3.1 3.2

K5.03 Pump/motor cooling: Plant-Specific ...................................... 2.7 2.7

K5.04 System venting ......................................................... 2.4 2.6

K5.05 End of cycle recirculation pump trip: Plant-Specific ......................... 3.5 3.6

K5.06 ATWS RPT: Plant-Specific .............................................. 3.6 3.7

K5.07 Natural circulation: Plant-Specific ........................................ 3.3 3.4

K5.08 E/P converters: Plant-Specific ........................................... 2.0* 2.1*

K5.09 Hydraulically operated valves: Plant-Specific ............................... 2.6* 2.6*

K5.10 Motor generator set operation: Plant-Specific .............................. 2.8* 2.8

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the RECIRCULATION SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 Jet pumps: Plant-Specific ............................................... 3.5 3.7

K6.02 Component cooling water systems ........................................ 3.1 3.2

K6.03 A.C. power: Plant-Specific .............................................. 2.9 3.0

K6.04 D.C. power: Plant-Specific .............................................. 2.7 2.8

K6.05 Control rod drive system: Plant-Specific .................................. 2.7 2.8

K6.06 Recirculation system motor-generator sets: PlantSpecific .............................................................. 3.1 3.1

K6.07 Feedwater flow ........................................................ 3.3 3.3

K6.08 Reactor water cleanup system ............................................ 2.3 2.3

K6.09 Reactor water level ..................................................... 3.4 3.4
NUREG-1123, Rev. 2 3.1-20 |

SYSTEM: 202001 Recirculation System

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A1. Ability to predict and/or monitor changes in

parameters associated with operating the RECIRCULATION

SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Recirculation pump flow: Plant-Specific ................................... 3.6 3.5

A1.02 Jet pump flow .......................................................... 3.4 3.4

A1.03 Core flow ............................................................. 3.6 3.6

A1.04 Reactor water level ..................................................... 3.3 3.3

A1.05 Reactor power ......................................................... 3.9 3.9

A1.06 Recirculation pump motor amps .......................................... 2.5 2.6

A1.07 Recirculation pump speed ............................................... 2.7 2.8

A1.08 Recirculation FCV position: BWR-5,6 .................................... 3.7 3.7

A1.09 Recirculation pump seal pressures ........................................ 3.3 3.3

A1.10 Recirculation seal purge flows ............................................ 2.6 2.7

A1.11 Vessel bottom head drain temperature ..................................... 2.8 2.9

A1.12 Recirculation pump differential pressure: PlantSpecific .............................................................. 2.6 2.6

A1.13 Recirculation loop temperatures: Plant-Specific ............................ 3.1 3.2

A1.14 Recirculation drive motor temperature:

Plant-Specific .......................................................... 2.4 2.4

A1.15 Recirculation MG set temperatures: Plant-Specific .......................... 2.4 2.4

A1.16 Recirculation MG drive motor amps: Plant-Specific ......................... 2.3* 2.3

A1.17 Recirculation MG set generator current, power,

voltage: Plant-Specific .................................................. 2.3* 2.3

A2. Ability to (a) predict the impacts of the following on

the RECIRCULATION SYSTEM ; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 †Jet pump failure: Plant-Specific ......................................... 3.4 3.9

A2.02 Recirculation system leak ............................................... 3.7 3.9

A2.03 Single recirculation pump trip ............................................ 3.6 3.7

A2.04 Multiple recirculation pump trip .......................................... 3.7 3.8

A2.05 Inadvertent recirculation flow increase ..................................... 3.8 4.0

A2.06 Inadvertent recirculation flow decrease .................................... 3.6 3.8

A2.07 Recirculation pump speed mismatch: Plant-Specific ......................... 3.1 3.3

A2.08 Recirculation flow mismatch: Plant-Specific ............................... 3.1 3.4

A2.09 Recirculation scoop tube lockup: Plant-Specific ............................ 3.2 3.4

A2.10 †Recirculation pump seal failure .......................................... 3.5 3.9

A2.11 Low reactor water level ................................................. 3.7 3.9

A2.12 Loss of reactor feedwater ................................................ 3.6 3.8

A2.13 Carryunder ............................................................ 2.6 2.8
3.1-21 NUREG-1123, Rev. 2 |

SYSTEM: 202001 Recirculation System

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A2.14 High reactor pressure (ATWS circuitry initiation):

Plant-Specific .......................................................... 3.9 4.2* |

A2.15 End of cycle trip circuitry: Plant-Specific ................................... 3.7 3.9

A2.16 Loss of seal purge flow (CRD) ............................................ 2.9 3.1

A2.17 Loss of seal cooling water ................................................ 3.1 3.2

A2.18 Loss of motor cooling ................................................... 2.9 3.1

A2.19 Loss of A.C. power: Plant-Specific ......................................... 3.1 3.2

A2.20 Loss of D.C. power: Plant-Specific ........................................ 2.8 2.9

A2.21 †Recirculation loop temperature out of spec: PlantSpecific ............................................................... 3.3 3.7 |

A2.22 Loss of component cooling water .......................................... 3.1 3.2

A2.23 Valve closures .......................................................... 3.2 3.2

A2.24 Valve opening ........................................................... 3.1 3.1

A2.25 Recirculation flow control valve lockup: PlantSpecific ............................................................... 3.3 3.3

A2.26 Incomplete start sequence: Plant-Specific .................................. 2.9 3.1

A3. Ability to monitor automatic operations of the

RECIRCULATION SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation ......................................................... 3.1 3.1

A3.02 Pump/MG set start sequence: Plant-Specific ................................ 3.1 3.0

A3.03 System flow ............................................................ 3.2 3.2

A3.04 Lights and alarms ........................................................ 3.2 3.1

A3.05 Pump speed: Plant-Specific .............................................. 2.9 2.9

A3.06 Flow control valve position: BWR-5,6 ..................................... 3.6 3.6

A3.07 Pump trips: Plant-Specific ............................................... 3.3 3.3

A3.08 Pump downshift: BWR-5,6 ............................................... 3.4 3.3

A3.09 MG set trip: Plant-Specific ............................................... 3.3 3.3

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Recirculation pumps ..................................................... 3.7 3.7

A4.02 System valves ........................................................... 3.5 3.4

A4.03 Reactor power .......................................................... 4.1 4.1

A4.04 System flow ............................................................ 3.7 3.7

A4.05 Lights and alarms ........................................................ 3.3 3.3

A4.06 Oil pumps .............................................................. 2.7 2.7

A4.07 Vent fans: Plant-Specific ................................................. 2.4 2.3

A4.08 Motor-generator sets: Plant-Specific ...................................... 3.2 3.1

A4.09 Reactor water level ...................................................... 3.7 3.7

A4.10 Seal flow: Plant-Specific ................................................. 2.8 2.8

A4.11 Seal pressures: Plant-Specific ............................................ 3.2 3.3

A4.12 Core flow .............................................................. 3.9 3.8

A4.13 Core differential pressure ................................................ 3.1 3.3
NUREG-1123, Rev. 2 3.1-22 |

SYSTEM: 201005 Rod Control and Information System (RCIS)

TASK: Operate control rods using "single notch" mode 

Operate control rods using "notch override" 

Conduct "emergency rod in" control rod insertion 

Operate control rod drive system to bring the reactor critical 

Operate the control rod drive system manually at power 

Operate the control rod drive system to shutdown the reactor 

Conduct control rod operability test 

Conduct refueling interlocks functional test/control rod drive maintenance test 

Conduct CRD hydraulics valve testing during cold shutdown 

Conduct rod sequence control test 

Conduct rod sequence control integrity test 

Perform control rod drive stall flow testing (CRD 18-month accumulator operability test) 

Startup the rod position indication system 

Perform a position indication alignment during a reactor startup 

Monitor the rod position indication system 

Shutdown the rod position indication system (RPIS)

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between ROD CONTROL AND

INFORMATION SYSTEM (RCIS) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Neutron monitoring system: BWR-6 ....................................... 3.3 3.3

K1.02 Reactor/turbine pressure control system: BWR-6 ............................ 3.3 3.5

K1.03 Control rod drive system: BWR-6 ......................................... 3.7 3.7

K1.04 Rod position information system: BWR-6 .................................. 3.7 3.7

K1.05 Rod action control system: BWR-6 ........................................ 3.5 3.5

K1.06 Rod gang drive system: BWR-6 ........................................... 3.3 3.3

K1.07 Rod interface system: BWR-6 ............................................ 3.3 3.3

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 A.C. electrical power: BWR-6 ............................................ 2.4 2.6

K3. Knowledge of the effect that a loss or malfunction of

the ROD CONTROL AND INFORMATION SYSTEM (RCIS) will

have on following:

(CFR: 41.7 / 45.4)

K3.01 Control rod drive system: BWR-6 ......................................... 3.3 3.7

K3.02 Reactor startup: BWR-6 ................................................. 3.5 3.5

K3.03 Reactor shutdown: BWR-6 ............................................... 3.0 3.2

K3.04 †FlUX shaping: BWR-6 .................................................. 3.0 3.3
3.1-23 NUREG-1123, Rev. 2 |

SYSTEM: 201005 Rod Control and Information System (RCIS)

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4. Knowledge of ROD CONTROL AND INFORMATION SYSTEM (RCIS)

design feature(s) and/or interlocks which provide for

the following:

(CFR: 41.7)

K4.01 Limiting the effects of a control Rod accident: BWR-6 ....................... 3.2 3.2

K4.02 Bank position withdrawal sequence (BPWS): BWR-6 ........................ 3.3 3.3

K4.03 Rod withdrawal block signals: BWR-6 ..................................... 3.5 3.5

K4.04 Rod insertion block signals: BWR-6 ...................................... 3.5 3.5

K4.05 Rod withdrawal limiter: BWR-6 .......................................... 3.5 3.5

K4.06 Rod pattern controller rod blocks: BWR-6 ................................. 3.5 3.5

K5. Knowledge of the operational implications of the

following concepts as they apply to ROD CONTROL AND

INFORMATION SYSTEM (RCIS) :

(CFR: 41.5 / 45.3)

K5.01 †Rod pattern and program development: BWR-6 ............................ 2.3 3.2

K5.02 Rod pattern controller (RPC): BWR-6 .................................... 2.8 3.3

K5.03 Rod groups: BWR-6 .................................................... 2.3 2.7

K5.04 †Rod sequences: BWR-6 ............................................... 2.7 3.0

K5.05 Rod density: BWR-6 ................................................... 2.7 3.0

K5.06 Target rod pattern: BWR-6 .............................................. 2.8 2.8

K5.07 Low power alarm point: BWR-6 .......................................... 3.5 3.5

K5.08 Transition zone: BWR-6 ................................................ 3.2 3.5

K5.09 High power setpoints BWR-6 ............................................ 3.5 3.5 |

K5.10 Rod withdrawal limiter: BWR-6 .......................................... 3.2 3.3

K5.11 Control rod motion: BWR-6 ............................................. 3.3 3.3

K5.12 Command word generation and sequencing (operator

follow, scan and test): BWR-6 ........................................... 1.8* 2.2*

K5.13 Position indication probes: BWR-6 ....................................... 2.5 2.7

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the ROD CONTROL AND

INFORMATION SYSTEM (RCIS) :

(CFR: 41.7 / 45.7)

K6.01 First stage shell pressure or opening of a bypass

valve(s): BWR-6 ....................................................... 3.2 3.2

K6.02 Rod position signal: BWR-6 ............................................. 3.2 3.3

K6.03 A.C. electrical power: BWR-6 ........................................... 2.5 2.8

K6.04 IRM channel: BWR-6 .................................................. 3.0 3.2

K6.05 SRM channel: BWR-6 .................................................. 3.0 3.2

K6.06 APRM channel: BWR-6 ................................................ 3.0 3.0
NUREG-1123, Rev. 2 3.1-24 |

SYSTEM: 201005 Rod Control and Information System (RCIS)

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A1. Ability to predict and/or monitor changes in

parameters associated with operating the ROD CONTROL

AND INFORMATION SYSTEM (RCIS) controls including:

(CFR: 41.5 / 45.5)

A1.01 First stage shell pressure/turbine load: BWR-6 .............................. 3.2 3.3

A2. Ability to (a) predict the impacts of the following on

the ROD CONTROL AND INFORMATION SYSTEM (RCIS) ; and

(b) based on those predictions, use procedures to

correct, control, or mitigate the consequences of

those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 High flux (SRM, IRM, APRM): BWR-6 .................................... 3.5 3.5

A2.02 Position indication probe failure: BWR-6 ................................... 2.8 3.2

A2.03 Insert block: BWR-6 .................................................... 3.2 3.2

A2.04 Withdraw block: BWR-6 ................................................. 3.2 3.2

A2.05 Insert required: BWR-6 .................................................. 3.2 3.2

A2.06 Insert inhibit: BWR-6 ................................................... 3.2 3.2

A2.07 Withdraw inhibit: BWR-6 ................................................ 3.2 3.2

A2.08 LPRM upscale/down scale: BWR-6 ........................................ 3.2 3.2

A2.09 Test display blinking: BWR-6 ............................................. 2.8 3.0

A2.10 Data fault: BWR-6 ...................................................... 2.8 3.0

A2.11 Accumulator fault: BWR-6 ............................................... 3.3 3.5

A2.12 Rod uncoupled: BWR-6 .................................................. 3.7 3.8

A2.13 Rod drift: BWR-6 ....................................................... 3.8 3.8

A3. Ability to monitor automatic operations of the ROD

CONTROL AND INFORMATION System (RCIS) including:

(CFR: 41.7 / 45.7)

A3.01 Operator control module lights: BWR-6 .................................... 3.5 3.5

A3.02 Rod display module lights: BWR-6 ........................................ 3.5 3.5

A3.03 †Verification of proper functioning/ operability:

BWR-6 ................................................................ 3.4 3.3

A3.04 Annunciator and alarm signals: BWR-6 ..................................... 3.3 3.3

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Operator control module (lights and push buttons):

| BWR-6 ................................................................ 3.7 3.7

A4.02 Rod display module (lights and push buttons): BWR-6 . ........................ 3.7 3.7

A4.03 Back panel indicating lights: BWR-6 ....................................... 3.4 3.3
3.1-25 NUREG-1123, Rev. 2 |

SYSTEM: 211000 Standby Liquid Control System

TASK: Perform lineups on the standby liquid control system 

Charge the standby liquid control tank 

Place the standby liquid control system in standby readiness 

Monitor the standby liquid control system 

Inject poison solution into the reactor vessel 

Purge the standby liquid control tank level indicator 

Perform standby liquid control recirculation test 

Perform standby liquid control relief valve test 

Perform standby liquid control and demineralized water injection reactor vessel test 

Perform standby liquid control explosive valve inspection 

Perform standby liquid control component inoperable test

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between STANDBY LIQUID CONTROL

SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Core spray line break detection: Plant-Specific ............................. 3.0* 3.3*

K1.02 Core plate differential pressure indication .................................. 2.7 2.7

K1.03 Plant air systems: Plant-Specific ......................................... 2.5 2.6

K1.04 Demineralized water/ condensate storage system ............................ 2.2* 2.3*

K1.05 RWCU ............................................................... 3.4 3.6

K1.06 Reactor vessel ......................................................... 3.7 3.7

K1.07 Jet pump differential pressure indication: PlantSpecific .............................................................. 2.6 2.6

K1.08 CRD drive and cooling water differential pressure

indication ............................................................. 2.3* 2.4*

K1.09 Core spray system: Plant-Specific ........................................ 3.2* 3.4*

K1.10 HPCI: Plant-Specific ................................................... 2.8* 3.0*

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 SBLC pumps .......................................................... 2.9* 3.1*

K2.02 Explosive valves ........................................................ 3.1* 3.2*

K2.03 Heater power .......................................................... 2.2* 2.4*

K3. Knowledge of the effect that a loss or malfunction of

the STANDBY LIQUID CONTROL SYSTEM will have on

following:

(CFR: 41.7 / 45.4)

K3.01 †Ability to shutdown the reactor in certain conditions ......................... 4.3* 4.4*

K3.02 Core spray line break detection system: PlantSpecific ............................................................... 3.0* 3.2*

K3.03 Core plate differential pressure indication .................................. 2.6* 2.7*
NUREG-1123, Rev. 2 3.1-26 |

SYSTEM: 211000 Standby Liquid Control System

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3.04 Jet pump differential pressure indication: BWR3,4,5,6 ................................................................ 2.4* 2.5*

K3.05 CRD drive and cooling water differential pressure

| indication ............................................................. 2.3* 2.3*

K4. Knowledge of STANDBY LIQUID CONTROL SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Zero leakage to the reactor (squib valves) .................................. 3.1 3.2

K4.02 Component and system testing ............................................ 3.0 3.2

K4.03 Keeping sodium pentaborate in solution .................................... 3.8 3.9

K4.04 Indication of fault in explosive valve firing circuits

...................................................................... 3.8 3.9

K4.05 Dispersal of boron upon injection into the vessel ............................ 3.4 3.6

K4.06 Core plate differential pressure indication .................................. 2.6 2.7

K4.07 RWCU isolation ....................................................... 3.8* 3.9*

K4.08 System initiation upon operation of SBLC control

switch ................................................................ 4.2* 4.2*

K4.09 Dampening of positive displacement pump discharge

oscillations (accumulators): Plant-Specific ................................ 2.5* 2.5*

K4.10 Over pressure protection ................................................ 2.8 3.1

K5. Knowledge of the operational implications of the

following concepts as they apply to STANDBY LIQUID

CONTROL SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Effects of the moderator temperature coefficient of

reactivity on the boron .................................................. 2.7 2.9

K5.02 Chugging (as it pertains to boron mixing) ................................... 2.8 3.0

K5.03 Shutdown margin ....................................................... 3.2 3.5

K5.04 Explosive valve operation ................................................ 3.1 3.2

K5.05 Accumulator operation: Plant-Specific .................................... 2.5* 2.5

K5.06 Tank level measurement ................................................. 3.0 3.2

K5.07 Tank heater operation ................................................... 2.7 2.9

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the STANDBY LIQUID CONTROL

SYSTEM :

(CFR: 41.7 / 45.7)

| K6.01 Plant air systems: Plant-Specific ......................................... 2.4* 2.4*

| K6.02 Demineralized water storage system ....................................... 1.9* 2.0*

K6.03 A.C. power ............................................................ 3.2 3.3

| K6.04 Core spray system: Plant-Specific ........................................ 2.7* 2.8*

| K6.05 HPCI system: Plant-Specific ............................................ 2.7* 2.7*
3.1-27 NUREG-1123, Rev. 2 |

SYSTEM: 211000 Standby Liquid Control System

Tasks as noted previously

IMPORTANCE 

K/A NO. ABILITY RO SRO

A1. Ability to predict and/or monitor changes in

parameters associated with operating the STANDBY

LIQUID CONTROL SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Tank level ............................................................. 3.6 3.7

A1.02 Explosive valve indication ............................................... 3.8 3.9

A1.03 Pump discharge pressure ................................................ 3.6 3.6

A1.04 Valve operations ....................................................... 3.6 3.7

A1.05 Pump amps: Plant-Specific .............................................. 2.7* 2.8*

A1.06 Flow indication: Plant-Specific .......................................... 3.8 3.9

A1.07 Reactor power ......................................................... 4.3* 4.4*

A1.08 RWCU system lineup ................................................... 3.7 3.8

A1.09 SBLC system lineup .................................................... 4.0* 4.1

A1.10 Lights and alarms ....................................................... 3.7 3.7

A2. Ability to (a) predict the impacts of the following on

the STANDBY LIQUID CONTROL SYSTEM ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Pump trip ............................................................. 3.5 3.8*

A2.02 Failure of explosive valve to fire .......................................... 3.6 3.9*

A2.03 A.C. power failures ..................................................... 3.2 3.4*

A2.04 Inadequate system flow .................................................. 3.1* 3.4*

A2.05 Loss of SBLC tank heaters ............................................... 3.1 3.4

A2.06 Valve openings ......................................................... 3.1 3.3

A2.07 Valve closures ......................................................... 2.9 3.2

A2.08 Failure to SCRAM ...................................................... 4.1* 4.2*

A3. Ability to monitor automatic operations of the STANDBY

LIQUID CONTROL SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Pump discharge pressure: Plant-Specific .................................. 3.5 3.5

A3.02 Tank level: Plant-Specific ............................................... 3.9 3.9

A3.03 Explosive valves indicating lights: Plant-Specific ............................ 3.8 3.8

A3.04 Reactor power: Plant-Specific ........................................... 4.3* 4.4*

A3.05 Flow indication: Plant-Specific .......................................... 4.1* 4.2*

A3.06 RWCU system isolation: Plant-Specific ................................... 4.0* 4.1*

A3.07 Lights and alarms: Plant-Specific ......................................... 3.7 3.6

A3.08 System initiation: Plant-Specific ......................................... 4.2* 4.2*
NUREG-1123, Rev. 2 3.1-28 |

SYSTEM: 211000 Standby Liquid Control System

Tasks as noted previously

A4. Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

IMPORTANCE 

K/A NO. ABILITY RO SRO

A4.01 Tank level ............................................................. 3.9 3.9

A4.02 SBLC control switch .................................................... 4.2* 4.2*

A4.03 Explosive valves firing circuit status ....................................... 4.1 4.1

A4.04 Reactor power ......................................................... 4.5* 4.6*

| A4.05 Flow indication: Plant-Specific .......................................... 4.1* 4.0

| A4.06 RWCU system isolation ................................................. 3.9* 3.9

A4.07 Lights and alarms ....................................................... 3.6 3.6

A4.08 System initiation: Plant-Specific ......................................... 4.2* 4.2*
3.1-29 NUREG-1123, Rev. 2 |

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3.2-1 NUREG-1123, Rev. 2 |

3.2 Reactor Water Inventory Control page

206000 High Pressure Coolant Injection System 3.2-3

209002 High Pressure Core Spray System 3.2-8

209001 Low Pressure Core Spray System 3.2-12

256000 Reactor Condensate System 3.2-16

217000 Reactor Core Isolation Cooling System 3.2-21

259001 Reactor Feedwater System 3.2-25

204000 Reactor Water Cleanup System 3.2-29

259002 Reactor Water Level Control System 3.2-33

203000 Residual Heat Removal /Low Pressure Coolant Injection: 3.2-38

Injection Mode (Plant Specific)
NUREG-1123, Rev. 2 3.2-2 |

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3.2-3 NUREG-1123, Rev. 2 |

SYSTEM: 206000 High Pressure Coolant Injection System

TASK: Place the high pressure (Feedwater) coolant injection system (FWCI) in standby readiness

Monitor the high pressure (feedwater) coolant injection system operation

Return the high pressure (feedwater) coolant injection system to stand-by readiness after automatic

initiation

Perform lineups of the high pressure coolant injection system (write in)

Manually initiate high pressure coolant injection

Perform high pressure coolant injection (HPCI) simulated automatic actuation test

Perform high pressure (feedwater) coolant injection flow rate test

Perform high pressure (feedwater) coolant injection (HPCI) pump operability test

Perform high pressure (feedwater) coolant injection motor operated valve operability test

Perform HPCI subsystem logic system functional test

Perform HPCI subsystem automatic isolation logic system functional test

Perform HPCI system inoperable test

Perform HPCI turbine overspeed test

Perform high pressure (feedwater) coolant injection operability test when reactor core isolation cooling

is inoperable

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between HIGH PRESSURE COOLANT

INJECTION SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor vessel: BWR-2,3,4 .............................................. 3.8 3.9

K1.02 Reactor water level: BWR-2,3,4 .......................................... 4.0 4.1* |

K1.03 Reactor pressure: BWR-2,3,4 ............................................ 3.8 3.8 |

K1.04 Reactor feedwater system: BWR-2,3,4 .................................... 3.6 3.6

K1.05 Condensate storage system: BWR-2,3,4 ................................... 3.7 3.7 |

K1.06 Suppression chamber: BWR-2,3,4 ........................................ 3.7 3.7 |

K1.07 D.C. power: BWR-2,3,4 ................................................. 3.7* 3.8* |

K1.08 A.C. power: BWR-2,3,4 ................................................. 3.0* 3.1* |

K1.09 ECCS keep fill system: BWR-2,3,4(P-Spec) ................................ 4.0* 4.0 |

K1.10 Condensate storage and transfer system: BWR-2,3,4 ......................... 3.4 3.4

K1.11 PCIS: BWR-2,3,4 ...................................................... 3.5 3.5

K1.12 Nuclear boiler instrumentation: BWR-2,3,4 ................................ 3.4 3.4 |

K1.13 Main condenser: BWR-2,3,4(P-Spec) ..................................... 2.8* 2.9* |

K1.14 SBGT: BWR-2,3,4(P-Spec) .............................................. 2.9 3.1

K1.15 Plant air systems: BWR-2,3,4 ............................................ 2.3* 2.3* |

K1.16 Containment/Torus pressure: BWR-2,3,4 .................................. 3.5 3.5 |
NUREG-1123, Rev. 2 3.2-4 |

SYSTEM: 206000 High Pressure Coolant Injection System

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 System valves: BWR-2,3,4 .............................................. 3.2* 3.3*

K2.02 System pumps: BWR-2,3,4 .............................................. 2.8* 3.1*

K2.03 Initiation logic: BWR-2,3,4 ............................................. 2.8* 2.9*

K2.04 Turbine control circuits: BWR-2,3,4 ...................................... 2.5* 2.7*

K3. Knowledge of the effect that a loss or malfunction of

the HIGH PRESSURE COOLANT INJECTION SYSTEM will have

on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level control: BWR-2,3,4 ................................... 4.0 4.0

K3.02 Reactor pressure control: BWR-2,3,4 ..................................... 3.8* 3.8*

K3.03 Suppression pool level control: BWR-2,3,4 ................................ 3.4* 3.5*

K4. Knowledge of HIGH PRESSURE COOLANT INJECTION SYSTEM

design feature(s) and/or interlocks which provide for

the following:

(CFR: 41.7)

K4.01 Turbine trips: BWR-2,3,4 ............................................... 3.8 3.9

K4.02 System isolation: BWR-2,3,4 ............................................ 3.9 4.0

K4.03 Resetting turbine trips: BWR-2,3,4 ....................................... 4.2 4.1

K4.04 Resetting system isolations: BWR-2,3,4 ................................... 4.0 3.9

K4.05 Preventing water hammer in turbine exhaust line

(procedural control): BWR-2,3,4 ......................................... 3.1 3.4

K4.06 Preventing water hammer in pump discharge line

(procedural control ): BWR-2, 3, 4 ....................................... 3.2 3.4

K4.07 Automatic system initiation: BWR-2,3,4 .................................. 4.3* 4.3

K4.08 Manual system initiation: BWR-2,3,4 ..................................... 4.2* 4.3

K4.09 Automatic flow control: BWR-2,3,4 ...................................... 3.8 3.9

K4.10 Surveillance for all operable components: BWR-2,3,4 . ....................... 3.7 3.8

K4.11 Turbine speed control: BWR-2,3,4 ....................................... 3.4 3.5

K4.12 Condensation of shaft sealing steam: BWR-2,3,4 ........................... 2.9 3.0

K4.13 Turbine and pump lubrication: BWR-2,3,4 ................................. 3.0 3.1

K4.14 Control oil to turbine speed controls: BWR-2,3,4 ........................... 3.4 3.4

K4.15 Low speed turning of the turbine rotor: BWR-2,3,4(PSpec) ................................................................. 3.2 3.2

K4.16 Minimizing fission product concentration in the

condensate storage tank (valve closures on system

initiation): BWR-2,3,4(P-Spec) .......................................... 3.1 3.3

K4.17 Protection against draining the condensate storage

tank to the suppression pool: BWR-2,3,4 .................................. 3.4 3.4

K4.18 Pump minimum flow: BWR-2,3,4 ........................................ 3.2 3.3

K4.19 Automatic transfer of HPCI pump suction: BWR-2,3,4 ....................... 3.7 3.8
3.2-5 NUREG-1123, Rev. 2 |

SYSTEM: 206000 High Pressure Coolant Injection System

Tasks as noted previously

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K5. Knowledge of the operational implications of the

following concepts as they apply to HIGH PRESSURE

COOLANT INJECTION SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Turbine operation: BWR-2,3,4 ........................................... 3.3 3.4

K5.02 Turbine shaft sealing: BWR-2,3,4 ......................................... 2.8 2.9

K5.03 GEMAC controllers: BWR-2,3,4(P-Spec) .................................. 3.1 3.1

K5.04 Indications of pump cavitation: BWR-2,3,4 ................................. 2.6* 2.7* |

K5.05 Turbine speed control: BWR-2,3,4 ........................................ 3.3 3.3

K5.06 Turbine speed measurement: BWR-2,3,4 ................................... 2.6* 2.6

K5.07 System venting: BWR-2,3,4 .............................................. 2.8 2.8

K5.08 Vacuum breaker operation: BWR-2,3,4 .................................... 3.0 3.2

K5.09 Testable check valve operation: BWR-2,3,4 ................................. 2.7* 2.8

K5.10 Assist core cooling: BWR-2,3,4 .......................................... 3.5 3.5

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the HIGH PRESSURE COOLANT

INJECTION SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 Plant air systems: BWR-2,3,4 ............................................ 2.3* 2.3* |

K6.02 D.C. power: BWR-2,3,4 ................................................. 3.3 3.7* |

K6.03 A.C. power: BWR-2,3,4 ................................................. 2.9 3.1* |

K6.04 Condensate storage tank level: BWR-2,3,4 ................................. 3.5 3.7

K6.05 Suppression pool level: BWR-2,3,4 ....................................... 3.5 3.7

K6.06 SBGTS: BWR-2,3,4(P-Spec) ............................................. 3.1 3.2

K6.07 ECCS keep fill system: BWR-2,3,4(P-Spec) ................................ 3.4 3.4

K6.08 Reactor pressure: BWR-2,3,4 ............................................ 3.8 3.8

K6.09 Condensate storage and transfer system: BWR-2,3,4 ......................... 3.5 3.5

K6.10 PCIS: BWR-2,3,4 ...................................................... 3.8 4.0

K6.11 Nuclear boiler instrumentation: BWR-2,3,4 ................................ 3.6 3.7

K6.12 Reactor water level: BWR-2,3,4 .......................................... 4.2* 4.3* |

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the HIGH PRESSURE

COOLANT INJECTION SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor water level: BWR-2,3,4 .......................................... 4.3* 4.4* |

A1.02 Reactor pressure: BWR-2,3,4 ............................................ 4.2* 4.2

A1.03 Condensate storage tank level: BWR-2,3,4 ................................. 3.5 3.6

A1.04 Suppression pool level: BWR-2,3,4 ....................................... 3.7 3.8

A1.05 Suppression pool temperature: BWR-2,3,4 ................................. 4.1 4.2

A1.06 System flow: BWR-2,3,4 ................................................ 3.8 3.7

A1.07 System discharge pressure: BWR-2,3,4 .................................... 3.7 3.6

A1.08 System lineup: BWR-2,3,4 ............................................... 4.1* 4.0
NUREG-1123, Rev. 2 3.2-6 |

SYSTEM: 206000 High Pressure Coolant Injection System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A1.09 Turbine speed: BWR-2,3,4 .............................................. 3.5 3.4

A2. Ability to (a) predict the impacts of the following on

the HIGH PRESSURE COOLANT INJECTION SYSTEM ; and (b)

based on those predictions, use procedures to correct,

control, or mitigate the consequences of those

abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Turbine trips: BWR-2,3,4 ................................................ 4.0 4.0

A2.02 Valve closures: BWR-2,3,4 .............................................. 3.5 3.5

A2.03 Valve openings: BWR-2,3,4 .............................................. 3.5 3.5

A2.04 A.C. failures: BWR-2,3,4 ................................................ 2.7* 3.0*

A2.05 D.C. failures: BWR-2,3,4 ................................................ 3.5 3.8*

A2.06 Inadequate system flow: BWR-2,3,4 ....................................... 3.3 3.5

A2.07 Low suppression pool level: BWR-2,3,4 ................................... 3.4 3.6

A2.08 †High suppression pool temperature: BWR-2,3,4 ............................ 3.9 4.2

A2.09 †Low condensate storage tank level: BWR-2,3,4 ............................ 3.5 3.7

A2.10 System isolation: BWR-2,3,4 ............................................ 4.0 4.1

A2.11 Low reactor water level: BWR-2,3,4 ...................................... 4.1 4.2

A2.12 Loss of room cooling: BWR-2,3,4 ........................................ 3.4 3.5

A2.13 Loss of applicable plant air systems: BWR-2,3,4 ............................ 2.4* 2.4*

A2.14 Flow controller failure: BWR-2,3,4 ....................................... 3.3 3.4

A2.15 Loss of control oil pressure: BWR-2,3,4 ................................... 3.4 3.5

A2.16 High drywell pressure: BWR-2,3,4 ........................................ 4.0 4.1

A2.17 †HPCI inadvertent initiation: BWR-2,3,4 ................................... 3.9 4.3*

A3. Ability to monitor automatic operations of the HIGH

PRESSURE COOLANT INJECTION SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Turbine speed: BWR-2,3,4 ............................................... 3.6 3.5

A3.02 System Flow: BWR-2,3,4 ................................................ 3.8 3.8

A3.03 System lineup: BWR-2,3,4 ............................................... 3.9 3.8

A3.04 Reactor pressure: BWR-2,3,4 ............................................ 4.2* 4.1

| A3.05 Reactor water level: BWR-2,3,4 .......................................... 4.3* 4.3*

A3.06 System discharge pressure: BWR-2,3,4 .................................... 3.8 3.8

A3.07 Lights and alarms: BWR-2,3,4 ............................................ 3.9 3.8

A3.08 Condensate storage tank level: BWR-2,3,4 ................................. 3.7 3.6

A3.09 Response to system isolation: BWR-2,3,4 .................................. 4.2* 4.1

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Turbine speed controls: BWR-2,3,4 ....................................... 3.8 3.7

A4.02 Flow controller: BWR-2,3,4 ............................................. 4.0* 3.8
3.2-7 NUREG-1123, Rev. 2 |

SYSTEM: 206000 High Pressure Coolant Injection System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A4.03 Turbine temperatures: BWR-2,3,4 ........................................ 3.1 3.0

A4.04 Major system valves: BWR-2,3.4 ......................................... 3.7 3.7

A4.05 Reactor water level: BWR-2,3,4 .......................................... 4.4* 4.4*

A4.06 Reactor pressure: BWR-2,3,4 ............................................ 4.3* 4.3*

A4.07 Condensate storage tank level: BWR-2,3,4 ................................. 3.5 3.5

A4.08 Suppression pool temperature: BWR-2,3,4 ................................. 4.1* 4.1

A4.09 Suppression pool level: BWR-2,3,4 ....................................... 3.8 3.7

A4.10 System pumps: BWR-2,3,4 .............................................. 3.7 3.5

A4.11 Turning gear: BWR-2,3,4(P-Spec) ........................................ 3.0 3.0

A4.12 Turbine trip controls: BWR-2,3,4 ......................................... 4.0 3.9

A4.13 Turbine reset control: BWR-2,3,4 ......................................... 4.1* 4.0

A4.14 System auto start control: BWR-2,3,4(P-Spec) .............................. 4.2* 4.1
NUREG-1123, Rev. 2 3.2-8 |

SYSTEM: 209002 High Pressure Core Spray System (HPCS)

TASK: Perform lineups on the core spray system

Place core spray (CS) system in standby readiness

Monitor automatic operation of core spray system

Shutdown core spray cooling system

Perform core spray simulated automatic actuation test

Perform core spray pump operability test

Perform core spray system inop test

Conduct core spray - cold shutdown valve testing

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between HIGH PRESSURE CORE SPRAY

SYSTEM (HPCS) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Condensate transfer and storage system: BWR-5,6 ........................... 3.4 3.4

K1.02 Suppression Pool: BWR-5,6 ............................................. 3.5 3.5

K1.03 Water leg (jockey) pump: BWR-5,6 ....................................... 3.0 3.0

K1.04 HPCS diesel generator: BWR-5,6 ......................................... 3.8 3.8

K1.05 Standby liquid control system: Plant-Specific ............................... 2.8 2.8

K1.05 Suppression pool cleanup system: BWR-5,6 ................................ 2.0* 2.0

K1.07 ECCS room coolers: BWR-5,6 ........................................... 2.4 2.4

K1.08 Component cooling water systems: BWR-5,6 ............................... 2.4 2.6

K1.09 Leak detection: BWR-5,6 ................................................ 2.5 2.5

K1.10 Suppression pool suction strainers: BWR-5,6 ............................... 2.1* 2.1

K1.11 Adequate core cooling: BWR-5,6 ......................................... 3.8 4.0

Kl.12 Reactor vessel: BWR-5,6 ................................................ 3.4 3.6

K1.13 Instrument nitrogen: BWR-5,6 ........................................... 2.7 2.7

K1.14 Plant air systems: BWR-5,6 .............................................. 2.6 2.6

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Pump electrical power: BWR-5,6 ......................................... 3.2 3.3

K2.02 Valve electrical power: BWR-5,6 ......................................... 2.8 2.9

K2.03 Initiation logic: BWR-5,6 ................................................ 2.8 2.9

K3. Knowledge of the effect that a loss or malfunction of

the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) will have

on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level: BWR-5,6 ............................................ 3.9 3.9

K3.02 Standby liquid control system: Plant-Specific ............................... 3.3 3.3

K3.03 Adequate core cooling: BWR-5,6 ......................................... 3.9 4.1
3.2-9 NUREG-1123, Rev. 2 |

SYSTEM: 209002 High Pressure Core Spray System (HPCS)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4. Knowledge of HIGH PRESSURE CORE SPRAY SYSTEM (HPCS)

design feature(s) and/or interlocks which provide for

the following:

(CFR: 41.7)

K4.01 Prevents water hammer: BWR-5,6 ........................................ 2.9 3.0

K4.02 Prevents over filling reactor vessel: Plant-Specific. .......................... 3.4 3.5

K4.03 Prevents pump over heating: BWR-5,6 ..................................... 2.3* 2.4

K4.04 Testable check valve operation: BWR-5,6 .................................. 2.3* 2.3*

K4.05 Motor operated valve operation: BWR-5,6 ................................. 2.4 2.4

K4.06 Centrifugal pump operation: BWR-5,6 ..................................... 2.3* 2.4*

K4.07 Override of reactor water level interlock: PlantSpecific ............................................................... 3.5 3.7

K5. Knowledge of the operational implications of the

following concepts as they apply to HIGH PRESSURE CORE

SPRAY SYSTEM (HPCS):

(CFR: 41.5 / 45.3)

K5.01 Indications of pump cavitation: BWR-5,6 ................................... 2.5 2.8

K5.02 Heat removal (transfer) mechanism: BWR-5,6 .............................. 2.6 2.7

K5.03 System venting: BWR-5,6 ............................................... 2.4 2.4

K5.04 Adequate core cooling: BWR-5,6 ......................................... 3.8 4.0

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the HIGH PRESSURE CORE

SPRAY SYSTEM (HPCS):

(CFR: 41.7 / 45.7)

K6.01 Electrical power: BWR-5,6 .............................................. 3.6 3.6

K6.02 Condensate storage tank water level: BWR-5,6 .............................. 3.4 3.4

K6.03 Component cooling water systems: BWR-5,6 ............................... 2.5 2.6

K6.04 Suppression pool suction strainer: BWR-5,6 ................................ 2.5 2.5

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the HIGH PRESSURE

CORE SPRAY SYSTEM (HPCS) controls including:

(CFR: 41.5 / 45.5)

A1.01 HPCS flow: BWR-5,6 ................................................... 3.6 3.7

A1.02 HPCS pressure: BWR-5,6 ............................................... 3.4 3.6

A1.03 Reactor water level: BWR-5,6 ............................................ 3.7 3.7

A1.04 Reactor pressure: BWR-5,6 .............................................. 3.3 3.3

A1.05 Suppression pool water level: BWR-5,6 .................................... 3.3 3.4

A1.06 Motor amps: BWR-5,6 .................................................. 1.9* 2.3*

A1.07 Diesel loading: BWR-5,6 ................................................ 2.5* 2.8

A1.08 System lineup: BWR-5,6 ................................................ 3.1 3.3
NUREG-1123, Rev. 2 3.2-10 |

SYSTEM: 209002 High Pressure Core Spray System (HPCS)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A1.09 Condensate storage tank level: BWR-5,6 2.6 2.8

A2. Ability to (a) predict the impacts of the following on

the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) ; and (b)

based on those predictions, use procedures to correct,

control, or mitigate the consequences of those

abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 System initiation: BWR-5,6 ............................................... 3.8 3.8

A2.02 Pump trips: BWR-5,6 .................................................... 3.6 3.7

A2.03 Valve closures: BWR-5,6 ................................................. 3.2 3.4

A2.04 A.C. electrical failure: BWR-5,6 ........................................... 3.1 3.2

A2.05 D.C. electrical failure: BWR-5,6 ........................................... 2.8 2.9

A2.06 Core spray line break: BWR-5,6 ........................................... 3.4 3.6

A2.07 Pump seal failure: BWR-5,6 .............................................. 2.6 3.0

A2.08 Inadequate system flow: BWR-5,6 ......................................... 3.1 3.2

A2.09 Loss of room cooling: BWR-5,6 ........................................... 2.4 2.6

A2.10 Valve openings: BWR-5,6 ................................................ 2.7 3.0

A2.11 Low suppression pool level: BWR-5,6 ..................................... 3.3 3.5

A2.12 High suppression pool level BWR-5,6 ....................................... 3.3 3.5

A2.13 Low condensate storage tank level BWR-5,6 ................................. 3.4 3.5

A2.14 High suppression pool temperature: BWR-5,6 ............................... 3.0 3.3

A2.15 Clogged suppression pool suction strainers: BWR-5,6. ........................ 2.4 2.6

A3. Ability to monitor automatic operations of the HIGH

PRESSURE CORE SPRAY SYSTEM (HPCS) including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation: BWR-5,6 ................................................ 3.3 3.3

A3.02 Pump start: BWR-5,6 .................................................... 3.8 3.8

A3.03 System pressure: BWR-5,6 ............................................... 3.6 3.6

A3.04 System flow: BWR-5,6 ................................................... 3.7 3.7

A3.05 Reactor water level BWR-5,6 .............................................. 3.7 3.7

A3.06 Lights and alarms: BWR-5,6 .............................................. 2.8 2.8

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 HPCS pump: BWR-5,6 ................................................... 3.7 3.7

A4.02 Suction valves: BWR-5,6 ................................................. 3.6 3.6

A4.03 Injection valve: BWR-5,6 ................................................. 3.8 3.8

A4.04 Minimum flow valve: BWR-5,6 ............................................ 3.1 3.1

A4.05 Manual Initiation controls: BWR-5,6 ....................................... 3.8 3.8
3.2-11 NUREG-1123, Rev. 2 |

SYSTEM: 209002 High Pressure Core Spray System (HPCS)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A4.06 Testable check valve: BWR-5,6 2.6 2.6

A4.07 Line fill pump: BWR-5,6 2.8 2.8

A4.08 Reactor water level: BWR-5,6 3.6 3.7

A4.09 Suppression pool level: BWR-5,6 3.4 3.5

A4.10 Reactor pressure: BWR-5,6 3.3 3.3

A4.11 System flow: BWR-5,6 3.8 3.8

A4.12 System pressure: BWR-5,6 ............................................... 3.4 3.4

A4.13 Lights and alarms: BWR-5,6 .............................................. 2.6 2.6

A4.14 Test return valve: BWR-5,6 ............................................... 3.0 3.0

A4.15 Initiation reset: BWR-5,6 ................................................. 3.6 3.6
NUREG-1123, Rev. 2 3.2-12 |

SYSTEM: 209001 Low Pressure Core Spray System

TASK: Fill the core spray systems

Perform lineups on the core spray systems

Place the core spray system in standby readiness

Monitor automatic operation of the core spray system

Shutdown the core spray cooling system

Fill the reactor cavity from the condensate storage tank with the core spray system

Perform core spray pump flow rate test

Perform core spray simulated automatic actuation test

Perform core spray pump operability test

Perform core spray subsys and low pressure coolant injection subsys discharge piping ventilation

Perform core spray system inop test

Conduct core spray motor operated valve operability test

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between LOW PRESSURE CORE SPRAY

SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Condensate storage tank: Plant-Specific ................................... 3.1 3.1

K1.02 Torus/suppression pool .................................................. 3.4 3.4

K1.03 Keep fill system ....................................................... 2.9 3.0

K1.04 condensate transfer system .............................................. 2.3 2.4

K1.05 Automatic depressurization system ........................................ 3.7 3.7

K1.06 Plant air systems ....................................................... 2.0* 2.1*

K1.07 D.C. electrical power ................................................... 2.5 2.7

K1.08 A.C. electrical power ................................................... 3.2 3.3

K1.09 Nuclear boiler instrumentation ........................................... 3.2 3.4

K1.10 Emergency generator ................................................... 3.7 3.8

K1.11 Drywell coolers: Plant-Specific .......................................... 2.4 2.6

K1.12 ECCS room coolers .................................................... 2.9 3.1

K1.13 Leak detection ......................................................... 2.8 3.0

K1.14 Reactor vessel ......................................................... 3.7 3.8

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Pump power ........................................................... 3.0* 3.1*

K2.02 Valve power ........................................................... 2.5* 2.7*

K2.03 Initiation logic ......................................................... 2.9* 3.1*
3.2-13 NUREG-1123, Rev. 2 |

SYSTEM: 209001 Low Pressure Core Spray System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3. Knowledge of the effect that a loss or malfunction of

the LOW PRESSURE CORE SPRAY SYSTEM will have on

following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level ..................................................... 3.8 3.9 |

K3.02 ADS logic ............................................................. 3.8 3.9

K3.03 Emergency generators .................................................. 2.9 3.0

K3.04 Component cooling water systems ........................................ 2.1* 2.2

K3.05 Drywell cooling: Plant-Specific .......................................... 2.3 2.7

K4. Knowledge of LOW PRESSURE CORE SPRAY SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Prevention of overpressurization of core spray piping ......................... 3.2 3.4

K4.02 Prevents water hammer .................................................. 3.0 3.2

K4.03 Motor cooling ......................................................... 2.4 2.5

K4.04 Line break detection .................................................... 3.0 3.2

K4.05 Pump minimum flow .................................................... 2.6 2.6

K4.06 Adequate pump net positive suction head ................................... 2.6 2.9

K4.07 Pump operability testing ................................................. 2.8 3.0

K4.08 Automatic system initiation .............................................. 3.8 4.0

K4.09 Load sequencing ....................................................... 3.3 3.5

K4.10 Testability of all operable components ..................................... 2.8 2.9

K5. Knowledge of the operational implications of the

following concepts as they apply to LOW PRESSURE CORE

SPRAY SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Indications of pump cavitation ............................................ 2.6 2.7

K5.02 Differential pressure indication ........................................... 2.4 2.6

K5.03 Testable check valve operation ............................................ 2.3 2.4

K5.04 Heat removal (transfer) mechanisms ....................................... 2.8 2.9

K5.05 System venting ......................................................... 2.5 2.5

K5.06 Recirculation operation: Plant-Specific(BWR-1) ........................... 3.7 4.0

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the LOW PRESSURE CORE SPRAY

SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 A.C. power ............................................................ 3.4 3.4

K6.02 Emergency generators .................................................. 3.8 3.9

K6.03 Torus/suppression pool water level ........................................ 3.3 3.4
NUREG-1123, Rev. 2 3.2-14 |

SYSTEM: 209001 Low Pressure Core Spray System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6.04 D.C. power ............................................................ 2.8 2.9

K6.05 ECCS room cooler(s) ................................................... 2.8 2.9

K6.06 Pump motor cooler(s) .................................................. 2.4 2.4

K6.07 Pump seal cooler(s) .................................................... 2.3 2.3

K6.08 Keep fill system ....................................................... 2.9 3.0

K6.09 Fire protection: BWR-1 ................................................ 3.0* 3.3

K6.10 ECCS room integrity: Plant-Specific ...................................... 2.3 2.5

K6.11 ADS .................................................................. 3.6 3.7

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the LOW PRESSURE

CORE SPRAY SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Core spray flow ........................................................ 3.4 3.6

A1.02 Core spray pressure ..................................................... 3.2 3.4

A1.03 Reactor water level ..................................................... 3.8 3.9

A1.04 Reactor pressure ....................................................... 3.7 3.7

A1.05 Torus/suppression pool water level ........................................ 3.5 3.6

A1.06 Motor amps ........................................................... 2.3* 2.4

A1.07 Emergency generator loading ............................................. 3.0 3.1

A1.08 System lineup .......................................................... 3.3 3.2

A2. Ability to (a) predict the impacts of the following on

the LOW PRESSURE CORE SPRAY SYSTEM ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Pump trips ............................................................ 3.4 3.4

A2.02 Valve closures ......................................................... 3.2 3.2

A2.03 A.C. failures ........................................................... 3.4 3.6

A2.04 D.C. failures ........................................................... 2.9 3.0

A2.05 Core spray line break ................................................... 3.3 3.6

A2.06 Inadequate system flow .................................................. 3.2 3.2

A2.07 Loss of room cooling ................................................... 2.6 2.8

A2.08 Valve openings ......................................................... 3.1 3.1

A2.09 Low suppression pool level .............................................. 3.1 3.3

A2.10 †High suppression pool temperature ....................................... 3.1 3.4

A2.11 †Loss of fire protection: BWR-1 ......................................... 2.8* 3.3

SYSTEM: 209001 Low Pressure Core Spray System
3.2-15 NUREG-1123, Rev. 2 |

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A3. Ability to monitor automatic operations of the LOW

PRESSURE CORE SPRAY SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation ......................................................... 3.6 3.6

A3.02 Pump start ............................................................. 3.8 3.7

A3.03 System pressure ......................................................... 3.5 3.5

A3.04 System flow ............................................................ 3.7 3.6

A3.05 Reactor water level ...................................................... 3.9 3.9

A3.06 Lights and alarms ........................................................ 3.6 3.5

A4 Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Core spray pump ........................................................ 3.8 3.6

A4.02 Suction valves .......................................................... 3.5 3.4

A4.03 Injection valves ........................................................ 3.7 3.6

A4.04 Minimal flow valves ..................................................... 2.9 2.9

A4.05 Manual initiation controls ............................................... 3.8 3.6

A4.06 Testable check valves ................................................... 2.4 2.4

A4.07 Fill pump .............................................................. 2.7 2.8

A4.08 Reactor water level ...................................................... 3.9 3.9

A4.09 Suppression pool level .................................................. 3.6 3.5

A4.10 Reactor pressure ........................................................ 3.9 3.8

A4.11 System flow ........................................................... 3.7 3.6

A4.12 System pressure ........................................................ 3.6 3.5

A4.13 Lights and alarms ....................................................... 3.4 3.4

A4.14 Containment level: BWR-1 .............................................. 3.6 3.6
NUREG-1123, Rev. 2 3.2-16 |

SYSTEM: 256000 Reactor Condensate System

TASK: Perform lineups on condensate system

Fill the condensate storage tank

Deaerate condensate system prior to startup

Fill condenser hotwells

Fill the condenser system

Cleanup the condensate system

Startup the condensate systems

Operate condensate pumps in different combinations

Operate condensate booster pumps in different combinations

Operate hotwell pumps

Operate the hotwell dump and condensate transfer pump

Monitor condensate (and feedwater) system operation

Shut down the condensate system

Operate the low pressure heaters (operate the feedwater heaters)

Operate the low/intermediate pressure heaters

Operate the intermediate pressure heaters

Operate the feedwater heaters (write in)

Operate the condensate booster pumps forced lube oil pumps (write in)

What if hotwell level is high/low?

Perform lineups of the condenser air removal system

Monitor the condenser air removal system

Operate the mechanical vacuum pump(s)

Purge the offgas line

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between REACTOR CONDENSATE SYSTEM

and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Main turbine ........................................................... 2.6 2.6

K1.02 Reactor feedwater system ................................................ 3.3 3.3

K1.03 HPCI: Plant-Specific ................................................... 3.5 3.5

K1.04 RCIC: Plant-Specific ................................................... 3.2 3.3

K1.05 CRD hydraulics system .................................................. 3.1 3.1

K1.06 Extraction steam system ................................................. 2.7 2.7

K1.07 SJAE condenser ........................................................ 2.9 2.9

K1.08 Gland seal steam condenser: Plant-Specific ................................. 2.7 2.7

K1.09 Offgas condenser: Plant-Specific ......................................... 2.9 3.0

K1.10 Exhaust hood spray system ............................................... 2.4 2.5

K1.11 Plant air systems: Plant-Specific .......................................... 2.4 2.5

K1.12 Isolation condenser: Plant-Specific ....................................... 3.3* 3.3*

K1.13 Reactor water level ...................................................... 3.5 3.5

K1.14 RHR (LPCI): Plant-Specific ............................................. 3.0 3.0

K1.15 HPCS: Plant-Specific ................................................... 3.6 3.6

K1.16 RWCU ................................................................ 2.6 2.6

K1.17 ECCS keep fill system: Plant-Specific ..................................... 2.9* 2.9
3.2-17 NUREG-1123, Rev. 2 |

SYSTEM: 256000 Reactor Condensate System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.18 Circulating water system ................................................. 2.9 3.0

K1.19 Component cooling water (secondary equipment) systems:

Plant-Specific .......................................................... 2.7 2.7

K1.20 Demineralized water storage and makeup system ............................. 2.5 2.6

K1.21 Steam seal evaporator: Plant-Specific ...................................... 2.4 2.4

K1.22 Offgas system .......................................................... 2.8 2.8

K1.23 Auxiliary steam system: Plant-Specific .................................... 2.5 2.5

K1.24 Radwaste system: Plant-Specific .......................................... 2.4 2.4

K1.25 Main steam system: Plant-Specific ........................................ 3.0 3.1

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 System pumps ......................................................... 2.7* 2.8

K2.02 Motor operated valves ................................................... 1.9* 2.0*

K3. Knowledge of the effect that a loss or malfunction of

the REACTOR CONDENSATE SYSTEM will have on following:

(CFR: 41.7 / 45.4)

K3.01 Main turbine/main generator .............................................. 3.2 3.2

K3.02 CRD hydraulics system .................................................. 3.2 3.3

K3.03 Extraction steam system ................................................. 2.6 2.6

K3.04 Reactor feedwater system ................................................ 3.6 3.7

K3.05 HPCI: Plant-Specific ................................................... 3.3 3.3

K3.06 RCIC: Plant-Specific ................................................... 3.2 3.2

K3.07 Isolation condenser: Plant-Specific ....................................... 3.0* 3.0*

K3.08 SJAE ................................................................. 2.8 2.8

K3.09 Offgas ................................................................ 2.8 2.8

K3.10 Gland seal steam system: Plant-Specific ................................... 2.5 2.5

K3.11 Reactor water level ...................................................... 3.9 3.9

K3.12 HPCS: Plant-Specific ................................................... 3.3 3.3

K3.13 Main steam system ...................................................... 3.3 3.3

K4. Knowledge of REACTOR CONDENSATE SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Condensate and/or booster pump auto start: PlantSpecific ............................................................... 3.4 3.4

K4.02 CRD pump suction ...................................................... 2.9 2.9

K4.03 Condensate and/or booster pump protection ................................. 2.8 2.8

K4.04 Maintenance of water quality ............................................. 2.7 2.7

K4.05 Maintenance of 100% system flow if a feedwater string

isolates: Plant-Specific .................................................. 3.0 3.0
NUREG-1123, Rev. 2 3.2-18 |

SYSTEM: 256000 Reactor Condensate System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.06 Control of extraction steam 2.8 2.8

K4.07 Cascading heater drains 2.4 2.4

K4.08 Dedicated ECCS water supply: Plant-Specific ............................... 3.6 3.6

K4.09 Initial main condenser vacuum ............................................ 2.8 2.8

K4.10 Non-condensable gas removal ............................................. 2.7 2.7

K4.11 Isolation of SJAE's on low flow: Plant-Specific ............................. 2.9 3.0

K5. Knowledge of the operational implications of the

following concepts as they apply to REACTOR CONDENSATE

SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 System venting ......................................................... 2.5 2.5

K5.02 Water conductivity measurement .......................................... 2.4* 2.4

K5.03 Heat exchanger level operation ............................................ 2.6 2.7

K5.04 Ion exchange process .................................................... 2.1* 2.1*

K5.05 Deaeration of condensate ................................................ 2.2* 2.2

K5.06 Air operated valve operation .............................................. 2.4 2.4

K5.07 Level controller operation ................................................ 2.7 2.7

K5.08 Heat removal (transfer) mechanisms ....................................... 2.6 2.7

K5.09 Pump cavitation ........................................................ 2.5 2.6

K5.10 Air ejection operation ................................................... 2.8 2.8

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the REACTOR CONDENSATE

SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 Plant air systems ........................................................ 2.8 2.8

K6.02 Circulating water system ................................................. 3.1 3.1

K6.03 Extraction steam system ................................................. 2.9 2.9

K6.04 A.C. power ............................................................. 2.8 2.8

K6.05 Component cooling water systems ......................................... 2.9 2.9

K6.06 Reactor feedwater system ................................................ 3.3 3.3

K6.07 Demineralized water storage and makeup system ............................. 2.4 2.4

K6.08 Main turbine ........................................................... 2.9 2.9

K6.09 Offgas system .......................................................... 2.6 2.6

K6.10 Main steam system ...................................................... 2.9 2.9
3.2-19 NUREG-1123, Rev. 2 |

SYSTEM: 256000 Reactor Condensate System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the REACTOR

CONDENSATE SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 System flow ........................................................... 2.9 2.9

A1.02 Pump amps ............................................................ 2.3* 2.3

A1.03 System pressure ........................................................ 2.8 2.8

A1.04 Hotwell level ........................................................... 2.9 2.9

A1.05 Condensate storage tank level ............................................. 2.9 3.0

A1.06 Reactor water level ...................................................... 3.5 3.5

A1.07 System lineup .......................................................... 3.1 3.1 |

A1.08 System water quality .................................................... 2.7 2.9

A1.09 Feedwater temperature ................................................... 3.1 3.1

A1.10 Condenser vacuum ...................................................... 3.1 3.1

A2. Ability to (a) predict the impacts of the following on

the REACTOR CONDENSATE SYSTEM; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 Pump trips .............................................................. 3.3 3.3

A2.02 Valve closures ........................................................... 2.8 2.9

A2.03 Valve openings .......................................................... 2.8 2.9

A2.04 A.C. power failures ....................................................... 2.9 3.0

A2.05 Inadequate system flow ................................................... 2.9 2.9

A2.06 Low hotwell level ........................................................ 3.2 3.2

A2.07 High hotwell level ....................................................... 2.9 2.9

A2.08 High feedwater heater level ................................................ 3.1 3.1

A2.09 Low feedwater heater level ................................................ 2.8 2.8

A2.10 Main turbine trip ......................................................... 3.1 3.1

A2.11 Loss of circulating water system ........................................... 3.2 3.2

A2.12 Loss of equipment component cooling water systems .......................... 3.1 3.1

A2.13 Loss of applicable plant air systems ......................................... 2.9 3.0

A2.14 Low Condensate storage tank level .......................................... 3.3 3.4

A2.15 Abnormal water quality ................................................... 2.8 3.1

A2.16 High demineralizer differential pressure ..................................... 2.8 2.8

A2.17 Feedwater heater string trip: Plant-Specific .................................. 2.9 2.9

A2.18 Loss of SJAE ........................................................... 2.9 2.9
NUREG-1123, Rev. 2 3.2-20 |

SYSTEM: 256000 Reactor Condensate System

Tasks as noted previously

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A3. Ability to monitor automatic operations of the REACTOR

CONDENSATE SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation .......................................................... 2.7 2.7

A3.02 Pump starts ............................................................. 3.0 2.9

A3.03 System pressure ......................................................... 2.9 2.9

A3.04 System flow ............................................................ 3.0 3.0

A3.05 Lights and alarms ........................................................ 3.0 2.9

A3.06 Hotwell level ............................................................ 3.0 2.9

A3.07 Feedwater heater level .................................................... 2.9 2.9

A3.08 Feedwater temperature .................................................... 3.1 3.1

A3.09 Feedwater heater drain tank level: Plant-Specific ............................. 2.8 2.9

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Hotwell condensate/ condensate booster pumps .............................. 3.3 3.3

A4.02 System motor operated valves ............................................. 2.8 2.8

A4.03 Hotwell level controls ................................................... 3.2 3.1

A4.04 Minimum flow valves .................................................... 2.8 2.7

A4.05 System flow ........................................................... 3.1 3.1

A4.06 System pressure ........................................................ 3.1 3.0

A4.07 Lights and alarms ....................................................... 2.9 2.9

A4.08 Reactor water level ...................................................... 3.7 3.7

A4.09 System water quality .................................................... 2.9 3.1

A4.10 Feedwater temperature ................................................... 3.2 3.2

A4.11 Condensate storage tank level ............................................. 3.2 3.4

A4.12 Feedwater heater level: Plant-Specific ..................................... 3.0 3.0

A4.13 Condenser vacuum ...................................................... 3.3 3.4

A4.14 Feedwater heater drain tank level: Plant-Specific ............................ 2.7 2.7

A4.15 Air ejectors: Plant-Specific .............................................. 3.1 3.0
3.2-21 NUREG-1123, Rev. 2 |

SYSTEM: 217000 Reactor Core Isolation Cooling System (RCIC)

TASK: Lineup the reactor core isolation cooling (RCIC) system

Manually operate and adjust reactor core isolation cooling system flow with the turbine governor

Manually initiate startup of the reactor core isolation cooling (RCIC) system

Operate RCIC pump in different modes

Monitor RCIC operation

Shutdown RCIC

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between REACTOR CORE ISOLATION

COOLING SYSTEM (RCIC) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Condensate storage and transfer system .................................... 3.5 3.5

K1.02 Nuclear boiler system ................................................... 3.5 3.5

K1.03 Suppression pool ....................................................... 3.6 3.6 |

K1.04 Main condenser ........................................................ 2.6 2.6

K1.05 Residual heat removal system ............................................. 2.6 2.6

K1.06 Plant air systems: Plant-Specific .......................................... 2.3* 2.3*

K1.07 Leak detection ......................................................... 3.1 3.2

K1.08 Line fill pump: Plant-Specific ............................................ 3.3 3.4

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Motor operated valves ................................................... 2.8* 2.8*

K2.02 RCIC initiation signals (logic) ............................................ 2.8* 2.9*

K2.03 RCIC flow controller .................................................... 2.7* 2.8*

K2.04 Gland seal compressor (vacuum pump) ..................................... 2.6* 2.6*

K3. Knowledge of the effect that a loss or malfunction of

the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) will

have on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level ...................................................... 3.7 3.7

K3.02 Reactor vessel pressure .................................................. 3.6 3.6

K3.03 Decay heat removal ..................................................... 3.5 3.5

K3.04 Adequate core cooling ................................................... 3.6 3.6

K4. Knowledge of REACTOR CORE ISOLATION COOLING SYSTEM

(RCIC) design feature(s) and/or interlocks which

provide for the following:

(CFR: 41.7)

K4.01 Prevent water hammer: Plant-Specific ..................................... 2.8 2.8

K4.02 Prevent over filling reactor vessel ......................................... 3.3 3.3
NUREG-1123, Rev. 2 3.2-22 |

SYSTEM: 217000 Reactor Core Isolation Cooling System (RCIC)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.03 Prevents pump over heating ............................................... 2.9 3.0

K4.04 Prevents turbine damage: Plant-Specific ................................... 3.0 3.1

K4.05 Prevents radioactivity release to auxiliary/reactor

building ............................................................... 3.2 3.5

K4.06 Manual initiation ........................................................ 3.5 3.5

K4.07 Alternate supplies of water ............................................... 3.6 3.6

K5. Knowledge of the operational implications of the

following concepts as they apply to REACTOR CORE

ISOLATION COOLING SYSTEM (RCIC) :

(CFR: 41.5 / 45.3)

K5.01 Indications of pump cavitation ............................................ 2.6* 2.6*

K5.02 Flow indication ......................................................... 3.1 3.1

K5.03 Differential pressure indication ........................................... 2.6 2.6

K5.04 Testable check valve operation ............................................ 2.6 2.7

K5.05 Centrifugal pump operation ............................................... 2.4* 2.4*

K5.06 Turbine operation ....................................................... 2.7* 2.7

K5.07 Assist core cooling ..................................................... 3.1 3.1

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the REACTOR CORE ISOLATION

COOLING SYSTEM (RCIC) :

(CFR: 41.7 / 45.7)

K6.01 Electrical power ........................................................ 3.4 3.5

| K6.02 Plant air systems ........................................................ 2.2* 2.2*

K6.03 Suppression pool water supply ............................................ 3.5 3.5

K6.04 Condensate storage and transfer system .................................... 3.5 3.5

ABILITY

Al. Ability to predict and/or monitor changes in

parameters associated with operating the REACTOR CORE

ISOLATION COOLING SYSTEM (RCIC) controls including:

(CFR: 41.5 / 45.5)

A1.01 RCIC flow ............................................................. 3.7 3.7

A1.02 RCIC pressure .......................................................... 3.3 3.3

A1.03 Reactor water level ..................................................... 4.0 4.0

| A1.04 Reactor pressure ........................................................ 3.6* 3.6*

A1.05 RCIC turbine speed ..................................................... 3.7 3.7

A1.06 Condensate storage tank level ............................................. 3.2 3.3

A1.07 Suppression pool level ................................................... 3.3 3.5

A1.08 Suppression pool temperature ............................................. 3.5 3.6
3.2-23 NUREG-1123, Rev. 2 |

SYSTEM: 217000 Reactor Core Isolation Cooling System (RCIC)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A2. Ability to (a) predict the impacts of the following on

the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ; and

(b) based on those predictions, use procedures to

correct, control, or mitigate the consequences of

those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 System initiation signal .................................................. 3.8 3.7

A2.02 Turbine trips ........................................................... 3.8 3.7

A2.03 Valve closures .......................................................... 3.4 3.3

A2.04 A.C. power loss ......................................................... 2.3* 2.3*

A2.05 D.C. power loss ........................................................ 3.3 3.3

A2.06 Loss of applicable plant air systems ........................................ 2.2* 2.2* |

A2.07 Loss of lube oil ......................................................... 3.1 3.1

A2.08 Loss of lube oil cooling .................................................. 3.0 3.1

A2.09 Loss of vacuum pump .................................................... 2.9 3.0

A2.10 Turbine control system failures ........................................... 3.1 3.1

A2.11 Inadequate system flow .................................................. 3.1 3.2

A2.12 Valve openings ......................................................... 3.0 3.0 |

A2.13 Loss of room cooling ................................................... 2.9 3.0

A2.14 Rupture disc failure: Exhaust-Diaphragm ................................... 3.3 3.4

A2.15 Steam line break ........................................................ 3.8 3.8

A2.16 Low condensate storage tank level ........................................ 3.5 3.4

A2.17 High suppression pool level .............................................. 3.2 3.4

A2.18 Low suppression pool level .............................................. 3.1 3.2

A2.19 High suppression pool temperature ........................................ 3.5 3.6

A3. Ability to monitor automatic operations of the REACTOR

CORE ISOLATION COOLING SYSTEM (RCIC) including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation ......................................................... 3.5 3.5 |

A3.02 Turbine startup ......................................................... 3.6 3.5

A3.03 System pressure ........................................................ 3.7 3.6

A3.04 System flow ........................................................... 3.6 3.5

A3.05 Reactor water level ..................................................... 3.9 3.9

A3.06 Lights and alarms ....................................................... 3.5 3.4

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 RCIC turbine speed ..................................................... 3.7 3.7

A4.02 Turbine trip throttle valve reset ............................................ 3.9 3.9

A4.03 System valves .......................................................... 3.4 3.3

A4.04 Manually initiated controls ............................................... 3.6 3.6
NUREG-1123, Rev. 2 3.2-24 |

SYSTEM: 217000 Reactor Core Isolation Cooling System (RCIC)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

|

A4.05 Reactor water level ...................................................... 4.1 4.1

A4.06 Suppression pool level ................................................... 3.6 3.7

A4.07 Reactor pressure ........................................................ 3.9 3.8

A4.08 System flow ........................................................... 3.7 3.6

A4.09 System pressure ........................................................ 3.7 3.6

A4.10 Lights and alarms ....................................................... 3.6 3.5

A4.11 Condensate storage tank level ............................................. 3.5 3.5
3.2-25 NUREG-1123, Rev. 2 |

SYSTEM: 259001 Reactor Feedwater System

TASK: Perform lineups on the reactor feedwater system 

Fill the reactor feedwater system

Start a reactor feed pump

Monitor operation of a reactor feedwater pump 

Secure a reactor feed pump

Operate feedwater manual/automatic transfer switch (for individual feed regulator valve)

Operate vessel level master control station 

Operate feedwater low flow startup valve

Take local/manual control of feedwater regulating valves 

Operate the reactor feed pump seal injection system

Secure the reactor feedwater system

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between REACTOR FEEDWATER SYSTEM

and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor vessel ......................................................... 3.6 3.7

K1.02 HPCI: Plant-Specific ................................................... 3.6 3.8

K1.03 RWCU ................................................................ 2.7 2.9

K1.04 Extraction steam system ................................................. 2.8 2.9

K1.05 Condensate system ...................................................... 3.2 3.2

K1.06 Plant air systems ........................................................ 2.9 3.0

K1.07 A.C. electrical power .................................................... 2.9 2.9

K1.08 Reactor water level control system ........................................ 3.6 3.7

K1.09 Reactor water level ...................................................... 3.8 3.8

K1.10 Component cooling water systems ......................................... 2.7 2.7

K1.11 RFP lube oil system ..................................................... 2.7 2.7

K1.12 RFP turbine seal steam system: TDRFP's-Only .............................. 2.6 2.6

K1.13 Main turbine generator: Plant-Specific ..................................... 2.5 2.5

K1.14 RCIC: Plant-Specific ................................................... 3.1 3.1

K1.15 RHR: Plant-Specific .................................................... 3.0 3.1

K1.16 Recirculation .......................................................... 3.1 3.1

K1.17 Heater drains: Plant-Specific ............................................. 2.4 2.4

K1.18 Fire protection system (emergency cooling): PlantSpecific ............................................................... 2.4 2.6

K1.19 †Redundant reactivity control system: Plant-Specific . . ...................... 3.0 3.3*

K1.20 Main steam system: TDRFPs-Only ........................................ 3.1 3.2

K1.21 D.C. electric power ..................................................... 2.4 2.5

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Reactor feedwater pump(s): Motor-Driven-Only ............................ 3.3 3.3

K2.02 System motor operated valves ............................................. 2.1* 2.2* |
NUREG-1123, Rev. 2 3.2-26 |

SYSTEM: 259001 Reactor Feedwater System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K2.03 RFP auxiliary oil pumps .................................................. 2.3* 2.4

K3. Knowledge of the effect that a loss or malfunction of

the REACTOR FEEDWATER SYSTEM will have on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level ...................................................... 3.9 3.9

K3.02 Reactor water level control system ........................................ 3.8 3.8

K3.03 HPCI: Plant-Specific ................................................... 3.3 3.3

K3.04 RWCU ................................................................ 2.5 2.5

K3.05 Recirculation pump NPSH ............................................... 2.9 2.9

K3.06 Core inlet subcooling .................................................... 3.1 3.1

K3.07 Condensate system ...................................................... 3.0 3.0

| K3.08 RCIC ................................................................. 2.9 2.9

K3.09 Extraction steam system ................................................. 2.5 2.6

K3.10 HPCS: Plant-Specific ................................................... 3.2* 3.2*

K3.11 RHR: Plant-Specific .................................................... 3.3* 3.3*

K3.12 Reactor power .......................................................... 3.8 3.9

K4. Knowledge of REACTOR FEEDWATER SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Auto start of the RFP's: Plant-Specific ..................................... 3.8 4.0

K4.02 Feedwater heating ....................................................... 2.8 2.9

K4.03 RFP minimum flow ..................................................... 2.7 2.7

K4.04 Dispersal of feedwater in the reactor vessel ................................. 2.5 2.6

K4.05 RFP protection ......................................................... 2.7 2.8

K4.06 RFP lubrication ......................................................... 2.5 2.6

K4.07 RFP motor cooling: Motor-Driven-Only ................................... 2.5 2.6

K4.08 RFP turbine seals: TDRFP's-Only ......................................... 2.3 2.4

K4.09 System isolation from the reactor vessel (check

valves, double valve isolation inside/ outside

containment) ........................................................... 3.2 3.3

K4.10 Feedpump runbacks: Plant-Specific ....................................... 3.1 3.4

K4.11 Recirculation runbacks: Plant-Specific ..................................... 3.5 3.5

K5. Knowledge of the operational implications of the

following concepts as they apply to REACTOR FEEDWATER

SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 System venting ......................................................... 2.4* 2.4

K5.02 Water hammer ......................................................... 2.5 2.5

K5.03 Turbine operation: TDRFP's-Only ......................................... 2.8 2.8
3.2-27 NUREG-1123, Rev. 2 |

SYSTEM: 259001 Reactor Feedwater System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the REACTOR FEEDWATER

SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 Plant air systems ........................................................ 3.0 3.0

K6.02 Condensate system ...................................................... 3.3 3.4

K6.03 A.C. electrical power .................................................... 2.9 3.1

K6.04 Extraction steam ........................................................ 2.8 2.9

K6.05 Component cooling water systems ......................................... 2.7 2.7

K6.06 Plant service water ...................................................... 2.7 2.7

K6.07 Reactor water level control system ........................................ 3.8 3.8

K6.08 Reactor feedwater pump motor ventilation: MotorDriven-Only ........................................................... 2.1* 2.1*

K6.09 Reactor feedwater pump lube oil system .................................... 2.8 2.9

K6.10 RFP turbine seal system: TDRFP's-Only ................................... 2.5 2.5

K6.11 Main steam: TDRFP's-Only .............................................. 2.8 2.8

K6.12 D.C. electrical power .................................................... 2.3 2.4

K6.13 †Redundant reactivity control: Plant-Specific ............................... 3.0 3.3*

K6.14 Heater drains: Plant-Specific ............................................. 2.5 2.6

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the REACTOR

FEEDWATER SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Feedwater flow/pressure ................................................. 3.3 3.3

A1.02 Feedwater inlet temperature .............................................. 3.2 3.3

A1.03 RFP motor amps: Motor-Driven-Only ..................................... 2.8 2.8

A1.04 RFP turbine speed: Turbine-Driven-Only ................................... 2.8 2.7

A1.05 RFP turbine control valve position: Turbine-DrivenOnly .................................................................. 2.8 2.7

A1.06 Feedwater heater level .................................................. 2.7 2.7

A2. Ability to (a) predict the impacts of the following on

the REACTOR FEEDWATER SYSTEM ; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 Pump trip .............................................................. 3.7 3.7

A2.02 Feedwater heater isolation ................................................ 3.1 3.3

A2.03 Loss of condensate pump(s) .............................................. 3.6 3.6

A2.04 Loss of extraction steam ................................................. 3.3 3.4
NUREG-1123, Rev. 2 3.2-28 |

SYSTEM: 259001 Reactor Feedwater System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A2.05 Loss of applicable plant air systems 3.0 3.0

A2.06 Loss of A.C. electrical power 3.2 3.2

A2.07 Reactor water level control system malfunctions ............................. 3.7 3.8

A2.08 Loss of D.C. electrical power ............................................. 2.5 2.6

A2.09 †TDRFP steam inlet pressure flow: Plant-Specific ........................... 2.6 2.7

A3. Ability to monitor automatic operations of the REACTOR

FEEDWATER SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 RFP auto start: Plant-Specific ............................................ 3.3 3.5

A3.02 Motor amps: Motor-Driven-Only ......................................... 2.4 2.5

A3.03 System flow ........................................................... 3.3 3.2

A3.04 Reactor water level ...................................................... 3.8 3.7

A3.05 Feedwater inlet temperature .............................................. 3.1 3.2

A3.06 Pump discharge pressure ................................................. 3.1 3.1

A3.07 FWRV position ......................................................... 3.2 3.2

A3.08 Turbine speed: TDRFP'S-Only ............................................ 2.8 2.7

A3.09 Lights and alarms ....................................................... 3.0 3.0

A3.10 Pump trips ............................................................. 3.4 3.4

A3.11 Reactor feedpump runbacks: Plant-Specific ................................. 3.2 3.7

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 System flow ........................................................... 3.6 3.5

A4.02 Manually start/control a RFP/TDRFP ...................................... 3.9 3.7

A4.03 Feedwater heater/drain controls ........................................... 2.9 3.0

A4.04 System valves .......................................................... 3.1 2.9

A4.05 Reactor water level ...................................................... 4.0 3.9

A4.06 Feedwater inlet temperature .............................................. 3.4 3.5

A4.07 Pump discharge pressure ................................................. 3.3 3.2

A4.08 FWRV position ......................................................... 3.3 3.3
3.2-29 NUREG-1123, Rev. 2 |

SYSTEM: 204000 Reactor Water Cleanup System

TASK: Perform lineups on the reactor water cleanup system

Startup the reactor cleanup system

Operate the reactor cleanup system while reducing reactor pressure

Place the reactor water cleanup system in operation with the reactor at rated pressure

Remove the reactor cleanup (RWCU) system from service with the reactor at rated pressure

Return drained system to service with the reactor at rated pressure

Route primary system water to the main condenser hotwell

Operate the reactor cleanup system to conduct blowdowns

Route primary system water to radwaste

Drain the reactor cavity and equipment pool to the hotwell via the reactor cleanup system

Monitor the reactor water cleanup system (write in)

Place the reactor water cleanup system in operation with the 

( )reactor at rated temperature (write in)

Remove the reactor cleanup system from service with the reactor at rated temperature (write in)

Return drained system to service with the reactor at rated temperature (write in)

Perform reactor cleanup simulated automatic actuation test

Perform reactor cleanup isolation logic system functional test

Conduct reactor cleanup valve testing

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between REACTOR WATER CLEANUP

SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor vessel ........................................................... 3.1 3.3

K1.02 Recirculation system: Plant-Specific ....................................... 2.9 3.0

K1.03 Reactor feedwater system ................................................. 3.1 3.1

K1.04 Component cooling water systems .......................................... 2.9 2.9

K1.05 Plant air systems ......................................................... 2.7 2.7

K1.06 Main condenser ......................................................... 2.8 2.8

K1.07 Radwaste ............................................................... 2.6 2.7

K1.08 SBLC .................................................................. 3.7 3.8

K1.09 Reactor water level ....................................................... 3.2 3.3

K1.10 Reactor water quality ..................................................... 3.3 3.5

K1.11 PCIS/NSSSS ............................................................ 3.5 3.7

K1.12 Condensate storage and transfer system: PlantSpecific ................................................................ 2.6 2.6

K1.13 RHR system: Plant-Specific .............................................. 2.5 2.5

K1.14 Process sample system ................................................... 2.5 2.5

K1.15 Leak detection: Plant-Specific ............................................. 3.1 3.2

K1.16 CRD system: Plant-Specific .............................................. 2.8 2.8
NUREG-1123, Rev. 2 3.2-30 |

SYSTEM: 204000 Reactor Water Cleanup System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Pumps ................................................................ 2.3* 2.4*

K2.02 Valve motors ........................................................... 2.0* 2.1*

K3. Knowledge of the effect that a loss or malfunction of

the REACTOR WATER CLEANUP SYSTEM will have on

following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water quality .................................................... 3.2 3.6

K3.02 Reactor water level ...................................................... 3.1 3.1

K3.03 Component cooling water systems ......................................... 2.4 2.4

K3.04 Reactor water temperature ............................................... 2.6 2.6

K3.05 Area temperature ....................................................... 2.4* 2.4*

K3.06 Area radiation levels ..................................................... 2.6 2.7

K3.07 Drywell temperature .................................................... 2.1* 2.2*

K3.08 Drywell pressure ....................................................... 2.2* 2.3*

K4. Knowledge of REACTOR WATER CLEANUP SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Pump protection ........................................................ 2.5 2.5

K4.02 Piping over-pressurization protection: Plant-Specific ........................ 2.7 2.9

K4.03 Over temperature protection for system components ......................... 2.9 2.9

| K4.04 System isolation upon-receipt of isolation signals ............................ 3.5 3.6

K4.05 Double valve isolation from the reactor ..................................... 3.0 3.1

K4.06 Maximize plant efficiency (use of regenerative heat

exchanger) ............................................................. 2.6 2.8

K4.07 Draining of reactor water to various locations ............................... 2.9 2.9

K4.08 Reducing reactor pressure upstream of low pressure

piping: LP-RWCU ...................................................... 3.3 3.4

K5. Knowledge of the operational implications of the

following concepts as they apply to REACTOR WATER

CLEANUP SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Electro/ pneumatic converter operation ..................................... 1.9* 2.1*

K5.02 Control device operation ................................................. 2.2* 2.2*

K5.03 Demineralizer operation ................................................. 2.4 2.5

K5.04 Heat exchanger operation ................................................ 2.7 2.7

K5.05 Flow controllers ........................................................ 2.6 2.6
3.2-31 NUREG-1123, Rev. 2 |

SYSTEM: 204000 Reactor Water Cleanup System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K5.06 Pressure controllers ..................................................... 2.6* 2.6

K5.07 Conductivity measurement ............................................... 2.5 2.6

K5.08 Temperature measurement ............................................... 2.6 2.6

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the REACTOR WATER CLEANUP

SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 Component cooling water systems ......................................... 3.1 3.3

K6.02 Main condenser ........................................................ 2.4 2.4

K6.03 Radwaste .............................................................. 2.4 2.4

K6.04 Plant air systems ........................................................ 2.7 2.8

K6.05 A. C. power ............................................................ 2.6 2.6

K6.06 Reactor feedwater system ................................................ 2.4* 2.4* |

K6.07 SBLC logic ............................................................ 3.3 3.5

K6.08 PCIS/NSSSS ........................................................... 3.5 3.5

K6.09 CRD hydraulics: Plant-Specific ........................................... 2.7 2.9

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the REACTOR WATER 

CLEANUP SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor water level ..................................................... 3.1 3.2

A1.02 Component cooling water temperature ..................................... 2.9 2.9

A1.03 Reactor water temperature ............................................... 2.8 2.9

A1.04 System flow ........................................................... 2.8 2.8

A1.05 System pressure ........................................................ 2.6 2.6

A1.06 System temperature ..................................................... 2.8 2.8

A1.07 RWCU drain flow ....................................................... 2.9 2.9

A1.08 Main condenser hotwell level ............................................. 2.3 2.3

A1.09 Reactor water conductivity ............................................... 3.0 3.2

A2. Ability to (a) predict the impacts of the following on

the REACTOR WATER CLEANUP SYSTEM ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Loss of component cooling water ......................................... 3.2 3.4

A2.02 Pressure control valve failure: LP-RWCU .................................. 3.2 3.2

A2.03 Flow control valve failure ................................................ 2.9 2.9

A2.04 Pump trips ............................................................. 2.7 2.9
NUREG-1123, Rev. 2 3.2-32 |

SYSTEM: 204000 Reactor Water Cleanup System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A2.05 Valve openings ......................................................... 2.7 2.8

A2.06 A.C. failure ............................................................ 2.5 2.6

A2.07 Loss of plant air systems ................................................. 2.5 2.6

A2.08 RWCU pump seal failure ................................................. 2.9 3.1

A2.09 Loss of room coolers ................................................... 2.8 2.8

A2.10 Valve closures .......................................................... 2.7 2.8

A2.11 Inadequate system flow: Plant-Specific .................................... 2.6 2.7

A2.12 Excessive drain flow rates ................................................ 2.7 2.8

A2.13 Signal received which results in a system isolation ........................... 3.4 3.4

A2.14 System high temperature ................................................. 3.2 3.2

A2.15 Cleanup demineralizer high differential pressure ............................. 2.8 2.9

A3. Ability to monitor automatic operations of the REACTOR

WATER CLEANUP SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 System pressure downstream of the pressure regulating

valve: LP-RWCU ....................................................... 3.3 3.3

A3.02 Reactor water quality .................................................... 2.9 3.2

A3.03 Response to system isolations ............................................ 3.6 3.6

A3.04 Response to interlocks and trips designed to protect

 system components ........................................................ 3.4 3.5

A3.05 Reactor water temperature ............................................... 2.8 2.8

A3.06 Lights and alarms ....................................................... 3.1 3.1

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 System pumps .......................................................... 3.1 3.0

A4.02 Valve controllers ....................................................... 2.9 2.9

A4.03 RWCU drain flow regulator .............................................. 3.2 3.1

A4.04 Heat exchanger operation ................................................ 2.8 2.8

A4.05 System pressure ........................................................ 2.9 2.8

A4.06 System flow ........................................................... 3.0 2.9

A4.07 System temperature ..................................................... 3.1 3.1

A4.08 Reactor water level ...................................................... 3.4 3.4

A4.09 Reactor water temperature ............................................... 2.9 2.9
3.2-33 NUREG-1123, Rev. 2 |

SYSTEM: 259002 Reactor Water Level Control System

TASK: Operate feedwater manual/automatic transfer switch (for individual feed regulator valve)

Operate vessel level master control station

Operate feedwater low flow startup valve

Place the high pressure (feedwater) coolant injection system (FWCI) in standby readiness

Monitor the high pressure (feedwater) coolant injection system operation

Return the high pressure (feedwater) coolant injection system to standby readiness after automatic

initiation

Perform high pressure (feedwater) coolant injection operability test when reactor core isolation coolant

is inoperable

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between REACTOR WATER LEVEL

CONTROL SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 RPS .................................................................. 3.8 3.9

K1.02 Main steam flow ....................................................... 3.2 3.3

K1.03 Reactor water level ..................................................... 3.8 3.9

K1.04 Reactor feedwater flow .................................................. 3.5 3.6

K1.05 Reactor feedwater system ............................................... 3.6 3.7

K1.06 Plant air systems ....................................................... 3.0 3.1

K1.07 Rod worth minimizer: Plant-Specific ...................................... 2.6 2.7 |

K1.08 Recirculation system: Plant-Specific ...................................... 3.2 3.2

K1.09 P sat/T sat (compensation) ............................................... 2.9 3.0

K1.10 Emergency generator(s): FWCI/HPCI ..................................... 2.9 3.0

K1.11 Drywell pressure: FWCI/HPCI ........................................... 3.0 3.2

K1.12 Emergency condensate transfer pump: FWCI/HPCI .......................... 2.6* 2.6*

K1.13 Condensate system ..................................................... 3.2 3.2

K1.14 Main turbine ........................................................... 2.9 3.0

K1.15 Recirculation flow control system ........................................ 3.2 3.2

K1.16 HPCI: Plant-Specific ................................................... 3.4 3.5

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Reactor water level control system circuits ................................. 2.4* 2.7

K2.02 Feedwater coolant injection (FWCI) initiation logic:

FWCI/HPCI ............................................................ 3.5* 3.5*
NUREG-1123, Rev. 2 3.2-34 |

SYSTEM: 259002 Reactor Water Level Control System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3. Knowledge of the effect that a loss or malfunction of

the REACTOR WATER LEVEL CONTROL SYSTEM will have on

following:

(CFR: 41.7 / 45.4)

(CFR: 41.7 / 45.5 to 45.8)

K3.01 Reactor water level ..................................................... 3.8 3.8

| K3.02 Reactor feedwater system ............................................... 3.7 3.7

| K3.03 Rod worth minimizer: Plant-Specific ...................................... 2.7 2.9

K3.04 Recirculation system: Plant-Specific ...................................... 2.9 3.0

K3.05 Recirculation flow control system ........................................ 2.8 2.9

K3.06 Main turbine ........................................................... 2.8 2.8

K3.07 Reactor water level indication ............................................ 3.4* 3.4

K4. Knowledge of REACTOR WATER LEVEL CONTROL SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Ensuring adequate NPSH for recirculation pumps:

Plant-Specific .......................................................... 3.0 3.1

| K4.02 Bypassing of the RWM: Plant-Specific .................................... 2.8 3.0

K4.03 Reactor feedpump runout protection: MDFP ................................ 2.8* 2.8

K4.04 Reactor water level setpoint setdown following a

reactor scram .......................................................... 2.9 2.9

K4.05 P sat/T sat (compensation) ............................................... 2.9 2.9

| K4.06 Control signal failure .................................................... 3.1 3.2

| K4.07 TDRFP 20% power interlock: TDRFP ..................................... 3.1 3.3

| K4.08 TDRFP speed control: TDRFP ............................................ 2.9 3.0

| K4.09 Single element control (reactor water level provides

the only input) .......................................................... 3.1 3.1

K4.10 Three element control (main steam flow, reactor

feedwater flow and reactor water level provide input) ......................... 3.4 3.4

K4.11 DP control: Plant-Specific ............................................... 3.3 3.3

K4.12 Manual and automatic control of the system ................................ 3.5 3.4

| K4.13 FWRV lockup ......................................................... 3.5 3.6

| K4.14 Selection of various instruments to provide reactor

water level input ........................................................ 3.4 3.4

K4.15 Automatic initiation of the feedwater system upon

| receipt of an ECCS initiation signal: FWCI/HPCI ........................... 4.5* 4.5*

| K4.16 Dedication of feedwater string(s) to ECCS: FWCI/HPCI ...................... 4.5* 4.5*

K4.17 Simultaneous Manual and Auto operation of the system

(i.e. 1 FP in Auto, 1 FP in Manual) ........................................ 3.1 3.0
3.2-35 NUREG-1123, Rev. 2 |

SYSTEM: 259002 Reactor Water Level Control System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K5. Knowledge of the operational implications of the

following concepts as they apply to REACTOR WATER

LEVEL CONTROL SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 GEMAC/Foxboro/Bailey controller operation: PlantSpecific .............................................................. 3.1 3.1

K5.02 Electro/ Pneumatic converter operation .................................... 2.2* 2.4

K5.03 Water level measurement ................................................ 3.1 3.2

K5.04 Moisture carryover ..................................................... 2.3 2.3

K5.05 Moisture carryunder ..................................................... 2.3 2.3 |

K5.06 Pump runout ........................................................... 2.4 2.4

K5.07 Turbine speed control mechanisms: TDRFP ................................ 2.7 2.7

K5.08 Heat removal mechanisms: FWCI ......................................... 3.6 3.8

K5.09 †Adequate core cooling: FWCI .......................................... 3.8 4.2*

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the REACTOR WATER LEVEL

CONTROL SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 Plant air systems ....................................................... 3.2 3.2

K6.02 A.C. power ............................................................ 3.3 3.4

K6.03 Main steam flow input ................................................... 3.1 3.1

K6.04 Reactor feedwater flow input ............................................. 3.1 3.1

K6.05 Reactor water level input ................................................. 3.5 3.5

K6.06 Reactor pressure/temperature input (for water level

input compensation) .................................................... 2.6 2.7

K6.07 Drywell pressure input: FWCI ........................................... 3.0* 3.0*

K6.08 Loss of dP across startup level control bypass valve:

Plant-Specific ......................................................... 2.7 2.7

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the REACTOR WATER

LEVEL CONTROL SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor water level ...................................................... 3.8 3.8

A1.02 Reactor feedwater flow .................................................. 3.6 3.5

A1.03 Reactor power .......................................................... 3.8 3.8

A1.04 Reactor water level control controller indications ........................... 3.6 3.6

A1.05 FWRV/startup level control position: Plant-Specific . ........................ 2.9 2.9

A1.06 Feedwater string(s) selected for FWCI: FWCI .............................. 3.3* 3.3*

A1.07 TDRFP speed: TDRFP .................................................. 2.6 2.6
NUREG-1123, Rev. 2 3.2-36 |

SYSTEM: 259002 Reactor Water Level Control System

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A2. Ability to (a) predict the impacts of the following on

the REACTOR WATER LEVEL CONTROL SYSTEM ; and (b) based

on those predictions, use procedures to correct,

control, or mitigate the consequences of those

abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Loss of any number of main steam flow inputs ............................... 3.3 3.4

A2.02 Loss of any number of reactor feedwater flow inputs ......................... 3.3 3.4

A2.03 Loss of reactor water level input .......................................... 3.6 3.7

A2.04 RFP runout condition: Plant-Specific ..................................... 3.0 3.1

A2.05 Loss of applicable plant air systems ....................................... 3.2 3.4

A2.06 Loss of controller signal output ........................................... 3.3 3.4

A2.07 Loss of comparator bias signal ........................................... 2.4 2.5

| A2.08 Receipt of an ECCS initiation signal: FWCI ................................ 4.5* 4.5*

A2.09 FWCI system failure alarm: FWCI ........................................ 4.0 4.0

A3. Ability to monitor automatic operations of the REACTOR

WATER LEVEL CONTROL SYSTEM including:

(CFR: 41.7 / 45.7)

| A3.01 Runout flow control: Plant-Specific ...................................... 3.0* 3.0*

A3.02 Changes in reactor water level ............................................ 3.4 3.4

A3.03 Changes in main steam flow .............................................. 3.2 3.2

A3.04 Changes in reactor feedwater flow ........................................ 3.2 3.2

A3.05 Changes in reactor power ................................................ 3.4 3.4

A3.06 Reactor water level setpoint setdown following a

reactor scram: Plant-Specific ............................................ 3.0 3.0

A3.07 FWRV lockup ......................................................... 3.5 3.6

A3.08 FWCI system initiation: FWCI ........................................... 4.0 4.0

A3.09 Transfer of system from flow control to level control

| mode: FWCI .......................................................... 4.3* 4.3

A3.10 TDRFP lockup: TDRFP ................................................. 3.1 3.0

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 All individual component controllers in the manual

mode ................................................................. 3.8 3.6

A4.02 All individual component controllers in the automatic

mode ................................................................. 3.7 3.6

A4.03 All individual component controllers when transferring

from manual to automatic modes .......................................... 3.8 3.6

A4.04 FWRV lockup reset controls ............................................. 3.7 3.6

A4.05 Runout flow control reset controls: Plant-Specific .......................... 3.8 3.5

A4.06 DP/Single/three element control selector switch:

Plant-Specific ......................................................... 3.1 3.2

SYSTEM: 259002 Reactor Water Level Control System
3.2-37 NUREG-1123, Rev. 2 |

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A4.07 All individual component controllers when transferring

from automatic to manual mode 3.8 3.6

A4.08 Manually initiate FWCI: FWCI 4.5* 4.5* |

A4.09 TDRFP lockout reset: TDRFP 3.4 3.1

A4.10 Setpoint setdown reset controls: Plant-Specific 3.1 2.9

A4.11 High level lockout reset controls: Plant-Specific 3.5 3.3
NUREG-1123, Rev. 2 3.2-38 |

SYSTEM: 203000 RHR/LPCI: Injection Mode (Plant Specific)

TASK: Perform lineups on the low pressure coolant injection system

Place the low pressure coolant injection system in standby readiness

Monitor operational sequence of low pressure coolant injection (LPCI) system

Secure the low pressure coolant injection system

Perform LPCI subsystem logic system functional test

Perform LPCI mode inoperable test

Perform LPCI mov power supply simulated auto. act test and battery serv. tests

Conduct LPCI independent power supply weekly battery test

Conduct LPCI independent power supply performance discharge test

Perform low pressure coolant injection sound analysis and flow test (write in)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between RHR/LPCI: INJECTION MODE

(PLANT SPECIFIC) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Condensate storage and transfer system: PlantSpecific ............................................................... 2.8 2.8

K1.02 Suppression pool ....................................................... 3.9 3.9

K1.03 Condensate transfer ..................................................... 2.5* 2.6*

K1.04 Keep fill system ........................................................ 3.3 3.4

K1.05 Recirculation system: BWR-3,4 .......................................... 3.8 3.8

K1.06 Automatic depressurization ............................................... 3.9 3.9

K1.07 D.C. electrical power .................................................... 3.1 3.3

K1.08 A.C. electrical power .................................................... 3.5 3.5

K1.09 Emergency generators ................................................... 3.8 3.8

K1.10 ECCS room coolers ..................................................... 3.2 3.2

K1.11 Nuclear boiler instrumentation ............................................ 3.7 3.7

K1.12 Plant air systems: Plant-Specific .......................................... 2.6* 2.7*

K1.13 Drywell pressure ....................................................... 3.9 4.0

K1.14 Shutdown cooling system: Plant-Specific .................................. 3.6 3.7

K1.15 Reactor building drain system: Plant-Specific ............................... 2.4* 2.6

K1.16 Component cooling water systems ......................................... 3.1 3.2

K1.17 Reactor pressure ........................................................ 4.0 4.0

K1.18 Reactor vessel: Plant-Specific ............................................ 3.8 3.8

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Pumps ................................................................ 3.5* 3.5*

K2.02 Valves ................................................................ 2.5* 2.7*

K2.03 Initiation logic ......................................................... 2.7* 2.9*
3.2-39 NUREG-1123, Rev. 2 |

SYSTEM 203000 RHR/LPCI: Injection Mode (Plant Specific)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3. Knowledge of the effect that a loss or malfunction of

the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) will

have on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level ..................................................... 4.3* 4.4*

K3.02 Suppression pool level .................................................. 3.5 3.5

K3.03 Automatic depressurization logic ......................................... 4.2* 4.3*

K3.04 Adequate core cooling .................................................. 4.6* 4.6*

K4. Knowledge of RHR/LPCI: INJECTION MODE (PLANT SPECIFIC)

design feature(s) and/or interlocks which provide for

the following:

(CFR: 41.7)

K4.01 Automatic system initiation/ injection ..................................... 4.2* 4.2

K4.02 Prevention of piping overpressurization .................................... 3.3 3.4

K4.03 Pump minimum flow protection .......................................... 3.2 3.3

K4.04 Pump motor cooling: Plant-Specific ...................................... 2.6 2.7

K4.05 Prevention of water hammer ............................................. 3.2 3.3

K4.06 Adequate pump net positive suction head (interlock

suction valve open): Plant-Specific ....................................... 3.5 3.5

K4.07 Emergency generator load sequencing ..................................... 3.7 3.9

K4.08 Pump operability testing ................................................. 3.3 3 .4*

K4.09 Surveillance for all operable components ................................... 3.1 3.4

K4.10 Dedicated injection system during automatic system

initiation (injection valve interlocks) ...................................... 3.9 4.1

K4.11 Loop selection logic: Plant-Specific ...................................... 4.0 4.0

K4.12 System redundancy ..................................................... 3.5 3.6

K4.13 The prevention of leakage to the environment through

LPCI/RHR heat exchanger: Plant-Specific ................................. 3.4 3.7

K4.14 †Operation from remote shutdown panel ................................... 3.6 3.7

K4.15 Pump runout protection: Plant-Specific ................................... 2.5* 2.5

K5. Knowledge of the operational implications of the

following concepts as they apply to RHR/LPCI:

INJECTION MODE (PLANT SPECIFIC) :

(CFR: 41.5 / 45.3)

K5.01 Testable check valve operation ............................................ 2.7* 2.9

K5.02 †Core cooling methods ................................................. 3.5 3.7
NUREG-1123, Rev. 2 3.2-40 |

SYSTEM: 203000 RHR/LPCI: Injection Mode (Plant Specific)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the RHR/LPCI: INJECTION

MODE (PLANT SPECIFIC) :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical power .................................................... 3.6 3.7

K6.02 D.C. electrical power .................................................... 2.8* 3.0*

K6.03 Emergency generator .................................................... 3.7 3.9

K6.04 Keep fill system ........................................................ 3.3 3.5

K6.05 Condensate storage and transfer system: Plant-Specific ....................... 2.5 2.5

| K6.06 Suppression pool ....................................................... 3.8 3.9

K6.07 Plant air systems: Plant-Specific .......................................... 2.7 2.7

K6.08 ECCS room cooling ..................................................... 2.9 3.1

K6.09 Nuclear boiler instrumentation ............................................ 3.4 3.4

K6.10 Component cooling water systems ......................................... 3.0 3.1

| K6.11 ADS .................................................................. 4.1* 4.1

K6.12 †ECCS room integrity ................................................... 2.7 2.9

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the RHR/LPCI:

INJECTION MODE (PLANT SPECIFIC) controls including:

(CFR: 41.5 / 45.5)

| A1.01 Reactor water level ...................................................... 4.2* 4.3*

| A1.02 Reactor pressure ........................................................ 3.9* 4.0*

A1.03 System flow ........................................................... 3.8 3.7

A1.04 System pressure ........................................................ 3.6 3.6

A1.05 Suppression pool level ................................................... 3.8 3.7

| A1.06 Condensate storage tank level: Plant-Specific ............................... 2.4* 2.5*

| A1.07 Motor amps: Plant-Specific .............................................. 2.4* 2.5*

A1.08 †Emergency generator loading ............................................ 3.7 3.8

A1.09 Component cooling water systems ......................................... 2.9 2.9

A2. Ability to (a) predict the impacts of the following on

the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) ; and

(b) based on those predictions, use procedures to

correct, control, or mitigate the consequences of

those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Inadequate net positive suction head ........................................ 3.2 3.4

A2.02 Pump trips ............................................................. 3.5 3.5

A2.03 Valve closures .......................................................... 3.2 3.3

A2.04 A.C. failures ........................................................... 3.5 3.6

A2.05 D.C. failures ........................................................... 3.0 3.2
3.2-41 NUREG-1123, Rev. 2 |

SYSTEM: 203000 RHR/LPCI: Injection Mode (Plant Specific)

Tasks as noted previously

 IMPORTANCE 

K/A NO. KNOWLEDGE ........................................................ RO SRO

A2.06 Emergency generator failure .............................................. 3.8 3.9

A2.07 Pump seal failure ....................................................... 3.0 3.1

A2.08 Inadequate room cooling ................................................. 2.9 3.0

A2.09 Inadequate system flow .................................................. 3.3 3.4

A2.10 Nuclear boiler instrument failures ......................................... 3.3 3.5

A2.11 Motor operated valve failures ............................................. 3.4 3.6

A2.12 Pump runout ........................................................... 2.6* 2.7* |

A2.13 Valve openings ......................................................... 3.2 3.3 |

A2.14 Initiating logic failure ................................................... 3.8 3.9* |

A2.15 Loop selection logic failure: Plant-Specific ................................ 4.2* 4.2*

A2.16 Loss of coolant accident ................................................. 4.4* 4.5*

A2.17 Keep fill system failure .................................................. 3.3 3.5

A3. Ability to monitor automatic operations of the

RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation ......................................................... 3.8* 3.7

A3.02 Pump start ............................................................. 4.0 3.9

A3.03 Pump discharge pressure ................................................. 3.7 3.6

A3.04 System flow ........................................................... 3.8 3.7

A3.05 Reactor water level ...................................................... 4.4* 4.4*

A3.06 Indicating lights and alarms ............................................... 3.7* 3.6

A3.07 Loop selection: Plant-Specific ........................................... 4.2* 4.6*

A3.08 System initiation sequence ............................................... 4.1 4.1

A3.09 Emergency generator load sequencing ...................................... 3.6 3.9*

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Pumps ................................................................ 4.3* 4.1* |

A4.02 System valves .......................................................... 4.1* 4.1* |

A4.03 Keep fill system ........................................................ 3.4 3.4

A4.04 Heat exchanger cooling flow.............................................. 3.6 3.6

A4.05 Manual initiation controls ................................................ 4.3* 4.1* |

A4.06 System reset following automatic initiation: Plant-Specific ................... 3.9 3.9

A4.07 Reactor water level ...................................................... 4.5* 4.5* |

A4.08 Reactor pressure ........................................................ 4.3* 4.3* |

A4.09 System flow ........................................................... 4.1 4.0

A4.10 Pump/system discharge pressure: Plant-Specific ............................ 3.7 3.6

A4.11 Indicating lights and alarms ............................................... 3.7* 3.5* |

A4.12 Condensate storage tank level: Plant-Specific ............................... 2.5 2.6

A4.13 Suppression pool level/temperature ........................................ 3.9 3.9

A4.14 Testable check valves .................................................... 2.7* 2.7* |
3.3-1 NUREG-1123, Rev. 2 |

3.3 Reactor Pressure Control page

218000 Automatic Depressurization System 3.3-3

239001 Main and Reheat Steam System 3.3-6

241000 Reactor/Turbine Pressure Regulating System 3.3-11

239002 Safety Relief Valves 3.3-18
NUREG-1123, Rev. 2 3.3-2 |

This page left blank
3.3-3 NUREG-1123, Rev. 2 |

SYSTEM: 218000 Automatic Depressurization System

TASK: Monitor the automatic depressurization system (ADS)

Manually operate the automatic depressurization system

 

 IMPORTANCE

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between AUTOMATIC

DEPRESSURIZATION SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 RHR/LPCI: Plant-Specific ............................................... 4.0 4.1

K1.02 Low pressure core spray: Plant-Specific ................................... 4.0 4.1

K1.03 Nuclear boiler instrument system .......................................... 3.7 3.8

K1.04 Drywell/containment pressure: Plant-Specific .............................. 3.9 4.2

K1.05 Remote shutdown system: Plant-Specific .................................. 3.9 3.9

K1.06 Safety/relief valves ...................................................... 3.9* 3.9*

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 ADS logic ............................................................. 3.1* 3.3* |

K3. Knowledge of the effect that a loss or malfunction of

the AUTOMATIC DEPRESSURIZATION SYSTEM will have on

following:

(CFR: 41.7 / 45.4)

K3.01 Restoration of reactor water level after a break that

does not depressurize the reactor when required ............................. 4.4* 4.4*

K3.02 Ability to rapidly depressurize the reactor ................................... 4.5* 4.6*

K4. Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Prevent inadvertent initiatior of ADS logic .................................. 3.7 3.9

K4.02 Allows manual initiation of ADS logic ...................................... 3.8 4.0

K4.03 ADS logic control ...................................................... 3.8 4.0

K4.04 Insures adequate air supply to ADS valves: PlantSpecific ............................................................... 3.5 3.6

K5. Knowledge of the operational implications of the

following concepts as they apply to AUTOMATIC

DEPRESSURIZATION SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 ADS logic operation ..................................................... 3.8 3.8
NUREG-1123, Rev. 2 3.3-4 |

SYSTEM: 218000 Automatic Depressurization System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the AUTOMATIC

DEPRESSURIZATION SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 RHR/LPCI system pressure: Plant-Specific ................................. 3.9 4.1

K6.02 Low pressure core spray system pressure: PlantSpecific ............................................................... 4.1 4.1

K6.03 Nuclear boiler instrument system (level indication) .......................... 3.8 3.9

K6.04 Air supply to ADS valves: Plant-Specific ................................... 3.6 3.7

K6.05 A.C. power: Plant-Specific ............................................... 3.0* 3.1*

K6.06 D.C. power: Plant-Specific ............................................... 3.4* 3.6*

K6.07 Primary containment instrumentation ...................................... 3.4 3.5

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the AUTOMATIC

DEPRESSURIZATION SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 ADS valve tail pipe temperatures .......................................... 3.4 3.6

A1.02 ADS valve acoustical monitor noise: Plant-Specific .......................... 3.7 4.0

A1.03 ADS valve Air supply pressure: Plant-Specific .............................. 3.2 3.4*

A1.04 Reactor pressure ........................................................ 4.1* 4.2*

A1.05 Reactor water level ...................................................... 4.1* 4.1

A1.06 Suppression pool temperature ............................................. 4.1 4.3*

A2. Ability to (a) predict the impacts of the following on

the AUTOMATIC DEPRESSURIZATION SYSTEM ; and (b) based

on those predictions, use procedures to correct,

control, or mitigate the consequences of those

abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Small steam line break L0CA ............................................. 4.1 4.3*

A2.02 Large break LOCA ...................................................... 3.5 3.6*

A2.03 Loss of air supply to ADS valves: Plant-Specific ............................. 3.4 3.6

A2.04 ADS failure to initiate ................................................... 4.1 4.2*

A2.05 Loss of A.C. or D.C. power to ADS valves .................................. 3.4* 3.6*

A2.06 ADS initiation signals present ............................................. 4.2 4.3*

A3. Ability to monitor automatic operations of the

AUTOMATIC DEPRESSURIZATION SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 ADS valve operation ..................................................... 4.2* 4.3
3.3-5 NUREG-1123, Rev. 2 |

SYSTEM: 218000 Automatic Depressurization System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A3.02 ADS valve tail pipe temperatures .......................................... 3.6 3.7

A3.03 ADS valve acoustical monitor noise: Plant-Specific .......................... 3.7 3.8

A3.04 Primary containment pressure ............................................ 3.7 3.8

A3.05 Suppression pool level ................................................... 3.6 3.7

A3.06 Suppression pool temperature ............................................. 3.9 3.9

A3.07 Lights and alarms ....................................................... 3.7 3.6

A3.08 Reactor pressure ........................................................ 4.2* 4.3*

A3.09 Reactor vessel water level ................................................ 4.1* 4.2*

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 ADS valves ............................................................ 4.4* 4.4*

A4.02 ADS logic initiation ..................................................... 4.2* 4.2*

A4.03 ADS logic reset ........................................................ 4.2* 4.2*

A4.04 ADS inhibit: Plant-Specific .............................................. 4.1 4.1*

A4.05 ADS timer reset ........................................................ 4.2* 4.2*

A4.06 ADS valve tail pipe temperature ........................................... 3.5 3.6

A4.07 ADS valve acoustical monitor noise: Plant-Specific .......................... 3.5 3.8

A4.08 Suppression pool level ................................................... 3.7 3.8

A4.09 Suppression pool temperature ............................................. 3.9 3.9

A4.10 Lights and alarms ....................................................... 3.8 3.8

A4.11 Reactor pressure ........................................................ 4.3* 4.3*

A4.12 Reactor vessel water level ................................................ 4.2* 4.3*
NUREG-1123, Rev. 2 3.3-6 |

SYSTEM: 239001 Main and Reheat Steam System

TASK: Perform lineups on the main steam system

Startup the main steam system (cold)

Operate the main steam isolation valves

Place the automatic pressure relief valves in service

Monitor the main steam system

Perform main steam isolation valve (MSIV) fast closure test (MSIV operability testing)

Perform main steam line high radiation functional test perform MSIV's, steam line drain valves and reactor

sample valves logic functional test

Perform main mechanical vacuum pump and valve

Isolation system functional test

Perform main steam isolation valve, main steam drain valve and reactor water sample valve simulated

automatic isolation test

Perform main steam isolation valves limit switch instrument functional test

Perform main steam line closure scram (MSLCS) operational test

Perform one train MSLCS inop surveillance

Perform main steam leakage control system operational test (write in)

Perform one train main steam leakage control system operability surveillance (write in)

Perform monthly main steam leakage control system division 1 and division 2 fan and heater tests (write

in)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between MAIN AND REHEAT STEAM

SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor vessel .......................................................... 3.4 3.4

K1.02 SPDS/ERlS/CRIDS/GDS: Plant-Specific ................................... 2.6 2.8

| K1.03 Main turbine ........................................................... 3.4 3.4

| K1.04 Moisture separators ..................................................... 2.8 2.9

K1.05 Moisture separator reheaters: Plant-Specific ................................ 2.8 2.8

K1.06 Steam bypass system .................................................... 3.4 3.4

K1.07 Offgas system .......................................................... 3.1 3.l

K1.08 Condenser air removal system ............................................ 2.9 3.1

K1.09 Steam seal/gland seal system ............................................. 2.7 2.8

K1.10 Extraction steam system ................................................. 2.7 2.8

K1.11 High pressure heater drains and vents ...................................... 2.5 2.5

K1.12 Plant air systems ........................................................ 2.5 2.6

K1.13 Main steam isolation valve leakage control: PlantSpecific ............................................................... 2.6 2.8

K1.14 Positive leakage control system: Plant Specific ............................. 2.8 3.1

K1.15 Process computer/ performance monitor system ............................ 2.1* 2.1

K1.16 Process radiation monitoring system ...................................... 3.2 3.4
3.3-7 NUREG-1123, Rev. 2 |

SYSTEM: 239001 Main and Reheat Steam System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.17 Containment system .................................................... 3.1 3.2

K1.18 High pressure coolant injection: Plant-Specific ............................. 3.5 3.6

K1.19 Reactor core isolation cooling system: 

Plant-Specific .......................................................... 3.1 3.2

K1.20 Residual heat removal system: Plant-Specific .............................. 2.9 2.9

K1.21 Isolation condenser system: Plant-Specific ................................ 3.7 3.7

K1.22 Feedwater system ...................................................... 3.1 3.2

K1.23 Reactor water level control system ........................................ 3.2 3.3

K1.24 Head vent ............................................................. 2.7 2.7

K1.25 Relief valves ........................................................... 3.5 3.5

Kl.26 Safety valves ........................................................... 3.7 3.8

K1.27 Reactor protection system ............................................... 4.0 4.1

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Main steam isolation valve solenoids ...................................... 3.2* 3.3*

K2.02 Main steam line shutoff valves (guard valves):

Plant-Specific ......................................................... 2.3* 2.3*

K3. Knowledge of the effect that a loss or malfunction of

the MAIN AND REHEAT STEAM SYSTEM will have on

following:

(CFR: 41.7 / 45.4)

K3.01 Turbine generator ...................................................... 3.2 3.3

K3.02 Condenser ............................................................ 3.1 3.2

K3.03 Reactor feedpump turbines: Plant-Specific ................................. 3.2 3.3

K3.04 Offgas system ......................................................... 2.8 2.8

K3.05 Condenser air removal .................................................. 2.8 2.9

K3.06 Seal steam/gland and seal system .......................................... 2.6 2.7

K3.07 Containment ........................................................... 3.1 3.3

K3.08 Decay heat removal ..................................................... 3.4 3.5

K3.09 Steam bypass capability ................................................. 3.6 3.7

K3.10 High pressure coolant injection system: PlantSpecific .............................................................. 3.5 3.5

K3.11 Reactor core isolation cooling system: Plant-Specific

...................................................................... 3.2 3.3

K3.12 Isolation condenser: Plant-Specific ....................................... 3.7 3.7

K3.13 Moisture separator reheaters: Plant-Specific ............................... 2.4 2.4

K3.14 Residual heat removal system: Plant-Specific .............................. 2.7 2.7

K3.15 Reactor water level control .............................................. 3.5 3.5

K3.16 Relief/safety valves ..................................................... 3.6 3.6

K3.17 Reactor vessel and internals .............................................. 3.2 3.3
NUREG-1123, Rev. 2 3.3-8 |

SYSTEM: 239001 Main and Reheat Steam System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4. Knowledge of MAIN AND REHEAT STEAM SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Automatic isolation of steam lines ........................................ 3.8 3.8

K4.02 Automatic isolation and opening of drain valves:

Plant-Specific ......................................................... 3.1 3.2

K4.03 Insures that steam released from a steam line break

will not bypass suppression pool; BWR-6 .................................. 3.2 3.3

K4.04 Limits steam flow during a steam line rupture to 200% ........................ 3.4 3.5

K4.05 Steam flow measurement ................................................ 3.1 3.2

K4.06 Allows for removal or prevents escape of radioactive

steam from systems that have leaky MSIV's ................................. 3.1 3.2

K4.07 Over pressure control ................................................... 3.7 3.7

K4.08 Removal of non condensable gases from reactor head

area .................................................................. 2.5 2.6

K4.09 Equalization of pressure across the MSIV's before

opening ............................................................... 3.3 3.3

K4.10 Moisture removal from steam lines prior to admitting

steam ................................................................. 2.9 3.0

K4.11 Positive sealing of the MSIV's when shutdown: PlantSpecific .............................................................. 2.9 3.1

K5. Knowledge of the operational implications of the

following concepts as they apply to MAIN AND REHEAT

STEAM SYSTEM :

(CFR: 41.5 / 45.3)

| K5.01 Constant enthalpy expansion through a valve ................................ 2.0* 2.2*

K5.02 Definition and causes of steam/water hammer ............................... 2.9 3.1

K5.03 Definition and causes of thermal stress .................................... 2.7 2.9

K5.04 Definition and reason for steam blanketing of moisture

| separator reheater: Plant-Specific ........................................ 1.8* 1.9*

K5.05 Flow indication ........................................................ 2.8 2.8

K5.06 Air operated MSIV's .................................................... 2.8 2.9

K5.07 Hydraulic operated MSIV's ............................................... 2.6 2.7

K5.08 Solenoid operated valves ................................................ 2.6 2.7

K5.09 Decay heat removal ..................................................... 3.4 3.5

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the MAIN AND REHEAT STEAM SYSTEM:

(CFR: 41.7 / 45.7)

K6.01 Electrical power ....................................................... 3.1 3.3

| K6.02 Plant air systems ....................................................... 3.2 3.2

| K6.03 Safety valve operability .................................................. 3.6 3.6
3.3-9 NUREG-1123, Rev. 2 |

SYSTEM: 239001 Main and Reheat Steam System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6.04 Relief valve operability: Plant-Specific .................................... 3.4 3.5

K6.05 Steam line integrity ..................................................... 3.6 3.7 |

K6.06 MSIV isolation signal ................................................... 3.8 3.9

K6.07 MSIV leakage control ................................................... 2.8 3.2

K6.08 Main condenser vacuum ................................................. 3.3 3.4

K6.09 PCIS/NSSSS ........................................................... 3.9 4.1* |

K6.10 ADS/low low set: Plant-Specific ......................................... 3.6 3.7

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the MAIN AND

REHEAT STEAM SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Main steam pressure .................................................... 3.6 3.6

A1.02 Main steam temperature ................................................. 2.6 2.6

A1.03 Reheat steam pressure: Plant-Specific ..................................... 2.2* 2.2* |

A1.04 Reheater temperature: Plant-Specific ..................................... 2.3* 2.3

A1.05 Main steam line radiation monitors ........................................ 3.6 3.6

A1.06 Air ejector process radiation monitor ...................................... 3.4 3.4

A1.07 Reactor water level ..................................................... 3.7 3.7

A1.08 Reactor pressure ....................................................... 3.8 3.8

A1.09 Main steam flow ....................................................... 3.5 3.4

A1.10 Reactor power ......................................................... 3.8 3.8

A2. Ability to (a) predict the impacts of the following on

the MAIN AND REHEAT STEAM SYSTEM ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Malfunction of reactor turbine pressure regulating

system ................................................................ 3.8 3.9

A2.02 Change in steam demand and its effect on reactor

pressure and power ..................................................... 3.6 3.8

A2.03 MSIV closure .......................................................... 4.0 4.2

A2.04 Main steam line low pressure ............................................. 3.5 3.6

A2.05 †Main steam line high radiation ................................................. 3.9 4.2* |

A2.06 Turbine trip without bypass valves ......................................... 4.1 4.3* |

A2.07 Main steam area high temperature or differential |

temperature high ....................................................... 3.8 3.9

A2.08 Low condenser vacuum .................................................. 3.6 3.6

A2.09 Opening of head vent to drywell equipment sump with

pressure in the reactor vessel ............................................. 3.4 3.7

A2.10 Closure of one or more MSIV's at power ................................... 3.8 3.9
NUREG-1123, Rev. 2 3.3-10 |

SYSTEM: 239001 Main and Reheat Steam System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

| A2.11 Steam line break ....................................................... 4.1 4.3*

| A2.12 PCIS/NSSSS actuation ................................................... 4.2* 4.3*

A2.13 High reactor water level ................................................. 3.5 3.7

A2.14 Inadvertent initiation of HPCI/HPCS/RCIC (steam

quality and steam flow): Plant-Specific .................................... 3.4 3.5

A3. Ability to monitor automatic operations of the MAIN

AND REHEAT STEAM SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Isolation of main steam system ........................................... 4.2* 4.1*

A3.02 Opening and closing of drain valves as turbine load

changes: Plant-Specific ................................................. 2.9 2.9

A3.03 Moisture separator reheat steam supply: PlantSpecific .............................................................. 2.8 2.8

A3.04 Isolation of moisture separator reheater: PlantSpecific .............................................................. 2.7 2.7

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 MSIV's ............................................................... 4.2* 4.0

A4.02 Maim steam line drain valves ............................................. 3.2 3.2

A4.03 System flow ........................................................... 3.5 3.5

A4.04 System pressure ........................................................ 3.8 3.7

A4.05 System temperature ..................................................... 2.7 2.7

A4.06 System radiation levels .................................................. 3.6 3.8

A4.07 Lights and alarms ....................................................... 3.3 3.3

A4.08 Reactor water level ..................................................... 3.7 3.7

A4.09 Reactor pressure ....................................................... 3.9 3.9

A4.10 Reactor power ......................................................... 3.8 3.8

A4.11 Alternate methods of verifying valve positions .............................. 3.1 3.3
3.3-11 NUREG-1123, Rev. 2 |

SYSTEM: 241000 Reactor/Turbine Pressure Regulating System

TASK: Manually operate the steam dump/turbine bypass control systems 

Monitor steam dump/turbine bypass control system 

Lineup reactor pressure control system for auto operation (write in)

Test control system prior to auto operation (write in) 

Perform lineups of the electro-hydraulic control hydraulic power unit

Fill the hydraulic power unit when shutdown 

Startup the electro-hydraulic control hydraulic power unit 

Operate EHC hydraulic pumps 

Shift EHC hydraulic coolers 

Operate polishing filters (fuller earth filters) 

Replace electro-hydraulic control system filters 

Fill the hydraulic power unit reservoir during normal operations 

Sample EHC hydraulic fluid 

Change accumulators during operation 

Monitor electro-hydraulic control hydraulic unit operation 

Adjust turbine load limits 

Operate the turbine governor test mechanism (test for operation of the overspeed trip device and

mechanical trip valve) 

Shutdown the electro-hydraulic control power unit 

Discharge hydraulic fluid while shutdown 

Perform test of the turbine overspeed protection controller (write in)

Test the turbine overspeed trip by actual turbine overspeed (write in)

Perform manual trip of turbine at front standard (write in) 

Adjust turbine load limits 

Operate the turbine governor test mechanism 

Operate the reactor turbine pressure regulating system using manual control mode 

Shift control modes (mechanical [manual]/electrical) of the reactor/turbine pressure regulating system 

Monitor the reactor/turbine pressure regulating system 

What if reactor pressure is high? 

Shift control modes (manual/automatic) of the reactor/turbine pressure regulating system 

Adjust the reactor/turbine pressure regulating system pressure

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between REACTOR/TURBINE PRESSURE

REGULATING SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor power .......................................................... 3.8 3.9

K1.02 Reactor pressure ........................................................ 3.9 4.1

K1.03 Reactor water level ...................................................... 3.6 3.7

K1.04 Reactor steam flow ..................................................... 3.7 3.7
NUREG-1123, Rev. 2 3.3-12 |

SYSTEM: 241000 Reactor Turbine Pressure Regulating System

Tasks as noted previously

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.05 Main turbine steam flow ................................................. 3.5 3.6

K1.06 Bypass valves .......................................................... 3.8 3.9

K1.07 Main stop/throttle valves ................................................. 3.4 3.6

K1.08 Control/governor valves .................................................. 3.6 3.7

| K1.09 Combined intermediate valves: Plant-Specific ............................... 3.1 3.4

K1.10 Front standard trip system ................................................ 3.2 3.3

K1.11 RPS .................................................................. 3.7 3.8

K1.12 FW extraction non-return valves ........................................... 2.4 2.6

K1.13 Bearing oil ............................................................. 2.6 2.6

K1.14 A.C. electrical power .................................................... 2.8 2.9

K1.15 D.C. electrical power .................................................... 2.6 2.7

K1.16 Component cooling water systems ......................................... 2.5 2.6

K1.17 Turbine chest warming: EHC-Only ........................................ 2.4 2.5

K1.18 Turbine shell warming: EHC-Only ......................................... 2.4 2.5

K1.19 Turbine acceleration ..................................................... 2.6 2.6

K1.20 Turbine speed .......................................................... 2.7 2.7

K1.21 Turbine inlet pressure ................................................... 2.7 2.7

K1.22 Turbine trip ............................................................ 3.4 3.5

K1.23 Recirculation flow control system: Plant-Specific ........................... 3.0 3.1

K1.24 Main generator ......................................................... 2.7 2.8

K1.25 Stator water cooling: Plant-Specific ....................................... 2.8 2.8

K1.26 Main turbine PMG: Plant-Specific ........................................ 2.4 2.6

K1.27 Condenser vacuum ...................................................... 3.1 3.1

K1.28 Reactor startup ......................................................... 3.2 3.2

K1.29 Reactor heatup ......................................................... 3.4 3.4

K1.30 Reactor cooldown ...................................................... 3.2 3.3

K1.31 Turbine protection ...................................................... 3.1 3.2

K1.32 Turbine monitoring ...................................................... 2.7 2.8

K1.33 FW extraction steam valves ............................................... 2.4 2.6

K1.34 EGC system: Plant-Specific .............................................. 2.8 3.3

K1.35 Low pressure stop and control valves: Plant-Specific. ........................ 2.4 2.6

| K1.36 Primary water system: Plant-Specific ...................................... 2.1*? 2.1*?

K1.37 Turbine stress evaluator: Plant-Specific .................................... 1.8* 1.8*

K1.38 PCIS/NSSSS: Plant-Specific ............................................. 2.7 2.8

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Pumps ................................................................ 2.1* 2.2*

K2.02 Controls ............................................................... 2.1* 2.1*

K3. Knowledge of the effect that a loss or malfunction of

the REACTOR/TURBINE PRESSURE REGULATING SYSTEM will

have on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor power ......................................................... 4.1 4.1
3.3-13 NUREG-1123, Rev. 2 |

SYSTEM: 241000 Reactor/Turbine Pressure Regulating System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3.02 Reactor pressure ........................................................ 4.2* 4.3*

K3.03 Reactor water level ...................................................... 3.7 3.8

K3.04 Reactor steam flow ..................................................... 3.8 3.9

K3.05 Main turbine steam flow ................................................. 3.7 3.7

K3.06 Bypass valves .......................................................... 4.1* 4.1

K3.07 Main stop/throttle valves ................................................. 3.3 3.3

K3.08 Control/governor valves .................................................. 3.7 3.7

K3.09 Combined intermediate valves: Plant-Specific ............................... 3.2 3.3

K3.10 Front standard trip system ................................................ 2.9 3.0

K3.11 RPS .................................................................. 3.8 3.8

K3.12 FW extraction steam valves: Plant-Specific ................................. 2.4 2.4

K3.13 FW extraction non-return valves ........................................... 2.3 2.4

K3.14 Component cooling water systems: Plant-Specific ........................... 2.3 2.3

K3.15 Turbine chest warming: EHC-Only ........................................ 2.8 2.8

K3.16 Turbine shell warming: EHC-Only ......................................... 2.8 2.8

K3.17 Turbine acceleration ..................................................... 2.7 2.8

K3.18 Turbine speed .......................................................... 2.9 2.9

K3.19 Turbine inlet pressure ................................................... 2.7 2.7

K3.20 Turbine trip ............................................................ 3.3 3.4

K3.21 Recirculation flow control system: Plant-Specific ........................... 2.8 2.8

K3.22 Main generator ......................................................... 2.6 2.6

K3.23 Turbine trip testing: Plant-Specific ........................................ 2.8 2.9

K3.24 Reactor heatup ......................................................... 3.2 3.2

K3.25 Reactor cooldown ...................................................... 3.3 3.3

K3.26 Turbine protection ...................................................... 3.1 3.2

K3.27 Turbine monitoring ...................................................... 2.4 2.6

K3.28 Low pressure stop and control valves: Plant-Specific. ........................ 2.5 2.5

K3.29 PCIS/NSSSS ........................................................... 2.9 3.1

K3.30 EGC: Plant-Specific .................................................... 3.0 3.0

K4. Knowledge of REACTOR/TURBINE PRESSURE REGULATING

SYSTEM design feature(s) and/or interlocks which

provide for the following:

(CFR: 41.7)

K4.01 Reactor pressure control ................................................. 3.8 3.8

K4.02 Turbine inlet pressure control ............................................. 3.3 3.3

K4.03 Turbine speed control ................................................... 3.0 3.1

K4.04 Turbine acceleration control .............................................. 2.8 2.8

K4.05 Reactor scram .......................................................... 3.7* 3.8*

K4.06 Turbine trip ............................................................ 3.6 3.7*

K4.07 Generator runback: Plant-Specific ........................................ 3.2 3.5

K4.08 Feedwater heater isolation: Plant-Specific .................................. 2.6 2.9

K4.09 Turbine chest warming: EHC-Only ........................................ 2.4 2.4

K4.10 Turbine shell warming: EHC-Only ......................................... 2.5 2.5

K4.11 Load following: Plant-Specific ........................................... 2.6 2.6

K4.12 Recirculation flow control: Plant-Specific ................................. 2.9 2.9
NUREG-1123, Rev. 2 3.3-14 |

SYSTEM: 241000 Reactor/Turbine Pressure Regulating System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.13 Turbine trip testing: Plant-Specific ........................................ 2.9 3.0

K4.14 Reactor/turbine pressure regulating system oil

cooling: Plant-Specific .................................................. 2.2 2.4

K4.15 Automatic pump start .................................................... 2.6 2.6

K4.16 Reactor cooldown ...................................................... 3.3 3.4

K4.17 Turbine monitoring ...................................................... 2.4 2.6

K4.18 Turbine protection ...................................................... 2.8 2.8

K4.19 Steam bypass valve control ............................................... 3.6 3.7

K5. Knowledge of the operational Implications of the

following concepts as they apply to REACTOR/TURBINE

PRESSURE REGULATING SYSTEM :

(CFR: 41.5 / 45.3)

| K5.01 Accumulator operation: Plant-Specific ..................................... 2.0* 2.1*

| K5.02 Limit switch operation ................................................... 2.1* 2.2*

K5.03 Reactor power vs. reactor pressure ........................................ 3.5 3.6

K5.04 Turbine inlet pressure vs. reactor pressure .................................. 3.3 3.3

K5.05 Turbine inlet pressure vs. turbine load ...................................... 2.8 2.9

K5.06 Turbine speed measurement .............................................. 2.3 2.3

K5.07 Unitized actuator operation: Fermi-Only ................................... 2.5 3.0

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the REACTOR/TURBINE

PRESSURE REGULATING SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical power .................................................... 2.8 2.9

K6.02 D.C. electrical power .................................................... 2.6 2.7

K6.03 Component cooling water systems ......................................... 2.5 2.5

K6.04 Recirculation flow control system: Plant-Specific ........................... 3.0 3.0

K6.05 Condenser vacuum ...................................................... 3.4 3.4

| K6.06 Reactor pressure ........................................................ 3.8* 3.9*

K6.07 Turbine inlet pressure ................................................... 3.4 3.4

| K6.08 Reactor power .......................................................... 3.6 3.7

| K6.09 Main turbine steam flow ................................................. 3.1 3.1

K6.10 Bypass valves .......................................................... 3.6 3.7

K6.11 Main stop/throttle valves ................................................. 3.4 3.4

K6.12 Control/governor valves .................................................. 3.3 3.4

K6.13 Combined intermediate valves: Plant-Specific ............................... 3.1 3.2

K6.14 Bearing oil ............................................................. 2.7 2.8

K6.15 Turbine speed signal ..................................................... 2.3 2.4

K6.16 Stator water cooling system: Plant-Specific ................................ 2.9 3.1

K6.17 Main turbine PMG: Plant-Specific ........................................ 2.7 2.8

K6.18 Low pressure stop and control valves: Plant-Specific. ........................ 2.6 2.7

| K6.19 Primary water system: Plant-Specific ...................................... 2.1* 2.3*

K6.20 Main generator ......................................................... 2.8 3.0
3.3-15 NUREG-1123, Rev. 2 |

SYSTEM: 241000 Reactor/Turbine Pressure Regulating System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A1. Ability to predict and/or monitor changes in

parameters associated with operating the

REACTOR/TURBINE PRESSURE REGULATING SYSTEM controls

including:

(CFR: 41.5 / 45.5)

A1.01 Reactor pressure ........................................................ 3.9 3.8

A1.02 Reactor power .......................................................... 4.1* 3.9

A1.03 Reactor water level ...................................................... 3.7 3.7

A1.04 Main turbine inlet pressure ............................................... 3.1 3.1

A1.05 Reactor steam flow ..................................................... 3.5 3.6 |

A1.06 Ma in turbine steam flow ................................................. 3.2 3.2

A1.07 Bypass valve position .................................................... 3.8 3.7

A1.08 control/governor valve position ........................................... 3.3 3.2

A1.09 Main stop throttle valve position .......................................... 3.3 3.3

A1.10 Combined intermediate valve position: Plant-Specific. ....................... 3.3 3.2

A1.11 Reactor/turbine pressure regulating system oil

pressure: Plant-Specific ................................................. 2.7 2.7

A1.12 Reactor/turbine pressure regulating system load

set/reference: Plant-Specific ............................................. 2.9 2.8

A1.13 Main turbine speed ...................................................... 2.7 2.7

A1.14 Pressure setpoint/pressure demand ........................................ 3.4 3.4

A1.15 Maximum combined flow limit ............................................ 3.1 3.1

A1.16 Load limit set: Plant-Specific ............................................ 3.3 3.3

A1.17 Reactor/turbine pressure regulating system oil pump

current: Plant-Specific .................................................. 1.9* 1.9*

A1.18 Reactor/turbine pressure regulating system reservoir

oil level: Plant-Specific ................................................. 2.1* 2.0*

Al.l9 Reactor/turbine pressure regulating system reservoir

oil temperature: Plant-Specific ........................................... 2.0* 1.9*

A1.20 Servo valve currents: Plant-Specific ....................................... 2.2* 2.1*

A1.21 Main condenser vacuum .................................................. 3.4 3.4

A1.22 Reactor cooldown ...................................................... 3.4 3.3

A1.23 Main turbine vibration ................................................... 2.8 2.8

A1.24 Main turbine eccentricity ................................................ 2.6 2.7

A1.25 Main turbine expansion .................................................. 2.6 2.6

A1.26 Governor valve limit: Plant-Specific ....................................... 2.4 2.4

A2. Ability to (a) predict the impacts of the following on

the REACTOR/TURBINE PRESSURE REGULATING SYSTEM ; and

(b) based on those predictions, use procedures to

correct, control, or mitigate the consequences of

those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Loss of turbine inlet pressure signal ....................................... 3.5 3.7

A2.02 High reactor pressure .................................................... 3.7 3.7
NUREG-1123, Rev. 2 3.3-16 |

SYSTEM: 241000 Reactor/Turbine Pressure Regulating System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A2.03 Failed open/closed bypass valve(s) ......................................... 4.1* 4.2*

A2.04 Failed open/closed control/governor valve(s) ................................ 3.7 3.8

A2.05 Failed open/closed main stop valve(s) ...................................... 3.8 3.9

A2.06 Low reactor/turbine pressure regulating system oil

pressure: Plant-Specific ................................................. 3.1 3.2

A2.07 Loss of condenser vacuum ............................................... 3.7 3.6

A2.08 Main turbine overspeed .................................................. 3.3 3.3

A2.09 Loss of generator load ................................................... 3.4 3.5

A2.10 Loss of stator water cooling: Plant-Specific ................................ 3.1 3.2

A2.11 Loss of A.C. electrical power ............................................. 3.1 3.1

A2.12 Loss of D.C. electrical power ............................................. 2.7 2.8

A2.13 Loss of component cooling water systems .................................. 2.6 2.7

A2.14 Loss of main turbine PMG: Plant-Specific ................................. 2.7 2.7

A2.15 Loss of main turbine speed feedback: Plant-Specific ......................... 2.4 2.4

A2.16 Low turbine inlet pressure (loss of pressure signal) ........................... 3.4 3.4

A2.17 Turbine trip: Plant-Specific .............................................. 3.8 3.8

A2.18 Generator trip: Plant-Specific ............................................ 3.5 3.5

A2.19 Reactor scram .......................................................... 3.8 3.8

A2.20 Low reactor/turbine pressure regulating system oil

level: Plant-Specific .................................................... 2.5 2.6

A2.21 Reactor/turbine pressure regulating system pump trip:

Plant-Specific .......................................................... 2.7 2.8

A2.22 Turbine high vibration ................................................... 2.8 2.9

A2.23 Turbine high eccentricity ................................................. 2.6 2.6

A2.24 Turbine high differential expansion ........................................ 2.4 2.5

A2.25 Loss of primary water system: Plant-Specific ............................... 2.1 2.3

A3. Ability to monitor automatic operations of the

REACTOR/TURBINE PRESSURE REGULATING SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Turbine speed control: Plant-Specific ...................................... 2.8 2.7

A3.02 Turbine acceleration control: Plant-Specific ................................ 2.6 2.6

A3.03 Turbine inlet pressure control ............................................. 2.8 2.7

A3.04 Reactor/turbine pressure regulating system pump start:

Plant-Specific .......................................................... 2.5 2.5

A3.05 Reactor/turbine pressure regulating system low

pressure turbine trip: Plant-Specific ....................................... 2.9 2.8

A3.06 Reactor/turbine pressure regulating system low

pressure reactor scram: Plant-Specific ..................................... 3.3 3.3

A3.07 Reactor/turbine pressure regulating system oil

temperature control: Plant-Specific ....................................... 2.3 2.3

A3.08 Steam bypass valve operation ............................................. 3.8 3.8

A3.09 Control/governor valve operation .......................................... 3.3 3.2

A3.10 Main stop/throttle valve operation ......................................... 3.3 3.3

A3.11 Combined intermediate valve operation: Plant-Specific ....................... 3.3 3.1

A3.12 Turbine trip testing ...................................................... 2.9 2.9
3.3-17 NUREG-1123, Rev. 2 |

SYSTEM: 241000 Reactor/Turbine Pressure Regulating System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A3.13 FW heater isolation: Plant-Specific ....................................... 2.7 2.8

A3.14 Grid load following: Plant-Specific ....................................... 2.6 2.7

A3.15 Recirculation pump flow control: Plant-Specific ............................ 2.8 2.9

A3.16 Lights and alarms ....................................................... 3.0 2.9

A3.17 Turbine runback ........................................................ 3.3 3.4

A3.18 Turbine startup: Plant-Specific ........................................... 3.0 3.0 |

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Reactor power .......................................................... 3.9 4.0

A4.02 Reactor pressure ........................................................ 4.1* 4.1* |

A4.03 Reactor water level ...................................................... 3.8* 3.9

A4.04 Reactor steam flow ..................................................... 3.6 3.7

A4.05 Main turbine steam flow ................................................. 3.3 3.3

A4.06 Bypass valves (operation) ................................................ 3.9 3.9

A4.07 Main stop/throttle valves (operation) ....................................... 3.5 3.4

A4.08 Control/governor valves (operation) ....................................... 3.5 3.4

A4.09 Combined intermediate valves (operation): PlantSpecific ............................................................... 3.2 3.1

A4.10 Reactor/turbine pressure regulating system pumps:

Plant-Specific .......................................................... 2.9 2.9

A4.11 Turbine speed .......................................................... 3.1 3.1

A4.12 Turbine acceleration ..................................................... 3.0 3.0

A4.13 Turbine inlet pressure ................................................... 2.9 2.9

A4.14 Turbine trip ............................................................ 3.8 3.7

A4.15 Generator load ......................................................... 3.2 3.2

A4.16 Lights and alarms ....................................................... 3.3 3.2

A4.17 Turbine chest warming: Plant-Specific ..................................... 2.9 2.8

A4.18 Turbine shell warming: Plant-Specific ..................................... 2.9 2.8

A4.19 Turbine panel controls ................................................... 3.5 3.4
NUREG-1123, Rev. 2 3.3-18 |

 SYSTEM: 239002 Relief/Safety Valves

TASK: Place the automatic pressure relief valves in service

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between RELIEF/SAFETY VALVES and

the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Nuclear boiler ......................................................... 3.8 3.9

K1.02 SPDS/ERIS/CRIDS/GDS: Plant-Specific .................................. 2.5* 2.9

| K1.03 Nuclear boiler instrument system ......................................... 3.5 3.6

K1.04 Main steam ............................................................ 3.6 3.7

K1.05 Plant air systems: Plant-Specific ......................................... 3.1 3.3

K1.06 Drywell instrument air/ drywell pneumatics: PlantSpecific .............................................................. 3.4 3.6

K1.07 Suppression pool ....................................................... 3.6 3.8

K1.08 Automatic depressurization system ........................................ 4.0* 4.1

K1.09 Drywell pressure (for safety valves which discharge to

the drywell airspace): Plant-Specific ...................................... 4.0 4.0

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 SRV solenoids ......................................................... 2.8* 3.2*

K3. Knowledge of the effect that a loss or malfunction of

the RELIEF/SAFETY VALVES will have on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor pressure control ................................................ 3.9 4.0

| K3.02 Reactor over pressurization .............................................. 4.2* 4.4*

| K3.03 Ability to rapidly depressurize the reactor .................................. 4.3* 4.4*

K4. Knowledge of RELIEF/SAFETY VALVES design feature(s)

and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Insures that only one or two safety/relief valves

reopen following the initial portion of a reactor

isolation event (LLS logic): Plant-Specific ................................. 3.9 4.0

K4.02 Minimizes containment fatigue duty cycles resulting

from relief valve cycling during decay-heat-dominant

period late in an isolation transient (LLS logic):

Plant-Specific ......................................................... 3.4 3.6

K4.03 Prevents siphoning of water into SRV discharge piping

and limits loads on subsequent actuation of SRV's ........................... 3.1 3.3

K4.04 Ensures even distribution of heat load to suppression

pool, and adequate steam condensing ...................................... 3.4 3.6
3.3-19 NUREG-1123, Rev. 2 |

SYSTEM: 239002 Relief/Safety Valves

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.05 Allows for SRV operation from more than one location:

Plant-Specific .......................................................... 3.6 3.7

K4.06 Detection of valve leakage ................................................ 3.5 3.7

K4.07 Minimum steam pressure required to keep SRV open or to

open SRV .............................................................. 3.1 3.2

K4.08 Opening of the SRV from either an electrical or

mechanical signal ., ..................................................... 3.6 3.7

K4.09 Manual opening of the SRV ............................................... 3.7 3.6

K5. Knowledge of the operational implications of the

following concepts as they apply to RELIEF/SAFETY

VALVES :

(CFR: 41.5 / 45.3)

K5.01 Relief function of SRV operation .......................................... 3.4 3.5

K5.02 Safety function of SRV operation .......................................... 3.7 3.8

K5.03 Acoustical monitoring: Plant-Specific ..................................... 3.7 3.8

K5.04 Tail pipe temperature monitoring .......................................... 3.3 3.5

K5.05 Discharge line quencher operation ......................................... 2.6 2.9

K5.06 Vacuum breaker operation ................................................ 2.7 3.0

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the RELIEF/SAFETY VALVES :

(CFR: 41.7 / 45.7)

K6.01 Nuclear boiler instrument system (pressure indication) ....................... 3.2 3.4

K6.02 Air (Nitrogen) supply: Plant-Specific ...................................... 3.4 3.5

K6.03 A.C. power: Plant-Specific ............................................... 2.7* 2.9*

K6.04 D.C. power: Plant-Specific ............................................... 3.0 3.2

K6.05 Discharge line vacuum breaker ............................................ 3.0 3.2

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the RELIEF/SAFETY

VALVES controls including:

(CFR: 41.5 / 45.5)

A1.01 Tail pipe temperature .................................................... 3.3 3.4

A1.02 Acoustical monitor noise: Plant-Specific ................................... 3.7 3.8

A1.03 Air supply: Plant-Specific ............................................... 2.8 2.9

A1.04 Reactor pressure ........................................................ 3.8 3.8

A1.05 Reactor water level ...................................................... 3.7 3.8

A1.06 Reactor power .......................................................... 3.7 3.8

A1.07 Turbine load ........................................................... 2.9 3.0

A1.08 Suppression pool water temperature ....................................... 3.8 4.1

A1.09 Indicated vs. actual steam flow: Plant-Specific .............................. 3.1 3.3
NUREG-1123, Rev. 2 3.3-20 |

SYSTEM: 239002 Relief/Safety Valves

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A2. Ability to (a) predict the impacts of the following on

the RELIEF/SAFETY VALVES ; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 Stuck open vacuum breakers .............................................. 3.0 3.3

A2.02 Leaky SRV ............................................................. 3.1 3.2

A2.03 Stuck open SRV ........................................................ 4.1 4.2*

A2.04 ADS actuation .......................................................... 4.1* 4.2*

A2.05 Low reactor pressure .................................................... 3.2 3.4

A2.06 Reactor high pressure ................................................... 4.1 4.3*

A3. Ability to monitor automatic operations of the

RELIEF/SAFETY VALVES including:

(CFR: 41.7 / 45.7)

A3.01 SRV operation after ADS actuation ........................................ 3.8* 3.9*

A3.02 SRV operation on high reactor pressure .................................... 4.3* 4.3*

A3.03 Tail pipe temperatures ................................................... 3.6 3.6

A3.04 Acoustical monitor noise: Plant-Specific ................................... 3.6 3.7

A3.05 Suppression pool temperature ............................................. 4.1* 4.2*

A3.06 Reactor pressure ........................................................ 4.1* 4.1*

A3.07 Reactor water level ...................................................... 3.8 3.9

A3.08 Lights and alarms ....................................................... 3.6 3.6

A3.09 Low low set logic: Plant-Specific ......................................... 3.9 3.9

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 SRV's ................................................................. 4.4* 4.4*

A4.02 Tail pipe temperatures ................................................... 3.6 3.7

A4.03 Acoustical monitor noise: Plant-Specific ................................... 3.8 3.9

A4.04 Suppression pool temperature ............................................. 4.3* 4.3*

A4.05 Reactor pressure ........................................................ 4.3* 4.3*

A4.06 Reactor water level ...................................................... 3.9 4.1

A4.07 Lights and alarms ....................................................... 3.6 3.6

A4.08 Plant air system pressure: Plant-Specific ................................... 3.2 3.2
3.4-1 NUREG-1123, Rev. 2 |

3.4 Heat Removal from Reactor Core page

206000 High Pressure Coolant Injection System 3.4-3

209002 High Pressure Core Spray System 3.4-8

207000 Isolation (Emergency) Condenser 3.4-12

209001 Low Pressure Core Spray System 3.4-16

239001 Main and Reheat Steam System 3.4-20

245000 Main Turbine Generator and Auxiliary Systems 3.4-25

217000 Reactor Core Isolation Cooling System 3.4-29

202001 Recirculation System 3.4-33

203000 Residual Heat Removal /Low Pressure Coolant Injection: 3.4-38

 Injection Mode

205000 Shutdown Cooling System (RHR Shutdown Cooling Mode) 3.4-42
NUREG-1123, Rev. 2 3.4-2 |

This page left blank
3.4-3 NUREG-1123, Rev. 2 |

SYSTEM: 206000 High Pressure Coolant Injection System

TASK: Place the high pressure (Feedwater) coolant injection system (FWCI) in standby readiness

Monitor the high pressure (feedwater) coolant injection system operation

Return the high pressure (feedwater) coolant injection system to stand-by readiness after automatic

initiation

Perform lineups of the high pressure coolant injection system (write in)

Manually initiate high pressure coolant injection

Perform high pressure coolant injection (HPCI) simulated automatic actuation test

Perform high pressure (feedwater) coolant injection flow rate test

Perform high pressure (feedwater) coolant injection (HPCI) pump operability test

Perform high pressure (feedwater) coolant injection motor operated valve operability test

Perform HPCI subsystem logic system functional test

Perform HPCI subsystem automatic isolation logic system functional test

Perform HPCI system inoperable test

Perform HPCI turbine overspeed test

Perform high pressure (feedwater) coolant injection operability test when reactor core isolation cooling

is inoperable

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between HIGH PRESSURE COOLANT

INJECTION SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor vessel: BWR-2,3,4 .............................................. 3.8 3.9

K1.02 Reactor water level: BWR-2,3,4 .......................................... 4.0 4.1* |

K1.03 Reactor pressure: BWR-2,3,4 ............................................ 3.8 3.8 |

K1.04 Reactor feedwater system: BWR-2,3,4 .................................... 3.6 3.6

K1.05 Condensate storage system: BWR-2,3,4 ................................... 3.7 3.7 |

K1.06 Suppression chamber: BWR-2,3,4 ........................................ 3.7 3.7 |

K1.07 D.C. power: BWR-2,3,4 ................................................. 3.7* 3.8* |

K1.08 A.C. power: BWR-2,3,4 ................................................. 3.0* 3.1* |

K1.09 ECCS keep fill system: BWR-2,3,4(P-Spec) ................................ 4.0* 4.0 |

K1.10 Condensate storage and transfer system: BWR-2,3,4 ......................... 3.4 3.4

K1.11 PCIS: BWR-2,3,4 ...................................................... 3.5 3.5

K1.12 Nuclear boiler instrumentation: BWR-2,3,4 ................................ 3.4 3.4 |

K1.13 Main condenser: BWR-2,3,4(P-Spec) ..................................... 2.8* 2.9* |

K1.14 SBGT: BWR-2,3,4(P-Spec) .............................................. 2.9 3.1

K1.15 Plant air systems: BWR-2,3,4 ............................................ 2.3* 2.3* |

K1.16 Containment/Torus pressure: BWR-2,3,4 .................................. 3.5 3.5 |
NUREG-1123, Rev. 2 3.4-4 |

SYSTEM: 206000 High Pressure Coolant Injection System

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 System valves: BWR-2,3,4 .............................................. 3.2* 3.3*

K2.02 System pumps: BWR-2,3,4 .............................................. 2.8* 3.1*

K2.03 Initiation logic: BWR-2,3,4 ............................................. 2.8* 2.9*

K2.04 Turbine control circuits: BWR-2,3,4 ...................................... 2.5* 2.7*

K3. Knowledge of the effect that a loss or malfunction of

the HIGH PRESSURE COOLANT INJECTION SYSTEM will have

on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level control: BWR-2,3,4 ................................... 4.0 4.0

K3.02 Reactor pressure control: BWR-2,3,4 ..................................... 3.8* 3.8*

K3.03 Suppression pool level control: BWR-2,3,4 ................................ 3.4* 3.5*

K4. Knowledge of HIGH PRESSURE COOLANT INJECTION SYSTEM

design feature(s) and/or interlocks which provide for

the following:

(CFR: 41.7)

K4.01 Turbine trips: BWR-2,3,4 ............................................... 3.8 3.9

K4.02 System isolation: BWR-2,3,4 ............................................ 3.9 4.0

K4.03 Resetting turbine trips: BWR-2,3,4 ....................................... 4.2 4.1

K4.04 Resetting system isolations: BWR-2,3,4 ................................... 4.0 3.9

K4.05 Preventing water hammer in turbine exhaust line

(procedural control): BWR-2,3,4 ......................................... 3.1 3.4

K4.06 Preventing water hammer in pump discharge line

(procedural control ): BWR-2, 3, 4 ....................................... 3.2 3.4

K4.07 Automatic system initiation: BWR-2,3,4 .................................. 4.3* 4.3

K4.08 Manual system initiation: BWR-2,3,4 ..................................... 4.2* 4.3

K4.09 Automatic flow control: BWR-2,3,4 ...................................... 3.8 3.9

K4.10 Surveillance for all operable components: BWR-2,3,4 . ....................... 3.7 3.8

K4.11 Turbine speed control: BWR-2,3,4 ....................................... 3.4 3.5

K4.12 Condensation of shaft sealing steam: BWR-2,3,4 ........................... 2.9 3.0

K4.13 Turbine and pump lubrication: BWR-2,3,4 ................................. 3.0 3.1

K4.14 Control oil to turbine speed controls: BWR-2,3,4 ........................... 3.4 3.4

K4.15 Low speed turning of the turbine rotor: BWR-2,3,4(PSpec) ................................................................. 3.2 3.2

K4.16 Minimizing fission product concentration in the

condensate storage tank (valve closures on system

initiation): BWR-2,3,4(P-Spec) .......................................... 3.1 3.3

K4.17 Protection against draining the condensate storage

tank to the suppression pool: BWR-2,3,4 .................................. 3.4 3.4

K4.18 Pump minimum flow: BWR-2,3,4 ........................................ 3.2 3.3

K4.19 Automatic transfer of HPCI pump suction: BWR-2,3,4 ....................... 3.7 3.8
3.4-5 NUREG-1123, Rev. 2 |

SYSTEM: 206000 High Pressure Coolant Injection System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K5. Knowledge of the operational implications of the

following concepts as they apply to HIGH PRESSURE

COOLANT INJECTION SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Turbine operation: BWR-2,3,4 ........................................... 3.3 3.4

K5.02 Turbine shaft sealing: BWR-2,3,4 ......................................... 2.8 2.9

K5.03 GEMAC controllers: BWR-2,3,4(P-Spec) .................................. 3.1 3.1

K5.04 Indications of pump cavitation: BWR-2,3,4 ................................. 2.6* 2.7* |

K5.05 Turbine speed control: BWR-2,3,4 ........................................ 3.3 3.3

K5.06 Turbine speed measurement: BWR-2,3,4 ................................... 2.6* 2.6

K5.07 System venting: BWR-2,3,4 .............................................. 2.8 2.8

K5.08 Vacuum breaker operation: BWR-2,3,4 .................................... 3.0 3.2

K5.09 Testable check valve operation: BWR-2,3,4 ................................. 2.7* 2.8

K5.10 Assist core cooling: BWR-2,3,4 .......................................... 3.5 3.5

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the HIGH PRESSURE COOLANT

INJECTION SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 Plant air systems: BWR-2,3,4 ............................................ 2.3* 2.3* |

K6.02 D.C. power: BWR-2,3,4 ................................................. 3.3 3.7* |

K6.03 A.C. power: BWR-2,3,4 ................................................. 2.9 3.1* |

K6.04 Condensate storage tank level: BWR-2,3,4 ................................. 3.5 3.7

K6.05 Suppression pool level: BWR-2,3,4 ....................................... 3.5 3.7

K6.06 SBGTS: BWR-2,3,4(P-Spec) ............................................. 3.1 3.2

K6.07 ECCS keep fill system: BWR-2,3,4(P-Spec) ................................ 3.4 3.4

K6.08 Reactor pressure: BWR-2,3,4 ............................................ 3.8 3.8

K6.09 Condensate storage and transfer system: BWR-2,3,4 ......................... 3.5 3.5

K6.10 PCIS: BWR-2,3,4 ...................................................... 3.8 4.0

K6.11 Nuclear boiler instrumentation: BWR-2,3,4 ................................ 3.6 3.7

K6.12 Reactor water level: BWR-2,3,4 .......................................... 4.2* 4.3* |

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the HIGH PRESSURE

COOLANT INJECTION SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor water level: BWR-2,3,4 .......................................... 4.3* 4.4* |

A1.02 Reactor pressure: BWR-2,3,4 ............................................ 4.2* 4.2

A1.03 Condensate storage tank level: BWR-2,3,4 ................................. 3.5 3.6

A1.04 Suppression pool level: BWR-2,3,4 ....................................... 3.7 3.8

A1.05 Suppression pool temperature: BWR-2,3,4 ................................. 4.1 4.2

A1.06 System flow: BWR-2,3,4 ................................................ 3.8 3.7
NUREG-1123, Rev. 2 3.4-6 |

SYSTEM: 206000 High Pressure Coolant Injection System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A1.07 System discharge pressure: BWR-2,3,4 3.7 3.6

A1.08 System lineup: BWR-2,3,4 4.1* 4.0

A1.09 Turbine speed: BWR-2,3,4 ............................................... 3.5 3.4

A2. Ability to (a) predict the impacts of the following on

the HIGH PRESSURE COOLANT INJECTION SYSTEM ; and (b)

based on those predictions, use procedures to correct,

control, or mitigate the consequences of those

abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Turbine trips: BWR-2,3,4 ................................................ 4.0 4.0

A2.02 Valve closures: BWR-2,3,4 .............................................. 3.5 3.5

A2.03 Valve openings: BWR-2,3,4 .............................................. 3.5 3.5

A2.04 A.C. failures: BWR-2,3,4 ................................................ 2.7* 3.0*

A2.05 D.C. failures: BWR-2,3,4 ................................................ 3.5 3.8*

A2.06 Inadequate system flow: BWR-2,3,4 ....................................... 3.3 3.5

A2.07 Low suppression pool level: BWR-2,3,4 ................................... 3.4 3.6

A2.08 †High suppression pool temperature: BWR-2,3,4 ............................ 3.9 4.2

A2.09 †Low condensate storage tank level: BWR-2,3,4 ............................ 3.5 3.7

A2.10 System isolation: BWR-2,3,4 ............................................ 4.0 4.1

A2.11 Low reactor water level: BWR-2,3,4 ...................................... 4.1 4.2

A2.12 Loss of room cooling: BWR-2,3,4 ........................................ 3.4 3.5

A2.13 Loss of applicable plant air systems: BWR-2,3,4 ............................ 2.4* 2.4*

A2.14 Flow controller failure: BWR-2,3,4 ....................................... 3.3 3.4

A2.15 Loss of control oil pressure: BWR-2,3,4 ................................... 3.4 3.5

A2.16 High drywell pressure: BWR-2,3,4 ........................................ 4.0 4.1

A2.17 †HPCI inadvertent initiation: BWR-2,3,4 ................................... 3.9 4.3*

A3. Ability to monitor automatic operations of the HIGH

PRESSURE COOLANT INJECTION SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Turbine speed: BWR-2,3,4 ............................................... 3.6 3.5

A3.02 System Flow: BWR-2,3,4 ................................................ 3.8 3.8

A3.03 System lineup: BWR-2,3,4 ............................................... 3.9 3.8

A3.04 Reactor pressure: BWR-2,3,4 ............................................ 4.2* 4.1

A3.05 Reactor water level: BWR-2,3,4 .......................................... 4.3* 4.3

A3.06 System discharge pressure: BWR-2,3,4 .................................... 3.8 3.8

A3.07 Lights and alarms: BWR-2,3,4 ............................................ 3.9 3.8

A3.08 Condensate storage tank level: BWR-2,3,4 ................................. 3.7 3.6

A3.09 Response to system isolation: BWR-2,3,4 .................................. 4.2* 4.1
3.4-7 NUREG-1123, Rev. 2 |

SYSTEM: 206000 High Pressure Coolant Injection System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Turbine speed controls: BWR-2,3,4 ....................................... 3.8 3.7

A4.02 Flow controller: BWR-2,3,4 ............................................. 4.0* 3.8

A4.03 Turbine temperatures: BWR-2,3,4 ........................................ 3.1 3.0

A4.04 Major system valves: BWR-2,3.4 ......................................... 3.7 3.7

A4.05 Reactor water level: BWR-2,3,4 .......................................... 4.4* 4.4*

A4.06 Reactor pressure: BWR-2,3,4 ............................................ 4.3* 4.3*

A4.07 Condensate storage tank level: BWR-2,3,4 ................................. 3.5 3.5

A4.08 Suppression pool temperature: BWR-2,3,4 ................................. 4.1* 4.1

A4.09 Suppression pool level: BWR-2,3,4 ....................................... 3.8 3.7

A4.10 System pumps: BWR-2,3,4 .............................................. 3.7 3.5

A4.11 Turning gear: BWR-2,3,4(P-Spec) ........................................ 3.0 3.0

A4.12 Turbine trip controls: BWR-2,3,4 ......................................... 4.0 3.9

A4.13 Turbine reset control: BWR-2,3,4 ......................................... 4.1* 4.0

A4.14 System auto start control: BWR-2,3,4(P-Spec) .............................. 4.2* 4.1
NUREG-1123, Rev. 2 3.4-8 |

SYSTEM: 209002 High Pressure Core Spray System (HPCS)

TASK: Perform lineups on the core spray system

Place core spray (CS) system in standby readiness

Monitor automatic operation of core spray system

Shutdown core spray cooling system

Perform core spray simulated automatic actuation test

Perform core spray pump operability test

Perform core spray system inop test

Conduct core spray - cold shutdown valve testing

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between HIGH PRESSURE CORE SPRAY

SYSTEM (HPCS) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Condensate transfer and storage system: BWR-5,6 ........................... 3.4 3.4

K1.02 Suppression Pool: BWR-5,6 ............................................. 3.5 3.5

K1.03 Water leg (jockey) pump: BWR-5,6 ....................................... 3.0 3.0

K1.04 HPCS diesel generator: BWR-5,6 ......................................... 3.8 3.8

K1.05 Standby liquid control system: Plant-Specific ............................... 2.8 2.8

K1.05 Suppression pool cleanup system: BWR-5,6 ................................ 2.0* 2.0

K1.07 ECCS room coolers: BWR-5,6 ........................................... 2.4 2.4

K1.08 Component cooling water systems: BWR-5,6 ............................... 2.4 2.6

K1.09 Leak detection: BWR-5,6 ................................................ 2.5 2.5

K1.10 Suppression pool suction strainers: BWR-5,6 ............................... 2.1* 2.1

K1.11 Adequate core cooling: BWR-5,6 ......................................... 3.8 4.0

Kl.12 Reactor vessel: BWR-5,6 ................................................ 3.4 3.6

K1.13 Instrument nitrogen: BWR-5,6 ........................................... 2.7 2.7

K1.14 Plant air systems: BWR-5,6 .............................................. 2.6 2.6

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Pump electrical power: BWR-5,6 ......................................... 3.2 3.3

K2.02 Valve electrical power: BWR-5,6 ......................................... 2.8 2.9

K2.03 Initiation logic: BWR-5,6 ................................................ 2.8 2.9

K3. Knowledge of the effect that a loss or malfunction of

the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) will have

on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level: BWR-5,6 ............................................ 3.9 3.9

K3.02 Standby liquid control system: Plant-Specific ............................... 3.3 3.3

K3.03 Adequate core cooling: BWR-5,6 ......................................... 3.9 4.1
3.4-9 NUREG-1123, Rev. 2 |

SYSTEM: 209002 High Pressure Core Spray System (HPCS)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4. Knowledge of HIGH PRESSURE CORE SPRAY SYSTEM (HPCS)

design feature(s) and/or interlocks which provide for

the following:

(CFR: 41.7)

K4.01 Prevents water hammer: BWR-5,6 ........................................ 2.9 3.0

K4.02 Prevents over filling reactor vessel: Plant-Specific. .......................... 3.4 3.5

K4.03 Prevents pump over heating: BWR-5,6 ..................................... 2.3* 2.4

K4.04 Testable check valve operation: BWR-5,6 .................................. 2.3* 2.3*

K4.05 Motor operated valve operation: BWR-5,6 ................................. 2.4 2.4

K4.06 Centrifugal pump operation: BWR-5,6 ..................................... 2.3* 2.4*

K4.07 Override of reactor water level interlock: PlantSpecific ............................................................... 3.5 3.7

K5. Knowledge of the operational implications of the

following concepts as they apply to HIGH PRESSURE CORE

SPRAY SYSTEM (HPCS):

(CFR: 41.5 / 45.3)

K5.01 Indications of pump cavitation: BWR-5,6 ................................... 2.5 2.8

K5.02 Heat removal (transfer) mechanism: BWR-5,6 .............................. 2.6 2.7

K5.03 System venting: BWR-5,6 ............................................... 2.4 2.4

K5.04 Adequate core cooling: BWR-5,6 ......................................... 3.8 4.0

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the HIGH PRESSURE CORE

SPRAY SYSTEM (HPCS):

(CFR: 41.7 / 45.7)

K6.01 Electrical power: BWR-5,6 .............................................. 3.6 2.6

K6.02 Condensate storage tank water level: BWR-5,6 .............................. 3.4 3.4

K6.03 Component cooling water systems: BWR-5,6 ............................... 2.5 2.6

K6.04 Suppression pool suction strainer: BWR-5,6 ................................ 2.5 2.5

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the HIGH PRESSURE

CORE SPRAY SYSTEM (HPCS) controls including:

(CFR: 41.5 / 45.5)

A1.01 HPCS flow: BWR-5,6 ................................................... 3.6 3.7

A1.02 HPCS pressure: BWR-5,6 ............................................... 3.4 3.6

A1.03 Reactor water level: BWR-5,6 ............................................ 3.7 3.7

A1.04 Reactor pressure: BWR-5,6 .............................................. 3.3 3.3

A1.05 Suppression pool water level: BWR-5,6 .................................... 3.3 3.4

A1.06 Motor amps: BWR-5,6 .................................................. 1.9* 2.3*

A1.07 Diesel loading: BWR-5,6 ................................................ 2.5* 2.8

A1.08 System lineup: BWR-5,6 ................................................ 3.1 3.3
NUREG-1123, Rev. 2 3.4-10 |

SYSTEM: 209002 High Pressure Core Spray System (HPCS)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A1.09 Condensate storage tank level: BWR-5,6 ................................... 2.6 2.8

A2. Ability to (a) predict the impacts of the following on

the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) ; and (b)

based on those predictions, use procedures to correct,

control, or mitigate the consequences of those

abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 System initiation: BWR-5,6 ............................................... 3.8 3.8

A2.02 Pump trips: BWR-5,6 .................................................... 3.6 3.7

A2.03 Valve closures: BWR-5,6 ................................................. 3.2 3.4

A2.04 A.C. electrical failure: BWR-5,6 ........................................... 3.1 3.2

A2.05 D.C. electrical failure: BWR-5,6 ........................................... 2.8 2.9

A2.06 Core spray line break: BWR-5,6 ........................................... 3.4 3.6

A2.07 Pump seal failure: BWR-5,6 .............................................. 2.6 3.0

A2.08 Inadequate system flow: BWR-5,6 ......................................... 3.1 3.2

A2.09 Loss of room cooling: BWR-5,6 ........................................... 2.4 2.6

A2.10 Valve openings: BWR-5,6 ................................................ 2.7 3.0

A2.11 Low suppression pool level: BWR-5,6 ..................................... 3.3 3.5

A2.12 High suppression pool level BWR-5,6 ....................................... 3.3 3.5

A2.13 Low condensate storage tank level BWR-5,6 ................................. 3.4 3.5

A2.14 High suppression pool temperature: BWR-5,6 ............................... 3.0 3.3

A2.15 Clogged suppression pool suction strainers: BWR-5,6. ........................ 2.4 2.6

A3. Ability to monitor automatic operations of the HIGH

PRESSURE CORE SPRAY SYSTEM (HPCS) including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation: BWR-5,6 ................................................ 3.3 3.3

A3.02 Pump start: BWR-5,6 .................................................... 3.8 3.8

A3.03 System pressure: BWR-5,6 ............................................... 3.6 3.6

A3.04 System flow: BWR-5,6 ................................................... 3.7 3.7

A3.05 Reactor water level BWR-5,6 .............................................. 3.7 3.7

A3.06 Lights and alarms: BWR-5,6 .............................................. 2.8 2.8

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 HPCS pump: BWR-5,6 ................................................... 3.7 3.7

A4.02 Suction valves: BWR-5,6 ................................................. 3.6 3.6

A4.03 Injection valve: BWR-5,6 ................................................. 3.8 3.8

A4.04 Minimum flow valve: BWR-5,6 ............................................ 3.1 3.1

A4.05 Manual Initiation controls: BWR-5,6 ....................................... 3.8 3.8
3.4-11 NUREG-1123, Rev. 2 |

SYSTEM: 209002 High Pressure Core Spray System (HPCS)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A4.06 Testable check valve: BWR-5,6. . .......................................... 2.6 2.6

A4.07 Line fill pump: BWR-5,6 ................................................. 2.8 2.8

A4.08 Reactor water level: BWR-5,6 ............................................. 3.6 3.7

A4.09 Suppression pool level: BWR-5,6 ......................................... 3.4 3.5

A4.10 Reactor pressure: BWR-5,6 ............................................... 3.3 3.3

A4.11 System flow: BWR-5,6 ................................................... 3.8 3.8

A4.12 System pressure: BWR-5,6 ............................................... 3.4 3.4

A4.13 Lights and alarms: BWR-5,6 .............................................. 2.6 2.6

A4.14 Test return valve: BWR-5,6 ............................................... 3.0 3.0

A4.15 Initiation reset: BWR-5,6 ................................................. 3.6 3.6
NUREG-1123, Rev. 2 3.4-12 |

SYSTEM: 207000 Isolation (Emergency) Condenser

TASK: Perform lineups on the isolation condenser system

Fill and add makeup to the isolation condenser system

Place the isolation condenser (Iso-Cond) in standby

Place the isolation condenser system in service from a standby readiness condition

Remove the isolation condenser system from service

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between ISOLATION (EMERGENCY)

CONDENSER and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor vessel: BWR-2,3 ............................................... 3.8 4.0

K1.02 Reactor pressure: BWR-2,3 ............................................. 4.0 4.2

K1.03 Reactor water level: BWR-2,3 ........................................... 3.7 3.8

K1.04 Condensate transfer system: BWR-2,3 .................................... 3.5 3.8

K1.05 Demineralized water system: BWR-2,3(P-Spec) ............................ 3.4 3.6

K1.06 Fire protection/service water: BWR-2,3 ................................... 3.3* 3.7

K1.07 LPCI: BWR-2,3(P-Spec) ................................................ 3.0* 3.3*

K1.08 Recirculation system: BWR-2,3 .......................................... 3.0 3.2

Kl.09 Main steam system: BWR-2,3. ........................................... 3.0 3.2

K1.10 Plant air systems: BWR-2,3 ............................................. 3.0* 3.2

K1.11 Primary containment isolation system: BWR-2,3 ........................... 3.4 3.6

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Motor operated valves: BWR-2,3 ......................................... 3.6 3.8

K2.02 Initiation logic: BWR-2,3 ............................................... 3.5 3.7

K3. Knowledge of the effect that a loss or malfunction of

the ISOLATION (EMERGENCY) CONDENSER will have on

following:

(CFR: 41.7 / 45.4)

K3.01 Reactor pressure control during conditions in which

the reactor vessel is isolated: BWR-2,3 ................................... 4.2* 4.3*

K3.02 †Reactor water level (EPG's address the isolation

condenser as a water source): BWR-2,3 ................................... 3.8* 4.0*

K4. Knowledge of ISOLATION (EMERGENCY) CONDENSER design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Isolation of the system in the event of a line break:

BWR2,3 .............................................................. 4.3* 4.5*

K4.02 Automatic initiation: BWR-2,3 ........................................... 4.2* 4.2
3.4-13 NUREG-1123, Rev. 2 |

SYSTEM: 207000 Isolation (Emergency) Condenser

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.03 Filling of the system: BWR-2,3 .......................................... 3.3 3.5

K4.04 Steam and condensate flow indication: BWR-2,3 ............................ 3.2 3.4

K4.05 Detection of a tube bundle leak: BWR-2,3 ................................. 4.0* 4.2

K4.06 Throttling of system flow: BWR-2,3 ...................................... 3.8* 4.0

K4.07 Manual operation of the system: BWR-2,3 ................................. 3.8* 4.0

K4.08 Protection against incomplete steam condensation

(condensate outlet valve does not fully open): BWR2,3,(P-Spec) ........................................................... 3.4 3.6

K5. Knowledge of the operational implications of the

following concepts as they apply to ISOLATION

(EMERGENCY) CONDENSER :

(CFR: 41.5 / 45.3)

K5.01 Flow measurement across an elbow using differential

pressure: BWR-2,3 ..................................................... 2.6* 3.0*

K5.02 Heat exchanger operation: BWR-2,3 ...................................... 3.0 3.3

K5.03 Heat transfer: BWR-2,3 ................................................. 2.7 3.0

K5.04 Latent heat of vaporization: BWR-2,3 ...................................... 2.3* 2.7*

K5.05 Saturated steam: BWR-2,3 ............................................... 2.5* 2.7

K5.06 Saturated liquid: BWR-2,3 .............................................. 2.5* 2.7

K5.07 Temperature sensing: BWR-2,3 ........................................... 2.7* 2.8

K5.08 Level indicator operation: BWR-2,3 ....................................... 2.8* 3.0

K5.09 Cooldown rate: BWR-2,3 ................................................ 3.7 4.0

K5.10 System venting: BWR-2,3 ............................................... 3.0 3.2

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the ISOLATION (EMERGENCY)

CONDENSER :

(CFR: 41.7 / 45.7)

K6.01 Demineralized water system: BWR-2,3(P-Spec) ............................ 3.3 3.7

K6.02 Fire protection/service water system: BWR-2,3 ............................ 3.5 3.7

K6.03 Condensate transfer system: BWR-2,3 .................................... 3.5 3.8

K6.04 Plant air systems: BWR-2,3 ............................................. 3.2* 3.3*

K6.05 Primary containment isolation system: BWR-2,3 ........................... 3.6 3.8

K6.06 Recirculation system: BWR-2,3 .......................................... 3.0 3.2

K6.07 A.C. power: BWR-2,3 .................................................. 3.0* 3.2

K6.08 D.C. power: BWR-2,3 .................................................. 3.5 3.7
NUREG-1123, Rev. 2 3.4-14 |

SYSTEM: 207000 Isolation (Emergency) Condenser

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the ISOLATION

(EMERGENCY) CONDENSER controls including:

(CFR: 41.5 / 45.5)

A1.01 Isolation condenser level: BWR-2,3 ...................................... 3.7 3.8

A1.02 Shell side water temperature: BWR-2,3 ................................... 3.2 3.4

| A1.03 Steam flow: BWR-2,3 ................................................... 3.3* 3.5

A1.04 Condensate flow: BWR-2,3(P-Spec) ...................................... 3.3 3.5

A1.05 Reactor pressure: BWR-2,3 .............................................. 4.0* 4.2

A1.06 Reactor water level: BWR-2,3 ............................................ 3.5 3.7

A1.07 Vent radiation level: BWR-2,3 ............................................ 3.5 3.7

A1.08 Cooldown rate: BWR-2,3 ................................................ 3.7 4.0

A1.09 Valve operations: BWR-2,3 .............................................. 3.7 3.7

A1.10 Primary side temperature: BWR-2,3 ....................................... 3.2 3.4

A2. Ability to (a) predict the impacts of the following on

the ISOLATION (EMERGENCY) CONDENSER ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

| A2.01 Tube bundle leak: BWR-2,3 .............................................. 4.2* 4.5*

| A2.02 †High vent radiation: BWR-2,3 ........................................... 4.3* 4.7*

A2.03 PCIS signal resulting in system isolation: BWR-2,3 .......................... 3.8* 4.0

A2.04 Inadequate system flow: BWR-2,3 ........................................ 3.8 4.0

A2.05 Insufficient shell side makeup flow: BWR-2,3 .............................. 4.0 4.0

A2.06 Valve openings: BWR-2,3 ............................................... 3.3 3.3

A2.07 Valve closures: BWR-2,3 ................................................ 3.5 3.5

| A2.08 System initiation: BWR-2,3 .............................................. 3.8* 3.8*

A3. Ability to monitor automatic operations of the

ISOLATION (EMERGENCY) CONDENSER including:

(CFR: 41.7 / 45.7)

A3.01 Isolation condenser level: BWR-2,3 ....................................... 3.5 3.7

A3.02 Reactor pressure: BWR-2,3 .............................................. 3.8 4.0

A3.03 Reactor water level: BWR-2,3 ............................................ 3.5 3.7

A3.04 Vent radiation levels: BWR-2,3 ........................................... 4.0* 4.2

A3.05 System lineup: BWR-2,3 ................................................ 3.6 3.8

A3.06 Lights and alarms: BWR-2,3 ............................................. 3.3 3.3

A3.07 Primary and shell side temperatures: BWR-2,3 .............................. 3.2 3.3

A3.08 System flow: BWR-2,3 .................................................. 3.2 3.4
3.4-15 NUREG-1123, Rev. 2 |

SYSTEM: 207000 Isolation (Emergency) Condenser

Tasks as noted previously

 

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Isolation condenser level: BWR-2,3 ....................................... 3.7 3.8

A4.02 Steam line pressure: BWR-2,3 ........................................... 3.2 3.3

A4.03 Primary and shell side temperatures: BWR-2,3 .............................. 3.0 3.2

A4.04 Vent line radiation levels: BWR-2,3 ....................................... 3.8* 4.0

A4.05 Major system valves: BWR-2,3 ........................................... 3.5 3.7

A4.06 Shell side makeup valves: BWR-2,3 ....................................... 3.8* 4.0

A4.07 Manually initiate the isolation condenser: BWR-2,3 ......................... 4.2* 4.3* |
NUREG-1123, Rev. 2 3.4-16 |

SYSTEM: 209001 Low Pressure Core Spray System

TASK: Fill the core spray systems

Perform lineups on the core spray systems

Place the core spray system in standby readiness

Monitor automatic operation of the core spray system

Shutdown the core spray cooling system

Fill the reactor cavity from the condensate storage tank with the core spray system

Perform core spray pump flow rate test

Perform core spray simulated automatic actuation test

Perform core spray pump operability test

Perform core spray subsys and low pressure coolant injection subsys discharge piping ventilation

Perform core spray system inop test

Conduct core spray motor operated valve operability test

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between LOW PRESSURE CORE SPRAY

SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Condensate storage tank: Plant-Specific ................................... 3.1 3.1

K1.02 Torus/suppression pool .................................................. 3.4 3.4

K1.03 Keep fill system ....................................................... 2.9 3.0

K1.04 condensate transfer system .............................................. 2.3 2.4

K1.05 Automatic depressurization system ........................................ 3.7 3.7

K1.06 Plant air systems ....................................................... 2.0* 2.1*

K1.07 D.C. electrical power ................................................... 2.5 2.7

K1.08 A.C. electrical power ................................................... 3.2 3.3

K1.09 Nuclear boiler instrumentation ........................................... 3.2 3.4

K1.10 Emergency generator ................................................... 3.7 3.8

K1.11 Drywell coolers: Plant-Specific .......................................... 2.4 2.6

K1.12 ECCS room coolers .................................................... 2.9 3.1

K1.13 Leak detection ......................................................... 2.8 3.0

K1.14 Reactor vessel ......................................................... 3.7 3.8

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Pump power ........................................................... 3.0* 3.1*

K2.02 Valve power ........................................................... 2.5* 2.7*

K2.03 Initiation logic ......................................................... 2.9* 3.1*
3.4-17 NUREG-1123, Rev. 2 |

SYSTEM: 209001 Low Pressure Core Spray System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3. Knowledge of the effect that a loss or malfunction of

the LOW PRESSURE CORE SPRAY SYSTEM will have on

following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level ..................................................... 3.8 3.9 |

K3.02 ADS logic ............................................................. 3.8 3.9

K3.03 Emergency generators .................................................. 2.9 3.0

K3.04 Component cooling water systems ........................................ 2.1* 2.2

K3.05 Drywell cooling: Plant-Specific .......................................... 2.3 2.7

K4. Knowledge of LOW PRESSURE CORE SPRAY SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Prevention of overpressurization of core spray piping ......................... 3.2 3.4

K4.02 Prevents water hammer .................................................. 3.0 3.2

K4.03 Motor cooling ......................................................... 2.4 2.5

K4.04 Line break detection .................................................... 3.0 3.2

K4.05 Pump minimum flow .................................................... 2.6 2.6

K4.06 Adequate pump net positive suction head ................................... 2.6 2.9

K4.07 Pump operability testing ................................................. 2.8 3.0

K4.08 Automatic system initiation .............................................. 3.8 4.0

K4.09 Load sequencing ....................................................... 3.3 3.5

K4.10 Testability of all operable components ..................................... 2.8 2.9

K5. Knowledge of the operational implications of the

following concepts as they apply to LOW PRESSURE CORE

SPRAY SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Indications of pump cavitation ............................................ 2.6 2.7

K5.02 Differential pressure indication ........................................... 2.4 2.6

K5.03 Testable check valve operation ............................................ 2.3 2.4

K5.04 Heat removal (transfer) mechanisms ....................................... 2.8 2.9

K5.05 System venting ......................................................... 2.5 2.5

K5.06 Recirculation operation: Plant-Specific(BWR-1) ........................... 3.7 4.0

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the LOW PRESSURE CORE SPRAY

SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 A.C. power ............................................................ 3.4 3.4

K6.02 Emergency generators .................................................. 3.8 3.9

K6.03 Torus/suppression pool water level ........................................ 3.3 3.4
NUREG-1123, Rev. 2 3.4-18 |

SYSTEM: 209001 Low Pressure Core Spray System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE ........................................................ RO SRO

K6.04 D.C. power ............................................................ 2.8 2.9

K6.05 ECCS room cooler(s) ................................................... 2.8 2.9

K6.06 Pump motor cooler(s) .................................................. 2.4 2.4

K6.07 Pump seal cooler(s) .................................................... 2.3 2.3

K6.08 Keep fill system ....................................................... 2.9 3.0

K6.09 Fire protection: BWR-1 ................................................ 3.0* 3.3

K6.10 ECCS room integrity: Plant-Specific ...................................... 2.3 2.5

K6.11 ADS .................................................................. 3.6 3.7

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the LOW PRESSURE

CORE SPRAY SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Core spray flow ........................................................ 3.4 3.6

A1.02 Core spray pressure ..................................................... 3.2 3.4

A1.03 Reactor water level ..................................................... 3.8 3.9

A1.04 Reactor pressure ....................................................... 3.7 3.7

A1.05 Torus/suppression pool water level ........................................ 3.5 3.6

A1.06 Motor amps ........................................................... 2.3* 2.4

A1.07 Emergency generator loading ............................................. 3.0 3.1

A1.08 System lineup .......................................................... 3.3 3.2

A2. Ability to (a) predict the impacts of the following on

the LOW PRESSURE CORE SPRAY SYSTEM ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Pump trips ............................................................ 3.4 3.4

A2.02 Valve closures ......................................................... 3.2 3.2

A2.03 A.C. failures ........................................................... 3.4 3.6

A2.04 D.C. failures ........................................................... 2.9 3.0

A2.05 Core spray line break ................................................... 3.3 3.6

A2.06 Inadequate system flow .................................................. 3.2 3.2

A2.07 Loss of room cooling ................................................... 2.6 2.8

A2.08 Valve openings ......................................................... 3.1 3.1

A2.09 Low suppression pool level .............................................. 3.1 3.3

A2.10 †High suppression pool temperature ....................................... 3.1 3.4

A2.11 †Loss of fire protection: BWR-1 ......................................... 2.8* 3.3
3.4-19 NUREG-1123, Rev. 2 |

SYSTEM: 209001 Low Pressure Core Spray System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A3. Ability to monitor automatic operations of the LOW

PRESSURE CORE SPRAY SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation ......................................................... 3.6 3.6

A3.02 Pump start ............................................................. 3.8 3.7

A3.03 System pressure ......................................................... 3.5 3.5

A3.04 System flow ............................................................ 3.7 3.6

A3.05 Reactor water level ...................................................... 3.9 3.9

A3.06 Lights and alarms ........................................................ 3.6 3.5

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Core spray pump ........................................................ 3.8 3.6

A4.02 Suction valves .......................................................... 3.5 3.4

A4.03 Injection valves ........................................................ 3.7 3.6

A4.04 Minimal flow valves ..................................................... 2.9 2.9

A4.05 Manual initiation controls ............................................... 3.8 3.6

A4.06 Testable check valves ................................................... 2.4 2.4

A4.07 Fill pump .............................................................. 2.7 2.8

A4.08 Reactor water level ...................................................... 3.9 3.9

A4.09 Suppression pool level .................................................. 3.6 3.5

A4.10 Reactor pressure ........................................................ 3.9 3.8

A4.11 System flow ........................................................... 3.7 3.6

A4.12 System pressure ........................................................ 3.6 3.5

A4.13 Lights and alarms ....................................................... 3.4 3.4

A4.14 Containment level: BWR-1 .............................................. 3.6 3.6
NUREG-1123, Rev. 2 3.4-20 |

SYSTEM: 239001 Main and Reheat Steam System

TASK: Perform lineups on the main steam system

Startup the main steam system (cold)

Operate the main steam isolation valves

Place the automatic pressure relief valves in service

Monitor the main steam system

Perform main steam isolation valve (MSIV) fast closure test (MSIV operability testing)

Perform main steam line high radiation functional test perform MSIV's, steam line drain valves and reactor

sample valves logic functional test

Perform main mechanical vacuum pump and valve

Isolation system functional test

Perform main steam isolation valve, main steam drain valve and reactor water sample valve simulated

automatic isolation test

Perform main steam isolation valves limit switch instrument functional test

Perform main steam line closure scram (MSLCS) operational test

Perform one train MSLCS inop surveillance

Perform main steam leakage control system operational test (write in)

Perform one train main steam leakage control system operability surveillance (write in)

Perform monthly main steam leakage control system division 1 and division 2 fan and heater tests (write

in)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between MAIN AND REHEAT STEAM

SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor vessel .......................................................... 3.4 3.4

K1.02 SPDS/ERlS/CRIDS/GDS: Plant-Specific ................................... 2.6 2.8

| K1.03 Main turbine ........................................................... 3.4 3.4

| K1.04 Moisture separators ..................................................... 2.8 2.9

K1.05 Moisture separator reheaters: Plant-Specific ................................ 2.8 2.8

K1.06 Steam bypass system .................................................... 3.4 3.4

K1.07 Offgas system .......................................................... 3.1 3.l

K1.08 Condenser air removal system ............................................ 2.9 3.1

K1.09 Steam seal/gland seal system ............................................. 2.7 2.8

K1.10 Extraction steam system ................................................. 2.7 2.8

K1.11 High pressure heater drains and vents ...................................... 2.5 2.5

K1.12 Plant air systems ........................................................ 2.5 2.6

K1.13 Main steam isolation valve leakage control: PlantSpecific ............................................................... 2.6 2.8

| K1.14 Positive leakage control system: Plant Specific ............................. 2.8 3.0

K1.15 Process computer/ performance monitor system ............................ 2.1* 2.1

K1.16 Process radiation monitoring system ...................................... 3.2 3.4
3.4-21 NUREG-1123, Rev. 2 |

SYSTEM: 239001 Main and Reheat Steam System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.17 Containment system .................................................... 3.1 3.2

K1.18 High pressure coolant injection: Plant-Specific ............................. 3.5 3.6

K1.19 Reactor core isolation cooling system: Plant-Specific

...................................................................... 3.1 3.2

K1.20 Residual heat removal system: Plant-Specific .............................. 2.9 2.9

K1.21 Isolation condenser system: Plant-Specific ................................ 3.7 3.7

K1.22 Feedwater system ...................................................... 3.1 3.2

K1.23 Reactor water level control system ........................................ 3.2 3.3

K1.24 Head vent ............................................................. 2.7 2.7

K1.25 Relief valves ........................................................... 3.5 3.5

Kl.26 Safety valves ........................................................... 3.7 3.8

K1.27 Reactor protection system ............................................... 4.0 4.1

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Main steam isolation valve solenoids ...................................... 3.2* 3.3*

K2.02 Main steam line shutoff valves (guard valves):

Plant-Specific ......................................................... 2.3* 2.3*

K3. Knowledge of the effect that a loss or malfunction of

the MAIN AND REHEAT STEAM SYSTEM will have on

following:

(CFR: 41.7 / 45.4)

K3.01 Turbine generator ....................................................... 3.2 3.3

K3.02 Condenser ............................................................ 3.1 3.2

K3.03 Reactor feedpump turbines: Plant-Specific ................................. 3.2 3.3

K3.04 Offgas system ......................................................... 2.8 2.9 |

K3.05 Condenser air removal .................................................. 2.8 2.9

K3.06 Seal steam/gland and seal system .......................................... 2.6 2.7

K3.07 Containment ........................................................... 3.1 3.3

K3.08 Decay heat removal ..................................................... 3.4 3.5

K3.09 Steam bypass capability ................................................. 3.6 3.7

K3.10 High pressure coolant injection system: PlantSpecific .............................................................. 3.5 3.5

K3.11 Reactor core isolation cooling system: Plant-Specific

...................................................................... 3.2 3.3

K3.12 Isolation condenser: Plant-Specific ....................................... 3.7 3.7

K3.13 Moisture separator reheaters: Plant-Specific ............................... 2.4 2.4

K3.14 Residual heat removal system: Plant-Specific .............................. 2.7 2.7

K3.15 Reactor water level control .............................................. 3.5 3.5

K3.16 Relief/safety valves ..................................................... 3.6 3.6

K3.17 Reactor vessel and internals .............................................. 3.2 3.3
NUREG-1123, Rev. 2 3.4-22 |

SYSTEM: 239001 Main and Reheat Steam System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4. Knowledge of MAIN AND REHEAT STEAM SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Automatic isolation of steam lines ........................................ 3.8 3.8

K4.02 Automatic isolation and opening of drain valves:

Plant-Specific ......................................................... 3.1 3.2

K4.03 Insures that steam released from a steam line break

will not bypass suppression pool; BWR-6 .................................. 3.2 3.3

K4.04 Limits steam flow during a steam line rupture to 200% ........................ 3.4 3.5

K4.05 Steam flow measurement ................................................ 3.1 3.2

K4.06 Allows for removal or prevents escape of radioactive

steam from systems that have leaky MSIV's ................................. 3.1 3.2

K4.07 Over pressure control ................................................... 3.7 3.7

K4.08 Removal of non condensable gases from reactor head

area .................................................................. 2.5 2.6

K4.09 Equalization of pressure across the MSIV's before

opening ............................................................... 3.3 3.3

K4.10 Moisture removal from steam lines prior to admitting

steam ................................................................. 2.9 3.0

K4.11 Positive sealing of the MSIV's when shutdown: PlantSpecific .............................................................. 2.9 3.1

K5. Knowledge of the operational implications of the

following concepts as they apply to MAIN AND REHEAT

STEAM SYSTEM :

(CFR: 41.5 / 45.3)

| K5.01 Constant enthalpy expansion through a valve ................................ 2.0* 2.2*

K5.02 Definition and causes of steam/water hammer ............................... 2.9 3.1

K5.03 Definition and causes of thermal stress .................................... 2.7 2.9

K5.04 Definition and reason for steam blanketing of moisture

| separator reheater: Plant-Specific ........................................ 1.8* 1.9*

K5.05 Flow indication ........................................................ 2.8 2.8

K5.06 Air operated MSIV's .................................................... 2.8 2.9

K5.07 Hydraulic operated MSIV's ............................................... 2.6 2.7

K5.08 Solenoid operated valves ................................................ 2.6 2.7

K5.09 Decay heat removal ..................................................... 3.4 3.5

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the MAIN AND REHEAT STEAM

SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 Electrical power ....................................................... 3.1 3.3

| K6.02 Plant air systems ....................................................... 3.2 3.2

| K6.03 Safety valve operability .................................................. 3.6 3.6
3.4-23 NUREG-1123, Rev. 2 |

SYSTEM: 239001 Main and Reheat Steam System

Tasks as noted Previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6.04 Relief valve operability: Plant-Specific .................................... 3.4 3.5

K6.05 Steam line integrity ..................................................... 3.6 3.7 |

K6.06 MSIV isolation signal ................................................... 3.8 3.9

K6.07 MSIV leakage control ................................................... 2.8 3.2

K6.08 Main condenser vacuum ................................................. 3.3 3.4

K6.09 PCIS/NSSSS ........................................................... 3.9 4.1* |

K6.10 ADS/low low set: Plant-Specific ......................................... 3.6 3.7

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the MAIN AND

REHEAT STEAM SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Main steam pressure .................................................... 3.6 3.6

A1.02 Main steam temperature ................................................. 2.6 2.6

A1.03 Reheat steam pressure: Plant-Specific ..................................... 2.2* 2.2* |

A1.04 Reheater temperature: Plant-Specific ..................................... 2.3* 2.3

A1.05 Main steam line radiation monitors ........................................ 3.6 3.6

A1.06 Air ejector process radiation monitor ...................................... 3.4 3.4

A1.07 Reactor water level ..................................................... 3.7 3.7

A1.08 Reactor pressure ....................................................... 3.8 3.8

A1.09 Main steam flow ....................................................... 3.5 3.4

A1.10 Reactor power ......................................................... 3.8 3.8

A2. Ability to (a) predict the impacts of the following on

the MAIN AND REHEAT STEAM SYSTEM ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Malfunction of reactor turbine pressure regulating

system ................................................................ 3.8 3.9

A2.02 Change in steam demand and its effect on reactor

pressure and power ..................................................... 3.6 3.8

A2.03 MSIV closure .......................................................... 4.0 4.2

A2.04 Main steam line low pressure ............................................. 3.5 3.6

A2.05 †Main steam line high radiation ........................................... 3.9 4.2* |

A2.06 Turbine trip without bypass valves ......................................... 4.1 4.3* |

A2.07 Main steam area high temperature or differential |

temperature high ....................................................... 3.8 3.9

A2.08 Low condenser vacuum .................................................. 3.6 3.6

A2.09 Opening of head vent to drywell equipment sump with

pressure in the reactor vessel ............................................. 3.4 3.7

A2.10 Closure of one or more MSIV's at power ................................... 3.8 3.9
NUREG-1123, Rev. 2 3.4-24 |

SYSTEM: 239001 Main and Reheat Steam System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

| A2.11 Steam line break ....................................................... 4.1 4.3*

| A2.12 PCIS/NSSSS actuation ................................................... 4.2* 4.3*

A2.13 High reactor water level ................................................. 3.5 3.7

A2.14 Inadvertent initiation of HPCI/HPCS/RCIC (steam

quality and steam flow): Plant-Specific .................................... 3.4 3.5

A3. Ability to monitor automatic operations of the MAIN

AND REHEAT STEAM SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Isolation of main steam system ........................................... 4.2* 4.1*

A3.02 Opening and closing of drain valves as turbine load

changes: Plant-Specific ................................................. 2.9 2.9

A3.03 Moisture separator reheat steam supply: PlantSpecific .............................................................. 2.8 2.8

A3.04 Isolation of moisture separator reheater: PlantSpecific .............................................................. 2.7 2.7

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 MSIV's ............................................................... 4.2* 4.0

A4.02 Maim steam line drain valves ............................................. 3.2 3.2

A4.03 System flow ........................................................... 3.5 3.5

A4.04 System pressure ........................................................ 3.8 3.7

A4.05 System temperature ..................................................... 2.7 2.7

A4.06 System radiation levels .................................................. 3.6 3.8

A4.07 Lights and alarms ....................................................... 3.3 3.3

A4.08 Reactor water level ..................................................... 3.7 3.7

A4.09 Reactor pressure ....................................................... 3.9 3.9

A4.10 Reactor power ......................................................... 3.8 3.8

A4.11 Alternate methods of verifying valve positions .............................. 3.1 3.3
3.4-25 NUREG-1123, Rev. 2 |

SYSTEM: 245000 Main Turbine Generator and Auxiliary Systems

TASK: Perform lineups of the main turbine generator

Start up the turbine to rated speed

Perform generator excitation

Operate generator voltage regulator

Synchronize turbine generator with output grid at minimum load

Increase load on the turbine generator

Monitor the turbine generator

Secure the amplidyne (generator in service)

Return the amplidyne to service

Unload the turbine generator electrically to minimum load

Secure generator output and excitation

Shut down the turbine generator

Operate the turbine turning gear

Operate the turbine bearing lift oil pumps (jacking oil pumps)

Synchronize turbine generator with output grid at minimum load

Increase load on the turbine generator

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between MAIN TURBINE GENERATOR

AND AUXILIARY SYSTEMS and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 A. C. electrical distribution ............................................... 3.2 3.3

K1.02 Condensate system ...................................................... 2.5 2.5

K1.03 Main steam system ...................................................... 3.2 3.3

K1.04 Reactor protection system ............................................... 3.6 3.7

K1.05 Extraction steam system ................................................. 2.7 2.7

K1.06 Component cooling water systems ......................................... 2.6 2.6

K1.07 Plant air systems ........................................................ 2.5 2.5

K1.08 Reactor/turbine pressure control system: PlantSpecific ............................................................... 3.4 3.5

K1.09 D. C . electrical distribution .............................................. 2.7 2.7

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Stator water cooling pumps: Plant-Specific ................................. 2.4* 2.4

K2.02 Main lubricating oil pumps ............................................... 2.3* 2.4*

K2.03 Amplidyne: Plant-Specific ............................................... 1.7* 1.8*

K2.04 Hydrogen seal oil pumps ................................................. 2.3* 2.3*

K2.05 Air seal oil pumps: Plant-Specific ......................................... 1.7* 1.7*

K2.06 Turbine supervisory instrumentation ....................................... 2.3 2.5
NUREG-1123, Rev. 2 3.4-26 |

SYSTEM: 245000 Main Turbine Generator and Auxiliary Systems

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3. Knowledge of the effect that a loss or malfunction of

the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS will

have on following:

(CFR: 41.7 / 45.4)

K3.01 A.C. electrical distribution ............................................... 3.4 3.7

K3.02 Reactor pressure ........................................................ 3.9 4.0

K3.03 Reactor power .......................................................... 3.9 4.0

K3.04 Reactor feedwater system (feedwater heaters) ............................... 3.3 3.5

K3.05 Reactor feedwater pump: Plant-Specific ................................... 2.7 2.8

K3.06 Condensate system ...................................................... 2.5 2.5

K3.07 Reactor protection system ............................................... 3.6 3.7

K3.08 Reactor/turbine pressure control system: Plant-

 Specific .................................................................. 3.7 3.8

K4. Knowledge of MAIN TURBINE GENERATOR AND AUXILIARY

SYSTEMS design feature(s) and/or interlocks which

provide for the following:

(CFR: 41.7)

K4.01 Bearing lubrication ...................................................... 2.4 2.5

K4.02 Generator cooling ...................................................... 2.4 2.5

K4.03 Sealing to prevent hydrogen leakage ........................................ 2.7 2.8

K4.04 Hydrogen cooling ....................................................... 2.4 2.5

K4.05 Turbine protection ...................................................... 2.9 3.0

K4.06 Generator protection .................................................... 2.7 2.8

K4.07 Generator voltage regulation .............................................. 2.5 2.6

K4.08 Moisture removal from turbine steam ...................................... 2.4 2.4

K4.09 Turbine control ......................................................... 3.1 3.2

K4.10 Extraction steam ........................................................ 2.6 2.7

K5. Knowledge of the operational implications of the

following concepts as they apply to MAIN TURBINE

GENERATOR AND AUXILIARY SYSTEMS :

(CFR: 41.5 / 45.3)

K5.01 Heat exchanger operation ................................................ 2.3* 2.3*

K5.02 Turbine operation and limitations .......................................... 2.8 3.1

K5.03 Hydraulically operated valve operation ..................................... 2.6 2.6

K5.04 Turbine speed measurement .............................................. 1.9* 2.0*

K5.05 Relief valve operation ................................................... 2.4 2.4

K5.06 Turbine shaft sealing .................................................... 2.5 2.6

K5.07 Generator operations and limitations ....................................... 2.6 2.9

K5.08 Generator cooling ...................................................... 2.4 2.6
3.4-27 NUREG-1123, Rev. 2 |

SYSTEM: 245000 Main Turbine Generator and Auxiliary Systems

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the MAIN TURBINE GENERATOR

AND AUXILIARY SYSTEMS :

(CFR: 41.7 / 45.7)

K6.01 Gland seal ............................................................. 2.8 2.9

K6.02 Reactor/turbine pressure control system: PlantSpecific ............................................................... 3.5 3.7

K6.03 Hydrogen seal oil ....................................................... 2.8 3.1

K6.04 Hydrogen cooling ....................................................... 2.6* 2.7

K6.05 Stator water cooling ..................................................... 2.9 2.9

K6.06 Electrical distribution ................................................... 3.0 3.2

K6.07 Extraction steam ........................................................ 2.4 2.5

K6.08 Main steam ............................................................ 3.0 3.1

K6.09 Voltage regulation ...................................................... 2.3* 2.5*

K6.10 Lube oil system ........................................................ 2.8* 2.9

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the MAIN TURBINE

GENERATOR AND AUXILIARY SYSTEMS controls including:

(CFR: 41.5 / 45.5)

A1.01 Generator megawatts .................................................... 2.7 2.7

A1.02 Turbine speed .......................................................... 2.6 2.5

A1.03 Turbine valve position ................................................... 2.7 2.7

A1.04 Steam flow ............................................................ 2.7 2.8

A1.05 Reactor pressure ........................................................ 3.5 3.4

A1.06 Condenser vacuum ...................................................... 3.3 3.2

A1.07 First stage turbine pressure .............................................. 2.8 2.8

A1.08 Generator output voltage/reactive load ..................................... 2.5* 2.7

A2. Ability to (a) predict the impacts of the following on

the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS ; and

(b) based on those predictions, use procedures to

correct, control, or mitigate the consequences of

those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Turbine trip ............................................................ 3.7 3.9

A2.02 Loss of lube oil ......................................................... 3.3 3.5

A2.03 Loss of condenser vacuum ............................................... 3.5 3.6

A2.04 Reactor scram .......................................................... 3.7 3.8

A2.05 Generator trip .......................................................... 3.6 3.8

A2.06 Loss of extraction steam ................................................. 2.9 3.1
NUREG-1123, Rev. 2 3.4-28 |

SYSTEM: 245000 Main Turbine Generator and Auxiliary Systems

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A2.07 Loss of reactor/turbine pressure control system:

Plant-Specific 3.8 3.9

A2.08 Turbine rotor bow 2.3 2.6

A2.09 Turbine vibration 2.5 2.8

A3. Ability to monitor automatic operations of the MAIN

TURBINE GENERATOR AND AUXILIARY SYSTEMS including:

(CFR: 41.7 / 45.7)

A3.01 Turbine trip ............................................................ 3.6 3.6

A3.02 Turbine roll to rated speed ................................................ 2.8 2.8

A3.03 Generator megawatt output ............................................... 2.8 2.9

A3.04 Turbine speed .......................................................... 2.7* 2.8

A3.05 Control valve operation .................................................. 3.0 3.1

A3.06 Turbine lube oil pressure ................................................. 2.5 2.6

A3.07 Hydrogen seal oil pressure ............................................... 2.5 2.6

A3.08 Hydrogen gas pressure ................................................... 2.5 2.6

A3.09 Hydrogen gas temperature ................................................ 2.4 2.5

A3.10 Generator output voltage/reactive load ..................................... 2.5 2.6

| A3.11 Generator power factor: Plant-Specific .................................... 1.8* 2.1*

A3.12 Automatic turbine control: Plant-Specific .................................. 3.3 3.5

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Turbine lube oil pumps ................................................... 2.7 2.7

A4.02 Generator controls ...................................................... 3.1 2.9

A4.03 Stator water cooling pumps: Plant-Specific ................................. 2.7 2.8

A4.04 Hydrogen seal oil pumps ................................................. 2.7 2.7

A4.05 Generator megawatt output ............................................... 2.7 2.7

A4.06 Turbine speed .......................................................... 2.7 2.6

A4.07 Turbine valve position ................................................... 2.9 2.9

| A4.08 Turbine oil pressure ..................................................... 2.7 2.7

A4.09 Hydrogen seal oil pressure ............................................... 2.6 2.6

A4.10 Hydrogen gas pressure ................................................... 2.6 2.6

| A4.11 Hydrogen gas temperature ................................................ 2.4 2.4*

| A4.12 Generator output voltage ................................................. 2.6 2.6

| A4.13 Generator power factor: Plant-Specific .................................... 1.9* 2.1*

A4.14 Generator megavar output ................................................ 2.5 2.5
3.4-29 NUREG-1123, Rev. 2 |

SYSTEM: 217000 Reactor Core Isolation Cooling System (RCIC)

TASK: Lineup the reactor core isolation cooling (RCIC) system

Manually operate and adjust reactor core isolation cooling system flow with the turbine governor

Manually initiate startup of the reactor core isolation cooling (RCIC) system

Operate RCIC pump in different modes

Monitor RCIC operation

Shutdown RCIC

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between REACTOR CORE ISOLATION

COOLING SYSTEM (RCIC) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Condensate storage and transfer system .................................... 3.5 3.5

K1.02 Nuclear boiler system ................................................... 3.5 3.5

K1.03 Suppression pool ....................................................... 3.6 2.6

K1.04 Main condenser ........................................................ 2.6 2.6

K1.05 Residual heat removal system ............................................. 2.6 2.6

K1.06 Plant air systems: Plant-Specific .......................................... 2.3* 2.3*

K1.07 Leak detection ......................................................... 3.1 3.2

K1.08 Line fill pump: Plant-Specific ............................................ 3.3 3.4

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Motor operated valves ................................................... 2.8* 2.8*

K2.02 RCIC initiation signals (logic) ............................................ 2.8* 2.9*

K2.03 RCIC flow controller .................................................... 2.7* 2.8*

K2.04 Gland seal compressor (vacuum pump) ..................................... 2.6* 2.6*

K3. Knowledge of the effect that a loss or malfunction of

the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) will

have on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level ...................................................... 3.7 3.7

K3.02 Reactor vessel pressure .................................................. 3.6 3.6

K3.03 Decay heat removal ..................................................... 3.5 3.5

K3.04 Adequate core cooling ................................................... 3.6 3.6

K4. Knowledge of REACTOR CORE ISOLATION COOLING SYSTEM

(RCIC) design feature(s) and/or interlocks which

provide for the following:

(CFR: 41.7)

K4.01 Prevent water hammer: Plant-Specific ..................................... 2.8 2.8

K4.02 Prevent over filling reactor vessel ......................................... 3.3 3.3
NUREG-1123, Rev. 2 3.4-30 |

SYSTEM: 217000 Reactor Core Isolation Cooling System (RCIC)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.03 Prevents pump over heating ............................................... 2.9 3.0

K4.04 Prevents turbine damage: Plant-Specific ................................... 3.0 3.1

K4.05 Prevents radioactivity release to auxiliary/reactor

building ............................................................... 3.2 3.5

K4.06 Manual initiation ........................................................ 3.5 3.5

K4.07 Alternate supplies of water ............................................... 3.6 3.6

K5. Knowledge of the operational implications of the

following concepts as they apply to REACTOR CORE

ISOLATION COOLING SYSTEM (RCIC) :

(CFR: 41.5 / 45.3)

K5.01 Indications of pump cavitation ............................................ 2.6* 2.6*

K5.02 Flow indication ......................................................... 3.1 3.1

K5.03 Differential pressure indication ........................................... 2.6 2.6

K5.04 Testable check valve operation ............................................ 2.6 2.7

K5.05 Centrifugal pump operation ............................................... 2.4* 2.4*

K5.06 Turbine operation ....................................................... 2.7* 2.7

K5.07 Assist core cooling ..................................................... 3.1 3.1

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the REACTOR CORE ISOLATION

COOLING SYSTEM (RCIC) :

(CFR: 41.7 / 45.7)

K6.01 Electrical power ........................................................ 3.4 3.5

| K6.02 Plant air systems ........................................................ 2.2* 2.2*

K6.03 Suppression pool water supply ............................................ 3.5 3.5

K6.04 Condensate storage and transfer system .................................... 3.5 3.5

ABILITY

Al. Ability to predict and/or monitor changes in

parameters associated with operating the REACTOR CORE

ISOLATION COOLING SYSTEM (RCIC) controls including:

(CFR: 41.5 / 45.5)

A1.01 RCIC flow ............................................................. 3.7 3.7

A1.02 RCIC pressure .......................................................... 3.3 3.3

A1.03 Reactor water level ..................................................... 4.0 4.0

| A1.04 Reactor pressure ........................................................ 3.6* 3.6*

A1.05 RCIC turbine speed ..................................................... 3.7 3.7

A1.06 Condensate storage tank level ............................................. 3.2 3.3

A1.07 Suppression pool level ................................................... 3.3 3.5

A1.08 Suppression pool temperature ............................................. 3.5 3.6
3.4-31 NUREG-1123, Rev. 2 |

SYSTEM: 217000 Reactor Core Isolation Cooling System (RCIC)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A2. Ability to (a) predict the impacts of the following on

the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ; and

(b) based on those predictions, use procedures to

correct, control, or mitigate the consequences of

those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 System initiation signal .................................................. 3.8 3.7

A2.02 Turbine trips ........................................................... 3.8 3.7

A2.03 Valve closures .......................................................... 3.4 3.3

A2.04 A.C. power loss ......................................................... 2.3* 2.3*

A2.05 D.C. power loss ........................................................ 3.3 3.3

A2.06 Loss of applicable plant air systems ........................................ 2.2* 2.2* |

A2.07 Loss of lube oil ......................................................... 3.1 3.1

A2.08 Loss of lube oil cooling .................................................. 3.0 3.1

A2.09 Loss of vacuum pump .................................................... 2.9 3.0

A2.10 Turbine control system failures ........................................... 3.1 3.1

A2.11 Inadequate system flow .................................................. 3.1 3.2

A2.12 Valve openings ......................................................... 3.0 3.0 |

A2.13 Loss of room cooling ................................................... 2.9 3.0

A2.14 Rupture disc failure: Exhaust-Diaphragm ................................... 3.3 3.4

A2.15 Steam line break ........................................................ 3.8 3.8

A2.16 Low condensate storage tank level ........................................ 3.5 3.4

A2.17 High suppression pool level .............................................. 3.2 3.4

A2.18 Low suppression pool level .............................................. 3.1 3.2

A2.19 High suppression pool temperature ........................................ 3.5 3.6

A3. Ability to monitor automatic operations of the REACTOR

CORE ISOLATION COOLING SYSTEM (RCIC) including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation ......................................................... 3.5 3.5 |

A3.02 Turbine startup ......................................................... 3.6 3.5

A3.03 System pressure ........................................................ 3.7 3.6

A3.04 System flow ........................................................... 3.6 3.5

A3.05 Reactor water level ..................................................... 3.9 3.9

A3.06 Lights and alarms ....................................................... 3.5 3.4

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 RCIC turbine speed ..................................................... 3.7 3.7

A4.02 Turbine trip throttle valve reset ............................................ 3.9 3.9

A4.03 System valves .......................................................... 3.4 3.3

A4.04 Manually initiated controls ............................................... 3.6 3.6
NUREG-1123, Rev. 2 3.4-32 |

SYSTEM: 217000 Reactor Core Isolation Cooling System (RCIC)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A4.05 Reactor water level ...................................................... 4.1 4.1

A4.06 Suppression pool level ................................................... 3.6 3.7

A4.07 Reactor pressure ........................................................ 3.9 3.8

A4.08 System flow ........................................................... 3.7 3.6

A4.09 System pressure ........................................................ 3.7 3.6

A4.10 Lights and alarms ....................................................... 3.6 3.5

A4.11 Condensate storage tank level ............................................. 3.5 3.5
3.4-33 NUREG-1123, Rev. 2 |

SYSTEM: 202001 Recirculation System

TASK: Perform lineups on the recirculation system 

Vent recirculation pump seals 

Startup a recirculation pump (startup a second recirculation pump)

Operate recirculation pumps in various control modes (adjust the recirculation flow using "master manual"

control) 

Monitor recirculation pumps in operation 

Monitor jet pump operation 

Secure a recirculation pump 

Perform jet pump operability test 

Conduct heatup and cooldown temperature checks 

Conduct recirculation pump startup check of the delta temperature between the reactor coolant in the idle

loop to the reactor vessel

Conduct recirculation pump trip logic system functional test 

Conduct recirculation loop valve operability test 

Conduct recirculation system valve testing 

What if jet pumps not operating within required operating band

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between RECIRCULATION SYSTEM and

the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Core flow .............................................................. 3.6 3.7

K1.02 Reactor power .......................................................... 4.1 4.1

K1.03 Reactor moderator temperature ............................................ 3.2 3.3

K1.04 Reactor/turbine pressure regulating system: PlantSpecific ............................................................... 3.3 3.3

K1.05 Reactor pressure ........................................................ 3.4 3.4

K1.06 Jet pumps .............................................................. 3.6 3.6

K1.07 Component cooling water systems ......................................... 3.1 3.2

K1.08 A.C. electrical .......................................................... 3.1 3.2

K1.09 D.C. electrical .......................................................... 2.7 2.9

K1.10 Control rod drive system: Plant-Specific ................................... 2.8 2.8

K1.11 Drywell equipment drain sump ............................................. 2.7 2.8

K1.12 Recirculation system motor-generator sets: PlantSpecific ............................................................... 3.6 3.6

K1.13 Jet pump ring header and risers: Plant-Specific .............................. 3.1 3.2

K1.14 Rod block monitor: Plant-Specific ......................................... 3.0 3.2

K1.15 Nuclear boiler instrumentation (reactor water

level/pressure) .......................................................... 3.2 3.2

K1.16 Low pressure coolant injection logic: Plant-Specific .......................... 3.9 3.9

K1.17 Vessel bottom head drain temperature ...................................... 3.1 3.3

K1.18 RHR shutdown cooling mode .............................................. 3.3 3.3

K1.19 Feedwater flow ......................................................... 3.2 3.2

K1.20 Plant air systems: Plant-Specific .......................................... 2.4 2.5

K1.21 Reactor water cleanup system ............................................. 2.6 2.6
NUREG-1123, Rev. 2 3.4-34 |

SYSTEM: 202001 Recirculation System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.22 Reactor water level ..................................................... 3.5 3.6

K1.23 Average power range monitor flow converters: PlantSpecific .............................................................. 3.4 3.5

K1.24 Isolation condenser: Plant-Specific ....................................... 3.4 3.4

K1.25 Reactor water sampling system ............................................ 2.6 2.7

K1.26 Recirculation flow control system: Plant-Specific

| K1.27 ATWS circuitry: Plant-Specific .......................................... 4.1 4.3*

K1.28 End-of-cycle recirculation pump trip circuitry:

Plant-Specific ......................................................... 3.9 4.1

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Recirculation pumps: Plant-Specific ...................................... 3.2* 3.2

K2.02 MG sets: Plant-Specific ................................................ 3.2 3.3

K2.03 Recirculation system valves .............................................. 2.7* 2.8*

K2.04 Hydraulic power unit oil pumps: Plant-Specific ............................. 2.5* 2.5*

K2.05 MG set oil pumps: Plant-Specific ........................................ 2.3* 2.3*

K3. Knowledge of the effect that a loss or malfunction of

the RECIRCULATION SYSTEM will have on following:

(CFR: 41.7 / 45.4)

K3.01 Core flow ............................................................. 3.6 3.6

K3.02 Load following capabilities: Plant-Specific ................................ 2.8 2.8

K3.03 Reactor power ......................................................... 3.9 3.9

K3.04 Reactor water level ..................................................... 3.7 3.7

K3.05 Recirculation system MG sets: Plant-Specific .............................. 3.3 3.3

K3.06 Low pressure coolant injection logic: Plant-Specific ......................... 3.7 3.9

K3.07 Vessel bottom head drain temperature ...................................... 2.9 2.9

K3.08 Shutdown cooling system ................................................ 2.8 2.9

K3.09 Reactor water cleanup system ............................................ 2.4* 2.5*

K3.10 Average power range monitor flow converters ............................... 3.3 3.4

K3.11 Component cooling water systems ........................................ 2.3* 2.3*

K3.12 Isolation condenser: Plant-Specific ....................................... 3.0 3.0

K3.13 Reactor water sampling system ........................................... 2.5 2.5

K3.14 Primary containment integrity: Plant-Specific .............................. 3.5 3.5

K4. Knowledge of RECIRCULATION System design feature(s)

and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 2/3 core coverage: Plant-Specific ........................................ 3.9 3.9

K4.02 Adequate recirculation pump NPSH ....................................... 3.1 3.2

K4.03 Recirculation pump motor cooling ........................................ 2.8 2.8

K4.04 Controlled seal flow .................................................... 3.0 3.1

K4.05 Seal cooling ........................................................... 2.9 2.9
3.4-35 NUREG-1123, Rev. 2 |

SYSTEM: 202001 Recirculation System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.06 Automatic voltage/frequency regulation: PlantSpecific .............................................................. 2.6* 2.7

K4.07 Motor generator set trips: Plant-Specific .................................. 2.8 2.9

K4.08 Oil pump automatic starts: Plant-Specific .................................. 2.8 2.9

K4.09 Pump minimum flow limit: Plant-Specific ................................. 2.7 2.9

K4.10 Pump start permissives: Plant-Specific .................................... 3.3 3.4

K4.11 Limitation of recirculation pumps flow mismatch:

Plant-Specific ......................................................... 3.1 3.5

K4.12 Minimization of reactor vessel bottom head temperature

gradients: Plant-Specific ................................................ 3.2 3.5

K4.13 †End of cycle recirculation pump trip: Plant-Specific ........................ 3.7 4.0*

K4.14 ATWS: Plant-Specific .................................................. 4.0 4.1*

K4.15 Slow speed pump start: Plant-Specific ..................................... 3.1 3.4

K4.16 Recirculation pump downshift/runback: Plant-Specific ....................... 3.3 3.6

K4.17 Fast speed pump start: Plant-Specific ..................................... 3.3 3.5

K4.18 Automatic MG set start sequencing: Plant-Specific .......................... 2.8 3.0

K5. Knowledge of the operational implications of the

following concepts as they apply to RECIRCULATION

SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Indications of pump cavitation ............................................ 2.7 2.8

K5.02 Jet pump operation: BWR-3,4,5,6 ........................................ 3.1 3.2

K5.03 Pump/motor cooling: Plant-Specific ...................................... 2.7 2.7

K5.04 System venting ......................................................... 2.4 2.6

K5.05 End of cycle recirculation pump trip: Plant-Specific ......................... 3.5 3.6

K5.06 ATWS RPT: Plant-Specific .............................................. 3.6 3.7

K5.07 Natural circulation: Plant-Specific ........................................ 3.3 3.4

K5.08 E/P converters: Plant-Specific ........................................... 2.0* 2.1*

K5.09 Hydraulically operated valves: Plant-Specific ............................... 2.6* 2.6*

K5.10 Motor generator set operation: Plant-Specific .............................. 2.8* 2.8

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the RECIRCULATION SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 Jet pumps: Plant-Specific ............................................... 3.5 3.7

K6.02 Component cooling water systems ........................................ 3.1 3.2

K6.03 A.C. power: Plant-Specific .............................................. 2.9 3.0

K6.04 D.C. power: Plant-Specific .............................................. 2.7 2.8

K6.05 Control rod drive system: Plant-Specific .................................. 2.7 2.7

K6.06 Recirculation system motor-generator sets: PlantSpecific .............................................................. 3.1 3.1

K6.07 Feedwater flow ........................................................ 3.3 3.3

K6.08 Reactor water cleanup system ............................................ 2.3 2.3

K6.09 Reactor water level ..................................................... 3.4 3.4
NUREG-1123, Rev. 2 3.4-36 |

SYSTEM: 202001 Recirculation System Tasks as noted previously

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A1. Ability to predict and/or monitor changes in

parameters associated with operating the RECIRCULATION

SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Recirculation pump flow: Plant-Specific ................................... 3.6 3.5

A1.02 Jet pump flow .......................................................... 3.4 3.4

A1.03 Core flow ............................................................. 3.6 3.6

A1.04 Reactor water level ..................................................... 3.3 3.3

A1.05 Reactor power ......................................................... 3.9 3.9

A1.06 Recirculation pump motor amps .......................................... 2.5 2.6

A1.07 Recirculation pump speed ............................................... 2.7 2.8

A1.08 Recirculation FCV position: BWR-5,6 .................................... 3.7 3.7

A1.09 Recirculation pump seal pressures ........................................ 3.3 3.3

A1.10 Recirculation seal purge flows ............................................ 2.6 2.7

A1.11 Vessel bottom head drain temperature ..................................... 2.8 2.9

A1.12 Recirculation pump differential pressure: PlantSpecific .............................................................. 2.6 2.6

A1.13 Recirculation loop temperatures: Plant-Specific ............................ 3.1 3.2

A1.14 Recirculation drive motor temperature: Plant-Specific

...................................................................... 2.4 2.4

A1.15 Recirculation MG set temperatures: Plant-Specific .......................... 2.4 2.4

A1.16 Recirculation MG drive motor amps: Plant-Specific ......................... 2.3* 2.3

A1.17 Recirculation MG set generator current, power,

voltage: Plant-Specific .................................................. 2.3* 2.3

A2. Ability to (a) predict the impacts of the following on

the RECIRCULATION SYSTEM ; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 †Jet pump failure: Plant-Specific ......................................... 3.4 3.9

A2.02 Recirculation system leak ............................................... 3.7 3.9

A2.03 Single recirculation pump trip ............................................ 3.6 3.7

A2.04 Multiple recirculation pump trip .......................................... 3.7 3.8

A2.05 Inadvertent recirculation flow increase ..................................... 3.8 4.0

A2.06 Inadvertent recirculation flow decrease .................................... 3.6 3.8

A2.07 Recirculation pump speed mismatch: Plant-Specific ......................... 3.1 3.3

A2.08 Recirculation flow mismatch: Plant-Specific ............................... 3.1 3.4

A2.09 Recirculation scoop tube lockup: Plant-Specific ............................ 3.2 3.4

A2.10 †Recirculation pump seal failure .......................................... 3.5 3.9

A2.11 Low reactor water level ................................................. 3.7 3.9

A2.12 Loss of reactor feedwater ................................................ 3.6 3.8

A2.13 Carryunder ............................................................ 2.6 2.8
3.4-37 NUREG-1123, Rev. 2 |

SYSTEM: 202001 Recirculation System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A2.14 High reactor pressure (ATWS circuitry initiation):

Plant-Specific .......................................................... 3.9 4.2* |

A2.15 End of cycle trip circuitry: Plant-Specific ................................... 3.7 3.9

A2.16 Loss of seal purge flow (CRD) ............................................ 2.9 3.1

A2.17 Loss of seal cooling water ................................................ 3.1 3.2

A2.18 Loss of motor cooling ................................................... 2.9 3.1

A2.19 Loss of A.C. power: Plant-Specific ......................................... 3.1 3.2

A2.20 Loss of D.C. power: Plant-Specific ........................................ 2.8 2.9

A2.21 †Recirculation loop temperature out of spec: PlantSpecific ............................................................... 3.3 3 7

A2.22 Loss of component cooling water .......................................... 3.1 3.2

A2.23 Valve closures .......................................................... 3.2 3.2

A2.24 Valve opening ........................................................... 3.1 3.1

A2.25 Recirculation flow control valve lockup: PlantSpecific ............................................................... 3.3 3.3

A2.26 Incomplete start sequence: Plant-Specific .................................. 2.9 3.1

A3. Ability to monitor automatic operations of the

RECIRCULATION SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation ......................................................... 3.1 3.1

A3.02 Pump/MG set start sequence: Plant-Specific ................................ 3.1 3.0

A3.03 System flow ............................................................ 3.2 3.2

A3.04 Lights and alarms ........................................................ 3.2 3.1

A3.05 Pump speed: Plant-Specific .............................................. 2.9 2.9

A3.06 Flow control valve position: BWR-5,6 ..................................... 3.6 3.6

A3.07 Pump trips: Plant-Specific ............................................... 3.3 3.3

A3.08 Pump downshift: BWR-5,6 ............................................... 3.4 3.3

A3.09 MG set trip: Plant-Specific ............................................... 3.3 3.3

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Recirculation pumps ..................................................... 3.7 3.7

A4.02 System valves ........................................................... 3.5 3.4

A4.03 Reactor power .......................................................... 4.1 4.1

A4.04 System flow ............................................................ 3.7 3.7

A4.05 Lights and alarms ........................................................ 3.3 3.3

A4.06 Oil pumps .............................................................. 2.7 2.7

A4.07 Vent fans: Plant-Specific ................................................. 2.4 2.3

A4.08 Motor-generator sets: Plant-Specific ...................................... 3.2 3.1

A4.09 Reactor water level ...................................................... 3.7 3.7

A4.10 Seal flow: Plant-Specific ................................................. 2.8 2.8

A4.11 Seal pressures: Plant-Specific ............................................ 3.2 3.3

A4.12 Core flow .............................................................. 3.9 3.8

A4.13 Core differential pressure ................................................ 3.1 3.3
NUREG-1123, Rev. 2 3.4-38 |

SYSTEM: 203000 RHR/LPCI: Injection Mode (Plant Specific)

TASK: Perform lineups on the low pressure coolant injection system

Place the low pressure coolant injection system in standby readiness

Monitor operational sequence of low pressure coolant injection (LPCI) system

Secure the low pressure coolant injection system

Perform LPCI subsystem logic system functional test

Perform LPCI mode inoperable test

Perform LPCI mov power supply simulated auto. act test and battery serv. tests

Conduct LPCI independent power supply weekly battery test

Conduct LPCI independent power supply performance discharge test

Perform low pressure coolant injection sound analysis and flow test (write in)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between RHR/LPCI: INJECTION MODE

(PLANT SPECIFIC) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Condensate storage and transfer system: PlantSpecific ............................................................... 2.8 2.8

K1.02 Suppression pool ....................................................... 3.9 3.9

K1.03 Condensate transfer ..................................................... 2.5* 2.6*

K1.04 Keep fill system ........................................................ 3.3 3.4

K1.05 Recirculation system: BWR-3,4 .......................................... 3.8 3.8

K1.06 Automatic depressurization ............................................... 3.9 3.9

K1.07 D.C. electrical power .................................................... 3.1 3.3

K1.08 A.C. electrical power .................................................... 3.5 3.5

K1.09 Emergency generators ................................................... 3.8 3.8

K1.10 ECCS room coolers ..................................................... 3.2 3.2

K1.11 Nuclear boiler instrumentation ............................................ 3.7 3.7

K1.12 Plant air systems: Plant-Specific .......................................... 2.6* 2.7*

K1.13 Drywell pressure ....................................................... 3.9 4.0

K1.14 Shutdown cooling system: Plant-Specific .................................. 3.6 3.7

K1.15 Reactor building drain system: Plant-Specific ............................... 2.4* 2.6

K1.16 Component cooling water systems ......................................... 3.1 3.2

K1.17 Reactor pressure ........................................................ 4.0 4.0

K1.18 Reactor vessel: Plant-Specific ............................................ 3.8 3.8

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Pumps ................................................................ 3.5* 3.5*

K2.02 Valves ................................................................ 2.5* 2.7*

K2.03 Initiation logic ......................................................... 2.7* 2.9*
3.4-39 NUREG-1123, Rev. 2 |

SYSTEM 203000 RHR/LPCI: Injection Mode (Plant Specific)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3. Knowledge of the effect that a loss or malfunction of

the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) will

have on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level ..................................................... 4.3* 4.4*

K3.02 Suppression pool level .................................................. 3.5 3.5

K3.03 Automatic depressurization logic ......................................... 4.2* 4.3*

K3.04 Adequate core cooling .................................................. 4.6* 4.6*

K4. Knowledge of RHR/LPCI: INJECTION MODE (PLANT SPECIFIC)

design feature(s) and/or interlocks which provide for

the following:

(CFR: 41.7)

K4.01 Automatic system initiation/ injection ..................................... 4.2* 4.2

K4.02 Prevention of piping overpressurization .................................... 3.3 3.4

K4.03 Pump minimum flow protection .......................................... 3.2 3.3

K4.04 Pump motor cooling: Plant-Specific ...................................... 2.6 2.7

K4.05 Prevention of water hammer ............................................. 3.2 3.3

K4.06 Adequate pump net positive suction head (interlock

suction valve open): Plant-Specific ....................................... 3.5 3.5

K4.07 Emergency generator load sequencing ..................................... 3.7 3.9

K4.08 Pump operability testing ................................................. 3.3 3.4*

K4.09 Surveillance for all operable components ................................... 3.1 3.4

K4.10 Dedicated injection system during automatic system

initiation (injection valve interlocks) ...................................... 3.9 4.1

K4.11 Loop selection logic: Plant-Specific ...................................... 4.0 4.0

K4.12 System redundancy ..................................................... 3.5 3.6

K4.13 The prevention of leakage to the environment through

LPCI/RHR heat exchanger: Plant-Specific ................................. 3.4 3.7

K4.14 †Operation from remote shutdown panel ................................... 3.6 3.7

K4.15 Pump runout protection: Plant-Specific ................................... 2.5* 2.5

K5. Knowledge of the operational implications of the

following concepts as they apply to RHR/LPCI:

INJECTION MODE (PLANT SPECIFIC) :

(CFR: 41.5 / 45.3)

K5.01 Testable check valve operation ............................................ 2.7* 2.9

K5.02 †Core cooling methods ................................................. 3.5 3.7

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the RHR/LPCI: INJECTION

MODE (PLANT SPECIFIC) :

(CFR: 41.7 / 45.7)
NUREG-1123, Rev. 2 3.4-40 |

SYSTEM: 203000 RHR/LPCI: Injection Mode (Plant Specific)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6.01 A.C. electrical power ................................................... 3.6 3.7

K6.02 D.C. electrical power ................................................... 2.8* 3.0*

K6.03 Emergency generator ................................................... 3.7 3.9

K6.04 Keep fill system ........................................................ 3.3 3.5

K6.05 Condensate storage and transfer system: PlantSpecific ............................................................... 2.5 2.5

K6.07 Plant air systems: Plant-Specific .......................................... 2.7 2.7

K6.08 ECCS room cooling ..................................................... 2.9 3.1

K6.09 Nuclear boiler instrumentation ............................................ 3.4 3.4

K6.10 Component cooling water systems ......................................... 3.0 3.1

| K6.11 ADS .................................................................. 4.1* 4.1

K6.12 †ECCS room integrity ................................................... 2.7 2.9

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the RHR/LPCI:

INJECTION MODE (PLANT SPECIFIC) controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor water level ...................................................... 4.2* 4.3

A1.02 Reactor pressure ........................................................ 3.9* 4.0

A1.03 System flow ........................................................... 3.8 3.7

A1.04 System pressure ........................................................ 3.6 3.6

A1.05 Suppression pool level ................................................... 3.8 3.7

A1.06 Condensate storage tank level: Plant-Specific ............................... 2.4* 2.5

A1.07 Motor amps: Plant-Specific .............................................. 2.4* 2.5

A1.08 †Emergency generator loading ............................................ 3.7 3.8

A1.09 Component cooling water systems ......................................... 2.9 2.9

A2. Ability to (a) predict the impacts of the following on

the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) ; and

(b) based on those predictions, use procedures to

correct, control, or mitigate the consequences of

those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Inadequate net positive suction head ........................................ 3.2 3.4

A2.02 Pump trips ............................................................. 3.5 3.5

A2.03 Valve closures .......................................................... 3.2 3.3

A2.04 A.C. failures ........................................................... 3.5 3.6

A2.05 D.C. failures ........................................................... 3.0 3.2

A2.06 Emergency generator failure .............................................. 3.8 3.9

A2.07 Pump seal failure ....................................................... 3.0 3.1

A2.08 Inadequate room cooling ................................................. 2.9 3.0

A2.09 Inadequate system flow .................................................. 3.3 3.4

A2.10 Nuclear boiler instrument failures ......................................... 3.3 3.5
3.4-41 NUREG-1123, Rev. 2 |

SYSTEM: 203000 RHR/LPCI: Injection Mode (Plant Specific)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A2.11 Motor operated valve failures ............................................. 3.4 3.6

A2.12 Pump runout ........................................................... 2.6* 2.7* |

A2.13 Valve Openings ......................................................... 3.2 3.3 |

A2.14 Initiating logic failure ................................................... 3.8 3.9*

A2.15 Loop selection logic failure: Plant-Specific ................................ 4.2* 4.2*

A2.16 Loss of coolant accident ................................................. 4.4* 4.5*

A2.17 Keep fill system failure .................................................. 3.3 3.5

A3. Ability to monitor automatic operations of the

RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation ......................................................... 3.8* 3.7

A3.02 Pump start ............................................................. 4.0 3.9

A3.03 Pump discharge pressure ................................................. 3.7 3.6

A3.04 System flow ........................................................... 3.8 3.7

A3.05 Reactor water level ...................................................... 4.4* 4.4*

A3.06 Indicating lights and alarms ............................................... 3.7* 3.6

A3.07 Loop selection: Plant-Specific ........................................... 4.2* 4.6*

A3.08 System initiation sequence ............................................... 4.1 4.1

A3.09 Emergency generator load sequencing ...................................... 3.6 3.9*

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Pumps ................................................................ 4.3* 4.1

A4.02 System valves .......................................................... 4.1* 4.1

A4.03 Keep fill system ........................................................ 3.4 3.4

A4.04 Heat exchanger cooling flow.............................................. 3.6 3.6

A4.05 Manual initiation controls ................................................ 4.3* 4.1

A4.06 System reset following automatic initiation: PlantSpecific ............................................................... 3.9 3.9

A4.07 Reactor water level ...................................................... 4.5* 4.5

A4.08 Reactor pressure ........................................................ 4.3* 4.3

A4.09 System flow ........................................................... 4.1 4.0

A4.10 Pump/system discharge pressure: Plant-Specific ............................ 3.7 3.6

A4.11 Indicating lights and alarms ............................................... 3.7* 3.5

A4.12 Condensate storage tank level: Plant-Specific ............................... 2.5 2.6

A4.13 Suppression pool level/temperature ........................................ 3.9 3.9

A4.14 Testable check valves .................................................... 2.7* 2.7
NUREG-1123, Rev. 2 3.4-42 |

SYSTEM: 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)

TASK: Perform lineups of the residual heat removal (RHR) system

Fill and vent the residual heat removal system

Start up the residual heat removal system

Operate a residual heat removal heat exchanger

Perform purification of the residual heat removal system during shutdown cooling

Operate residual heat removal system with fuel pool cooling system

Monitor the residual heat removal system

Add chemicals to the residual heat removal system

Operate the residual heat removal system using the high pressure safety injection pumps

Shutdown the residual heat removal system

Drain the residual heat removal system

Fill the refueling cavity and/or dryer-separator using the residual heat removal system

Drain the refueling cavity and/or dryer-separator using the residual heat removal system

Perform RHR pump flow rate test

Perform residual heat removal pump operability test

Perform RHR service water pump flow rate test

Perform one RHR service water pump inoperable test

Perform one RHR pump inoperable test

Perform residual heat removal isolation valves, shutdown cooling valves and head spray simulated

automatic actuation test

Perform residual heat removal service water pump and motor operated valve operability test

Conduct RHR valve testing

Conduct RHR isolation valve control logic system functional test

Monitor the residual heat removal system

Shutdown the residual heat removal system

Fill the refueling cavity and/or dryer-separator using the residual heat removal system

Drain the refueling cavity and/or dryer-separator using the residual heat removal system

Perform one residual heat removal service water pump inoperable test

Perform one residual heat removal pump inoperable test

Perform residual heat removal isolation valves, shutdown cooling valves and head spray simulated

automatic actuation test

Conduct residual heat removal isolation valve control logic system functional test
3.4-43 NUREG-1123, Rev. 2 |

SYSTEM: 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between SHUTDOWN COOLING SYSTEM 

(RHR SHUTDOWN COOLING MODE) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor pressure ........................................................ 3.6 3.6

K1.02 Reactor water level ...................................................... 3.6 3.6

K1.03 Recirculation loop temperature ........................................... 3.4 3.5

K1.04 Fuel pool cooling assist: Plant-Specific .................................... 2.7 2.7

K1.05 Component cooling water systems ......................................... 3.1 3.1

K1.06 A.C. electrical power .................................................... 3.2 3.3

K1.07 D.C. electrical power .................................................... 2.4 2.6

K1.08 LPCI .................................................................. 3.9 3.9

K1.09 Auxiliary steam supply: Plant-Specific ..................................... 2.2* 2.2*

K1.10 RWCU ................................................................ 2.3* 2.3*

K1.11 Nitrogen: Plant-Specific ................................................ 1.8* 1.8*

K1.12 Isolation Condenser: Plant-Specific ....................................... 2.4* 2.4*

K1.13 Floor drain system: Plant-Specific ........................................ 1.7* 1.7*

K1.14 Reactor temperatures (moderator, vessel, flange) ............................ 3.6 3.6

K1.15 RHR service water: Plant-Specific ........................................ 3.5 3.6

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Pump motors ........................................................... 3.1* 3.1*

K2.02 Motor operated valves ................................................... 2.5* 2.7*

K3. Knowledge of the effect that a loss or malfunction of

the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING

MODE) will have on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor pressure ........................................................ 3.3 3.3

K3.02 Reactor water level: Plant-Specific ........................................ 3.2 3.3

K3.03 Reactor temperatures (moderator, vessel, flange) ............................ 3.8 3.9

K3.04 Recirculation loop temperatures .......................................... 3.7 3.7

K3.05 Fuel pool cooling assist: Plant-Specific .................................... 2.6 2.7

K4. Knowledge of SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN

COOLING MODE) design feature(s) and/or interlocks

which provide for the following:

(CFR: 41.7)

K4.01 High temperature isolation: Plant-Specific ................................. 3.4 3.4

K4.02 High pressure isolation: Plant-Specific .................................... 3.7 3.8

K4.03 Low reactor water level: Plant-Specific .................................... 3.8 3.8
NUREG-1123, Rev. 2 3.4-44 |

SYSTEM: 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.04 Adequate pump NPSH ................................................... 2.6 2.6

K4.05 Reactor cooldown rate .................................................. 3.6 3.7

K4.06 Motor cooling: Plant-Specific ............................................ 2.3* 2.3

K4.07 Pump minimum flow .................................................... 2.7 2.8

K5. Knowledge of the operational implications of the

following concepts as they apply to SHUTDOWN COOLING

SYSTEM (RHR SHUTDOWN COOLING MODE) :

(CFR: 41.5 / 45.3)

K5.01 NPSH ................................................................. 2.2* 2.4

K5.02 Valve operation ......................................................... 2.8 2.9

K5.03 Heat removal mechanisms ................................................ 2.8 3.1

K5.04 System venting ......................................................... 2.4 2.4

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the SHUTDOWN COOLING SYSTEM

(RHR SHUTDOWN COOLING MODE) :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical power .................................................... 3.3 3.4

K6.02 D.C. electrical power .................................................... 2.7 2.9

K6.03 Recirculation system .................................................... 3.1 3.2

K6.04 Reactor water level ...................................................... 3.6 3.6

K6.05 Component cooling water systems ......................................... 3.2 3.3

K6.06 Auxiliary steam supply: Plant-Specific ..................................... 2.0* 2.0*

K6.07 Nitrogen: Plant-Specific ................................................. 1.8* 1.8*

K6.08 RHR service water: Plant-Specific ........................................ 3.5 3.7

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the SHUTDOWN

COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) controls

including:

(CFR: 41.5 / 45.5)

A1.01 Heat exchanger cooling flow.............................................. 3.3 3.2

A1.02 SDC/RHR pump flow .................................................... 3.3 3.2

A1.03 Recirculation loop temperatures .......................................... 3.3 3.3

A1.04 SDC/RHR pump suction pressure .......................................... 2.7 2.7

A1.05 Reactor water level ...................................................... 3.4 3.4

A1.06 Reactor temperatures (moderator, vessel, flange) ............................ 3.7 3.7

| A1.07 Motor amps: Plant--Specific ............................................. 2.2* 2.1*

A1.08 Heat exchanger temperatures ............................................. 3.1 2.9

A1.09 SDC/RHR pump/system discharge pressure ................................. 2.8 2.8
3.4-45 NUREG-1123, Rev. 2 |

SYSTEM: 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A1.10 Throttle valve position ................................................... 3.0 2.9

A2. Ability to (a) predict the impacts of the following on

the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING

MODE) ; and (b) based on those predictions, use

procedures to correct, control, or mitigate the

consequences of those abnormal conditions or

operations:

(CFR: 41.5 / 45.6)

A2.01 Recirculation loop high temperature: Plant-Specific .......................... 3.1 3.3

A2.02 Low shutdown cooling suction pressure: Plant-Specific ....................... 2.6 2.7

A2.03 A.C. failure ............................................................. 3.2 3.2

A2.04 D.C. failure ............................................................. 2.5 2.6

A2.05 System isolation ......................................................... 3.5 3.7

A2.06 SDC/RHR pump trips ..................................................... 3.4 3.5

A2.07 Loss of motor cooling: Plant-Specific ...................................... 2.7 2.7

A2.08 Loss of heat exchanger cooling ............................................ 3.3 3.5

A2.09 Reactor low water level ................................................... 3.6 3.8

A2.10 Valve operation .......................................................... 2.9 2.9

A2.11 Recirculation pump trips: Plant-Specific .................................... 2.5 2.7

A2.12 Inadequate system flow ................................................... 2.9 3.0

A3. Ability to monitor automatic operations of the

SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE)

including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation .......................................................... 3.2 3.1

A3.02 Pump trips .............................................................. 3.2 3.2

A3.03 Lights and alarms ........................................................ 3.5 3.3

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 SDC/RHR pumps ........................................................ 3.7 3.7

A4.02 SDC/RHR suction valves .................................................. 3.6 3.5

A4.03 SDC/RHR discharge valves ................................................ 3.6 3.5

A4.04 Heat exchanger cooling water valves ........................................ 3.4 3.3

A4.05 Minimum flow valves ..................................................... 3.2 3.2

A4.06 Reactor water level ....................................................... 3.8 3.7

A4.07 Reactor temperatures (moderator, vessel, flange) ............................. 3.7 3.7

A4.08 Reactor power: Plant-Specific ............................................. 3.1 3.2

A4.09 System flow ............................................................ 3.1 3.1

A4.10 System pressures ........................................................ 2.9 3.0
NUREG-1123, Rev. 2 3.4-46 |

SYSTEM: 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A4.11 Heat exchanger cooling flow 3.2 3.2

A4.12 Recirculation loop temperatures 3.4 3.4
3.5-1 NUREG-1123, Rev. 2 |

3.5 Containment Integrity page

223001 Primary Containment System and Auxiliaries 3.5-3

223002 Primary Containment Isolation System 3.5-8

/Nuclear Steam Supply Shut-Off

290002 Reactor Vessel Internals 3.5-12

219000 RHR/LPCI: Torus/Suppression Pool Cooling Mode 3.5-15

226001 RHR/LPCI: Containment Spray System Mode 3.5-19

230000 RHR/LPCI: Torus/Suppression Pool Spray Mode 3.5-23

290001 Secondary Containment 3.5-28
NUREG-1123, Rev. 2 3.5-2 |

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3.5-3 NUREG-1123, Rev. 2 |

SYSTEM: 223001 Primary Containment System and Auxiliaries

TASK: Conduct lineups on the containment system 

Conduct containment inerting-normal purge on startup 

Conduct containment inerting-makeup operation 

Ventilate the containment during heatup and startup 

Conduct containment de-inerting Monitor the containment system in standby readiness 

Pump torus water to radwaste (pump suppression pool water to radwaste)

Refill the torus/suppression pool from the condensate storage tank

Startup the suppression pool cleanup system (write in) 

Shutdown the suppression pool cleanup system (write in) 

Perform external visual inspection of suppression chamber after relief valve operation 

Conduct pressure suppression chamber (PSC)-drywell vacuum breaker visual inspection

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between PRIMARY CONTAINMENT

SYSTEM AND AUXILIARIES and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Containment isolation/integrity: Plant-Specific ............................. 3.7 3.9

K1.02 Drywell isolation/integrity: Plant-Specific ................................. 3.6 3.8

K1.03 Containment/drywell atmosphere control ................................... 3.2 3.3

K1.04 Drywell floor and equipment floor drain system ............................. 3.1 3.2

K1.05 Suppression pool makeup system: Mark-III ................................. 3.3 3.5

K1.06 RHR/LPCI ............................................................. 3.4 3.6

K1.07 Suppression pool cleanup system: Plant-Specific ............................ 2.4 2.5

K1.08 Relief/safety valves ..................................................... 3.6 3.8

K1.09 SBGT/FRVS: Plant-Specific ............................................. 3.4 3.6

K1.10 Plant air systems ........................................................ 3.0 3.1

K1.11 Post accident sampling system ............................................ 2.7 2.9

K1.12 LPCS: Plant-Specific ................................................... 3.5 3.6

K1.13 HPCS: Plant-Specific ................................................... 3.4 3.5

K1.14 RCIC: Plant-Specific ................................................... 3.3 3.6

K1.15 HPCI: Plant-Specific ................................................... 3.5 3.9

K1.16 Containment and drywell atmosphere monitoring:

Plant-Specific .......................................................... 3.3 3.4

K1.17 Reactor building HVAC: Plant-Specific .................................... 3.1 3.1

K1.18 Drywell pneumatic compressors: Plant-Specific ............................. 2.6 2.8

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Atmosphere containment/ atmospheric dilution

compressors: Plant-Specific ............................................. 2.0* 2.1

K2.02 Drywell compressors .................................................... 1.8* 1.9*
NUREG-1123, Rev. 2 3.5-4 |

SYSTEM: 223001 Primary Containment System and Auxiliaries

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K2.03 Pumpback compressors: Plant-Specific .................................... 1.8* 1.8*

K2.04 Combustible gas mixing compressors: Mark-III ............................. 2.0* 2.4

K2.05 Hydrogen recombiners: Plant-Specific ..................................... 2.2* 2.4*

K2.06 Hydrogen igniters: Plant-Specific ......................................... 2.0* 2.4

K2.07 Containment atmosphere monitoring system ................................ 2.3* 2.6*

K2.08 Containment cooling air handling units: PlantSpecific ............................................................... 2.7 3.0*

K2.09 Drywell cooling fans: Plant-Specific ...................................... 2.7 2.9*

K2.10 Drywell chillers: Plant-Specific .......................................... 2.7 2.9*

K3. Knowledge of the effect that a loss or malfunction of

the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES will

have on following:

(CFR: 41.7 / 45.4)

K3.01 Secondary containment .................................................. 3.6 3.8

K3.02 Containment/drywell temperature: Plant-Specific ............................ 3.3 3.4

K3.03 Containment/drywell pressure: Plant-Specific ............................... 3.4 3.5

K3.04 Containment/drywell hydrogen gas concentration ............................ 3.3 3.5

K3.05 Containment/drywell oxygen gas concentration .............................. 3.1 3.2

K3.06 Differential pressure between secondary and primary

containment ............................................................ 3.3 3.6

K3.07 Differential pressure between suppression pool and

drywell/containment ..................................................... 3.1 3.2

K3.08 Pneumatically operated valves internal to

containment/drywell: Plant-Specific ....................................... 2.7 2.9

K3.09 Nuclear boiler instrumentation ............................................ 2.8 3.1

K3.10 Containment/drywell moisture content ..................................... 2.4 2.6

K4. Knowledge of PRIMARY CONTAINMENT SYSTEM AND

AUXILIARIES design feature(s) and/or interlocks which

provide for the following:

(CFR: 41.7)

K4.01 Allows for absorption of the energy released during a

LOCA ................................................................. 3.7 3.8

K4.02 Contains fission products after a LOCA .................................... 3.6 3.7

K4.03 Containment/drywell isolation ............................................ 3.7 3.8

K4.04 Prevents hydrogen from reaching an explosive mixture ........................ 3.5 3.8

K4.05 Maintains proper suppression pool to drywell

differential pressure ..................................................... 2.9 3.1

K4.06 Maintains proper containment/secondary containment to

drywell differential pressure .............................................. 3.1 3.3

K4.07 Prevents localized heating of suppression pool (SRV

steam quenchers) ....................................................... 3.1 3.3
3.5-5 NUREG-1123, Rev. 2 |

SYSTEM: 223001 Primary Containment System and Auxiliaries

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K5. Knowledge of the operational implications of the

following concepts as they apply to PRIMARY

CONTAINMENT SYSTEM AND AUXILIARIES :

(CFR: 41.5 / 45.3)

K5.01 Vacuum breaker/relief operation ........................................... 3.1 3.3

K5.02 Guard pipe operation: Mark-III ............................................ 2.3 2.4

K5.03 Down comer operation ................................................... 2.8 2.9

K5.04 Horizontal vent operation: Mark-III ......................................... 2.4 2.6

K5.05 Hydrogen recombiner operation: Plant-Specific .............................. 2.8 3.0

K5.06 Hydrogen igniter operation: Plant-Specific .................................. 2.8 2.9

K5.07 Suppression pool clean-up: Plant-Specific ................................... 2.3 2.4

K5.08 Pressure measurement .................................................... 2.7 2.8

K5.09 Hydrogen production mechanisms .......................................... 2.6 2.9*

K5.10 Hydrogen combustibility versus hydrogen concentration

and oxygen concentration ................................................. 2.9 3.1

K5.11 Temperature measurement ................................................ 2.7 2.7

K5.12 Hydrogen concentration measurement ....................................... 2.7 2.8

K5.13 Oxygen concentration measurement: Plant-Specific ........................... 2.7 2.8

K5.14 Differential pressure measurement ......................................... 2.6 2.8*

K5.15 Moisture content measurement: Plant-Specific ............................... 2.4 2.6

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the PRIMARY CONTAINMENT

SYSTEM AND AUXILIARIES :

(CFR: 41.7 / 45.7)

K6.01 Drywell cooling ......................................................... 3.6 3.8

K6.02 Containment cooling: Mark-III ............................................ 3.5 3.6

K6.03 Suppression pool makeup: Plant-Specific ................................... 2.8 3.1

K6.04 Combustible gas mixing: Plant-Specific ..................................... 2.8 2.8

K6.05 Hydrogen recombiner: Plant-Specific ...................................... 3.1 3.3

K6.06 Backup hydrogen purge: Plant-Specific ..................................... 2.8 3.0

K6.07 Hydrogen igniter system: Plant-Specific .................................... 3.0 3.1

K6.08 Containment atmospheric control .......................................... 3.3 3.4

K6.09 Drywell vacuum relief system .............................................. 3.4 3.6

K6.10 Containment vacuum relief system: Mark-III ................................. 3.0 3.2

K6.11 A.C. electrical distribution ................................................ 3.0 3.2

K6.12 D.C. electrical distribution ................................................ 2.7 3.0

K6.13 Applicable plant air system/ nitrogen make-up system. ......................... 3.2 3.4

K6.14 RHR/LPCI .............................................................. 3.6 3.8
NUREG-1123, Rev. 2 3.5-6 |

SYSTEM: 223001 Primary Containment System and Auxiliaries

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

ABILITY

Al. Ability to predict and/or monitor changes in

parameters associated with operating the PRIMARY

CONTAINMENT SYSTEM AND AUXILIARIES controls including:

(CFR: 41.5 / 45.5)

A1.01 Drywell temperature 3.5 3.6

A1.02 Drywell pressure 3.6 3.7

A1.03 Containment pressure: Mark-III 3.6 3.8

A1.04 Containment temperature: Mark-III 3.3 3.4

A1.05 Hydrogen concentration 3.1 3.3

A1.06 Oxygen concentration 3.1 3.3

A1.07 Drywell/suppression chamber differential pressure

(drywell to containment building): Plant-Specific 3.2 3.4

A1.08 Suppression pool level 3.5 3.6

A1.09 Suppression pool temperature 3.5 3.6

A1.10 Drywell leak detection system: Plant-Specific 3.4 3.6

A1.11 Reactor building to suppression chamber differential

pressure: Plant-Specific 3.1 3.2

A1.12 Moisture concentration 2.5 2.6

A2. Ability to (a) predict the impacts of the following on

the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES ; and

(b) based on those predictions, use procedures to

correct, control, or mitigate the consequences of

those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Loss of coolant accident ................................................. 4.3* 4.4*

A2.02 Steam bypass of suppression pool ......................................... 3.9 4.1

A2.03 Safety/relief valve leaking or stuck open ................................... 4.0 4.2*

A2.04 High containment/drywell hydrogen concentration ........................... 3.7 3.8

A2.05 High containment/drywell oxygen concentration ............................. 3.5 3.6

A2.06 High containment pressure: Mark-III ...................................... 4.1* 4.1*

A2.07 High drywell pressure ................................................... 4.2* 4.3*

A2.08 Compressor trips (loss of air): Plant-Specific .............................. 3.1 3.1

A2.09 Vacuum breaker malfunction ............................................. 3.4 3.6

A2.10 High drywell temperature ................................................ 3.6 3.8

A2.11 Abnormal suppression pool level .......................................... 3.6 3.8

A2.12 Abnormal suppression pool temperature ................................... 3.7 3.8

A2.13 High containment temperature: Mark-III ................................... 3.3 3.4

A2.14 Low containment to annulus pressure: Mark-III ............................. 3.4 3.4
3.5-7 NUREG-1123, Rev. 2 |

SYSTEM: 223001 Primary Containment System and Auxiliaries

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A3. Ability to monitor automatic operations of the PRIMARY

CONTAINMENT SYSTEM AND AUXILIARIES including:

(CFR: 41.7 / 45.7)

A3.01 Suppression pool level .................................................. 3.4 3.5

A3.02 Vacuum breaker/relief valve operation ..................................... 3.4 3.4

A3.03 System indicating light and alarms ......................................... 3.4 3.3

A3.04 Containment/drywell response during LOCA ................................ 4.2* 4.3* |

A3.05 Drywell pressure ....................................................... 4.3* 4.3* |

A3.06 Drywell/suppression chamber differential pressure:

Mark-I,II .............................................................. 3.4 3.3

A3.07 Containment/drywell differential pressure: Mark-III .......................... 3.6 3.6

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Containment relief valves: Mark-III ........................................ 3.5 3.5

A4.02 ACAD compressors: Plant-Specific ....................................... 2.6 2.6

A4.03 Air dilution valves to drywell and suppression pool:

Plant-Specific .......................................................... 3.4 3.4

A4.04 Containment/drywell hydrogen concentration ................................ 3.5 3.6

A4.05 Containment/drywell oxygen concentration ................................. 3.6 3.6

A4.06 Containment pressure: Mark-III ........................................... 4.0* 4.0*

A4.07 Drywell pressure ....................................................... 4.2* 4.1

A4.08 System indicating lights and alarms ........................................ 3.4 3.3

A4.09 SPDS/CRIDS/ERIS/GDS: Plant-Specific ................................... 2.5 2.9*

A4.10 Drywell nitrogen makeup: Mark-I,II ....................................... 3.2 3.2

A4.11 Drywell pneumatics ..................................................... 3.1 3.0

A4.12 Drywell coolers/chillers ................................................. 3.5 3.6

A4.13 Hydrogen recombiners: Plant-Specific ..................................... 3.4 3.4

A4.14 Hydrogen igniters: Plant-Specific ......................................... 3.7 3.7
NUREG-1123, Rev. 2 3.5-8 |

SYSTEM: 223002 Primary Containment Isolation System/Nuclear Steam Supply 

 Shut-Off

TASK: Conduct lineups on the containment system

Monitor the containment system in standby readiness

Perform primary containment isolation valve simulated automatic initiation and closure test

Conduct reactor building isolation logic system functional test

Perform drywell isolation, atmosphere control, and sump drain valves logic system test

Perform drywell isolation valves, atmosphere control valves, sump drain valves simulated auto actuation

test

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between PRIMARY CONTAINMENT

ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and the

following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Main steam system ...................................................... 3.8 3.9

K1.02 Reactor water cleanup ................................................... 3.3 3.5

K1.03 Plant ventilation ........................................................ 3.0 3.2

K1.04 High pressure coolant injection: Plant-Specific ............................. 3.5 3.8

K1.05 Isolation Condenser: Plant-Specific ....................................... 3.8 3.8

K1.06 Recirculation system .................................................... 2.9 3.2

K1.07 Reactor core isolation cooling; Plant-Specific ............................... 3.4 3.6

K1.08 Shutdown cooling system/RHR ........................................... 3.4 3.5

K1.09 Reactor vessel head spray: Plant-Specific .................................. 3.0 3.2

K1.10 Containment ventilation .................................................. 3.1 3.2

K1.11 Containment atmosphere sampling ......................................... 2.9 3.2

K1.12 Standby gas treatment system ............................................. 3.1 3.3

K1.13 Traversing in-core probe system ........................................... 2.7 2.9

K1.14 Containment drainage system ............................................. 2.8 3.1

K1.15 High pressure core spray : Plant-Specific .................................. 3.4 3.4

| K1.16 Process computer ....................................................... 2.1* 2.2*

K1.17 SPDS/ERIS/CRIDS/GDS: Plant-Specific ................................... 2.4 2.6

K1.18 Reactor building drainage system: Plant-Specific ............................ 2.5 2.6

K1.19 Component cooling water systems ......................................... 2.7 2.9

K1.20 A.C. distribution: Plant-Specific .......................................... 2.8 3.0

| K1.21 Circulating water: Plant-Specific .......................................... 2.2* 2.3*

K1.22 Containment nitrogen inerting system: Plant-Specific. ........................ 2.8 3.0

K1.23 River water makeup: Plant-Specific ....................................... 2.0* 2.1

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

| K2.01 Logic power supplies .................................................... 2.4* 2.7*
3.5-9 NUREG-1123, Rev. 2 |

SYSTEM: 223002 Primary Containment Isolation System/Nuclear Steam Supply 

 Shut-Off

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3. Knowledge of the effect that a loss or malfunction of

the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM

SUPPLY SHUT-OFF will have on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level ...................................................... 3.7 3.7

K3.02 Fuel cladding temperature ................................................ 3.6 3.7

K3.03 †Off-site radioactive release rates ......................................... 3.6 3.8

K3.04 Reactor building radiation level ........................................... 3.4 3.6

K3.05 Drainage sump levels .................................................... 2.7 2.8

K3.06 Turbine building radiation ................................................ 2.8 2.9

K3.07 Reactor pressure ........................................................ 3.7 3.8

K3.08 Reactor vessel temperature ............................................... 3.4 3.5

K3.09 Main steam system ...................................................... 3.4 3.6

K3.10 Reactor water cleanup ................................................... 2.9 3.1

K3.11 Plant ventilation ........................................................ 2.8 2.9

K3.12 High pressure coolant injection: Plant-Specific ............................. 3.6 3.6

K3.13 Isolation Condenser: Plant-Specific ....................................... 3.7 3.7

K3.14 Recirculation system: Plant-Specific ...................................... 3.0 3.0

K3.15 Reactor core isolation cooling: Plant-Specific .............................. 3.4 3.5

K3.16 Shutdown cooling system/RHR ........................................... 3.2 3.3

K3.17 Reactor vessel head spray: Plant-Specific .................................. 2.8 2.9

K3.18 Containment ventilation .................................................. 3.0 3.1

K3.19 Containment atmosphere sampling ......................................... 2.8 3.0

K3.20 Standby gas treatment system ............................................. 3.3 3.4

K3.21 Traversing in-core probe system ........................................... 2.6 2.7

K3.22 Containment drainage system ............................................. 2.5 2.6

K3.23 High pressure core spray : Plant-Specific .................................. 3.6 3.6

K3.24 Reactor building drainage system .......................................... 2.4 2.6

K3.25 Component cooling water systems ......................................... 2.3 2.3

K3.26 A.C. distribution ........................................................ 2.1* 2.2*

K3.27 Circulating water ....................................................... 1.8* 1.8*

K3.28 Containment nitrogen inerting system ...................................... 2.7 2.8

K3.29 River water makeup ..................................................... 1.8* 1.8*

K4. Knowledge of PRIMARY CONTAINMENT ISOLATION

SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF design feature(s)

and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Redundancy ............................................................ 3.0 3.2

K4.02 Testability ............................................................. 2.7 2.9

K4.03 Manual initiation capability: Plant-Specific ................................. 3.5 3.6

K4.04 †Automatic bypassing of selected isolations during

specified plant conditions ................................................ 3.2 3.6
NUREG-1123, Rev. 2 3.5-10 |

SYSTEM: 223002 Primary Containment Isolation System/Nuclear Steam Supply 

 Shut-Off

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.05 Single failures will not impair the function ability

of the system ........................................................... 2.9 3.1

K4.06 Once initiated, system reset requires deliberate

operator action ......................................................... 3.4 3.5

K4.07 Physical separation of system components (to prevent

localized environmental factors, electrical faults,

and physical events from impairing system response) ......................... 2.8 2.9

K4.08 †Manual defeating of selected isolations during

specified emergency conditions ........................................... 3.3 3.7

K5. Knowledge of the operational implications of the

following concepts as they apply to PRIMARY

CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY

SHUT-OFF :

(CFR: 41.5 / 45.3)

| None

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the PRIMARY CONTAINMENT

ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical distribution ............................................... 3.1 3.3

K6.02 D.C. electrical distribution ............................................... 3.0 3.2

K6.03 Process radiation monitoring system ....................................... 2.9 3.1

K6.04 Nuclear boiler instrumentation ............................................ 3.3 3.5

K6.05 Containment instrumentation ............................................. 3.0 3.3

K6.06 Various process instrumentation .......................................... 2.8 2.9

K6.07 Essential A.C. power .................................................... 3.2 3.3

K6.08 Reactor protection system ............................................... 3.5 3.7

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the PRIMARY

CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY

SHUT-OFF controls including:

(CFR: 41.5 / 45.5)

A1.01 System indicating lights and alarms ........................................ 3.5 3.5

A1.02 Valve closures .......................................................... 3.7 3.7

A1.03 SPDS/ERIS/CRIDS/GDS: Plant-Specific ................................... 2.5* 2.8*

A1.04 Individual system relay status ............................................. 2.6 2.8
3.5-11 NUREG-1123, Rev. 2 |

SYSTEM: 223002 Primary Containment Isolation System/Nuclear Steam Supply 

 Shut-Off

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY .............................................................. RO SRO

A2. Ability to (a) predict the impacts of the following on

the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM

SUPPLY SHUT-OFF ; and (b) based on those predictions,

use procedures to correct, control, or mitigate the

consequences of those abnormal conditions or

operations:

(CFR: 41.5 / 45.6)

A2.01 A.C. electrical distribution failures ........................................ 3.2 3.5

A2.02 D.C. electrical distribution failures ........................................ 2.9 3.2

A2.03 System logic failures .................................................... 3.0 3.3

A2.04 Process radiation monitoring system failures ................................ 2.9 3.2

A2.05 Nuclear boiler instrumentation failures ..................................... 3.3 3.6

A2.06 Containment instrumentation failures ...................................... 3.0 3.2

A2.07 Various process instrumentation failures ................................... 2.7 2.9

A2.08 †Surveillance testing .................................................... 2.7 3.1

A2.09 System initiation ........................................................ 3.6 3.7

A2.10 Loss of coolant accidents ................................................ 3.9 4.2

A2.11 †Standby liquid initiation ................................................. 3.8 3.9

A3. Ability to monitor automatic operations of the PRIMARY

CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY

SHUT-OFF including:

(CFR: 41.7 / 45.7)

A3.01 System indicating lights and alarms ........................................ 3.4 3.4

A3.02 Valve closures .......................................................... 3.5 3.5

A3.03 SPDS/ERIS/CRIDS/GDS: Plant-Specific ................................... 2.5* 2.8*

A3.04 Verification of relay operation: Plant-Specific .............................. 2.3* 2.5

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Valve closures .......................................................... 3.6 3.5

A4.02 Manually initiate the system .............................................. 3.9 3.8

A4.03 Reset system isolations .................................................. 3.6 3.5

A4.04 System indicating lights and alarms ........................................ 3.5 3.6

A4.05 SPDS/ERIS/CRIDS/GDS: Plant-Specific ................................... 2.5* 2.8*

A4.06 Confirm initiation to completion .......................................... 3.6* 3.7
NUREG-1123, Rev. 2 3.5-12 |

SYSTEM: 290002 Reactor Vessel Internals

TASK: Perform heatup/cooldown of reactor vessel

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between REACTOR VESSEL INTERNALS

and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Main steam system ...................................................... 3.2 3.2

K1.02 Recirculation system .................................................... 3.2 3.2

K1.03 Reactor feedwater system ................................................ 3.2 3.2

K1.04 HPCI: Plant-Specific ................................................... 3.4 3.5

K1.05 RHR: Plant-Specific .................................................... 3.1 3.2

K1.06 HPCS: Plant-Specific ................................................... 3.1 3.1

K1.07 Isolation condenser: Plant-Specific ....................................... 3.4 3.4

K1.08 RCIC: Plant-Specific ................................................... 3.1 3.1

K1.09 LPCI: Plant-Specific .................................................... 3.2 3.3

K1.10 CRD hydraulic system ................................................... 3.1 3.1

K1.11 CRD mechanism ........................................................ 2.9 2.9

K1.12 SBLC ................................................................. 3.4 3.5

K1.13 Relief/safety valves ..................................................... 3.4 3.5

K1.14 RWCU ................................................................ 2.9 3.1

K1.15 Nuclear boiler instrumentation ............................................ 3.4 3.5

K1.16 LPCS ................................................................. 3.2 3.4

K1.17 ADS .................................................................. 3.3 3.4

K1.18 Loss parts monitoring: Plant-Specific ..................................... 2.1* 2.2*

K1.19 TIP ................................................................... 2.5 2.6

K1.20 Nuclear instrumentation ................................................. 3.2 3.3

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

| None

K3. Knowledge of the effect that a loss or malfunction of

the REACTOR VESSEL INTERNALS will have on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level ...................................................... 3.2 3.3

K3.02 Reactor pressure ....................................................... 2.9 3.0

K3.03 Reactor power .......................................................... 3.3 3.4

K3.04 Plant radiation levels .................................................... 2.9 3.2

K3.05 Off-site radiation levels .................................................. 2.9 3.2

K3.06 PCIS/NSSSS ........................................................... 3.1 3.1

K3.07 Nuclear boiler instrumentation ............................................ 3.1 3.1
3.5-13 NUREG-1123, Rev. 2 |

SYSTEM: 290002 Reactor Vessel Internals

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4. Knowledge of REACTOR VESSEL INTERNALS design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 2/3 core coverage following a DBA LOCA ................................... 3.7 3.9

K4.02 Separation of fluid flow paths within the vessel ............................... 3.1 3.2

K4.03 Core orificing ........................................................... 3.2 3.3

K4.04 Moisture removal from generated steam ..................................... 2.8 2.8

K4.05 Natural circulation ....................................................... 3.3 3.5

K5. Knowledge of the operational implications of the

following concepts as they apply to REACTOR VESSEL

INTERNALS :

(CFR: 41.5 / 45.3)

K5.01 †Thermal limits ........................................................ 3.5 3.9

K5.02 Fission product poisons .................................................. 2.9 3.1

K5.03 Burnable poisons ....................................................... 2.7 3.0

K5.04 †PCIOMR Plant-Specific ................................................ 3.1 3.7

K5.05 Brittle fracture ......................................................... 3.1 3.3

K5.06 Heat transfer mechanisms ................................................ 2.8 3.2

K5.07 †Safety limits .......................................................... 3.9 4.4*

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the REACTOR VESSEL

INTERNALS :

(CFR: 41.7 / 45.7)

K6.01 CRD hydraulic system ................................................... 2.8 2.9

K6.02 CRD mechanism ........................................................ 2.9 2.9

K6.03 Recirculation system .................................................... 3.1 3.2

K6.04 Reactor feedwater system ................................................ 3.0 3.1

K6.05 SBLC ................................................................. 3.3 3.4

K6.06 Relief/safety valves ..................................................... 3.0 3.2

K6.07 RWCU ................................................................ 2.6 2.7

K6.08 Nuclear boiler instrumentation ............................................ 2.9 3.2

K6.09 LPCS ................................................................. 3.2 3.3

K6.10 HPCI: Plant-Specific ................................................... 3.0 3.3

K6.11 RHR: Plant-Specific .................................................... 3.1 3.2

K6.12 Isolation condenser: Plant-Specific ....................................... 3.0 3.2

K6.13 RCIC: Plant-Specific ................................................... 2.7 2.8

K6.14 LPCI: Plant-Specific .................................................... 3.1 3.3

K6.15 ADS .................................................................. 3.1 3.4

K6.16 Loss parts monitoring ................................................... 2.0* 2.0*

K6.17 TIP ................................................................... 2.5 2.5
NUREG-1123, Rev. 2 3.5-14 |

SYSTEM: 290002 Reactor Vessel Internals

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6.18 Nuclear instrumentation ................................................. 3.0 3.1

K6.19 HPCS: Plant-Specific(BWR-5&6) ........................................ 3.0 3.1

K6.20 Main steam system ...................................................... 2.9 3.1

 ABILITY

A1. Ability to predict and/or monitor changes in parameters associated with 

 operating the REACTOR VESSEL INTERNALS controls including:

(CFR: 41.5 / 45.5)

| None

A2. Ability to (a) predict the impacts of the following on

the REACTOR VESSEL INTERNALS ; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 LOCA ................................................................. 3.7 4.0

A2.02 †Overpressurization transient ............................................. 3.6 3.9

A2.03 ^Control rod drop accident ............................................... 3.6 3.9

A2.04 Excessive heatup/cooldown rate ........................................... 3.7 4.1

A2.05 †Exceeding thermal limits ................................................ 3.7 4.2

A2.06 †Exceeding safety limits ................................................. 4.0 4.5*

A3. Ability to monitor automatic operations of the REACTOR

VESSEL INTERNALS including:

(CFR: 41.7 / 45.7)

| None

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

| None
3.5-15 NUREG-1123, Rev. 2 |

SYSTEM: 219000 RHR/LPCI: Torus/Suppression Pool Cooling Mode

TASK: Startup the torus cooling system

Shutdown the torus (cooling system)

Monitor the torus cooling system

Lineup torus/suppression pool cooling system for different modes (cooling, spray)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Suppression pool ....................................................... 3.8 3.9

K1.02 Condensate storage tank ................................................. 2.4* 2.4

K1.03 LPCI/RHR piping ...................................................... 3.7 3.8

K1.04 LPCI/RHR pumps ...................................................... 3.9 3.9

K1.05 A.C. electrical power ................................................... 3.5 3.6

K1.06 Keep fill system ....................................................... 3.2 3.3

K1.07 Condensate transfer ..................................................... 2.5 2.6

K1.08 D.C. electrical power ................................................... 2.6 2.8

K1.09 Nuclear boiler instrumentation ........................................... 3.3 3.4

K1.10 Reactor building drain system: Plant-Specific .............................. 1.9* 1.9*

K1.11 Component cooling water systems ........................................ 3.0 3.0

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 †Valves ............................................................... 2.5* 2.9*

K2.02 Pumps ................................................................ 3.1* 3.3*

K2.03 Valve control logic: Plant-Specific ....................................... 2.2* 2.6*

K3. Knowledge of the effect that a loss or malfunction of

the RHR/LPCI: TORUS/SUPPRESSION POOL COOLING MODE will

have on following:

(CFR: 41.7 / 45.4)

K3.01 Suppression pool temperature control ..................................... 3.9 4.1

K4. Knowledge of RHR/LPCI: TORUS/SUPPRESSION POOL COOLING

MODE design feature(s) and/or interlocks which provide

for the following:

(CFR: 41.7)

K4.01 Surveillance for all operable components ................................... 3.1 3.4

K4.02 Redundancy ........................................................... 3.5 3.5

K4.03 Unintentional reduction in vessel injection flow

during accident conditions: Plant-Specific ................................. 3.8 3.8

K4.04 Prevention of piping overpressurization: Plant-

 Specific ................................................................. 3.3 3.4
NUREG-1123, Rev. 2 3.5-16 |

SYSTEM: 219000 RHR/LPCI: Torus/Suppression Pool Cooling Mode

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.05 Pump minimum flow protection .......................................... 3.0 3.2

K4.06 Pump motor cooling: Plant-Specific ...................................... 2.7 2.7

K4.07 Prevention of water hammer: Plant-Specific ................................ 3.0 3.1

K4.08 Adequate pump net positive suction head ................................... 2.9 3.0

K4.09 Heat exchanger cooling ................................................. 3.3 3.4

K4.10 Prevention of leakage to the environment through

system heat exchanger: Plant-Specific ..................................... 3.3 3.6

K5. Knowledge of the operational implications of the

following concepts as they apply to RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE :

(CFR: 41.5 / 45.3)

K5.01 System venting ......................................................... 2.6 2.7

K5.02 Pump cavitation ........................................................ 2.7 2.8

K5.03 Pressure measurement .................................................. 2.7* 2.8*

K5.04 Heat exchanger operation ................................................ 2.9 2.9

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical power ................................................... 3.2 3.3

K6.02 D.C. electrical power ................................................... 2.5* 2.8*

K6.03 Emergency generator ................................................... 3.5 3.5

K6.04 Keep fill system ....................................................... 2.9* 3.0

K6.05 Condensate storage tank: Plant-Specific ................................... 2.2* 2.2*

K6.06 Suppression pool ....................................................... 3.7 3.7

K6.07 Condensate transfer ..................................................... 2.2* 2.2*

K6.08 ECCS room cooling .................................................... 2.7* 2.7

K6.09 Nuclear boiler instrumentation ........................................... 3.0 3.1

K6.10 Component cooling water systems ........................................ 2.9 2.9

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE controls

including:

(CFR: 41.5 / 45.5)

A1.01 Suppression pool temperature ............................................ 4.0 4.0

A1.02 System flow ........................................................... 3.5 3.5

A1.03 System pressure ........................................................ 2.9 2.9

A1.04 Suppression pool level .................................................. 3.2 3.2

A1.05 Condensate storage tank level: Plant-Specific .............................. 2.1* 2.1*
3.5-17 NUREG-1123, Rev. 2 |

SYSTEM: 219000 RHR/LPCI: Torus/Suppression Pool Cooling Mode

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A1.06 Motor amps: Plant-Specific ............................................. 2.3* 2.4*

A1.07 Emergency generator loading ............................................. 3.2 3.3

A1.08 System lineup .......................................................... 3.7 3.6

A1.09 Suppression chamber air temperature: Plant-Specific ......................... 3.2 3.3

A1.10 Containment air temperature: Mark-III ..................................... 3.1 3.1

A2. Ability to (a) predict the impacts of the following on

the RHR/LPCI: TORUS/SUPPRESSION POOL COOLING MODE ;

and (b) based on those predictions, use procedures to

correct, control, or mitigate the consequences of

those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Inadequate net positive suction head ........................................ 3.0 3.1

A2.02 Pumps trips ............................................................ 3.3 3.3

A2.03 Valve closures .......................................................... 3.1 3.2

A2.04 Valve openings ......................................................... 3.1 3.2

A2.05 A.C. electrical failures ................................................... 3.3 3.5

A2.06 D.C. electrical failures ................................................... 2.7* 2.9* |

A2.07 Emergency generator failure .............................................. 3.5 3.7

A2.08 Pump seal failure ....................................................... 2.8 3.1

A2.09 Inadequate room cooling ................................................. 2.7 2.9

A2.10 Nuclear boiler instrument failures ......................................... 3.1 3.2

A2.11 Motor operated valve failures ............................................. 3.1 3.3

A2.12 Valve logic failure: Plant-Specific ........................................ 3.0 3.1* |

A2.13 High suppression pool temperature ........................................ 3.5 3.7

A2.14 Loss of coolant accident ................................................. 4.1 4.3* |

A2.15 Loss of, or inadequate, heat exchanger cooling flow .......................... 3.3 3.4

A2.16 High suppression pool level .............................................. 2.9 3.2

A3. Ability to monitor automatic operations of the

RHR/LPCI: TORUS/SUPPRESSION POOL COOLING MODE

including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation ......................................................... 3.3 3.3

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Pumps ................................................................ 3.8* 3.7* |

A4.02 Valve lineup ............................................................ 3.7* 3.5

A4.03 Keep fill system ........................................................ 2.9 2.9

A4.04 Minimum flow valves .................................................... 3.0 2.9

A4.05 Heat exchanger cooling flow.............................................. 3.4 3.4

A4.06 Valve logic reset following automatic initiation of

LPCI/RHR in injection mode ............................................. 3.9 3.7
NUREG-1123, Rev. 2 3.5-18 |

SYSTEM: 219000 RHR/LPCI: Torus/Suppression Pool Cooling Mode

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A4.07 System flow ........................................................... 3.5 3.4

A4.08 Pump/system discharge pressure: Plant-Specific ............................ 2.9 2.9

A4.09 Indicating lights and alarms ............................................... 3.4 3.3

A4.10 Condensate storage tank level: Plant-Specific ............................... 2.2* 2.2*

| A4.11 System venting ......................................................... 2.4 2.4

| A4.12 Suppression pool temperature ............................................. 4.1 4.1

A4.13 Suppression pool level ................................................... 3.9 3.8

A4.14 The overrides for suppression pool cooling valve

logic: Plant-Specific .................................................... 3.7 3.5
3.5-19 NUREG-1123, Rev. 2 |

SYSTEM: 226001 RHR/LPCI: Containment Spray System Mode

TASK: Lineup the containment spray system

Manually initiate containment spray

Shutdown the containment spray system

Monitor the containment spray system

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between RHR/LPCI: CONTAINMENT

SPRAY SYSTEM MODE and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Suppression pool ....................................................... 3.4 3.6

K1.02 LPCI/RHR piping ....................................................... 3.5 3.7

K1.03 LPCI/RHR pumps ....................................................... 3.5 3.6

K1.04 A.C. electrical power .................................................... 3.1 3.3

K1.05 Keep fill system ........................................................ 2.9 2.9

K1.06 Condensate Transfer ..................................................... 2.5 2.5

K1.07 D.C. electrical power .................................................... 2.4 2.5

K1.08 Nuclear boiler instrumentation ............................................ 3.2 3.4

K1.09 Drywell (spray penetration): Mark-I-II ..................................... 3.0 3.1

K1.10 Containment (spray penetration): Mark-III .................................. 3.0 3.0

K1.11 Component cooling water systems ......................................... 2.8 3.0

K1.12 Suppression pool (spray penetration): Plant-Specific. ........................ 3.0 3.0

K1.13 Containment instrumentation ............................................. 3.1 3.2

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Valves ................................................................ 2.1* 2.3*

K2.02 Pumps ................................................................ 2.9* 2.9*

K2.03 Valve control logic ...................................................... 2.4* 2.5*

K3. Knowledge of the effect that a loss or malfunction of

the RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE will have

on following:

(CFR: 41.7 / 45.4)

K3.01 Containment/drywell/suppression chamber pressure .......................... 3.6 3.7

K3.02 Containment/drywell/suppression chamber temperature ....................... 3.5 3.5

K3.03 Containment/drywell/suppression chamber components,

continued operation with elevated pressure and/or

temperature and/or level ................................................. 2.9 3.2

K4. Knowledge of RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE

design feature(s) and/or interlocks which provide for

the following:

(CFR: 41.7)

K4.01 Testability of all operable components ..................................... 2.6 2.8
NUREG-1123, Rev. 2 3.5-20 |

SYSTEM: 226001 RHR/LPCI: Containment Spray System Mode

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.02 Redundancy ............................................................ 2.8 2.9

K4.03 Reduction in vessel injection flow during accident 

conditions ............................................................. 2.9 3.1

K4.04 Prevention of piping overpressurization .................................... 2.4 2.6

K4.05 Pump minimum flow protection ........................................... 2.5 2.5

K4.06 Pump motor cooling .................................................... 2.2* 2.3

K4.07 Prevention of water hammer .............................................. 2.6 2.8

K4.08 Adequate pump net positive suction head .................................... 2.3 2.4

K4.09 Automatic containment spray initiation: BWR-6 ............................. 3.2 3.4

K4.10 Spray flow cooling ...................................................... 2.9 3.0

K4.11 Prevention of leakage to the environment through 

system heat exchanger ................................................... 2.7 2.9

K4.12 Prevention of inadvertent containment spray activation ........................ 2.9 2.9

K5. Knowledge of the operational implications of the

following concepts as they apply to RHR/LPCI:

CONTAINMENT SPRAY SYSTEM MODE :

(CFR: 41.5 / 45.3)

K5.01 System venting ......................................................... 2.2* 2.2*

K5.02 Water hammer ......................................................... 2.6 2.7

K5.03 Pump cavitation ........................................................ 2.3 2.5

K5.04 Evaporative cooling ..................................................... 2.1* 2.1*

K5.05 Convective cooling ...................................................... 2.1* 2.1*

K5.06 Vacuum breaker operation ................................................ 2.6 2.8

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the RHR/LPCI: CONTAINMENT

SPRAY SYSTEM MODE :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical power .................................................... 3.0 3.3

K6.02 D.C. electrical power .................................................... 2.6 2.9

K6.03 Emergency generator .................................................... 3.4 3.6

K6.04 Keep fill system ........................................................ 2.7 2.7

K6.05 Suppression pool (temperature level and pressure) ........................... 3.4 3.6

K6.06 Condensate transfer ..................................................... 2.4 2.4

K6.07 ECCS room cooling ..................................................... 2.4 2.6

K6.08 Nuclear boiler instrumentation ............................................ 2.7 2.8

K6.09 †Reactor building to suppression chamber vacuum

breakers: Plant-Specific ................................................. 3.3 3.5

K6.10 †Suppression chamber to drywell vacuum breakers:

Mark-1-II .............................................................. 3.3 3.5

K6.11 Component cooling water systems ......................................... 2.8 2.8

K6.12 Containment integrity ................................................... 3.4 3.5
3.5-21 NUREG-1123, Rev. 2 |

SYSTEM: 226001 RHR/LPCI: Containment Spray System Mode

Tasks as noted previously

IMPORTANCE

K/A NO. KNOWLEDGE RO SRO

K6.13 Suction flow path ....................................................... 3.2 3.2

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the RHR/LPCI:

CONTAINMENT SPRAY SYSTEM MODE controls including:

(CFR: 41.5 / 45.5)

A1.01 Containment/drywell pressure ............................................ 3.6 3.8

A1.02 Containment/drywell temperature ......................................... 3.4 3.5

A1.03 †Suppression chamber pressure: Mark-I-II ................................. 3.5 3.8

A1.04 Suppression pool temperature: Mark-I-II ................................... 3.3 3.6

A1.05 System lineup .......................................................... 3.1 3.4

A1.06 System flow ........................................................... 3.2 3.2

A1.07 System pressure ........................................................ 3.1 3.1

A1.08 Suppression pool level .................................................. 3.1 3.4

A1.09 Motor amps ............................................................ 2.1* 2.1*

A1.10 Emergency generator loading ............................................. 3.0 3.2

A2. Ability to (a) predict the impacts of the following on

the RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE ; and (b)

based on those predictions, use procedures to correct,

control, or mitigate the consequences of those

abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Inadequate net positive suction head ....................................... 2.4 2.6

A2.02 Pumps trips ........................................................... 3.1 3.2

A2.03 Valve closures ......................................................... 3.1 3.1

A2.04 Valve openings ......................................................... 3.0 3.0

A2.05 A.C. electrical failures .................................................. 3.3 3.4

A2.06 D.C. electrical failures .................................................. 2.8 2.9

A2.07 Emergency generator failure ............................................. 3.4 3.6

A2.08 Pump seal failure ....................................................... 2.4 2.5

A2.09 Inadequate room cooling ................................................ 2.6 2.7

A2.10 Nuclear boiler instrument failures ......................................... 3.0 3.1

A2.11 Motor operated valve failures ............................................ 3.0 3.0

A2.12 Pump runout ........................................................... 2.5 2.6

A2.13 Valve logic failure ...................................................... 2.8 2.9

A2.14 High suppression pool level .............................................. 2.9 3.1

A2.15 High containment / drywell pressure ....................................... 3.6 3.8

A2.16 Loss of, or inadequate heat exchanger cooling flow .......................... 3.1 3.1

A2.17 †High containment / drywell temperature ................................... 3.2 3.2

A2.18 †Low (or negative) containment/drywell pressure during

system operation ....................................................... 3.3 3.5
NUREG-1123, Rev. 2 3.5-22 |

SYSTEM: 226001 RHR/LPCI: Containment Spray System Mode

Tasks as noted previously

IMPORTANCE

K/A NO. KNOWLEDGE RO SRO

A2.19 †Low (or negative) suppression chamber pressure during

system operation: Mark-I-II ............................................. 3.5 3.8

A2.20 †Loss of coolant accident ............................................... 3.7 4.1

A2.21 Loss of containment/drywell cooling system(s) ............................. 3.3 3.4

A3. Ability to monitor automatic operations of the

RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation: Plant-Specific ........................................... 3.0 3.0

A3.02 System pressure ........................................................ 2.8 2.8

A3.03 System flow ........................................................... 2.8 2.8

A3.04 Lights and alarms ....................................................... 3.1 3.1

| A3.05 Containment pressure ................................................... 4.0* 4.0*

A3.06 Containment temperature ................................................ 3.5 3.5

A3.07 Pump start ............................................................. 3.5 3.5

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Pumps ................................................................ 3.5 3.4

A4.02 Suction valves .......................................................... 3.1 3.1

A4.03 Spray valves ............................................................ 3.5 3.4

A4.04 Keep fill system ........................................................ 2.8 2.7

A4.05 Minimum flow valves .................................................... 2.9 2.8

A4.06 Heat exchanger cooling flow.............................................. 2.9 2.8

A4.07 Valve logic reset/ bypass/ override ......................................... 3.5 3.5

A4.08 System flow ........................................................... 3.2 3.1

A4.09 Pump discharge pressure ................................................. 2.8 2.7

A4.10 Indicating lights and alarms ............................................... 3.3 3.2

A4.11 System venting ......................................................... 2.2* 2.2*

A4.12 Containment/drywell pressure ............................................ 3.8 3.8

A4.13 Containment/drywell temperature ......................................... 3.3 3.3

| A4.14 Suppression pool temperature ............................................. 3.5 3.6

A4.15 Suppression chamber pressure: Mark-I-II ................................... 3.6 3.6

A4.16 The override for suppression pool spray valve logic ........................... 3.5 3.5

A4.17 Manual initiation controls: BWR-6 ........................................ 3.8 3.8

A4.18 Automatic system initiation reset: BWR-6 ................................. 3.8 3.8

A4.19 Drywell temperature .................................................... 3.4 3.4

A4.20 Drywell pressure ....................................................... 3.9 3.8
3.5-23 NUREG-1123, Rev. 2 |

SYSTEM: 230000 RHR/LPCI: Torus/Suppression Pool Spray Mode

TASK: Lineup the torus spray system

Manually initiate torus spray

Monitor the torus spray system

IMPORTANCE

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between RHR/LPCI:

TORUS/SUPPRESSION POOL SPRAY MODE and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Suppression pool ....................................................... 3.6 3.7

K1.02 Condensate storage and transfer system .................................... 2.4* 2.5

K1.03 LPCI/RHR piping ....................................................... 3.3 3.5

K1.04 LPCI/RHR pumps ....................................................... 3.4 3.6

K1.05 A.C. electrical .......................................................... 3.2 3.3

K1.06 Keep fill system ........................................................ 3.0 3.1

K1.07 D.C. electrical .......................................................... 2.4* 2.6*

K1.08 Nuclear boiler instrumentation ............................................ 3.1 3.2

K1.09 Reactor building drain system ............................................. 2.3* 2.4* |

K1.10 Component cooling water systems ......................................... 2.8 2.8

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Valves ................................................................ 2.1* 2.3* |

K2.02 Pumps ................................................................ 2.8* 2.9* |

K3. Knowledge of the effect that a loss or malfunction of

the RHR/LPCI: TORUS/SUPPRESSION POOL SPRAY MODE will

have on following:

(CFR: 41.7 / 45.4)

K3.01 Suppression chamber pressure ............................................ 3.7 3.9

K3.02 Suppression pool temperature ............................................. 3.3 3.5

K3.03 Drywell pressure ....................................................... 3.4 3.6

K3.04 Suppression chamber air temperature ...................................... 3.7 3.8

K4. Knowledge of RHR/LPCI: TORUS/SUPPRESSION POOL SPRAY

MODE design feature(s) and/or interlocks which provide

for the following:

(CFR: 41.7)

K4.01 Surveillance for all operable components ................................... 3.1 3.3

K4.02 Redundancy ............................................................ 3.1* 3.2

K4.03 Unintentional reduction in vessel injection flow

during accident conditions ................................................ 3.5 3.6

K4.04 Prevention of piping overpressurization .................................... 3.0 3.2

K4.05 Pump minimum flow protection ........................................... 2.8 3.1

K4.06 Pump motor cooling .................................................... 2.7 2.8
NUREG-1123, Rev. 2 3.5-24 |

SYSTEM: 230000 RHR/LPCI: Torus/Suppression Pool Spray Mode

Tasks as noted previously

IMPORTANCE

K/A NO. KNOWLEDGE RO SRO

K4.07 Prevention of water hammer .............................................. 3.1 3.2

K4.08 Adequate pump net positive suction head .................................... 2.9 3.2

K4.09 Spray flow cooling ...................................................... 3.0 3.1

K4.10 Prevention of leakage to the environment through

system heat exchanger ................................................... 3.2 3.5

K5. Knowledge of the operational implications of the

following concepts as they apply to RHR/LPCI:

TORUS/SUPPRESSION POOL SPRAY MODE :

(CFR: 41.5 / 45.3)

K5.01 System venting ......................................................... 2.6 2.7

K5.02 Pump cavitation ........................................................ 2.4* 2.5

K5.03 Pressure measurement ................................................... 2.5* 2.6*

K5.04 Evaporative cooling ..................................................... 2.5* 2.5*

K5.05 Convective cooling ...................................................... 2.6* 2.6*

K5.06 Heat exchanger operation ................................................ 2.5* 2.6

K5.07 Vacuum breaker operation ................................................ 2.9* 3.1

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the RHR/LPCI:

TORUS/SUPPRESSION POOL SPRAY MODE :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical .......................................................... 3.3 3.4

K6.02 D.C. electrica .......................................................... 2.5* 2.8*

K6.03 Emergency generator .................................................... 3.5 3.6

K6.04 Keep fill system ........................................................ 2.8 2.8

K6.05 Suppression pool ....................................................... 3.3 3.4

K6.06 Condensate storage and transfer system .................................... 2.3* 2.4*

K6.07 ECCS room cooling ..................................................... 2.8 3.0

K6.08 Nuclear boiler instrumentation ............................................ 2.9 3.1

K6.09 Reactor building to suppression pool vacuum breakers ........................ 3.5 3.8

K6.10 Component cooling water systems ......................................... 2.5 2.6

 ABILITY

A1. Ability to predict and/or monitor changes in parameters 

 associated with operating the RHR/LPCI:

TORUS/SUPPRESSION POOL SPRAY MODE controls including:

(CFR: 41.5 / 45.5)

A1.01 Suppression chamber pressure ............................................ 3.8 3.9

A1.02 Suppression pool temperature ............................................. 3.7 3.8

A1.03 Drywell pressure ....................................................... 3.6 3.8

A1.04 System flow ........................................................... 3.2* 3.3
3.5-25 NUREG-1123, Rev. 2 |

SYSTEM: 230000 RHR/LPCI: Torus/Suppression Pool Spray Mode

Tasks as noted previously

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A1.05 System pressure ........................................................ 2.8* 2.9

A1.06 Suppression pool level ................................................... 3.3 3.3

A1.07 Condensate storage tank level ............................................. 2.2* 2.3*

A1.08 Motor amps ............................................................ 2.4* 2.5*

A1.09 Emergency generator loading ............................................. 3.3 3.5

A1.10 System lineup .......................................................... 3.7 3.7

A1.11 Suppression chamber air temperature ...................................... 3.6 3.6

A2. Ability to (a) predict the impacts of the following on

the RHR/LPCI: TORUS/SUPPRESSION POOL SPRAY MODE ; and

(b) based on those predictions, use procedures to

correct, control, or mitigate the consequences of

those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Inadequate net positive suction head ........................................ 3.0 3.2

A2.02 Pump trips ............................................................. 3.3 3.4 |

A2.03 Valve closures .......................................................... 2.9 3.2

A2.04 Valve openings ......................................................... 2.8 3.1

A2.05 A.C. electrical failures ................................................... 3.3 3.6

A2.06 D.C. electrical failures ................................................... 2.6* 2.9*

A2.07 Emergency generator failure .............................................. 3.5 3.8

A2.08 Pump seal failure ....................................................... 2.8 3.2

A2.09 Inadequate room cooling ................................................. 2.8 3.0

A2.10 Nuclear boiler instrument failures ......................................... 2.8 3.0

A2.11 Motor operated valve failures ............................................. 3.1 3.3

A2.12 Valve logic failure ...................................................... 3.2 3.3

A2.13 High suppression pool level .............................................. 2.9 3.2

A2.14 Low (or negative) suppression pool pressure during

system operation ....................................................... 3.2 3.5

A2.15 Loss of coolant accident ................................................. 4.0 4.1

A2.16 Loss of, or inadequate, heat exchanger cooling flow .......................... 3.1 3.3

A3. Ability to monitor automatic operations of the

RHR/LPCI: TORUS/SUPPRESSION POOL SPRAY MODE including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation ......................................................... 3.4 3.3

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Pumps ................................................................ 3.7* 3.5

A4.02 Spray valves ............................................................ 3.8 3.6

A4.03 Keep fill system ........................................................ 3.1 3.0

A4.04 Minimum flow valves ................................................... 3.1 2.9

A4.05 Heat exchanger cooling flow.............................................. 3.2 3.1
NUREG-1123, Rev. 2 3.5-26 |

SYSTEM: 230000 RHR/LPCI: Torus/Suppression Pool Spray Mode

Tasks as noted previously

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A4.06 Valve logic reset following automatic initiation of

LPCI/RHR in injection mode 4.0 3.9

A4.07 System flow 3.6 3.4

A4.08 Pump/system discharge pressure 3.0 2.9
3.5-27 NUREG-1123, Rev. 2 |

SYSTEM: 230000 RHR/LPCI: Torus/Suppression Pool Spray Mode

Tasks as noted previously

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A4.09 Indicating lights and alarms ............................................... 3.6 3.3

A4.10 Condensate storage tank level ............................................. 2.4* 2.4

A4.11 System venting ......................................................... 2.5 2.4

A4.12 Suppression pool level ................................................... 3.8 3.8

A4.13 Suppression chamber pressure ............................................ 4.0 3.9

A4.14 Suppression pool temperature ............................................. 3.8 3.8

A4.15 Drywell pressure ....................................................... 3.9 4.0

A4.16 The override for suppression pool spray valve logic ........................... 3.8 3.8
NUREG-1123, Rev. 2 3.5-28 |

SYSTEM: 290001 Secondary Containment

IMPORTANCE

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between SECONDARY CONTAINMENT and

the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor building ventilation: Plant-Specific ................................. 3.3 3.5

K1.02 Primary containment system: Plant-Specific ................................ 3.4 3.6

K1.03 Radwaste building ventilation: Plant-Specific ............................... 2.4 2.7

K1.04 SBGT ................................................................. 3.7 3.9

K1.05 Auxiliary building ventilation: Plant-Specific ............................... 3.1 3.3

K1.06 Auxiliary building isolation: BWR-6 ....................................... 3.4 3.6

K1.07 Turbine building ventilation (steam tunnel): PlantSpecific ............................................................... 3.0 3.1

K1.08 Exhaust stack: BWR-2,3,4 ............................................... 3.2 3.3

K1.09 Plant air systems ........................................................ 2.9 2.9

K1.10 Auxiliary boiler system: BWR-2,3,4 ....................................... 1.6* 1.6*

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

| None

K3. Knowledge of the effect that a loss or malfunction of

the SECONDARY CONTAINMENT will have on following:

(CFR: 41.7 / 45.4)

K3.01 †Off-site radioactive release rates ......................................... 4.0 4.4*

K4. Knowledge of SECONDARY CONTAINMENT design feature(s)

and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Personnel access without breaching secondary

containment: Plant-System ............................................... 3.5 3.8

K4.02 Protection against over pressurization: Plant-System ......................... 3.4 3.5

K4.03 Fluid leakage collection .................................................. 2.8 2.9

K4.04 Auxiliary building isolation: BWR-6 ....................................... 3.4 3.4

K5. Knowledge of the operational implications of the

following concepts as they apply to SECONDARY

CONTAINMENT :

(CFR: 41.5 / 45.3)

| K5.01 Vacuum breaker operation: BWR-4 ....................................... 3.3* 3.4*

K5.02 Flow measurement: BWR-3 .............................................. 2.2 2.2
3.5-29 NUREG-1123, Rev. 2 |

SYSTEM: 290001 Secondary Containment

Tasks as noted previously

IMPORTANCE

K/A NO. KNOWLEDGE RO SRO

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the SECONDARY CONTAINMENT :

(CFR: 41.7 / 45.7)

K6.01 Reactor building ventilation: Plant-Specific ................................. 3.5 3.6

K6.02 Radwaste building ventilation: Plant-Specific ............................... 2.4 2.6

K6.03 SBGT ................................................................. 3.8 4.0

K6.04 Primary containment system .............................................. 3.9 4.1

K6.05 Auxiliary building ventilation: Plant-Specific ............................... 2.9 3.0

K6.06 Turbine building ventilation: Plant-Specific ................................. 2.2* 2.3

K6.07 Auxiliary boiler system: BWR-3,4 ........................................ 1.9* 2.0*

K6.08 Plant air systems ........................................................ 2.7 2.8

K6.09 A.C. power: BWR-6 .................................................... 3.4 3.6

 ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the SECONDARY

CONTAINMENT controls including:

(CFR: 41.5 / 45.5)

A1.01 System lineups ......................................................... 3.1 3.1

A1.02 High area temperature: BWR-6 ........................................... 3.6 3.6

A2. Ability to (a) predict the impacts of the following on

the SECONDARY CONTAINMENT ; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 †Personnel airlock failure ................................................ 3.3 3.7

A2.02 †Excessive outleakage ................................................... 3.5 3.7

A2.03 High area radiation ...................................................... 3.4 3.6

A2.04 High airborne radiation .................................................. 3.4 3.7

A2.05 High area temperature ................................................... 3.1 3.3

A2.06 Auxiliary building isolation: BWR-6 ....................................... 3.7 4.0

A3. Ability to monitor automatic operations of the

SECONDARY CONTAINMENT including:

(CFR: 41.7 / 45.7)

A3.01 Secondary containment isolation .......................................... 3.9 4.0

A3.02 Normal building differential pressure: Plant-Specific ........................ 3.5 3.5
NUREG-1123, Rev. 2 3.5-30 |

SYSTEM: 290001 Secondary Containment

Tasks as noted previously

IMPORTANCE

K/A NO. ABILITY RO SRO

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Reactor building differential pressure: PlantSpecific ............................................................... 3.3 3.4

A4.02 Reactor building area temperatures: Plant-Specific ........................... 3.3 3.4

A4.03 Auxiliary building differential pressure: PlantSpecific ............................................................... 2.6* 2.7

A4.04 Auxiliary building area temperature: Plant-Specific ........................... 2.6* 2.7

A4.05 Fuel building differential pressure: Plant-Specific ............................ 3.3 3.5

A4.06 Fuel building area temperature: Plant-Specific ............................... 3.3 3.5

A4.07 Radwaste building differential pressure: PlantSpecific ................................................................ 2.3 2.5

A4.08 Radwaste building area temperature: Plant-Specific ........................... 2.2 2.4

A4.09 System status lights and alarms: Plant-Specific ............................... 3.2 3.2

A4.10 System lineups: Plant-Specific ............................................ 3.4 3.3

A4.11 System reset: Plant-Specific .............................................. 3.4 3.4

A4.12 Surveillance testing: Plant-Specific ........................................ 2.8 3.2
3.6-1 NUREG-1123, Rev. 2 |

3.6 Electrical page

262001 A.C. Electrical Distribution 3.6-3

263000 D.C. Electrical Distribution 3.6-6

264000 Emergency Generators (Diesel/Jet) 3.6-9

262002 Uninterruptable Power Supply (A.C. /D.C.) 3.6-13
NUREG-1123, Rev. 2 3.6-2 |

This page left blank
3.6-3 NUREG-1123, Rev. 2 |

SYSTEM: 226001 A.C. Electrical Distribution

TASK: Lineup the electrical distribution system ( from station power to reserve station power)

Shift auxiliary buses between the unit auxiliary XFMR and the service/startup XFMR

Monitor the A.C. electrical distribution system (monitor the 416V A.C. power distribution system)

Deenergize a motor control center bus from service

Restore a motor control center bus to service

Deenergize an engineering safeguards (4160V vital) bus from service

Restore an engineering safeguards bus

Backfeed unit auxiliary transformer from main transmission switchyard (main turbine generator links

removed)

Transfer a vital (120V)/instrument bus power supply

Operate a vital motor-generator set

Perform ground isolation

Lineup the electrical distribution system ( from normal power to startup power) (write in)

Perform equipment/bus testing for ground faults

Perform operation of circuit breakers and disconnects

Perform emergency A.C. load sequencing and 4KV emergency systems volt relays instrumentation

function tests

Perform circuit or equipment grounding using built-in devices

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between A.C. ELECTRICAL

DISTRIBUTION and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Emergency generators (diesel/jet) .......................................... 3.8 4.3*

K1.02 D.C. electrical distribution ................................................ 3.3 3.6

K1.03 Off-site power sources ................................................... 3.4 3.8

K1.04 Uninterruptible power supply .............................................. 3.1 3.4

K1.05 Main turbine/generator ................................................... 3.0 3.2 |

K1.06 Alternate shutdown system: Plant-Specific .................................. 3.6 3.9

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Off-site sources of power ................................................. 3.3 3.6

K3. Knowledge of the effect that a loss or malfunction of

the A.C. ELECTRICAL DISTRIBUTION will have on

following:

(CFR: 41.7 / 45.4)

K3.01 Major system loads ...................................................... 3.5 3.7

K3.02 Emergency generators .................................................... 3.8 4.2
NUREG-1123, Rev. 2 3.6-4 |

SYSTEM: 262001 A.C. Electrical Distribution

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3.03 D.C. electrical distribution ................................................ 2.9 3.2

K3.04 Uninterruptible power supply .............................................. 3.1 3.3

K3.05 Off-site power system .................................................... 3.2 3.5

K3.06 Reactor protection system ................................................ 3.8 4.1*

K4. Knowledge of A.C. ELECTRICAL DISTRIBUTION design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Bus lockouts ............................................................ 3.0 3.4

K4.02 Circuit breaker automatic trips ............................................. 2.9 3.3

K4.03 Interlocks between automatic bus transfer and breakers ........................ 3.1 3.4

K4.04 Protective relaying ....................................................... 2.8 3.1

K4.05 Paralleling of A.C. sources (synchroscope) .................................. 3.4 3.6

K4.06 Redundant power sources to vital buses ...................................... 3.6 3.9

K5. Knowledge of the operational implications of the

following concepts as they apply to A.C. ELECTRICAL

DISTRIBUTION:

(CFR: 41.5 / 45.3)

K5.01 Principle involved with paralleling two A.C. sources ........................... 3.1 3.4

K5.02 Breaker control .......................................................... 2.6 2.9

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the A.C. ELECTRICAL

DISTRIBUTION:

(CFR: 41.7 / 45.7)

K6.01 D.C. power ............................................................. 3.1 3.4

K6.02 Off-site power .......................................................... 3.6 3.9

K6.03 Generator trip ........................................................... 3.5 3.7

 ABILITY

A1. Ability to predict and/or monitor changes in

 parameters associated with operating the A.C.

ELECTRICAL DISTRIBUTION controls including:

(CFR: 41.5 / 45.5)

A1.01 Effect on instrumentation and controls of switching

power supplies .......................................................... 3.1 3.4

A1.02 Effects of loads when energizing a bus ...................................... 3.1 3.5

A1.03 Bus voltage ............................................................. 2.9 3.1
3.6-5 NUREG-1123, Rev. 2 |

SYSTEM: 262001 A.C. Electrical Distribution

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A1.04 Load currents ........................................................... 2.7 2.9

A1.05 Breaker lineups .......................................................... 3.2 3.5

A2. Ability to (a) predict the impacts of the following on

the A.C. ELECTRICAL DISTRIBUTION ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Turbine/generator trip .................................................... 3.4 3.6

A2.02 Loss of coolant accident .................................................. 3.6 3.9

A2.03 Loss of off-site power .................................................... 3.9 4.3*

A2.04 Types of loads that, if deenergized, would degrade or

hinder plant operation .................................................... 3.8 4.2

A2.05 Bus grounds ............................................................. 2.9 3.3

A2.06 Deenergizing a plant bus .................................................. 2.7 2.9

A2.07 Energizing a dead bus ..................................................... 3.0 3.2

A2.08 Opening a disconnect under load ........................................... 3.3 3.6

A2.09 Exceeding voltage limitations .............................................. 3.1 3.4

A2.10 Exceeding current limitations .............................................. 2.9 3.4

A2.11 Degraded system voltages ................................................. 3.2 3.6

A3. Ability to monitor automatic operations of the A.C.

ELECTRICAL DISTRIBUTION including:

(CFR: 41.7 / 45.7)

A3.01 Breaker tripping ......................................................... 3.1 3.2

A3.02 Automatic bus transfer .................................................... 3.2 3.3

A3.03 Load shedding ........................................................... 3.4 3.5

A3.04 Load sequencing ......................................................... 3.4 3.6

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 All breakers and disconnects (including available

switch yard): Plant-Specific ............................................... 3.4 3.7

A4.02 Synchroscope, including understanding of running and

incoming voltages ........................................................ 3.4 3.4

A4.03 Local operation of breakers ............................................... 3.2 3.4

A4.04 Synchronizing and paralleling of different A.C.

supplies ................................................................ 3.6 3.7

A4.05 Voltage, current, power, and frequency on A.C. buses .......................... 3.3 3.3
NUREG-1123, Rev. 2 3.6-6 |

SYSTEM: 263000 D.C. Electrical Distribution

TASK: Startup a battery charger 

Shift battery chargers 

Monitor the D.C. electrical distribution system (battery, chargers, distribution and PWR panels) 

Monitor the D.C. electrical distribution system for grounds 

Energize D.C. switchboards 

Deenergize D.C. switchboards 

Energize D.C. equipment 

Deenergize D.C. equipment 

Secure a battery charger

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between D.C. ELECTRICAL

DISTRIBUTION and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 A.C. electrical distribution ............................................... 3.3 3.5

K1.02 Battery charger and battery ............................................... 3.2 3.3

K1.03 Battery ventilation ...................................................... 2.6 2.8

K1.04 Ground detection ....................................................... 2.6 2.9

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Major D.C. loads ....................................................... 3.1 3.4

K2.02 Battery room ventilation ................................................. 2.1* 2.2*

K3. Knowledge of the effect that a loss or malfunction of

the D.C. ELECTRICAL DISTRIBUTION will have on

following:

(CFR: 41.7 / 45.4)

K3.01 Emergency generators: Plant-Specific ..................................... 3.4 3.8

K3.02 Components using D.C. control power (i.e. breakers) ......................... 3.5 3.8

K3.03 Systems with D.C. components (i.e. valves, motors,

solenoids, etc.) ......................................................... 3.4 3.8

K4. Knowledge of D.C. ELECTRICAL DISTRIBUTION design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Manual/ automatic transfers of control: PlantSpecific ............................................................... 3.1 3.4

K4.02 Breaker interlocks, permissives, bypasses and cross

ties: Plant-Specific ..................................................... 3.1 3.5
3.6-7 NUREG-1123, Rev. 2 |

SYSTEM: 263000 D.C. Electrical Distribution

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K5. Knowledge of the operational implications of the

following concepts as they apply to D.C. ELECTRICAL

DISTRIBUTION :

(CFR: 41.5 / 45.3)

K5.01 Hydrogen generation during battery charging. . . . . ............................ 2.6 2.9

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the D.C. ELECTRICAL

DISTRIBUTION :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical distribution ................................................ 3.2 3.5

K6.02 Battery ventilation ....................................................... 2.5 2.6

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the D.C.

ELECTRICAL DISTRIBUTION controls including:

(CFR: 41.5 / 45.5)

A1.01 Battery charging/discharging rate ........................................... 2.5 2.8

A2. Ability to (a) predict the impacts of the following on

the D.C. ELECTRICAL DISTRIBUTION ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Grounds ................................................................ 2.8 3.2

A2.02 Loss of ventilation during charging ......................................... 2.6 2.9

A3. Ability to monitor automatic operations of the D.C.

ELECTRICAL DISTRIBUTION including:

(CFR: 41.7 / 45.7)

A3.01 Meters, dials, recorders, alarms, and indicating

lights .................................................................. 3.2 3.3

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Major breakers and control power fuses: PlantSpecific ................................................................ 3.3 3.5
NUREG-1123, Rev. 2 3.6-8 |

SYSTEM: 263000 D.C. Electrical Distribution

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A4.02 Battery voltage indicator: Plant-Specific 3.2 3.1

A4.03 Battery discharge rate: Plant-Specific 2.7 2.8

A4.04 Ground detection circuit: Plant-Specific 3.0 3.2
3.6-9 NUREG-1123, Rev. 2 |

SYSTEM: 264000 Emergency Generators (Diesel/Jet)

TASK: Perform a lineup of the diesel generator system 

Start a diesel generator (D/G)

Load the diesel generator (D/G) 

Monitor the diesel generator

Unload the diesel generator

Shutdown the diesel generator (D/G)

Transfer fuel oil from main storage tanks to various system tanks

Operate the diesel starting air compressor

Restart a diesel generator (D/G) with an automatic start signal present

Perform emergency diesel generator (EDG) load tests

Perform lineups on the gas turbine generator

Start the gas turbine generator remotely

Monitor gas turbine generator emergency start

Monitor the gas turbine generator during operation

Conduct normal shutdown of the gas turbine generator

Conduct emergency shutdown of the gas turbine generator

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between EMERGENCY GENERATORS

(DIESEL/JET) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 A.C. electrical distribution ............................................... 3.8 4.1

K1.02 D.C. electrical distribution ............................................... 3.3 3.4

K1.03 Fire protection system ................................................... 2.9 3.2

K1.04 Emergency generator cooling water system ................................. 3.2 3.3

K1.05 Emergency generator fuel oil supply system ................................. 3.2 3.3

K1.06 Starting system ......................................................... 3.2 3.2

K1.07 Emergency core cooling systems .......................................... 3.9 4.1

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Air compressor ......................................................... 2.2* 2.4*

K2.02 Fuel oil pumps ......................................................... 2.2* 2.4*

K2.03 Turning gear (jet engine): Plant-Specific ................................... 2.0* 2.3*

K2.04 Ignition system (jet engine): Plant-Specific ................................. 2.3* 2.7*

K2.05 Lube oil pumps ......................................................... 2.3* 2.4*

K2.06 Battery charger ......................................................... 2.2* 2.2*

K2.07 Emergency generator field flash ........................................... 2.1* 2.3*
NUREG-1123, Rev. 2 3.6-10 |

SYSTEM: 264000 Emergency Generators (Diesel/Jet)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3. Knowledge of the effect that a loss or malfunction of

the EMERGENCY GENERATORS (DIESEL/JET) will have on

following:

(CFR: 41.7 / 45.4)

K3.01 Emergency core cooling systems 4.2* 4.4*

K3.02 A.C. electrical distribution 3.9 4.0

K3.03 Major loads powered from electrical buses fed by the

emergency generator(s) 4.1* 4.2*

K4. Knowledge of EMERGENCY GENERATORS (DIESEL/JET) design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Emergency generator trips (normal) ....................................... 3.5 3.7

K4.02 Emergency generator trips (emergency/LOCA) .............................. 4.0 4.2

K4.03 Speed droop control ..................................................... 2.5 2.7

K4.04 Field flashing .......................................................... 2.6 2.7

K4.05 Load shedding and sequencing ............................................ 3.2 3.5

K4.06 Governor control ....................................................... 2.6 2.7

K4.07 Local operation and control .............................................. 3.3 3.4

K4.08 Automatic startup ....................................................... 3.8 3.7

K5. Knowledge of the operational implications of the

following concepts as they apply to EMERGENCY

GENERATORS (DIESEL/JET) :

(CFR: 41.5 / 45.3)

K5.01 Definition of frequency and synchronous frequency .......................... 2.0* 2.1*

K5.02 Reactive power control .................................................. 2.0* 2.1*

| K5.03 Real power control ...................................................... 2.4* 2.4*

| K5.04 Governor control ....................................................... 2.4 2.5

K5.05 Paralleling A.C. power sources ............................................ 3.4 3.4

K5.06 Load sequencing ........................................................ 3.4 3.5

K5.07 Speed droop ........................................................... 2.3 2.4

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the EMERGENCY GENERATORS

(DIESEL/JET) :

(CFR: 41.7 / 45.7)

K6.01 Starting air ............................................................. 3.8 3.9

K6.02 Fuel oil pumps ......................................................... 3.6 3.6

K6.03 Lube oil pumps ......................................................... 3.5 3.7

K6.04 Turning gear (jet engine): Plant-Specific ................................... 2.5 2.5

K6.05 Ignition system (jet engine): Plant-Specific ................................. 2.5 3.0
3.6-11 NUREG-1123, Rev. 2 |

SYSTEM: 264000 Emergency Generators (Diesel/Jet)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6.06 Battery charger ......................................................... 2.9 3.1

K6.07 Cooling water system .................................................... 3.8 3.9

K6.08 A.C. power ............................................................. 3.6 3.7

K6.09 D.C. power ............................................................ 3.3 3.5

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the EMERGENCY

GENERATORS (DIESEL/JET) controls including:

(CFR: 41.5 / 45.5)

A1.01 Lube oil temperature .................................................... 3.0* 3.0*

A1.02 Fuel consumption rate ................................................... 2.2* 2.3

A1.03 Operating voltages, currents, and temperatures ............................... 2.8 2.9

A1.04 Crank case temperature and pressure ....................................... 2.6 2.7

A1.05 Cylinder temperature differential .......................................... 2.4* 2.4*

A1.06 Emergency generator room temperature .................................... 2.3 2.4

A1.07 Gas generator temperature: Plant-Specific .................................. 2.0* 2.5

A1.08 Gas generator speed: Plant-Specific ....................................... 2.0* 2.5

A1.09 Maintaining minimum load on emergency generator (to

prevent reverse power) ................................................... 3.0 3.1

A2. Ability to (a) predict the impacts of the following on

the EMERGENCY GENERATORS (DIESEL/JET) ; and (b) based

on those predictions, use procedures to correct,

control, or mitigate the consequences of those

abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Parallel operation of emergency generator .................................. 3.5 3.6

A2.02 Unloading prior to securing emergency generator ............................ 3.1 3.1

A2.03 Operating unloaded, lightly loaded, and highly loaded. ......................... 3.4 3.4

A2.04 Consequences of operating under/over excited ............................... 2.9 3.0

A2.05 Synchronization of the emergency generator with other

electrical supplies ...................................................... 3.6 3.6

A2.06 Opening normal and/or alternate power to emergency bus ..................... 3.4 3.4

A2.07 Loss of off-site power during full-load testing ............................... 3.5 3.7

A2.08 Initiation of emergency generator room fire protection

system ................................................................ 3.3 3.7

A2.09 Loss of A.C. power ...................................................... 3.7 4.1

A2.10 LOCA ................................................................. 3.9 4.2*
NUREG-1123, Rev. 2 3.6-12 |

SYSTEM: 264000 Emergency Generators (Diesel/Jet)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A3. Ability to monitor automatic operations of the

EMERGENCY GENERATORS (DIESEL/JET) including:

(CFR: 41.7 / 45.7)

A3.01 Automatic starting of compressor and emergency

generator .............................................................. 3.0 3.1

A3.02 Minimum time for load pick up ........................................... 3.1 3.1

A3.03 Indicating lights, meters, and recorders ..................................... 3.4 3.4

A3.04 Operation of the governor control system on frequency

and voltage control ...................................................... 3.1 3.1

A3.05 Load shedding and sequencing ............................................ 3.4 3.5

A3.06 Cooling water system operation ........................................... 3.1 3.2

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Adjustment of exciter voltage ............................................. 3.3 3.4

A4.02 Synchroscope .......................................................... 3.4 3.4

A4.03 Transfer of emergency control between manual and

automatic .............................................................. 3.2 3.4

A4.04 Manual start, loading, and stopping of emergency

generator: Plant-Specific ................................................ 3.7 3.7

A4.05 Transfer of emergency generator (with load) to grid .......................... 3.6 3.7

A4.06 Droop setting .......................................................... 2.4* 2.8*
3.6-13 NUREG-1123, Rev. 2 |

SYSTEM: 262002 Uninterruptable Power Supply (A.C./D.C.)

TASK: Operate a static inverter

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between UNINTERRUPTABLE POWER

SUPPLY (A.C./D.C.) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Feedwater level control: Plant-Specific .................................... 2.8 3.0

K1.02 RFPT control: Plant-Specific ............................................. 2.8 3.0

K1.03 Rod position information: Plant-Specific ................................... 2.7 2.9

K1.04 Reactor manual control: Plant-Specific .................................... 2.8 3.0

K1.05 Reactor/turbine pressure control system control unit:

Plant-Specific .......................................................... 2.7 2.9

K1.06 Unit computer: Plant-Specific ............................................ 2.6 2.7

K1.07 Rod worth minimizer: Plant-Specific ...................................... 2.8 2.9

K1.08 Containment isolation system: Plant-Specific ............................... 2.9 3.1

K1.09 Drywell ventilation control: Plant-Specific ................................. 2.5 2.7

K1.10 Fire protection system: Plant-Specific ..................................... 2.6 2.8

K1.11 Control room recorders: Plant-Specific .................................... 2.5 2.6

K1.12 Generator hydrogen and stator cooling water controls:

Plant-Specific .......................................................... 2.1* 2.3*

K1.13 Recirculation pump speed control: Plant-Specific ........................... 2.5 2.6

K1.14 Main steam line radiation monitors: Plant-Specific .......................... 2.8 3.0

K1.15 Stack gas monitors: Plant-Specific ........................................ 2.7 3.0

K1.16 MSIV's: Plant-Specific .................................................. 3.1 3.2

K1.17 Scram solenoid valves: Plant-Specific ..................................... 3.1 3.3

K1.18 Process radiation monitoring system: Plant-Specific ......................... 2.5 2.7

K1.19 Power range neutron monitoring system: Plant-Specific ...................... 2.9* 3.1*

K1.20 Plant communications equipment: Plant-Specific ............................ 2.4 2.7

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

None |

K3. Knowledge of the effect that a loss or malfunction of

the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) will have

on following:

(CFR: 41.7 / 45.4)

K3.01 Water level control: Plant-Specific ........................................ 3.1 3.3

K3.02 Recirculation pump speed: Plant-Specific .................................. 2.9 2.9

K3.03 RFPT speed: Plant-Specific .............................................. 3.0 3.1

K3.04 Fire protection system: Plant-Specific .................................... 2.5 2.7

K3.05 Rod worth minimizer: Plant-Specific ...................................... 2.9 3.0

K3.06 Rod position indication: Plant-Specific .................................... 2.8 2.9

K3.07 Movement of control rods: Plant-Specific .................................. 2.6 2.8

K3.08 Computer operation: Plant-Specific ....................................... 2.7 2.8
NUREG-1123, Rev. 2 3.6-14 |

SYSTEM: 262002 Uninterruptable Power Supply (A.C./D.C.)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3.09 Drywell ventilation control: Plant-Specific ................................. 2.4 2.7

K3.10 Containment isolation: Plant-Specific ..................................... 2.7 2.8

K3.11 MSIV's: Plant-Specific .................................................. 2.8 2.9

K3.12 Control rod drive mechanism: Plant-Specific ............................... 2.3* 2.5

K3.13 Rx pressure: Plant-Specific .............................................. 2.7 2.9

K3.14 Rx power: Plant-Specific ................................................ 2.8 3.1

K3.15 Main turbine operation: Plant-Specific ..................................... 2.6 2.7

K3.16 Control room recorders: Plant-Specific .................................... 2.4 2.6

K3.17 Process monitoring: Plant-Specific ....................................... 2.9 3.1

K4. Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.)

design feature(s) and/or interlocks which provide for

the following:

(CFR: 41.7)

K4.01 Transfer from preferred power to alternate power

supplies ............................................................... 3.1 3.4

K5. Knowledge of the operational implications of the

following concepts as they apply to UNINTERRUPTABLE

POWER SUPPLY (A.C./D.C.) :

(CFR: 41.5 / 45.3)

K5.01 General principles of static inverter operation ............................... 2.3* 2.3

K5.02 General principles of motor generator operation:

Plant-Specific .......................................................... 2.4 2.5

K5.03 General principles of inertia fly wheel operation:

Plant-Specific .......................................................... 2.3* 2.4*

K5.04 General principles of static switch operation ................................ 2.1* 2.2*

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the UNINTERRUPTABLE POWER

SUPPLY (A.C./D.C.) :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical power .................................................... 2.7 2.9

K6.02 D.C. electrical power .................................................... 2.8 3.1

K6.03 Static inverter .......................................................... 2.7 2.9
3.6-15 NUREG-1123, Rev. 2 |

SYSTEM: 262002 Uninterruptable Power Supply (A.C./D.C.)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A1. Ability to predict and/or monitor changes in

parameters associated with operating the

UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls

including:

(CFR: 41.5 / 45.5)

A1.01 Inverter electrical outputs ................................................ 2.4 2.6

A1.02 Motor generator outputs ................................................. 2.5 2.9

A2. Ability to (a) predict the impacts of the following on

the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) ; and (b)

based on those predictions, use procedures to correct,

control, or mitigate the consequences of those

abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Under voltage .......................................................... 2.6 2.8

A2.02 Over voltage ........................................................... 2.5 2.7

A2.03 Frequency changes in the system .......................................... 2.4* 2.6

A2.04 Abnormal battery operation: BWR-1 ...................................... 3.2 3.4

A3. Ability to monitor automatic operations of the

UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) including:

(CFR: 41.7 / 45.7)

A3.01 Transfer from preferred to alternate source ................................. 2.8 3.1

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Transfer from alternative source to preferred source .......................... 2.8 3.1
3.7-1 NUREG-1123, Rev. 2 |

3.7 Instrumentation page

215005 Average Power Range Monitor/Local Power Range Monitor 3.7-3

215003 Intermediate Range Monitor System 3.7-7

216000 Nuclear Boiler Instrumentation 3.7-10

272000 Radiation Monitoring System 3.7-15

212000 Reactor Protection System 3.7-19

215002 Rod Block Monitor System 3.7-24

201005 Rod Control and Information System 3.7-27

214000 Rod Position Information System 3.7-30

201004 Rod Sequence Control System (Plant Specific) 3.7-33

201006 Rod Worth Minimizer System (Plant Specific) 3.7-35

215004 Source Range Monitor System 3.7-38

215001 Traversing In-Core Probe 3.7-41
NUREG-1123, Rev. 2 3.7-2 |

This page left blank
3.7-3 NUREG-1123, Rev. 2 |

SYSTEM: 215005 Average Power Range Monitor/Local Power Range Monitor System

TASK: Perform lineups of the nuclear instrumentation system 

Monitor the nuclear instrumentation system 

Startup the nuclear instrumentation system 

Place a source range module in/out of service 

Place power range instruments in/out of service 

Operate the nuclear instrumentation system

Secure the nuclear instrumentation system

Place transversing incore probe in/out of service

Operate range switches on IRM on power increase and decrease (write in)

Conduct average power range meter (APRM) instrument functional test

Conduct intermediate range monitor - average power range monitor instrument range overlap check

Conduct IRM-inoperative functional test and IRM-high flux functional instrument check

Conduct APRM-high flux in start up or refuel functional test

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between AVERAGE POWER RANGE

MONITOR/LOCAL POWER RANGE MONITOR SYSTEM and the

following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 RPS ................................................................... 4.0 4.0

K1.02 IRM ................................................................... 3.7 3.7

K1.03 RBM: Plant-Specific ..................................................... 3.4 3.5

K1.04 LPRM channels ......................................................... 3.6 3.6

K1.05 Four rod display: Plant-Specific ........................................... 3.2 3.2

K1.06 SPDS/ERIS/CRIDS/GDS: Plant-Specific .................................... 2.5 2.8*

K1.07 Process computer, performance monitoring system ........................... 2.6 2.9

K1.08 Display control system: Plant-Specific ..................................... 3.0 3.0

K1.09 Reactor recirculation system: BWR-5,6 .................................... 3.6 3.6

K1.10 Reactor manual control system: Plant-Specific ............................... 3.3 3.3

K1.11 Rod control and information system: Plant-Specific .......................... 3.4 3.4

K1.12 Full core display ......................................................... 3.2 3.2

K1.13 Traversing incore probe system ............................................ 2.6 3.0

K1.14 Reactor vessel ........................................................... 2.8 2.9

K1.15 Redundant reactivity control system: Plant-Specific ........................... 3.7 4.0

K1.16 Flow converter/comparator network: Plant-Specific ........................... 3.3 3.4

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 LPRM channels ......................................................... 2.4 2.6

K2 02 APRM channels ......................................................... 2.6 2.8
NUREG-1123, Rev. 2 3.7-4 |

SYSTEM: 215005 Average Power Range Monitor/Local Power Range Monitor System

Tasks as noted previously

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3. Knowledge of the effect that a loss or malfunction of

the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE

MONITOR SYSTEM will have on following:

(CFR: 41.7 / 45.4)

K3.01 RPS ............................................................... 4.0 4.0

K3.02 Reactor recirculation system: BWR-5,6 ................................ 3.5 3.5

K3.03 Reactor manual control system: Plant-Specific ........................... 3.3 3.3

K3.04 Rod control and information system: Plant-Specific 3.4 ................. 3.4

K3.05 Reactor power indication .............................................. 3.8 3.8

K3.06 IRM: Plant-Specific ................................................. 3.5 3.6

K3.07 Rod block monitor: Plant-Specific ..................................... 3.2 3.3

K3.08 †core thermal calculations ............................................ 3.0 3.4

K4. Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER

RANGE MONITOR SYSTEM design feature(s) and/or

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Rod withdrawal blocks ............................................... 3.7 3.7

K4.02 Reactor SCRAM signals 4.1* 4.2

K4.03 Eliminates the necessity of running signal leads from

each LPRM channel to the operator's console full core

display 2.1?* 2.2?*

K4.04 Individual LPRM detector replacement 2.0* 2.4*

K4.05 Alarm seal-in 2.4 2.4

K4.06 Effects of detector aging on LPRM/APRM readings 2.6 2.8

K4.07 Flow biased trip setpoints 3.7 3.7

K4.08 Sampling of overall core power in each APRM

(accomplished through LPRM assignments and symmetrical

rod patterns) 2.7 3.1

K5. Knowledge of the operational implications of the

following concepts as they apply to AVERAGE POWER

RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 LPRM detector operation 2.8 2.9

K5.02 Effects of voids on LPRM indication 2.7 2.8

K5.03 Control rod symmetrical patterns 2.9 3.3

K5.04 LPRM detector location and core symmetry 2.9 3.2

K5.05 Core flow effects on APRM trip setpoints 3.6 3.6

K5.06 Assignment of LPRM's to specific APRM channels 2.5* 2.6*
3.7-5 NUREG-1123, Rev. 2 |

SYSTEM: 215005 Average Power Range Monitor/Local Power Range Monitor System

Tasks as noted previously

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the AVERAGE POWER RANGE

MONITOR/LOCAL POWER RANGE MONITOR SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 RPS ............................................................... 3.7 3.8

K6.02 †Traversing incore probe system ....................................... 2.4 2.8

K6.03 Detectors ........................................................... 3.1 3.3

K6.04 Trip units ........................................................... 3.1 3.2

K6.05 IRM: Plant-Specific ................................................. 2.9 3.1

K6.06 Recorder ........................................................... 2.3 2.4

K6.07 Flow converter/comparator network: Plant-Specific ....................... 3.2 3.3

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the AVERAGE POWER

RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM

controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor power indication ................................................. 4.0 4.0

A1.02 RPS status ............................................................. 3.9 4.0

A1.03 Control rod block status ................................................. 3.6 3.6

A1.04 SCRAM and rod block trip setpoints ....................................... 4.1 4.1

A1.05 Lights and alarms ....................................................... 3.3 3.2

A1.06 Recirculation flow control valve position: PlantSpecific ............................................................... 3.1 3.3

A1.07 APRM (gain adjustment factor) ........................................... 3.0 3.4

A2. Ability to (a) predict the impacts of the following on

the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE

MONITOR SYSTEM ; and (b) based on those predictions,

use procedures to correct, control, or mitigate the

consequences of those abnormal conditions or

operations:

(CFR: 41.5 / 45.6)

A2.01 Power supply degraded .................................................. 2.7 3.1

A2.02 Upscale or downscale trips ............................................... 3.6 3.7

A2.03 Inoperative trip (all causes) ............................................... 3.6 3.8

A2.04 SCRAM trip signals ..................................................... 3.8 3.9

A2.05 Loss of recirculation flow signal .......................................... 3.5 3.6

A2.06 Recirculation flow channels upscale ....................................... 3.4 3.5

A2.07 Recirculation flow channels flow mismatch ................................. 3.2 3.4

A2.08 Faulty or erratic operation of detectors/systems ............................. 3.2 3.4

A2.09 Failed recorder ......................................................... 2.4* 2.4
NUREG-1123, Rev. 2 3.7-6 |

SYSTEM: 215005 Average Power Range Monitor/Local Power Range Monitor System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A2.10 Changes in void concentration ............................................ 2.8 2.9

A3. Ability to monitor automatic operations of the AVERAGE

POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM

including:

(CFR: 41.7 / 45.7)

A3.01 Four rod display: Plant-Specific .......................................... 3.5 3.5

A3.02 Full core display ........................................................ 3.5 3.5

A3.03 Meters and recorders .................................................... 3.3 3.3

A3.04 Annunciator and alarm signals ............................................. 3.2 3.2

A3.05 Flow converter/comparator alarms ......................................... 3.3 3.3

A3.06 Maximum disagreement between flow comparator channels:

Plant-Specific .......................................................... 3.0 3.1

A3.07 RPS status ............................................................. 3.8 3.8

A3.08 Control rod block status ................................................. 3.7 3.6

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 IRM/APRM recorder .................................................... 3.2 3.1

A4.02 CRT display indicators: Plant-Specific ..................................... 2.8 2.8

A4.03 APRM back panel switches, meters and indicating lights ....................... 3.2 3.3

A4.04 LPRM back panel switches, meters and indicating lights ....................... 3.2 3.2

A4.05 Trip bypasses ........................................................... 3.4 3.4

A4.06 Verification of proper functioning/ operability ............................... 3.6 3.8
3.7-7 NUREG-1123, Rev. 2 |

SYSTEM: 215003 Intermediate Range Monitor (IRM) System

TASK: Perform lineups of the nuclear instrumentation system

Monitor the nuclear instrumentation system

Startup the nuclear instrumentation system

Place an intermediate range module in/out of service

Operate the nuclear instrumentation system

Secure the nuclear instrumentation system

Operate range switches on IRM on power increase and decrease (write in)

Conduct source range meter, intermediate range meter detector not in startup rod block functional test

Conduct intermediate range monitor - average power range monitor instrument range overlap check

Conduct IRM-inoperative functional test and IRM-high flux functional instrument check

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between INTERMEDIATE RANGE

MONITOR (IRM) SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 RPS .................................................................. 3.9 3.9

K1.02 Reactor manual control .................................................. 3.6 3.6

K1.03 Rod control and information system: Plant-Specific ......................... 3.1 3.1

K1.04 Process computer/ performance monitoring system

(SPDS/ERIS/CRIDS/GDS): Plant-Specific ................................. 2.5 2.8

K1.05 Display control system: Plant-Specific .................................... 3.3 3.3

K1.06 APRM SCRAM signals: Plant-Specific .................................... 3.9 4.0

K1.07 Reactor vessel ......................................................... 3.0 3.0

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 IRM channels/detectors ................................................. 2.5* 2.7

K3. Knowledge of the effect that a loss or malfunction of

the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM will have

on following:

(CFR: 41.7 / 45.4)

K3.01 RPS .................................................................. 3.9 4.0

K3.02 Reactor manual control .................................................. 3.6 3.6

K3.03 Rod control and information system: Plant-Specific ......................... 3.7 3.7

K3.04 Reactor power indication ................................................ 3.6 3.6

K3.05 APRM: Plant-Specific .................................................. 3.7 3.8
NUREG-1123, Rev. 2 3.7-8 |

SYSTEM: 215003 Intermediate Range Monitor (IRM) System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4. Knowledge of INTERMEDIATE RANGE MONITOR (IRM) SYSTEM

design feature(s) and/or interlocks which provide for

the following:

(CFR: 41.7)

K4.01 Rod withdrawal blocks ................................................... 3.7 3.7

K4.02 Reactor SCRAM signals ................................................. 4.0 4.0

K4.03 Gamma compensation ................................................... 2.4 2.4

K4.04 Varying system sensitivity levels using range switches ........................ 2.9 2.9

K4.05 Changing detector position ............................................... 2.9 3.0

K4.06 Alarm seal-in ........................................................... 2.6 2.6

K5. Knowledge of the operational implications of the

following concepts as they apply to INTERMEDIATE RANGE

MONITOR (IRM) SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Detector operation ...................................................... 2.6 2.7

K5.02 Gamma discrimination ................................................... 2.2* 2.3

K5.03 Changing detector position ............................................... 3.0 3.1

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the INTERMEDIATE RANGE

MONITOR (IRM) SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 Reactor protection system (power supply): PlantSpecific ............................................................... 3.8 3.8

K6.02 24/48 volt D.C. power: Plant-Specific ..................................... 3.6 3.8

K6.03 Detector drive motor .................................................... 2.8 2.9

K6.04 Detectors .............................................................. 3.0 3.0

K6.05 Trip units .............................................................. 3.1 3.2

K6.06 APRM ................................................................ 3.2 3.4

K6.07 Recorder .............................................................. 2.3 2.3

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the INTERMEDIATE

RANGE MONITOR (IRM) SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Detector position ....................................................... 3.4 3.3

A1.02 Reactor power indication response to rod position

 changes .................................................................. 3.7 3.7

A1.03 RPS status ............................................................. 3.6 3.7

A1.04 Control rod block status ................................................. 3.4 3.4
3.7-9 NUREG-1123, Rev. 2 |

SYSTEM: 215003 Intermediate Range Monitor (IRM) System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A1.05 SCRAM and rod block trip setpoints ....................................... 3.9 3.9

A1.06 Lights and alarms ....................................................... 3.3 3.2

A2. Ability to (a) predict the impacts of the following on

the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM ; and (b)

based on those predictions, use procedures to correct,

control, or mitigate the consequences of those

abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Power supply degraded ................................................... 2.8 3.2

A2.02 IRM inop condition ...................................................... 3.5 3.7

A2.03 Stuck detector ........................................................... 2.9 3.1

A2.04 Up scale or down scale trips ............................................... 3.7 3.8

A2.05 Faulty or erratic operation of detectors/system ............................... 3.3 3.5

A2.06 Faulty range switch ....................................................... 3.0 3.2

A2.07 Failed recorder .......................................................... 2.5 2.7

A3. Ability to monitor automatic operations of the

INTERMEDIATE RANGE MONITOR (IRM) SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Meters and recorders ..................................................... 3.3 3.3

A3.02 Annunciator and alarm signals .............................................. 3.3 3.3

A3.03 RPS status .............................................................. 3.7 3.6

A3.04 Control rod block status .................................................. 3.5 3.5

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 IRM recorder indication .................................................. 3.3 3.3

A4.02 CRT display indications: Plant-Specific ..................................... 2.9 2.8

A4.03 IRM range switches ...................................................... 3.6 3.4

A4.04 IRM back panel switches, meters, and indicating lights ......................... 3.1 3.3

A4.05 Trip bypasses ............................................................ 3.4 3.4

A4.06 Detector drives .......................................................... 3.0 2.9

A4.07 Verification of proper functioning/ operability ................................ 3.6 3.6
NUREG-1123, Rev. 2 3.7-10 |

SYSTEM: 216000 Nuclear Boiler Instrumentation

TASK: Perform lineups of the non-nuclear instrumentation system

 Monitor the non-nuclear instrumentation system

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between NUCLEAR BOILER

INSTRUMENTATION and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor protection system ............................................... 3.9 4.1

K1.02 PCIS/NSSSS ........................................................... 3.8 4.0

Kl.03 Reactor core isolation cooling system: Plant-Specific

...................................................................... 3.4 3.6

K1.04 High pressure core spray system: Plant-Specific ............................ 3.9 4.0

K1.05 Residual heat removal: Plant-Specific ..................................... 3.7 3.9

K1.06 Low pressure core spray ................................................. 3.9 3.9

K1.07 Automatic depressurization system ........................................ 3.9 4.1

K1.08 Relief/safety valves ..................................................... 3.7 3.9

K1.09 Redundant reactivity control/ alternate rod insertion;

Plant-Specific ......................................................... 3.7 4.0

K1.10 Recirculation flow control system ......................................... 3.2 3.4

K1.11 MSIV leakage control system: Plant-Specific ............................... 2.7 2.8

K1.12 Reactor water level control system ........................................ 3.6 3.7

K1.13 Feedwater system ....................................................... 3.4 3.5

K1.14 High pressure coolant injection: Plant-Specific ............................. 3.8 4.1*

K1.15 Isolation condenser: Plant-Specific ....................................... 3.9* 4.1*

K1.16 Main turbine ........................................................... 3.0 3.1

K1.17 Emergency generators ................................................... 3.5 3.7

K1.18 Analog trip system: Plant-Specific ........................................ 3.0* 3.1

K1.19 Anticipated transient without scram system: PlantSpecific .............................................................. 3.8 3.9

K1.20 Process computer: Plant-Specific ......................................... 2.6 2.8

K1.21 SPDS/ERIS/CRIDS/GDS: Plant-Specific ................................... 2.6* 2.9*

K1.22 Reactor vessel ......................................................... 3.6 3.8

K1.23 Recirculation system ................................................... 3.3 3.4

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Analog trip system: Plant-Specific ........................................ 2.8 2.8

K3. Knowledge of the effect that a loss or malfunction of

the NUCLEAR BOILER Instrumentation will have on

following:

(CFR: 41.7 / 45.4)

K3.01 Reactor protection system ............................................... 4.0 4.3*

K3.02 PCIS/NSSSS ........................................................... 4.0 4.3*
3.7-11 NUREG-1123, Rev. 2 |

SYSTEM: 216000 Nuclear Boiler Instrumentation

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3.03 Reactor core isolation cooling system: Plant-Specific

...................................................................... 3.5 3.8

K3.04 High pressure core spray system: Plant-Specific ............................ 3.8 4.0

K3.05 Residual heat removal: Plant-Specific ..................................... 3.8 3.9

K3.06 Low pressure core spray ................................................. 3.8 3.9

K3.07 Automatic depressurization system ........................................ 3.9 4.1

K3.08 Relief/safety valves ..................................................... 3.6 3.7

K3.09 Redundant reactivity control/ alternate rod insertion:

Plant-Specific ......................................................... 3.7 4.0

K3.10 Recirculation flow control system ........................................ 3.2 3.3

K3.11 MSIV leakage control system: Plant-Specific ............................... 2.8 2.8

K3.12 Reactor water level control system ........................................ 3.7 3.8

K3.13 Feedwater system ...................................................... 3.4 3.5

K3.14 High pressure coolant injection: Plant-Specific ............................. 3.8 4.2*

K3.15 Isolation condenser: Plant-Specific ....................................... 3.8 4.2*

K3.16 Main turbine ........................................................... 3.0 3.1

K3.17 Emergency generators .................................................. 3.5 3.7

K3.18 Analog trip system: Plant-Specific ........................................ 2.9* 3.0

K3.19 Anticipated transient without scram system: PlantSpecific .............................................................. 3.7 4.0*

K3.20 Process computer: Plant-Specific ........................................ 2.5 2.6

K3.21 SPDS/ERIS/CRIDS/GDS: Plant-Specific .................................. 2.6* 2.8*

K3.22 Reactor vessel ......................................................... 3.2 3.3 |

K3.23 Vessel temperature monitoring ........................................... 3.1 3.3 |

K3.24 Vessel level monitoring ................................................. 3.9 4.1

K3.25 Vessel pressure monitoring .............................................. 3.9 4.1 |

K3.26 Core flow monitoring ................................................... 3.6 3.7 |

K3.27 Core differential pressure monitoring ..................................... 2.9 3.1

K3.28 Loose parts detection in the primary system: PlantSpecific .............................................................. 2.0* 2.1*

K3.29 Jet pump flow monitoring: Plant-Specific .................................. 3.1 3.2

K3.30 Recirculation system ................................................... 3.2 3.3

K4. Knowledge of NUCLEAR BOILER INSTRUMENTATION design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Reading of nuclear boiler parameters outside the

control room .......................................................... 3.6 3.6

K4.02 Physical separation of sensors ............................................ 3.0 3.2

K4.03 Redundancy of sensors .................................................. 3.4 3.6

K4.04 Inputs to the reactor protection system ..................................... 3.7 3.8 |

K4.05 Initiation of the emergency core cooling systems ............................ 3.9 4.1 |

K4.06 Initiation of the PCIS/NSSSS ............................................. 3.8 4.0

K4.07 Recirculation pump protection: Plant-Specific .............................. 2.9 3.0
NUREG-1123, Rev. 2 3.7-12 |

SYSTEM: 216000 Nuclear Boiler Instrumentation

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.08 Protection for the main turbine from high moisture

carryover ............................................................. 2.9 3.0

K4.09 Protection against filling the main steam lines from

the feed system ........................................................ 3.3 3.3

K4.10 Automatic recirculation pump speed control: PlantSpecific .............................................................. 2.9 3.1

K4.11 Inputs to the redundant reactivity control

system/alternate rod insertion: Plant-Specific .............................. 4.0 4.0

K4.12 Reactor vessel overpressure protection .................................... 3.7 3.9

K4.13 Overpressure protection for various low-pressure

 systems .................................................................. 3.4 3.4

K4.14 Temperature compensation for reactor water level

indication: Plant-Specific ............................................... 3.3 3.4

K5. Knowledge of the operational implications of the

following concepts as they apply to NUCLEAR BOILER

INSTRUMENTATION :

(CFR: 41.5 / 45.3)

K5.01 Vessel level measurement ............................................... 3.1 3.2

K5.02 Vessel pressure measurement ............................................ 3.1 3.2

K5.03 Vessel temperature measurement ......................................... 3.0 3.2

K5.04 Vessel differential pressure measurement .................................. 2.8 2.9

K5.05 Vessel vibration measurement (loose parts monitor) ......................... 2.3 2.3

K5.06 Rapid vessel depressurization effects on vessel level

indications ............................................................ 3.4 3.6

K5.07 Elevated containment temperature effects on level

indication ............................................................. 3.6 3.8

K5.08 Steam flow effect on reactor water level ................................... 3.1 3.2

K5.09 Recirculation flow effects on level indications:

Design-Specific ........................................................ 2.9 2.9

K5.10 Indicated level versus actual vessel level during

vessel heatups or cooldowns ............................................. 3.1 3.3

K5.11 Indicated vessel temperature response during rapid

heatups or cooldowns ................................................... 3.2 3.3

K5.12 Effects on level indication due to rapid changes in

void fraction ........................................................... 3.2 3.3

K5.13 Reference leg flashing: Design-Specific ................................... 3.5 3.6

K5.14 Density ............................................................... 2.6 2.6

K5.15 Static pressure ......................................................... 2.2* 2.2*

K5.16 Dynamic pressure ...................................................... 2.1* 2.1*
3.7-13 NUREG-1123, Rev. 2 |

SYSTEM: 216000 Nuclear Boiler Instrumentation

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the NUCLEAR BOILER

INSTRUMENTATION :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical distribution ............................................... 3.1 3.3

K6.02 D.C. electrical distribution ............................................... 2.8 3.0

K6.03 Temperature compensation: Plant-Specific ................................. 2.8 2.8

ABILITY

Al. Ability to predict and/or monitor changes in

parameters associated with operating the NUCLEAR

BOILER INSTRUMENTATION controls including:

(CFR: 41.5 / 45.5)

A1.01 Recorders and meters ................................................... 3.4 3.3

A1.02 Removing or returning a sensor (transmitter) to

service ............................................................... 2.9* 3.1*

A1.03 Surveillance testing ..................................................... 2.9* 3.2*

A1.04 System venting ......................................................... 2.6* 2.8*

A2. Ability to (a) predict the impacts of the following on

the NUCLEAR BOILER INSTRUMENTATION ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Detector equalizing valve leaks ........................................... 2.9 3.2

A2.02 Instrument line plugging ................................................. 2.9 3.0

A2.03 Instrument line leakage .................................................. 3.0 3.1

A2.04 Detector diaphragm failure or leakage ..................................... 2.9 3.0

A2.05 Surveillance testing ..................................................... 2.8 3.1

A2.06 Loss of power supply ................................................... 2.9 3.1

A2.07 Reference leg flashing .................................................. 3.4 3.5

A2.08 Elevated containment temperature ......................................... 3.2 3.4

A2.09 Jet pump flow: Design-Specific .......................................... 3.1 3.2

A2.10 Rapid vessel depressurizations ............................................ 3.3 3.5

A2.11 Heatup or cooldown of the reactor vessel .................................. 3.2 3.3

A2.12 Instrument isolation valve closures ........................................ 2.8 2.9

A2.13 Instrument isolation valve openings ........................................ 2.8 3.0

A2.14 Recirculation flow: Design-Specific ...................................... 2.9 2.9
NUREG-1123, Rev. 2 3.7-14 |

SYSTEM: 216000 Nuclear Boiler Instrumentation

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A3. Ability to monitor automatic operations of the NUCLEAR

BOILER Instrumentation including:

(CFR: 41.7 / 45.7)

A3.01 Relationship between meter/recorder readings and

actual parameter values: Plant-Specific .................................... 3.4 3.4

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Recorders ............................................................. 3.3 3.1

A4.02 Channel select controls ................................................. 3.3 3.1

A4.03 Process computer: Design-Specific ....................................... 3.0 3.1
3.7-15 NUREG-1123, Rev. 2 |

SYSTEM: 272000 Radiation Monitoring System

TASK: Perform lineups of the area radiation monitoring system

Operate area radiation monitors

Monitor area radiation

Perform lineups of process radiation monitoring system

Operate process radiation monitors

Monitor process radiation monitor operation

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between RADIATION MONITORING

SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Main steam system ..................................................... 3.6 3.8

K1.02 Offgas system (augmented offgas): Plant-Specific .......................... 3.2 3.5

K1.03 Stack gas: Plant-Specific ................................................ 3.3 3.6

K1.04 Applicable component cooling water system ................................ 2.9 2.9

K1.05 Radwaste system ....................................................... 2.8 3.1 |

K1.06 Reactor building ventilation system: Plant-Specific .......................... 3.2 3.3

K1.07 Isolation condenser: Plant-Specific ....................................... 3.0 3.2

K1.08 Reactor protection system ............................................... 3.6 3.9

K1.09 Primary containment isolation system ..................................... 3.6 3.8

K1.10 Reactor building refuel floor: Plant-Specific ............................... 3.4 3.6

K1.11 Reactor building overhead crane; Plant-Specific ............................. 2.1* 2.4*

K1.12 Reactor building ........................................................ 3.1 3.2

K1.13 Turbine building ........................................................ 2.9 3.0

K1.14 Radwaste building: Plant-Specific ........................................ 2.7 2.8

K1.15 Filter building: Plant-Specific ............................................ 2.8 3.0

K1.16 Process computer ....................................................... 2.2* 2.3*

K1.17 SPDS/ERIS/CRIDS/GDS: Plant-Specific .................................. 2.4 2.7

K1.18 Primary containment/containment building: PlantSpecific .............................................................. 3.1 3.1

K1.19 Drywell ............................................................... 3.1 3.2

K1.20 †Auxiliary building: Plant-Specific ....................................... 2.8 3.0

K1.21 Circulating water: Plant-Specific ......................................... 2.3 2.4

K1.22 Fuel building: mark-III .................................................. 3.0 3.4

K1.23 Continuous air monitoring: Plant-Specific ................................. 3.0 3.3

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Main steamline radiation monitors ......................................... 2.5 2.8

K2.02 Offgas radiation monitoring system ........................................ 2.5 2.8

K2.03 Stack gas radiation monitoring system ..................................... 2.5 2.8

K2.04 Process liquid radiation monitoring system ................................. 2.3 2.5
NUREG-1123, Rev. 2 3.7-16 |

SYSTEM: 272000 Radiation Monitoring System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K2.05 Reactor building ventilation monitors: Plant-Specific

...................................................................... 2.6 2.9

K2.06 Area radiation monitors ................................................. 2.1* 2.2*

K2.07 Control room ventilation monitors: Plant-Specific .......................... 2.2* 2.4*

K3 Knowledge of the effect that a loss or malfunction of

the RADIATION MONITORING System will have on

following:

(CFR: 41.5 / 45.3)

K3.01 †Station liquid effluent release monitoring ................................. 3.2 3.8

K3.02 †Station gaseous effluent release monitoring ............................... 3.1 3.8

K3.03 Station area radiation monitoring .......................................... 3.2 3.4

K3.04 Main steam system ..................................................... 3.7 3.8

K3.05 Offgas system ......................................................... 3.5 3.7

K3.06 Reactor building ventilation: Plant-Specific ................................ 3.4 3.6

K3.07 Reactor building overhead crane operation: PlantSpecific .............................................................. 2.4* 3.0

K3.08 †Auxiliary building ventilation: Plant-Specific .............................. 2.9 3.3

K3.09 Radwaste building ventilation: Plant-Specific ............................... 2.8 3.1

K3.10 Control room ventilation: Plant-Specific .................................. 2.9 3.3

K4. Knowledge of RADIATION MONITORING System design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Redundancy ........................................................... 2.7 2.8

K4.02 Automatic actions to contain the radioactive release

in the event that the predetermined release rates are

exceeded .............................................................. 3.7 4.1

K4.03 Fail safe tripping of process radiation monitoring

logic during conditions of instrument failure ................................ 3.6 3.9

K5. Knowledge of the operational implications of the

following concepts as they apply to RADIATION

MONITORING SYSTEM :

(CFR: 41.7 / 45.4)

K5.01 Hydrogen injection operation's effect on process

radiation indications: Plant-Specific ...................................... 3.2 3.5
3.7-17 NUREG-1123, Rev. 2 |

SYSTEM: 272000 Radiation Monitoring System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6 Knowledge of the effect that a loss or malfunction of

the following will have on the RADIATION MONITORING

SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 Reactor protection system ............................................... 3.0 3.2

K6.02 D.C. power ............................................................ 2.5 2.7

K6.03 A.C. power ............................................................ 2.8 3.0

K6.04 Process computer ...................................................... 2.0* 2.2*

K6.05 SPDS/ERIS/CRID/GDS: Plant-Specific ................................... 2.1* 2.4*

K6.06 Continuous air monitoring: Plant-Specific ................................. 2.4 2.6

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the RADIATION

MONITORING SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Lights, alarms, and indications associated with normal

operations ............................................................. 3.2 3.2

A1.02 Lights, alarms, and indications associated with

surveillance testing ..................................................... 2.9 2.9

A2. Ability to (d) predict the impacts of the following on

the RADIATION MONITORING SYSTEM ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Fuel element failure .................................................... 3.7 4.1

A2.02 Reactor protection system power failure ................................... 3.3 3.6

A2.03 A.C. electrical failure ................................................... 2.9 3.1

A2.04 D.C. electrical failure ................................................... 2.7 2.8

A2.05 Loss of dilution steam .................................................. 2.5 2.6

A2.06 Downscale trips ........................................................ 2.8 2.9

A2.07 Hydrogen injection operation: Plant-Specific ............................... 2.6 2.8

A2.08 Offgas system failure ................................................... 2.9 3.1

A2.09 Low fuel pool level ..................................................... 3.1 3.3

A2.10 Loss of coolant accident ................................................. 3.9 4.1

A2.11 Leakage and/or breaks from contaminated systems to

atmosphere or to other process systems .................................... 3.4 3.7

A2.12 †Refuel floor handling accidents/operations ................................ 3.3 4.0

A2.13 Low reactor water level during refueling operations .......................... 3.3 3.8

A2.14 Loss of, or inadequate, shielding .......................................... 3.2 3.5

A2.15 Maintenance operations ................................................. 2.5 2.7
NUREG-1123, Rev. 2 3.7-18 |

SYSTEM: 272000 Radiation Monitoring System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A2.16 Instrument malfunctions ................................................. 2.7 2.9

A3. Ability to monitor automatic operations of the

RADIATION MONITORING SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Main steam isolation indications .......................................... 3.8 3.9

A3.02 Offgas system isolation indications ....................................... 3.6 3.7

A3.03 Liquid radwaste isolation indications ...................................... 3.1 3.5

A3.04 Radwaste handing interlocks ............................................. 2.3 2.8

A3.05 Refuel floor overhead crane operation interrupt:

Plant-Specific ......................................................... 3.0 3.1

| A3.06 Ventilation system isolation indications .................................... 3.4 3.4

| A3.07 Recorder indications .................................................... 2.8 2.9

A3.08 Meter indications ...................................................... 2.9 2.9

A3.09 Containment isolation indications ......................................... 3.6 3.5

A3.10 Lights and alarms ....................................................... 3.3 3.2

A3.11 Circulating water system blowdown isolations: PlantSpecific .............................................................. 2.6 2.7

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Recorder indications .................................................... 2.9 2.9

A4.02 Meter indications ...................................................... 3.0 3.0

| A4.03 Power supply status indicators ............................................ 2.6 2.6

| A4.04 SPDS/ERIS/CRID/GDS ................................................. 2.5* 2.7*

A4.05 †Convert process radiation monitor readings to offsite

 release rates: Plant-Specific ............................................ 2.3* 3.7*

A4.06 †Manually trip process radiation monitor logic .............................. 2.9 3.2
3.7-19 NUREG-1123, Rev. 2 |

SYSTEM: 212000 Reactor Protection System

TASK: Energize the reactor protection system 

Place a reactor protection channel in the tripped condition 

Bypass a trip condition on a reactor protection channel (bypass an average power range monitor trip) 

Deenergize the reactor protection system 

Monitor the reactor protection system 

Operate the reactor protection system MG sets 

Operate the reactor mode switch 

Operate the reactor trip breakers 

Shift the reactor protection system bus to the alternate power supply

Conduct manual SCRAM functional test 

Conduct mode switch in shutdown functional test 

Conduct RPS channel test switch functional test

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between REACTOR PROTECTION SYSTEM

and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Nuclear instrumentation .................................................. 3.7 3.9

K1.02 Nuclear boiler instrumentation ............................................. 3.7 3.9

K1.03 Recirculation system ..................................................... 3.4 3.6

K1.04 A.C. electrical distribution ................................................ 3.4 3.6

K1.05 Process radiation monitoring system ........................................ 3.3 3.6

K1.06 Control rod drive hydraulic system ......................................... 3.5 3.6

K1.07 Relief/safety valves (low-low-set logic): Plant-

 Specific ................................................................... 3.3 3.5

K1.08 Control rod and drive mechanism ........................................... 3.0 3.1

K1.09 Process computer ........................................................ 2.3 2.4

K1.10 Main turbine ............................................................ 3.2 3.4

K1.11 Condenser vacuum ....................................................... 3.3 3.5

K1.12 Reactor/turbine pressure control system: PlantSpecific ................................................................ 3.4 3.6

K1.13 Containment pressure .................................................... 3.5 3.6

K1.14 Main steam system ....................................................... 3.6 3.7

K1.15 SCRAM air header pressure ............................................... 3.8 3.9

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 RPS motor-generator sets ................................................. 3.2 3.3

K2.02 Analog trip system logic cabinets ........................................... 2.7 2.9
NUREG-1123, Rev. 2 3.7-20 |

SYSTEM: 212000 Reactor Protection System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3. Knowledge of the effect that a loss or malfunction of

the REACTOR PROTECTION SYSTEM will have on following:

(CFR: 41.7 / 45.4)

K3.01 Process radiation monitoring 3.0 3.2

K3.02 Primary containment isolation system/nuclear steam

supply shut-off: Plant-Specific 3.7 3.9

K3.03 Local power range monitoring system: Plant-Specific 3.3 3.4

K3.04 Average power range monitoring system: Plant-Specific

3.5 3.6

K3.05 RPS logic channels 3.7 3.8

K3.06 Scram air header solenoid operated valves 4.0 4.1

K3.07 Reactor power (thermal heat flux) 3.8 3.9

K3.08 Reactor coolant primary system integrity 3.6 3.8

K3.09 The magnitude of heat energy that must be absorbed by

the containment during accident/transient conditions 3.2 

3.6

K3.10 The ability of the core cooling systems to provide

adequate core cooling during loss of coolant accidents 3.5 3.9

K3.11 Recirculation system 3.0 3.3

K3.12 Secondary containment integrity 3.2 3.3

K4. Knowledge of REACTOR PROTECTION SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 System redundancy and reliability ......................................... 3.4 3.6

K4.02 The prevention of a reactor SCRAM following a single

component failure ...................................................... 3.5 3.7

K4.03 The prevention of supplying power to a given RPS bus

from multiple sources simultaneously ..................................... 3.0* 3.1*

K4.04 The prevention of supplying both RPS buses

simultaneously from the alternate power source:

Plant-Specific ......................................................... 3.1 3.1

K4.05 Functional testing of the system while maintaining

power operation ........................................................ 3.4 3.6

K4.06 Select rod insertion: Plant-Specific ....................................... 3.0 3.0

K4.07 Manual system activation (trip) ........................................... 4.1* 4.1

K4.08 Complete control rod insertion following SCRAM signal

generation ............................................................. 4.2* 4.2*

K4.09 Control rod insertion following RPS system electrical

failure ................................................................ 3.8 3.9

K4.10 Individual rod SCRAM testing ............................................ 3.3 3.6

K4.11 Operation with shorting links removed: Plant-Specific

...................................................................... 3.3 3.5

K4.12 Bypassing of selected SCRAM signals (manually and

automatically): Plant-Specific ........................................... 3.9 4.1
3.7-21 NUREG-1123, Rev. 2 |

SYSTEM: 212000 Reactor Protection System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K5. Knowledge of the operational implications of the

following concepts as they apply to REACTOR PROTECTION

SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Fuel thermal time constant ............................................... 2.7 2.9

K5.02 Specific logic arrangements .............................................. 3.3 3.4

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the REACTOR PROTECTION

SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical distribution ............................................... 3.6 3.8

K6.02 Nuclear instrumentation ................................................. 3.7 3.9

K6.03 Nuclear boiler instrumentation ........................................... 3.5 3.7

K6.04 D.C. electrical distribution ............................................... 2.8 3.1

K6.05 RPS sensor inputs ...................................................... 3.5 3.8

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the REACTOR

PROTECTION SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 RPS motor-generator output voltage ....................................... 2.8* 2.9

A1.02 RPS motor-generator output amps ........................................ 2.8* 2.9

A1.03 RPS motor-generator output frequency: Plant-Specific ....................... 2.4* 2.5

A1.04 RPS bus voltage: Plant-Specific .......................................... 2.8* 3.0

A1.05 RPS bus frequency: Plant-Specific ........................................ 2.6* 2.7

A1.06 Reactor power ......................................................... 4.2* 4.2*

A1.07 Rod position information ................................................ 3.4 3.4

A1.08 Valve position ......................................................... 3.4 3.4

A1.09 Individual relay status: Plant-Specific ..................................... 2.7 3.0

A1.10 Process computer ...................................................... 2.2* 2.4*

A1.11 System status lights and alarms ........................................... 3.4 3.3

A2. Ability to (a) predict the impacts of the following on

the REACTOR PROTECTION SYSTEM ; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 RPS motor-generator set failure .......................................... 3.7 3.9

A2.02 RPS bus power supply failure ............................................. 3.7 3.9
NUREG-1123, Rev. 2 3.7-22 |

SYSTEM: 212000 Reactor Protection System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A2.03 Surveillance testing ..................................................... 3.3 3.5

A2.04 Nuclear instrument system failure ......................................... 3.5 3.7

A2.05 Nuclear boiler instrument system failure ................................... 3.4 3.7

A2.06 High reactor power ..................................................... 4.1* 4.2*

A2.07 High reactor pressure ................................................... 4.1* 4.2*

A2.08 Low reactor level ....................................................... 4.1* 4.2*

A2.09 High containment/drywell pressure ........................................ 4.1* 4.3*

A2.10 Reactor/turbine pressure control system low pressure:

Plant-Specific ......................................................... 3.6 3.8

A2.11 Main steamline isolation valve closure ..................................... 4.0 4.1

A2.12 Main turbine stop control valve closure .................................... 4.0 4.1

A2.13 Low condenser vacuum: Plant-Specific .................................... 3.8 3.9

A2.14 High SCRAM instrument volume water level ................................ 3.9 4.0

A2.15 Load rejection ......................................................... 3.7 3.8

A2.16 Changing mode switch position ........................................... 4.0 4.1

A2.17 Main steamline high radiation ............................................ 4.0 4.2*

A2.18 †SCRAM air header low pressure ......................................... 3.8 3.9

A2.19 Partial system activation (half-SCRAM) .................................... 3.8 3.9

A2.20 Full system activation (full-SCRAM) ...................................... 4.1* 4.2*

A2.21 †Failure of individual relays to reposition: PlantSpecific .............................................................. 3.6 3.9

A3. Ability to monitor automatic operations of the REACTOR

PROTECTION SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Reactor Power ......................................................... 4.4* 4.4*

A3.02 Individual system relay status: Plant-Specific ............................... 3.2 3.5

A3.03 Rod position ........................................................... 4.2* 4.2*

A3.04 System status lights and alarms ........................................... 3.9* 3.8

A3.05 SCRAM instrument volume level ......................................... 3.9 3.9

A3.06 Main turbine trip: Plant-Specific ......................................... 4.2* 4.2*

A3.07 SCRAM air header pressure .............................................. 3.6 3.6

A3.08 Recirculation pump trip ................................................. 3.7 3.7

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

| A4.01 Provide manual SCRAM signal(s) ......................................... 4.6* 4.6*

A4.02 Perform system functional test(s) ......................................... 3.6 3.7

| A4.03 Provide manual select rod insertion: Plant-Specific . ......................... 3.9 3.9

| A4.04 Bypass SCRAM instrument volume high level SCRAM signal .................. 3.9 3.9

A4.05 Reactor power ......................................................... 4.3* 4.3*

A4.06 Control rod position .................................................... 4.2* 4.1*

A4.07 System status lights and alarms ........................................... 4.0* 3.9*

A4.08 Individual system relay status: Plant-Specific ............................... 3.4 3.4
3.7-23 NUREG-1123, Rev. 2 |

SYSTEM: 212000 Reactor Protection System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A4.09 SCRAM instrument volume level ......................................... 3.9 3.8

A4.10 Main turbine trip: Plant-Specific ......................................... 4.1 4.0

A4.11 Scram air header pressure ................................................ 3.7 3.7

A4.12 Close/open SCRAM instrument volume vent and/or drain

valves ................................................................ 3.9 3.9

A4.13 †Perform individual control rod SCRAM testing ............................ 3.4 3.6

A4.14 Reset system following system activation .................................. 3.8 3.8

A4.15 Recirculation pump trip/EOC RPT ........................................ 3.9 3.8 |

A4.16 Manually activate anticipated transient without SCRAM |

circuitry/RRCS: Plant-Specific .......................................... 4.4* 4.4*

A4.17 Perform alternate reactivity/ shutdown operations ............................ 4.1 4.1
NUREG-1123, Rev. 2 3.7-24 |

SYSTEM: 215002 Rod Block Monitor System

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between ROD BLOCK MONITOR SYSTEM

and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 APRM: BWR-3,4,5 ..................................................... 2.9 3.0

K1.02 LPRM: BWR-3,4,5 ..................................................... 3.2 3.1

| K1.03 Reactor manual control: BWR-3,4,5 ....................................... 3.2 3.2

| K1.04 Recirculation system: BWR-3,4,5 ........................................ 3.1 3.1

K1.05 Four rod display: BWR-3,4,5 ............................................. 3.0 3.0

K1.06 Control rod selection: BWR-3,4,5 ........................................ 3.0 3.1

K1.07 IRM: BWR-3,4,5 ....................................................... 2.0* 2.0*

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 RBM channels: BWR-3,4,5 .............................................. 2.5* 2.8*

K2.02 Recorders: BWR-3,4,5 .................................................. 2.1* 2.1*

K2.03 APRM channels: BWR-3,4,5 ............................................. 2.8 2.9

K3. Knowledge of the effect that a loss or malfunction of

the ROD BLOCK MONITOR SYSTEM will have on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor manual control system: BWR-3,4,5 ................................ 3.3 3.5

K3.02 †Limiting control rod pattern: Plant-Specific ...................................... 3.1 3.6

K4. Knowledge of ROD BLOCK MONITOR SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Prevent control rod withdrawal: BWR-3,4,5 ................................ 3.4 3.5

K4.02 Allows stepping up of rod block setpoint: BWR-3,4,5 ........................ 2.9 3.0

K4.03 Initiation point (30%): BWR-3,4,5 ........................................ 2.9 3.0

K5. Knowledge of the operational implications of the

following concepts as they apply to ROD BLOCK MONITOR

SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Trip reference selection: Plant-Specific .................................... 2.6 2.8

K5.02 Null sequence control: BWR-3,4,5 ........................................ 2.4 2.5
3.7-25 NUREG-1123, Rev. 2 |

SYSTEM: 215002 Rod Block Monitor System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the ROD BLOCK MONITOR

SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 RPS: BWR-3,4,5 ....................................................... 3.0 3.2

K6.02 Instrument power: Plant-Specific .......................................... 2.4 2.5

K6.03 Essential power: Plant-Specific ........................................... 2.5 2.5

K6.04 APRM reference channel: BWR-3,4,5 ..................................... 2.8 3.0

K6.05 LPRM detectors: BWR-3,4,5 ............................................. 2.8 3.1

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the ROD BLOCK

MONITOR SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Trip reference: BWR-3,4,5 ............................................... 2.7 2.8

A2. Ability to (a) predict the impacts of the following on

the ROD BLOCK MONITOR SYSTEM ; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 Withdrawal of control rod in high power region of

core: BWR-3,4,5 ....................................................... 3.3 3.5

A2.02 Loss or reduction in recirculation system flow (flow

comparator): BWR-3,4,5 ................................................. 3.3 3.3 |

A2.03 Loss of associated reference APRM channel: BWR-3,4,5 ...................... 3.1 3.3

A2.04 Power supply losses: BWR-3,4,5 .......................................... 2.7 2.8

A2.05 RBM high or inoperable: BWR-3,4,5 ...................................... 3.2 3.3

A3. Ability to monitor automatic operations of the ROD

BLOCK MONITOR SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Four rod display: BWR-3,4,5 ............................................. 3.1 3.1

A3.02 Meters and recorders: BWR-3,4,5 ......................................... 3.1 3.0

A3.03 Alarm and indicating lights: BWR-3,4,5 ..................................... 3.1 3.1

A3.04 Verification or proper functioning/ operability:

BWR-3,4,5 ............................................................. 3.6 3.5

A3.05 Back panel meters and indicating lights: BWR-3,4,5 .......................... 3.2 3.2

A3.06 Transfer to alternate APRM when referenced APRM

bypassed: BWR-3,4,5 ................................................... 2.6 2.6
NUREG-1123, Rev. 2 3.7-26 |

SYSTEM: 215002 Rod Block Monitor System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 IRM/RBM recorder/switch: BWR-3,4,5 .................................... 2.8 2.7

A4.02 RBM back panel switches, meters and indicating lights:

BWR-3,4,5 ............................................................. 2.9 2.9

A4.03 Trip bypasses: BWR-3,4,5 ................................................ 2.8 2.8

A4.04 "Push to Check" pushbutton: Plant-Specific ................................. 2.6 2.5

A4.05 "Setup" pushbutton: Plant-Specific ........................................ 2.5 2.5

A4.06 Surveillance testing: BWR-3,4,5 .......................................... 2.7* 2.7
3.7-27 NUREG-1123, Rev. 2 |

SYSTEM: 201005 Rod Control and Information System (RCIS)

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between ROD CONTROL AND

INFORMATION SYSTEM (RCIS) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Neutron monitoring system: BWR-6 ....................................... 3.3 3.3

K1.02 Reactor/turbine pressure control system: BWR-6 ............................ 3.3 3.5

K1.03 Control rod drive system: BWR-6 ......................................... 3.7 3.7

K1.04 Rod position information system: BWR-6 .................................. 3.7 3.7

K1.05 Rod action control system: BWR-6 ........................................ 3.5 3.5

K1.06 Rod gang drive system: BWR-6 ........................................... 3.3 3.3

K1.07 Rod interface system: BWR-6 ............................................ 3.3 3.3

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 A.C. electrical power: BWR-6 ............................................ 2.4 2.6

K3. Knowledge of the effect that a loss or malfunction of

the ROD CONTROL AND INFORMATION SYSTEM (RCIS) will

have on following:

(CFR: 41.7 / 45.4)

K3.01 Control rod drive system: BWR-6 ......................................... 3.3 3.7

K3.02 Reactor startup: BWR-6 ................................................. 3.5 3.5

K3.03 Reactor shutdown: BWR-6 ............................................... 3.0 3.2

K3.04 †FlUX shaping: BWR-6 .................................................. 3.0 3.3
NUREG-1123, Rev. 2 3.7-28 |

SYSTEM: 201005 Rod Control and Information System (RCIS)

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4. Knowledge of ROD CONTROL AND INFORMATION SYSTEM (RCIS)

design feature(s) and/or interlocks which provide for

the following:

(CFR: 41.7)

K4.01 Limiting the effects of a control Rod accident: BWR-6

...................................................................... 3.2 3.2

K4.02 Bank position withdrawal sequence (BPWS): BWR-6 ........................ 3.3 3.3

K4.03 Rod withdrawal block signals: BWR-6 ..................................... 3.5 3.5

K4.04 Rod insertion block signals: BWR-6 ...................................... 3.5 3.5

K4.05 Rod withdrawal limiter: BWR-6 .......................................... 3.5 3.5

K4.06 Rod pattern controller rod blocks: BWR-6 ................................. 3.5 3.5

K5. Knowledge of the operational implications of the

following concepts as they apply to ROD CONTROL AND

INFORMATION SYSTEM (RCIS) :

(CFR: 41.5 / 45.3)

K5.01 †Rod pattern and program development: BWR-6 ............................ 2.3 3.2

K5.02 Rod pattern controller (RPC): BWR-6 .................................... 2.8 3.3

K5.03 Rod groups: BWR-6 .................................................... 2.3 2.7

K5.04 †Rod sequences: BWR-6 ............................................... 2.7 3.0

K5.05 Rod density: BWR-6 ................................................... 2.7 3.0

K5.06 Target rod pattern: BWR-6 .............................................. 2.8 2.8

K5.07 Low power alarm point: BWR-6 .......................................... 3.5 3.5

K5.08 Transition zone: BWR-6 ................................................ 3.2 3.5

K5.09 High power setpoints BWR-6 ............................................ 3.5 3,5

K5.10 Rod withdrawal limiter: BWR-6 .......................................... 3.2 3.3

K5.11 Control rod motion: BWR-6 ............................................. 3.3 3.3

K5.12 Command word generation and sequencing (operator

follow, scan and test): BWR-6 ........................................... 1.8* 2.2*

K5.13 Position indication probes: BWR-6 ....................................... 2.5 2.7

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the ROD CONTROL AND

INFORMATION SYSTEM (RCIS) :

(CFR: 41.7 / 45.7)

K6.01 First stage shell pressure or opening of a bypass

valve(s): BWR-6 ....................................................... 3.2 3.2

K6.02 Rod position signal: BWR-6 ............................................. 3.2 3.3

K6.03 A.C. electrical power: BWR-6 ........................................... 2.5 2.8

K6.04 IRM channel: BWR-6 .................................................. 3.0 3.2

K6.05 SRM channel: BWR-6 .................................................. 3.0 3.2

K6.06 APRM channel: BWR-6 ................................................ 3.0 3.0
3.7-29 NUREG-1123, Rev. 2 |

SYSTEM: 201005 Rod Control and Information System (RCIS)

Tasks as noted previously

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A1. Ability to predict and/or monitor changes in

parameters associated with operating the ROD CONTROL

AND INFORMATION SYSTEM (RCIS) controls including:

(CFR: 41.5 / 45.5)

A1.01 First stage shell pressure/turbine load: BWR-6 .............................. 3.2 3.3

A2. Ability to (a) predict the impacts of the following on

the ROD CONTROL AND INFORMATION SYSTEM (RCIS) ; and

(b) based on those predictions, use procedures to

correct, control, or mitigate the consequences of

those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 High flux (SRM, IRM, APRM): BWR-6 .................................... 3.5 3.5

A2.02 Position indication probe failure: BWR-6 ................................... 2.8 3.2

A2.03 Insert block: BWR-6 .................................................... 3.2 3.2

A2.04 Withdraw block: BWR-6 ................................................. 3.2 3.2

A2.05 Insert required: BWR-6 .................................................. 3.2 3.2

A2.06 Insert inhibit: BWR-6 ................................................... 3.2 3.2

A2.07 Withdraw inhibit: BWR-6 ................................................ 3.2 3.2

A2.08 LPRM upscale/down scale: BWR-6 ........................................ 3.2 3.2

A2.09 Test display blinking: BWR-6 ............................................. 2.8 3.0

A2.10 Data fault: BWR-6 ...................................................... 2.8 3.0

A2.11 Accumulator fault: BWR-6 ............................................... 3.3 3.5

A2.12 Rod uncoupled: BWR-6 .................................................. 3.7 3.8

A2.13 Rod drift: BWR-6 ....................................................... 3.8 3.8

A3. Ability to monitor automatic operations of the ROD

CONTROL AND INFORMATION System (RCIS) including:

(CFR: 41.7 / 45.7)

A3.01 Operator control module lights: BWR-6 .................................... 3.5 3.5

A3.02 Rod display module lights: BWR-6 ........................................ 3.5 3.5

A3.03 †Verification of proper functioning/ operability:

BWR-6 ................................................................ 3.4 3.3

A3.04 Annunciator and alarm signals: BWR-6 ..................................... 3.3 3.3

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Operator control module (lights and push buttons):

BWR-6 ................................................................ 3.7 3.7

A4.02 Rod display module (lights and push buttons): BWR-6 . ........................ 3.7 3.7

A4.03 Back panel indicating lights: BWR-6 ....................................... 3.4 3.3
NUREG-1123, Rev. 2 3.7-30 |

SYSTEM: 214000 Rod Position Information System

TASK: Startup the rod position indication system 

Perform a position indication alignment during a reactor startup 

Monitor the rod position indication system 

Shutdown the rod position indication system (RPIS)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between ROD POSITION INFORMATION

SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 RWM: Plant-Specific ................................................... 3.0 3.2

K1.02 RSCS: Plant-Specific ................................................... 2.9 3.1

K1.03 CRDM ................................................................ 3.0 3.1

K1.04 RMCS: Plant-Specific .................................................. 3.2 3.2

K1.05 Full core display: Plant-Specific .......................................... 3.3 3.3

K1.06 RCIS: Plant-Specific .................................................... 3.4 3.4

K1.07 Process computer ....................................................... 2.7 3.0

K1.08 CRIDS/ERIS/SPDS/GDS: Plant-Specific ................................... 2.4 2.6

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

| None

K3. Knowledge of the effect that a loss or malfunction of

the ROD POSITION INFORMATION SYSTEM will have on

following:

(CFR: 41.7 / 45.4)

K3.01 RWM: Plant-Specific ................................................... 3.0 3.2

K3.02 RSCS: Plant-Specific ................................................... 3.0 3.1

K3.03 RMCS: Plant-Specific .................................................. 3.1 3.2

K3.04 RCIS: Plant-Specific .................................................... 3.3 3.3

K3.05 Process computer ....................................................... 2.3 2.6

K3.06 CRIDS/ERIS/SPDS/GDS: Plant-Specific ................................... 2.3* 2.5

K4. Knowledge of ROD POSITION INFORMATION SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Reed switch locations ................................................... 3.0 3.1

K4.02 Thermocouple .......................................................... 2.5* 2.5
3.7-31 NUREG-1123, Rev. 2 |

SYSTEM: 214000 Rod Position Information System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K5. Knowledge of the operational implications of the

following concepts as they apply to ROD POSITION

INFORMATION SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Reed switches .......................................................... 2.7 2.8

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the ROD POSITION

INFORMATION SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical power .................................................... 2.5 2.6

K6.02 Position indication probe ................................................ 2.7 2.7

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the ROD POSITION

INFORMATION SYSTEM controls including:

(CFR: 41.5 / 45.5)

None |

A2. Ability to (a) predict the impacts of the following on

the ROD POSITION INFORMATION SYSTEM ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Failed reed switches ..................................................... 3.1 3.3

A2.02 Reactor SCRAM ........................................................ 3.6 3.7 |

A2.03 Overtravel/in-out ....................................................... 3.6 3.9 |

A3. Ability to monitor automatic operations of the ROD

POSITION INFORMATION SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Full core display ........................................................ 3.4 3.3

A3.02 Alarm and indicating lights ............................................... 3.2 3.1

A3.03 Verification of proper functioning/ operability ............................... 3.5 3.7

A3.04 RCIS: Plant-Specific .................................................... 3.5 3.8
NUREG-1123, Rev. 2 3.7-32 |

SYSTEM: 214000 Rod Position Information System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 RCIS rod action control bypass switches .................................... 3.2 3.3

A4.02 Control rod position ..................................................... 3.8* 3.8*

A4.03 Control rod drive temperature ............................................. 2.8 2.7
3.7-33 NUREG-1123, Rev. 2 |

SYSTEM: 201004 Rod Sequence Control System (Plant Specific)

TASK: Conduct rod sequence control functional test

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between ROD SEQUENCE CONTROL

SYSTEM (PLANT SPECIFIC) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor manual control system: BWR-4,5 .................................. 3.2 3.3

K1.02 Turbine generator system: BWR-4,5 ....................................... 3.1 3.1

K1.03 Rod position information system: BWR-4,5 ................................. 3.1 3.1

K1.04 Rod worth minimizer: BWR-4,5 ........................................... 2.8 3.0

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

None |

K3. Knowledge of the effect that a loss or malfunction of

the ROD SEQUENCE CONTROL SYSTEM (PLANT SPECIFIC) will

have on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor manual control: BWR-4,5 ......................................... 3.3 3.4

K4. Knowledge of ROD SEQUENCE CONTROL SYSTEM (PLANT

SPECIFIC) design feature(s) and/or interlocks which

provide for the following:

(CFR: 41.7)

K4.01 Select blocks: BWR-4,5 ................................................. 3.0 3.1

K4.02 Insert rod blocks: BWR-4,5 .............................................. 3.1 3.2

K4.03 Withdraw rod blocks: BWR-4,5 ........................................... 3.3 3.4

K4.04 RSCS bypass as reactor power increases: BWR-4,5 .......................... 3.3 3.3

K4.05 Rod movement, direction, and selection information:

BWR-4,5 .............................................................. 3.2 3.2

K4.06 Group notch control: BWR-4,5 ........................................... 3.3 3.4

K4.07 Minimizing rod worth: BWR-4,5 .......................................... 3.6 3.7

K5. Knowledge of the operational implications of the

following concepts as they apply to ROD SEQUENCE

(CFR: 41.5 / 45.3)

CONTROL SYSTEM (PLANT SPECIFIC) :

K5.01 Prevention of clad damage if a control rod drop

accident (CRDA) occurs: BWR-4,5 ........................................ 3.6 4.0

K5.02 Sequences and groups: BWR-4,5 .......................................... 3.1 3.3

K5.03 Group notch control limits and rod density: BWR-4,5 ......................... 3.3 3.5
NUREG-1123, Rev. 2 3.7-34 |

SYSTEM: 201004 Rod Sequence Control System (Plant Specific)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the ROD SEQUENCE CONTROL

SYSTEM (PLANT SPECIFIC) :

(CFR: 41.7 / 45.7)

K6.01 Rod position information: BWR-4,5 ....................................... 3.3 3.3

K6.02 Rod direction information: BWR-4,5 ...................................... 3.1 3.2

K6.03 Rod movement information: BWR-4,5 ..................................... 3.2 3.2

K6.04 Turbine generator (1st stage shell pressure): BWR-4,5 ....................... 3.3 3.4

ABILITY

A1. Ability to predict and/or monitor changes in

parameters, associated with operating the ROD SEQUENCE

CONTROL SYSTEM (PLANT SPECIFIC) controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor manual control system: BWR-4,5 .................................. 3.3 3.3

A2. Ability to (a) predict the impacts of the following on

the ROD SEQUENCE CONTROL SYSTEM (PLANT SPECIFIC) ; and

(b) based on those predictions, use procedures to

correct, control, or mitigate the consequences of

those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Loss of rod position information: BWR-4,5 ................................ 3.3 3.6

A2.02 Attempting to move a stuck control rod: BWR-4,5 ........................... 3.4 3.6

A2.03 Turbine trip: BWR-4,5 .................................................. 3.2 3.2

A3. Ability to monitor automatic operations of the ROD

SEQUENCE CONTROL SYSTEM (PLANT SPECIFIC) including:

(CFR: 41.7 / 45.7)

A3.01 Rod select switch light: BWR-4,5 ......................................... 3.2 3.1

A3.02 Rod select bottom lamp dimmer logic: BWR-4,5 ............................ 3.1* 3.1*

A3.03 Back panel indicators: BWR-4,5 .......................................... 2.8 3.0

A3.04 Annunciator and alarm signals: BWR-4,5 ................................... 3.2 3.2

A3.05 †Verification of proper function/ operability: BWR-4,5 ...................... 3.5 3.7

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

| A4.01 †System bypass switches: BWR-4,5 ...................................... 3.4 3.5

A4.02 RSCS console switches and indicators: BWR-4,5 ............................ 3.5 3.2

A4.03 †Rscs back panel switches and indicators: BWR-4,5 ......................... 3.0 3.1
3.7-35 NUREG-1123, Rev. 2 |

SYSTEM: 201006 Rod Worth Minimizer System (RWM) (Plant Specific)

TASK: Conduct rod worth minimizer functional test

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between ROD WORTH MINIMIZER

SYSTEM (RWM) (PLANT SPECIFIC) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor manual control: P-Spec(Not-BWR6) .............................. 3.4 3.4

K1.02 Rod position indication system: P-Spec(Not-BWR6) ........................ 3.4 3.4

K1.03 Reactor water level control (feed flow): P-Spec(NotBWR6) ............................................................... 3.1 3.2

K1.04 Steam flow/reactor power: P-Spec(Not-BWR6) ............................ 3.1 3.2

K1.05 Control rod drop accident: P-Spec(Not-BWR6) ............................ 3.5 3.8

K1.06 Rod sequence control system: P-Spec(Not-BWR6) ......................... 3.3 3.4

K1.07 Process computer: P-Spec(Not-BWR6) ................................... 2.8 2.9

K1.08 Reactor power (turbine first stage pressure): PSpec(Not-BWR6) ...................................................... 3.2 3.3

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Rod worth minimizer: P-Spec(Not-BWR6) ................................ 2.2* 2.5*

K3. Knowledge of the effect that a loss or malfunction of

the ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC)

will have on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor manual control system: P-Spec(Not-BWR6) ........................ 3.2 3.5

K4. Knowledge of ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT

SPECIFIC) design feature(s) and/or interlocks which

provide for the following:

(CFR: 41.7)

K4.01 Insert blocks/errors: P-Spec(Not-BWR6) .................................. 3.4 3.5

K4.02 Withdraw blocks/errors: P-Spec(Not-BWR6) .............................. 3.5 3.5

K4.03 Select blocks/errors: P-Spec(Not-BWR6) ................................. 3.3 3.4

K4.04 System bypass: P-Spec(Not-BWR6) ...................................... 3.4 3.5

K4.05 Substitute rod position data: P-Spec(Not-BWR6) ........................... 2.8 3.0

K4.06 Correction of out of sequence rod positions: PSpec(Not-BWR6) ...................................................... 3.2 3.4

K4.07 Display of out of position control rods without rod

blocks (transition zone): P-Spec(Not-BWR6) .............................. 3.1 3.2

K4.08 System testing: P-Spec(Not-BWR6) ...................................... 2.8 2.8

K4.09 System initialization: P-Spec(Not-BWR6) ................................. 3.2 3.2
NUREG-1123, Rev. 2 3.7-36 |

SYSTEM: 201006 Rod Worth Minimizer System (RWM) (Plant Specific)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K5. Knowledge of the operational implications of the

following concepts as they apply to ROD WORTH

MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) :

(CFR: 41.5 / 45.3)

K5.01 Minimize clad damage if a control rod drop accident

(CRDA) occurs: P-Spec(Not-BWR6) ...................................... 3.3 3.7

K5.02 Low power set point: P-Spec(Not-BWR6) .................................. 2.9 3.0

K5.03 Low power alarm point (LPAP): P-Spec(Not-BWR6) ......................... 2.8 2.9

K5.04 Transition zone: P-Spec(Not-BWR6) ...................................... 2.8 2.8

K5.05 High power set point: P-Spec(Not-BWR6) .................................. 2.9 3.0

K5.06 Rod groups and steps: P-Spec(Not-BWR6) ................................. 2.8 3.0

K5.07 Latch groups: P-Spec(Not-BWR6) ........................................ 2.8 2.9

K5.08 Operating sequence: P-Spec(Not-BWR6) ................................... 2.9 2.9

K5.09 Select error: P-Spec(Not-BWR6) ......................................... 3.2 3.2

K5.10 Withdraw error: P-Spec(Not-BWR6) ...................................... 3.2 3.3

K5.11 Insert error: P-Spec(Not-BWR6) .......................................... 3.2 3.3

K5.12 Withdraw block: P-Spec(Not-BWR6) ...................................... 3.5 3.5

K5.13 Insert block: P-Spec(Not-BWR6) ......................................... 3.5 3.5

K5.14 Alternate withdraw and insert limits: P-Spec(NotBWR6) ................................................................ 3.0 3.0

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the ROD WORTH MINIMIZER

SYSTEM (RWM) (PLANT SPECIFIC) :

(CFR: 41.7 / 45.7)

K6.01 RWM power supply: P-Spec(Not-BWR6) .................................. 2.8 3.2

K6.02 Reactor water level control input: P-Spec(Not-BWR6) . ....................... 2.9 2.9

K6.03 Rod position indication: P-Spec(Not-BWR6) ............................... 2.9 2.9

K6.04 Process computer: P-Spec(Not-BWR6) .................................... 2.7 2.8

K6.05 Steam flow input: P-Spec(Not-BWR6) ..................................... 2.7 2.7

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the ROD WORTH

MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) controls

including:

(CFR: 41.5 / 45.5)

A1.01 Rod position: P-Spec(Not-BWR6) ........................................ 3.2 3.3

A1.02 Status of control rod movement blocks; P-Spec(NotBWR6) ................................................................ 3.4 3.5

A1.03 Latched group indication: P-Spec(Not-BWR6) .............................. 2.9 3.0
3.7-37 NUREG-1123, Rev. 2 |

SYSTEM; 201006 Rod Worth Minimizer System (RWM) (Plant Specific)

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A2. Ability to (a) predict the impacts of the following on

the ROD WORTH MINIMIZER SYSTEM (RWH) (PLANT SPECIFIC)

; and (b) based on those predictions, use procedures

to correct, control, or mitigate the consequences of

those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Power supply loss: P-Spec(Not-BWR6) .................................... 2.5 2.8

A2.02 Loss of steam flow input: P-Spec(Not-BWR6) ............................... 2.6 2.9

A2.03 Rod drift: P-Spec(Not-BWR6) ............................................ 3.0 3.2

A2.04 Stuck rod: P-Spec(Not-BWR6) ............................................ 3.0 3.3

A2.05 Out of sequence rod movement; P-Spec(Not-BWR6) .......................... 3.1 3.5

A2.06 Loss of reactor water level control input: PSpec(Not-BWR6) ........................................................ 2.9 3.3

A2.07 RWM hardware/software failure: P-Spec(Not-BWR6) ........................ 2.5 2.8

A3. Ability to monitor automatic operations of the ROD

WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC)

including:

(CFR: 41.7 / 45.7)

A3.01 System window and light indication: P-Spec(Not-BWR6). ..................... 3.2 3.1

A3.02 Verification of proper functioning/ operability: Plant-

 Spec(Not-BWR6) ........................................................... 3.5 3.4

A3.03 Annunciator and alarm signals: P-Spec(Not-BWR6) ........................... 3.1 3.0

A3.04 Control rod movement blocks: P-Spec(Not-BWR6) .......................... 3.5 3.4

A3.05 Latched group indication: P-Spec(Not-BWR6) ............................... 3.0 3.1

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 System bypass switch: P-Spec(Not-BWR6) .................................. 3.2 3.4

A4.02 Pushbutton indicating switches: P-Spec(Not-BWR6) .......................... 2.9 2.9

A4.03 Latched group indication: P-Spec(Not-BWR6) ............................... 3.0 3.0

A4.04 Rod withdrawal error indication: P-Spec(Not-BWR6) ......................... 3.3 3.2

A4.05 Rod insert error indication: P-Spec(Not-BWR6) ............................. 3.2 3.2

A4.06 Selected rod position indication: P-Spec(Not-BWR6) ......................... 3.2 3.2
NUREG-1123, Rev. 2 3.7-38 |

SYSTEM: 215004 Source Range Monitor (SRM) System

TASK: Perform lineups of the nuclear instrumentation system 

Monitor the nuclear instrumentation system 

Startup the nuclear instrumentation system 

Place a source range module in/out of service 

Operate the nuclear instrumentation system 

Secure the nuclear instrumentation system 

Conduct source range meter, intermediate range meter detector not in Startup rod block functional test 

Conduct SRM functional test

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between SOURCE RANGE MONITOR

(SRM) SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor protection system ............................................... 3.6 3.7

K1.02 Reactor manual control .................................................. 3.4 3.4

K1.03 Rod control and information system: Plant-Specific ......................... 3.0 3.0

K1.04 Process computer/ performance monitoring system

(SPDS/ERIS/CRIDS/GDS): Plant-Specific ................................. 2.4 2.6*

K1.05 Display control system: Plant-Specific .................................... 2.8 3.0

K1.06 Reactor vessel ......................................................... 2.8 2.8

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 SRM channels/detectors ................................................. 2.6 2.8

K2.02 Detector drive modules ................................................. 2.1* 2.3*

K2.03 Detector drive module control ............................................ 2.0* 2.1*

K3. Knowledge of the effect that a loss or malfunction of

the SOURCE RANGE MONITOR (SRM) SYSTEM will have on

following:

(CFR: 41.7 / 45.4)

K3.01 RPS .................................................................. 3.4 3.4

K3.02 Reactor manual control: Plant-Specific .................................... 3.4 3.4

K3.03 Rod control and information system: Plant-Specific ......................... 3.3 3.3

K3.04 Reactor power and indication ............................................. 3.7 3.7

K4. Knowledge of SOURCE RANGE MONITOR (SRM) SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Rod withdrawal blocks .................................................. 3.7 3.7

K4.02 Reactor SCRAM signals ................................................. 3.4 3.5

K4.03 Gamma compensation ................................................... 2.4 2.4
3.7-39 NUREG-1123, Rev. 2 |

SYSTEM: 215004 Source Range Monitor (SRM) System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.04 Changing detector position ............................................... 2.8 2.9

K4.05 Alarm seal-in ........................................................... 2.5 2.5

K4.06 IRM/SRM interlock ..................................................... 3.2 3.2

K5. Knowledge of the operational implications of the

following concepts as they apply to SOURCE RANGE

MONITOR (SRM) SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Detector operation ...................................................... 2.6 2.6

K5.02 Gamma discrimination ................................................... 2.2* 2.2*

K5.03 Changing detector position ............................................... 2.8 2.8

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the SOURCE RANGE MONITOR

(SRH) SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 RPS .................................................................. 3.2 3.3

K6.02 24/48 volt D.C. power ................................................... 3.1 3.3

K6.03 Detector drive motor .................................................... 2.4 2.4

K6.04 Detectors .............................................................. 2.9 2.9

K6.05 Trip units .............................................................. 2.6 2.8

K6.06 Recorder .............................................................. 2.2* 2.2*

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the SOURCE RANGE

MONITOR (SRM) SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Detector position ....................................................... 3.0 3.1

A1.02 Reactor power indication ................................................. 3.6 3.7

A1.03 RPS status ............................................................. 3.4 3.5 |

A1.04 Control rod block status ................................................. 3.5 3.5

A1.05 SCRAM, rod block, and period alarm trip setpoints ........................... 3.6 3.8

A1.06 Lights and alarms ....................................................... 3.1 3.1

A2. Ability to (a) predict the impacts of the following on

the SOURCE RANGE MONITOR (SRM) SYSTEM ; and (b) based

on those predictions, use procedures to correct,

control, or mitigate the consequences of those

abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Power supply degraded .................................................. 2.7 2.9
NUREG-1123, Rev. 2 3.7-40 |

SYSTEM: 215004 Source Range Monitor (SRM) System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A2.02 SRM inop condition ..................................................... 3.4 3.7

| A2.03 Stuck detector .......................................................... 3.0 3.3

| A2.04 Up scale and downscale trips .............................................. 3.5 3.7

A2.05 Faulty or erratic operation of detectors/system .............................. 3.3 3.5

A2.06 Failed recorder ......................................................... 2.4* 2.5

A3. Ability to monitor automatic operations of the SOURCE

RANGE MONITOR (SRM) SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Meters and recorders .................................................... 3.2 3.2

A3.02 Annunciator and alarm signals ............................................. 3.4 3.3

A3.03 RPS status ............................................................. 3.6 3.5

A3.04 Control rod block status ................................................. 3.6 3.6

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 SRM count rate and period ............................................... 3.9 3.8

A4.02 SRM recorder .......................................................... 3.0 3.1

A4.03 CRT displays: Plant-Specific ............................................. 2.9 2.7

A4.04 SRM drive control switches .............................................. 3.2 3.2

A4.05 SRM back panel switches, meters, and indicating lights ........................ 3.1 3.2

A4.06 Alarms and lights ....................................................... 3.2 3.1

A4.07 Verification of proper functioning/ operability ............................... 3.4 3.6
3.7-41 NUREG-1123, Rev. 2 |

System: 215001 Traversing In-Core Probe

TASK: Perform lineups of the nuclear instrumentation system 

Monitor the nuclear instrumentation system 

Startup the nuclear instrumentation system 

Operate the nuclear instrumentation system 

Secure the nuclear instrumentation system 

Place transversing in-core probe in/out of service

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between TRAVERSING IN-CORE PROBE

and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Local power range monitors: (Not-BWR1) ................................. 2.5 2.8

K1.02 Process computer: (Not-BWR1) .......................................... 2.5 3.1

K1.03 Nitrogen purge system: P-Spec(Not-BWR1) ................................ 2.1* 2.3

K1.04 Plant air systems: P-Spec(Not-BWR1) .................................... 1.8* 2.0*

K1.05 Primary containment isolation system: (Not-BWR1) ......................... 3.3 3.4

K1.06 D.C. electrical: (Not-BWR1) ............................................. 1.8* 1.9*

K1.07 A.C. electrical: (Not-BWR1) ............................................. 1.8* 1.9*

K1.08 Reactor pressure vessel: (Not-BWR1) ..................................... 2.5 2.6

K1.09 Primary containment: (Not-BWR1) ....................................... 2.6 2.7

K1.10 Area radiation monitoring system: (Not-BWR1) ............................. 2.6 2.8

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Shear valves: Mark-I&II(Not-BWR1) ...................................... 1.9* 2.1*

K3. Knowledge of the effect that a loss or malfunction of

the TRAVERSING IN-CORE PROBE will have on following:

(CFR: 41.7 / 45.4)

K3.01 Local power range monitor's calibration: (Not-BWR1) ....................... 2.3 2.8

K4. Knowledge of TRAVERSING IN-CORE PROBE design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Primary containment isolation: Mark-I&II(Not-BWR1) ...................... 3.4 3.5

K4.02 Corrosion prevention: (Not-BWR1) ....................................... 1.9* 2.1*

K4.03 Radiation shielding: (Not-BWR1) ......................................... 2.4 2.7
NUREG-1123, Rev. 2 3.7-42 |

SYSTEM: 215001 Traversing In-Core Probe

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K5. Knowledge of the operational implications of the

following concepts as they apply to TRAVERSING IN-CORE

PROBE:

(CFR: 41.5 / 45.3)

K5.01 Neutron flux detection: (Not-BWR1) ...................................... 2.2* 2.5

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the TRAVERSING IN-CORE

PROBE :

(CFR: 41.7 / 45.7)

K6.01 D.C. electrical power: (Not-BWR1) ....................................... 1.9* 2.1*

K6.02 A.C. electrical power: (Not-BWR1) ....................................... 1.9* 2.1*

K6.03 Process computer: BWR-2,3,4,5,6 ........................................ 2.3 2.7

K6.04 Primary containment isolation system: Mark-I&II(NotBWR1) ............................................................... 3.1 3.4

K6.05 Plant air systems: P-Spec(Not-BWR1) .................................... 1.8* 2.1*

K6.06 Nitrogen purge: P-Spec(Not-BWR1) ...................................... 2.0* 2.2

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the TRAVERSING

IN-CORE PROBE controls including:

(CFR: 41.5 / 45.5)

A1.01 Radiation levels: (Not-BWR1) ........................................... 2.8 2.9

A1.02 Detector position: (Not-BWR1) .......................................... 2.5 2.4

A1.03 Valve status: Mark-I&II(Not-BWR1) ...................................... 2.6* 2.8

A1.04 Drive speed: (Not-BWR1) ............................................... 2.0* 2.2*

A1.05 Detector output: (Not-BWR1) ............................................ 2.0* 2.3*

A1.06 Radiation alarms: (Not-BWR1) ........................................... 2.9 2.8

A2. Ability to (a) predict the impacts of the following on

the TRAVERSING IN-CORE PROBE ; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 Low reactor water level: Mark-I&II(Not-BWR1) ............................ 2.7 2.9

A2.02 High primary containment pressure: Mark-l&II(NotBWR1) ............................................................... 2.9 3.0

A2.03 Drive mechanism failure: (Not-BWR1) .................................... 2.1* 2.4

A2.04 A.C. failure: (Not-BWR1) ............................................... 1.8* 2.0*

A2.05 D.C. failure: (Not-BWR1) ............................................... 1.8* 2.0*
3.7-43 NUREG-1123, Rev. 2 |

SYSTEM: 215001 Traversing In-Core Probe

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A2.06 Valve closures: Mark-I&II(Not-BWR1) .................................... 2.4* 2.6

A2.07 †Failure to retract during accident conditions: MarkI&II(Not-BWR1) ....................................................... 3.4 3.7

A2.08 Failure to retract to shield: (Not-BWR1) ................................... 2.7* 2.9

A3. Ability to monitor automatic operations of the

TRAVERSING IN-CORE PROBE including:

(CFR: 41.7 / 45.7)

A3.01 Detector position: P-Spec(Not-BWR1) .................................... 2.3* 2.5*

A3.02 Detector drive speed: P-Spec(Not-BWR1) ................................. 1.9* 2.2*

A3.03 Valve operation: Not-BWR1 ............................................. 2.5* 2.6*

A3.04 Indicating lights: P-Spec(Not-BWR1) ..................................... 2.2* 2.4*

A3.05 Detector output: P-Spec(Not-BWR1) ..................................... 1.9* 2.2*

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Detector drive speed: P-Spec(Not-BWR1) ................................. 2.0* 2.2*

A4.02 Detector position: P-Spec(Not-BWR1) .................................... 2.4* 2.6*

A4.03 Isolation valves: Mark-I&II(Not-BWR1) ................................... 3.0 3.1

A4.04 Detector output: P-Spec(Not-BWR1) ..................................... 2.0* 2.3*

A4.05 Indicating lights: P-Spec(Not-BWR1) ..................................... 2.3* 2.5
3.8-1 NUREG-1123, Rev. 2 |

3.8 Plant Service Systems page

286000 Fire Protection System 3.8-3

234000 Fuel Handling 3.8-7

300000 Instrument Air System 3.8-10

400000 Component Cooling Water System 3.8-13
NUREG-1123, Rev. 2 3.8-2 |

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3.8-3 NUREG-1123, Rev. 2 |

SYSTEM: 286000 Fire Protection System

TASK: Perform lineups of the fire protection system (CO2, deluge, freon/halon 1301, foam)

Place the fire protection system in standby

Operate fire protection equipment to combat a fire 

Monitor the fire protection system

Operate the fire detection/alarm equipments 

Shut down the fire protection system

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between FIRE PROTECTION SYSTEM

and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Component cooling water systems ......................................... 2.7 2.8

K1.02 Isolation condenser: Plant-Specific ....................................... 3.8 3.8

K1.03 Reactor water level: Plant-Specific ........................................ 2.9 3.0

K1.04 D.C. electrical distribution: Plant-Specific ................................. 2.6 2.6

K1.05 Main generator hydrogen system: Plant-Specific ............................ 3.1 3.1

K1.06 Auxiliary (boiler) steam system: Plant-Specific ............................. 2.2* 2.3*

K1.07 A.C. power supplies ..................................................... 2.8 2.9

K1.08 Intake canals: Plant-Specific ............................................. 3.0 3.0

K1.09 Emergency generator rooms: Plant-Specific ................................ 3.2 3.3

K1.10 Main generator exciter: Plant-Specific ..................................... 2.8 2.8

K1.11 Screen wash system: Plant-Specific ....................................... 2.5 2.5

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Fire protection supervisory circuits: Plant-Specific. ......................... 2.3* 2.5*

K2.02 Pumps ................................................................ 2.9 3.1 |

K2.03 Fire detection system: Plant-Specific ...................................... 2.5* 2.7* |

K3. Knowledge of the effect that a loss or malfunction of

the FIRE PROTECTION SYSTEM will have on following:

(CFR: 41.7 / 45.4)

K3.01 The ability to detect fires ................................................. 3.2 3.4

K3.02 Personnel protection .................................................... 3.2 3.4

K3.03 Plant protection ........................................................ 3.6 3.8
NUREG-1123, Rev. 2 3.8-4 |

SYSTEM: 286000 Fire Protection System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4. Knowledge of FIRE PROTECTION SYSTEM design feature(s)

and/or interlocks which provide for the following:

(CFR: 41.7)

(CFR: 41.5 / 45.3)

(CFR: 41.7 / 45.7)

(CFR: 41.5 / 45.5)

(CFR: 41.5 / 45.6)

(CFR: 41.7 / 45.7)

(CFR: 41.7 / 45.5 to 45.8)

K4.01 Adequate supply of water for the fire protection

system ................................................................ 3.4 3.6

K4.02 Automatic system initiation .............................................. 3.3 3.5

K4.03 Maintenance of fire header pressure ....................................... 3.3 3.4

K4.04 Personnel safety during halon and/or carbon dioxide

system actuation ....................................................... 3.6 3.7

K4.05 Fire protection capability during loss of off-site

power ................................................................ 3.7 3.8

K4.06 Fire suppression capability that does not rely on the

displacement of oxygen (Halon): Plant-Specific ............................ 3.4 3.4

K4.07 Diesel engine protection ................................................ 3.3 3.3

K5. Knowledge of the operational implications of the

following concepts as they apply to FIRE PROTECTION

SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Effect of carbon dioxide on fires .......................................... 2.6 2.7

K5.02 Effect of Halon on fires: Plant-Specific ................................... 2.6 2.6

K5.03 Effect of water spray on electrical components .............................. 3.3 3.4

K5.04 Valve operation ........................................................ 2.9 2.9

| K5.05 Diesel operations ...................................................... 3.0* 3.1*

| K5.06 Heat detection ......................................................... 2.6 2.7

K5.07 Smoke detection ....................................................... 2.6 2.7

| K5.08 Gas refrigeration: Plant-Specific ......................................... 2.4* 2.5*

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the FIRE PROTECTION SYSTEM

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical distribution: Plant-Specific ................................. 3.1 3.1

| K6.02 D. C . electrical distribution .............................................. 2.8* 2.9*

K6.03 Applicable component cooling water system: PlantSpecific .............................................................. 2.4* 2.5

K6.04 Diesel fuel transfer system: Plant-Specific ................................. 2.8 3.0

K6.05 Screen wash system: Plant-Specific ....................................... 2.6 2.6
3.8-5 NUREG-1123, Rev. 2 |

SYSTEM: 286000 Fire Protection System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

Al. Ability to predict and/or monitor changes in

parameters associated with operating the FIRE

PROTECTION SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 System pressure ........................................................ 2.9 2.9

A1.02 System flow ........................................................... 2.4* 2.5*

A1.03 Fire doors ............................................................. 2.8 3.1

A1.04 Fire dampers .......................................................... 2.8 3.1

A1.05 System lineups ......................................................... 3.2 3.2

A1.06 Tank pressure: Plant-Specific ............................................ 2.9 3.0

A2. Ability to (a) predict the impacts of the following on

the FIRE PROTECTION SYSTEM ; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 †System logic failure: Plant-Specific ...................................... 2.7 2.9

A2.02 D.C. distribution failure: Plant-Specific .................................... 2.6* 2.7*

A2.03 A.C. distribution failure: Plant-Specific .................................... 2.9 3.0

A2.04 Applicable component cooling water system failure:

Plant-Specific .......................................................... 2.3* 2.4*

A2.05 Fire protection diesel trips ............................................... 3.1 3.3

A2.06 Low fire main pressure: Plant-Specific .................................... 3.1 3.2

A2.07 Inadvertent system initiation .............................................. 2.9 2.9

A2.08 Failure to actuate when required ........................................... 3.2 3.3

A2.09 Valve closures: Plant-Specific ............................................ 2.7 2.8

A2.10 Valve openings: Plant-Specific ........................................... 2.6* 2.7

A2.11 Pump trips: Plant-Specific ............................................... 3.1 3.2

A2.12 Low diesel fuel supply: Plant-Specific ..................................... 3.1 3.3

A3. Ability to monitor automatic operations of the FIRE

PROTECTION SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Fire water pump start .................................................... 3.4 3.4

A3.02 Fire main pressure ...................................................... 3.1 3.2

A3.03 Actuation of fire detectors ............................................... 3.3 3.3

A3.04 System initiation ........................................................ 3.2 3.3

A3.05 Fire doors ............................................................. 3.0 3.1

A3.06 Fire dampers ........................................................... 3.0 3.1
NUREG-1123, Rev. 2 3.8-6 |

SYSTEM: 286000 Fire Protection System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 System alarms and indicating lights ........................................ 3.3 3.2

A4.02 Applicable component cooling water system: PlantSpecific ............................................................... 2.5* 2.5*

A4.03 Applicable component cooling water pressure ............................... 2.5* 2.5*

A4.04 Fire main pressure: Plant-Specific ........................................ 2.8 2.8

A4.05 Fire pump ............................................................. 3.3 3.3

A4.06 Fire diesel ............................................................. 3.4 3.4
3.8-7 NUREG-1123, Rev. 2 |

SYSTEM: 234000 Fuel Handling Equipment

TASK: Operate the spent fuel handling machine/bridge

Operate the refueling machine/main fuel handling bridge (fuel element change)

Operate the control rod change machine/main fuel handling bridge (control rod change)

Operate the fuel transfer system/fuel transfer carriages and upenders

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between FUEL HANDLING EQUIPMENT

and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 †Fuel ...................................................................... 3.2 3.7

K1.02 †Core components ........................................................... 2.9 3.3

K1.03 Spent fuel cask ............................................................... 2.7* 2.9

K1.04 †Reactor manual control system: Plant-Specific .................................. 3.3 3.6

K1.05 Reactor vessel components: Plant-Specific ...................................... 2.9 3.3

K1.06 RC & IS: Plant-Specific ....................................................... 3.0 3.2

K1.07 Fuel transfer tube system: Mark-III ............................................. 3.0 3.4

K1.08 Fuel pools configuration: Mark-III .............................................. 2.7 3.0

K1.09 Fuel pool ventilation: Plant-Specific ............................................ 2.8 2.9

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

None |

K3. Knowledge of the effect that a loss or malfunction of

the FUEL HANDLING EQUIPMENT will have on following:

(CFR: 41.7 / 45.4)

K3.01 †Reactor manual control system: Plant-Specific ................................... 2.9 3.3

K3.02 RC & IS: Plant-Specific ........................................................ 3.0 3.0

K3.03 †Fuel handling operations ....................................................... 3.1 3.8 |

K3.04 †core modifications/alterations .................................................. 2.9 3.8

K4. Knowledge of FUEL HANDLING EQUIPMENT design feature(s)

and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 †Prevention of core alterations during control rod

movements ............................................................ 3.3 4.1

K4.02 †Prevention of control rod movement during core

alterations ............................................................. 3.3 4.1

K4.03 †Protection against inadvertently lifting radioactive

components out of the water .............................................. 3.4 4.2

K4.04 †Movement of the spent fuel cask only over designated

areas: Plant-Specific ................................................... 2.8 3.3

K4.05 †Movement of fuel via fuel transfer tube: Mark-III ................................. 3.0 3.8
NUREG-1123, Rev. 2 3.8-8 |

SYSTEM: 234000 Fuel Handling Equipment

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K5. Knowledge of the operational implications of the

following concepts as they apply to FUEL HANDLING

EQUIPMENT :

(CFR: 41.5 / 45.3)

K5.01 †Crane/hoist operation .......................................................... 2.9 3.4

K5.02 †Fuel handling equipment interlocks ............................................... 3.1 3.7

K5.03 †Water as a shield against radiation ................................................ 2.9 3.4

K5.04 Spent fuel pool design ........................................................... 2.6 3.1

K5.05 †Fuel orientation ............................................................... 3.0 3.7

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the FUEL HANDLING EQUIPMENT

(CFR: 41.7 / 45.7)

K6.01 †Electrical power .............................................................. 2.7 3.2

K6.02 Reactor manual control system: Plant-Specific ..................................... 2.8 3.5

K6.03 RC & IS: Plant-Specific ......................................................... 3.0 3.6

K6.04 †Refueling platform air system: Plant-Specific ..................................... 2.9 3.7

K6.05 Upper fuel pool water inventory: Mark-III .......................................... 3.2 3.3

K6.06 Fuel transfer tube interlocks: Mark-III ............................................. 3.0 3.6

K6.07 †Fuel pool ventilation: Plant-Specific ............................................. 2.9 3.4

ABILITY

Al. Ability to predict and/or monitor changes in

parameters associated with operating the FUEL HANDLING

EQUIPMENT controls including:

(CFR: 41.5 / 45.5)

A1.01 Spent fuel pool level ............................................................ 3.1 3.4

A1.02 †Refuel floor radiation levels/ airborne levels ....................................... 3.3 3.8

A1.03 †core reactivity level ........................................................... 3.4 3.9

A2. Ability to (a) predict the impacts of the following on

the FUEL HANDLING EQUIPMENT ; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 †Interlock failure ............................................................... 3.3 3.7

A2.02 †Loss of refueling platform air system ............................................. 3.1 3.6

A2.03 †Loss of electrical power ........................................................ 2.8 3.1
3.8-9 NUREG-1123, Rev. 2 |

SYSTEM: 234000 Fuel Handling Equipment

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A3. Ability to monitor automatic operations of the FUEL

HANDLING EQUIPMENT including:

(CFR: 41.7 / 45.7)

A3.01 †Crane/refuel bridge movement: Plant-Specific ..................................... 2.6 3.6

A3.02 †Interlock operation ........................................................... 3.1 3.7

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 †Neutron monitoring system .................................................... 3.7 3.9

A4.02 Control rod drive system ................................................. 3.4 3.7
NUREG-1123, Rev. 2 3.8-10 |

SYSTEM: 300000 Instrument Air System (IAS)

Task: Perform lineups of the IAS

Start up the IAS

Monitor the IAS

Shift instrument air compressors

Operate instrument air compressors

Operate system air dryers

Perform testing of automatic operation of the IAS

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1 Knowledge of the connections and / or cause effect

relationships between INSTRUMENT AIR SYSTEM and 

the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Sensor air ............................................................. 2.4 2.7

K1.02 Service air ............................................................. 2.7 2.8

K1.03 Containment air ........................................................ 2.8 2.9

K1.04 Cooling water to compressor ............................................. 2.8 2.9

K1.05 Main Steam Isolation Valve air ............................................ 3.1 3.2

K2 Knowledge of electrical power supplies to the following:

(CFR: 41.7)

K2.01 Instrument air compressor ................................................ 2.8 2.8

K2.02 Emergency air compressor ............................................... 3.0 3.0

K3. Knowledge of the effect that a loss or malfunction of the ......................

(INSTRUMENT AIR SYSTEM) will have on the following: 

(CFR: 41.7 / 45.6)

K3.01 Containment air system .................................................. 2.7 2.9

K3.02 Systems having pneumatic valves and controls ............................... 3.3 3.4

K3.03 Cross-tied units ........................................................ 2.9 3.0

K4. Knowledge of (INSTRUMENT AIR SYSTEM) design feature(s) 

and or interlocks which provide for the following: 

(CFR: 41.7)

K4.01 Manual/automatic transfers of control ...................................... 2.8 2.9

K4.02 Cross-over to other air systems ........................................... 3.0 3.0

K4.03 Securing of IAS upon loss of cooling water ................................. 2.8 2.8

K5. Knowledge of the operational implications of the 

following concepts as they apply to the INSTRUMENT 

AIR SYSTEM:

(CFR: 41.5 / 45.3)

K5.01 Air compressors ........................................................ 2.5 2.5

K5.02 Pressure gauges ........................................................ 2.3 2.2
3.8-11 NUREG-1123, Rev. 2 |

SYSTEM: 300000 Instrument Air System (IAS)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K5.03 Temperature indicators .................................................. 2.1 2.1

K5.04 Service air refusal valve .................................................. 2.3 2.3

K5.06 Air dryers ............................................................. 2.4 2.5

K5.07 Valves ................................................................ 2.4 2.3

K5.08 Sensors and detectors ................................................... 2.3 2.5

K5.09 Controllers and positioners ............................................... 2.0 2.1

K5.10 Motors ................................................................ 2.1 2.2

K5.11 Heat exchangers and condensers ........................................... 2.2 2.2

K5.12 Breakers, relays and disconnects .......................................... 2.2 2.2

K5.13 Filters ................................................................ 2.9 2.9

K6 Knowledge of the effect that a loss or malfunction of 

the following will have on the INSTRUMENT AIR SYSTEM: 

(CFR: 41.7 / 45.7)

K6.01 Air compressors ........................................................ 2.2 2.2

K6.02 Pressure gauges ........................................................ 2.4 2.4

K6.03 Temperature indicators .................................................. 2.7 2.7

K6.04 Service air refusal valve .................................................. 2.6 2.5

K6.06 Air dryers ............................................................. 2.3 2.3

K6.07 Valves ................................................................ 2.5 2.6

K6.08 Sensors and detectors ................................................... 2.3 2.3

K6.09 Controllers and positioners ............................................... 2.3 2.3

K6.10 Motors ................................................................ 2.3 2.4

K6.11 Heat exchangers and condensers ........................................... 2.3 2.3

K6.12 Breakers, relays and disconnects .......................................... 2.9 2.9

K6.13 Filters ................................................................ 2.8 2.3

No. ABILITY

A1. Ability to predict and / or monitor changes in parameters ................. associated

with operating the INSTRUMENT AIR SYSTEM 

controls including:

(CFR: 41.5 / 45.5)

None |

A2. Ability to (a) predict the impacts of the following on the ..................

INSTRUMENT AIR SYSTEM and (b) based on those predictions,

use procedures to correct, control, or mitigate the 

consequences of those abnormal operation: 

(CFR: 41.5 / 45.6)

A2.01 Air dryer and filter malfunctions .......................................... 2.9 2.8
NUREG-1123, Rev. 2 3.8-12 |

SYSTEM: 300000 Instrument Air System (IAS)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A3. Ability to monitor automatic operations of the INSTRUMENT AIR SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Air pressure 2.3 2.1

A3.02 Air temperature 2.9 2.7

A4. Ability to manually operate and / or monitor in the 

control room: 

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Pressure gauges 2.6 2.7
3.8-13 NUREG-1123, Rev. 2 |

SYSTEM: 400000 Component Cooling Water System (CCWS)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

Task: Perform CCWS component operability test

Perform CCWS flow path verification

Perform CCWS pump test

Perform CCW flow balance

Determine CCWS leak rate from RCS

K1. Knowledge of the physical connections and / or cause-effect relationships

 between CCWS and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Service water system .................................................... 3.2 3.3

K1.02 Loads cooled by CCWS .................................................. 3.2 3.4

K1.03 Radiation monitoring systems ............................................. 2.7 3.0

K1.04 Reactor coolant system, in order to determine source (s)

of RCS leakage into CCWS ............................................... 2.9 3.1

K2. Knowledge of electrical power supplies to the following:

(CFR: 41.7)

K2.01 CCW pumps ........................................................... 2.9 3.0

K2.02 CCW valves ............................................................ 2.9 2.9

K3. Knowledge of the effect that a loss or malfunction of 

the CCWS will have on the following:

(CFR: 41.7 / 45.6)

K3.01 Loads cooled by CCWS .................................................. 2.9 3.3

K4. Knowledge of CCWS design feature(s) and or interlocks 

which provide for the following:

(CFR: 41.7)

K4.01 Automatic start of standby pump ........................................... 3.4 3.9

K5. Knowledge of the operational implications of the following 

concepts as they apply to the CCWS:

(CFR: 41.5 / 45.3)

K5.01 Chemistry control ...................................................... 1.9 2.0
NUREG-1123, Rev. 2 3.8-14 |

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6 Knowledge of the effect that a loss or malfunction of 

the following will have on the CCWS:

(CFR: 41.7 / 45.7)

K6.01 Valves ................................................................ 2.7 2.8

K6.02 Sensors and detectors ................................................... 2.3 2.4

K6.03 Controllers and positioners ............................................... 2.4 2.6

K6.05 Pumps ................................................................ 3.0 3.1

K6.05 Motors ................................................................ 2.8 2.9

K6.06 Heat exchangers and condensers ........................................... 2.9 2.9

K6.07 Breakers, relays, and disconnects .......................................... 2.7 2.8

No. ABILITY

A1. Ability to predict and / or monitor changes in parameters .....................

associated with operating the CCWS controls including:

(CFR: 41.5 / 45.5)

A1.01 CCW flow rate ......................................................... 2.8 2.8

A1.02 CCW temperature ....................................................... 2.8 2.8

A1.03 CCW Pressure ......................................................... 2.7 2.7

A1.04 Surge Tank Level ....................................................... 2.8 2.8

A2. Ability to (a) predict the impacts of the following on the 

CCWS and (b) based on those predictions, use procedures to 

correct, control, or mitigate the consequences of those 

abnormal operation:

(CFR: 41.5 / 45.6)

A2.01 Loss of CCW pump ..................................................... 3.3 3.4

A2.02 High/low surge tank level ................................................ 2.8 3.0

A2.03 High/low CCW temperature .............................................. 2.9 3.0

A2.04 Radiation monitoring system alarm ........................................ 2.9 3.0

A3. Ability to monitor automatic operations of the CCWS including:

(CFR: 41.7 / 45.7)

A3.01 Setpoints on instrument signal levels for normal operations,

warnings, and trips that are applicable to the CCWS ........................... 3.0 3.0

A4. Ability to manually operate and / or monitor in the 

control room: 

(CFR: 41.7 / 45.5 to 45.8)

A4.01 CCW indications and control ............................................. 3.1 3.0
3.9-1 NUREG-1123, Rev. 2 |

3.9 Radioactivity Release page

239003 Main Steam Isolation Valve Leakage Control System 3.9-3

271000 Offgas System 3.9-7

288000 Plant Ventilation Systems 3.9-11

272000 Radiation Monitoring System 3.9-14

268000 Radwaste 3.9-18

290002 Reactor Vessel Internals 3.9-21

233000 Fuel Pool Cooling and Clean-up 3.9-24

261000 Standby Gas Treatment System 3.9-29

290003 Control Room Heating, Ventilation and Air Conditioning 3.9-33
NUREG-1123, Rev. 2 3.9-2 |

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3.9-3 NUREG-1123, Rev. 2 |

SYSTEM: 239003 MSIV Leakage Control System

TASK: Perform one train MSLCS inoperable surveillance

Perform main steam leakage control system operational test (write in

Perform one train main steam leakage control system operability surveillance (write in)

Perform monthly main steam leakage control system DIV 1 and DIV 2 fan and heater tests (write in)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between MSIV LEAKAGE CONTROL

SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Main steam system: BWR-4,5,6(P-Spec) .................................. 3.3 3.4

K1.02 Standby gas treatment system: BWR-4,5,6(P-Spec) ......................... 2.9 3.0 |

K1.03 Main steam line pressure instrumentation: BWR- |

4,5,6(P-Spec) .......................................................... 3.1 3.1

K1.04 A.C. electrical distribution: BWR-4,5,6(P-Spec) ............................ 2.7 2.8

K1.05 Steam tunnel: BWR-4,5,6(P-Spec) ....................................... 2.9 2.9

K1.06 Radwaste system: BWR-4,5,6(P-Spec) .................................... 2.4 2.4

K1.07 Floor drainage system: BWR-4,5,6(P-Spec) ................................ 1.9* 1.9*

K1.08 Nuclear boiler instrumentation: BWR-4,5,6(P-Spec) ........................ 2.8 2.8

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Motor operated valves: BWR-4,5,6(P-Spec) ............................... 2.3* 2.3*

K2.02 Leakage control system blowers: BWR-4,5,6(P-Spec) ....................... 1.9* 2.0*

K2.03 Leakage control system heaters: BWR-4.5,6(P-Spec) ........................ 1.9* 2.0*

K3. Knowledge of the effect that a loss or malfunction of

the MSIV LEAKAGE CONTROL SYSTEM will have on

following:

(CFR: 41.5 / 45.3)

K3.01 †Radiation release to the environment: BWR-4,5,6(PSpec) ................................................................. 3.3 4.0

K4. Knowledge of MSIV LEAKAGE CONTROL SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Performance of its safety function following a loss of

offsite power: BWR-4,5,6(P-Spec) ....................................... 3.2 3.5

K4.02 Performance of intended safety function following any

single active component failure: BWR-4,5,6(P-Spec) ........................ 3.0 3.4

K4.03 The prevention of inadvertent system operation: BWR4,5,6(P-Spec) .......................................................... 2.9 3.2
NUREG-1123, Rev. 2 3.9-4 |

SYSTEM: 239003 MSIV Leakage Control System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.04 Surveillance for system operability: BWR-4,5,6 ............................ 2.4 2.8

K4.05 Assurance that any MSIV leakage will pass through the

system and into standby gas treatment prior to release

to the atmosphere: BWR-4,5,6(P-Spec) ................................... 2.4* 2.8*

K4.06 The depressurization of main steam piping prior to

routing leakage through system: BWR-4,5,6 ................................ 3.1 3.3

K4.07 The reduction of MSIV leakage temperature: BWR4,5,6(P-Spec) .......................................................... 2.4 2.4

K4.08 Prevention of collected condensate in system bleed

lines: BWR-4,5,6(P-Spec) .............................................. 2.3 2.4

K4.09 The dilution of MSIV leakage: BWR-4,5,6(P-Spec) ......................... 2.4 2.4

K5. Knowledge of the operational implications of the

following concepts as they apply to MSIV LEAKAGE

CONTROL SYSTEM :

(CFR: 41.7 / 45.4)

| None

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the MSIV LEAKAGE CONTROL

SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical distribution: BWR-4,5,6(P-Spec) ............................ 2.8 3.0

K6.02 Standby gas treatment system: BWR-4,5,6(P-Spec) ......................... 2.8 3.0

K6.03 Nuclear boiler instrumentation: BWR-4,5,6(P-Spec) ........................ 2.6 2.9

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the MSIV LEAKAGE

CONTROL SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Main steam line pressure: BWR-4,5,6 ..................................... 3.1 3.1

A1.02 Heater operation: BWR-4,5,6(P-Spec) .................................... 2.6 2.6

A1.03 Dilution air flow: BWR-4,5,6(P-Spec) ..................................... 2.4 2.6

A1.04 Status indicating lights and alarms: BWR-4,5,6 .............................. 2.9 2.8

A1.05 System lineup: BWR-4,5,6 ............................................... 3.0 2.9

A1.06 MSIV leakage flow: BWR-4,5,6 .......................................... 2.6 2.6

A1.07 Reactor building temperature: BWR-4,5,6(P-Spec) .......................... 2.7 2.7
3.9-5 NUREG-1123, Rev. 2 |

SYSTEM: 239003 MSIV Leakage Control System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A2. Ability to (a) predict the impacts of the following on

the MSIV LEAKAGE CONTROL SYSTEM ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Inboard MSIV valve leakage: BWR-4,5,6 2.8 3.2

A2.02 Outboard MSIV valves leakage: BWR-4,5,6 ................................. 2.9 3.3

A2.03 Low dilution air flow (inboard and/or outboard):

BWR-4,5,6(P-Spec) ..................................................... 2.6 2.7

A2.04 Outboard system logic failure: BWR-4,5,6 .................................. 2.7 3.0

A2.05 Inboard system logic failure: BWR-4,5,6 ................................... 2.7 3.0

A2.06 Blower failure: BWR-4,5,6(P-Spec) ....................................... 2.6 2.6

A2.07 Heater failure: BWR-4,5,6(P-Spec) ........................................ 2.4 2.4

A2.08 Motor operator valve failure(s): BWR-4,5,6 ................................. 2.8 3.0

A2.09 Outboard main steamline high pressure: BWR-4,5,6(PSpec) .................................................................. 2.8 3.0

A2.10 A.C. distribution power failures: BWR-4,5,6 ................................ 2.8 3.0

A2.11 High reactor pressure: BWR-4,5,6 ......................................... 3.1 3.3

A2.12 MSIV valve failure to close: BWR-4,5,6 .................................... 3.5 3.8

A3. Ability to monitor automatic operations of the MSIV

LEAKAGE CONTROL SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 System logic initiation: BWR-4,5,6(P-Spec) ................................ 3.0 2.8

A3.02 Main steamline pressures: BWR-4,5,6 ..................................... 3.1 2.8

A3.03 Dilution air flaws: BWR-4,5,6(P-Spec) ..................................... 2.4 2.3

A3.04 MSIV leakage flows: BWR-4,5,6(P-Spec) .................................. 2.8 2.6

A3.05 Heater operation: BWR-4,5,6(P-Spec) ..................................... 2.3 2.2

A3.06 System status lights and alarms: BWR-4,5,6 ................................. 2.8 2.8

A3.07 System lineups: BWR-4,5,6 .............................................. 3.1 2.9

A3.08 Blower operation: BWR-4,5,6(P-Spec) ..................................... 2.4 2.3

A3.09 Reactor building temperature: BWR-4,5,6(P-Spec) ........................... 2.6 2.5

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Manually initiate system operation: BWR-4,5,6(P-Spec)

....................................................................... 3.2 3.2

A4.02 †Surveillance testing: BWR-4,5,6(P-Spec) .................................. 2.5 2.8

A4.03 Main steamline pressures: BWR-4,5,6 ..................................... 3.3 3.2

A4.04 Dilution air flows: BWR-4,5,6(P-Spec) .................................... 2.5 2.4

A4.05 MSIV leakage flows: BWR-4,5,6(P-Spec) .................................. 2.8 2.7

A4.06 Heater operation: BWR-4,5,6(P-Spec) ..................................... 2.4 2.3
NUREG-1123, Rev. 2 3.9-6 |

SYSTEM: 239003 MSIV Leakage Control System

Tasks as noted previously

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A4.07 System status lights and alarms: BWR-4,5,6(P-Spec) 2.8 2.7

A4.08 System lineups: BWR-4,5,6(P-Spec) 3.1 2.9

A4.09 System reset: BWR-4,5,6(P-Spec) 3.0 2.8
3.9-7 NUREG-1123, Rev. 2 |

SYSTEM: 271000 Offgas System

TASK: Conduct lineups on the offgas system 

Startup the offgas system 

Monitor the offgas system 

Operate the recombiner Operate 

XE-KR removal equipment 

Secure the offgas system 

Conduct offgas line isolation logic system functional test 

Conduct offgas system automatic isolation and closure test 

Conduct offgas process radiation monitor instrument functional test

Conduct steam jet air ejector offgas line isolation logic system functional test

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between OFFGAS SYSTEM and the

following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Condenser air removal system ............................................ 3.1 3.1

K1.02 Process radiation monitoring system ...................................... 3.1 3.3

K1.03 Elevated release point ................................................... 2.7 3.0

K1.04 Condensate system ..................................................... 2.7 2.7

K1.05 Radwaste system ....................................................... 2.3 2.5

K1.06 Main steam system ..................................................... 2.8 2.9

K1.07 Plant air systems ....................................................... 2.7 2.7

K1.08 Oxygen injection system: Plant-Specific ................................... 2.3 2.3

K1.09 Component cooling water systems ........................................ 2.6 2.6

K1.10 Condenser vacuum ...................................................... 3.2 3.3

K1.11 †Station radioactive release rate .......................................... 3.1 3.6

K1.12 A.C. electrical distribution ............................................... 2.3 2.4

K1.13 Process sampling system ................................................ 2.6 2.8

K1.14 Radwaste sparging air: Design-Specific .................................... 2.0* 2.5

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Glycol pumps .......................................................... 1.5* 1.5*

K3. Knowledge of the effect that a loss or malfunction of

the OFFGAS SYSTEM will have on following:

(CFR: 41.5 / 45.3)

K3.01 Condenser vacuum ...................................................... 3.5 3.5

K3.02 †Off-site radioactive release rate ......................................... 3.3 3.9
NUREG-1123, Rev. 2 3.9-8 |

SYSTEM: 271000 Offgas System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4. Knowledge of OFFGAS SYSTEM design feature(s) and/or

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Dilution of hydrogen gas concentration 2.9 3.3

K4.02 Prevention of the poisoning of the recombiner catalyst

by the presence of water 2.6 2.7

K4.03 Maintenance of sufficient oxygen gas inventory to

allow for complete hydrogen recombination: PlantSpecific 2.4 2.8

K4.04 The prevention of hydrogen explosions and/or fires 3.3 3.6

K4.05 Redundancy 2.6 2.6

K4.06 Decay of fission product gases to particulate

daughters 2.7 2.9

K4.07 Maximizing charcoal bed efficiency 2.6 2.7

K4.08 Automatic system isolation 3.1 3.3

K4.09 Filtration of radioactive particulate 2.8 3.1

K5. Knowledge of the operational implications of the

following concepts as they apply to OFFGAS SYSTEM :

(CFR: 41.7 / 45.4)

K5.01 Air operated valve operation .............................................. 2.3 2.3

K5.02 Heat removal mechanisms ............................................... 2.2 2.2

K5.03 Heat addition mechanisms ............................................... 2.2* 2.2

K5.04 Hydrogen concentration measurement ..................................... 2.9 3.1

K5.05 Oxygen concentration measurement ....................................... 2.8 2.9

K5.06 Catalytic recombination ................................................. 2.7 2.7

K5.07 Radioactive decay ...................................................... 2.7 2.9

K5.08 Charcoal absorption of fission product gases ................................ 2.5 2.6

K5.09 Hydrogen and oxygen recombination ...................................... 2.6 2.8

K5.10 Decontamination factors ................................................ 2.0* 2.3*

K5.11 Explain the necessity of reducing relative humidity

for carbon bed filters. ................................................... 2.6 2.8

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the OFFGAS SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 Plant air systems ....................................................... 2.7 2.8

K6.02 Process radiation monitoring system ...................................... 3.0 3.2

K6.03 Component cooling water systems ........................................ 2.4 2.4

K6.04 Dilution steam ......................................................... 2.8 2.8

K6.05 Heating steam: Design-Specific .......................................... 2.4 2.4

K6.06 Oxygen injection system: Plant-Specific ................................... 2.5 2.5

K6.07 A.C. electrical distribution ............................................... 2.4 2.5

K6.08 Condenser air removal system ............................................ 2.9 3.0
3.9-9 NUREG-1123, Rev. 2 |

SYSTEM: 271000 Offgas System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6.09 Fuel cladding integrity .................................................. 3.4 3.6

K6.10 Condensate system flow ................................................. 2.7 2.8

K6.11 Condenser vacuum ...................................................... 3.2 3.3

K6.12 Glycol system ......................................................... 2.1* 2.2*

K6.13 Plant exhaust: BWR-1 .................................................. 3.0 3.4

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the OFFGAS SYSTEM

controls including:

(CFR: 41.5 / 45.5)

A1.01 Condenser vacuum ...................................................... 3.3 3.2

A1.02 Station radioactive release rate ........................................... 3.0 3.6

A1.03 Preheater discharge temperature .......................................... 2.2* 2.3

A1.04 Recombiner catalyst temperature ......................................... 2.2* 2.4

A1.05 Cooler condenser discharge temperature ................................... 2.2* 2.4

A1.06 Filter differential pressure ............................................... 2.4* 2.5

A1.07 Charcoal bed humidity .................................................. 2.4* 2.5

A1.08 System flow ........................................................... 3.1 3.1

A1.09 Charcoal bed temperature ................................................ 2.1* 2.4

A1.10 Charcoal vault temperature ............................................... 2.3 2.5

A1.11 Offgas condenser temperatures ........................................... 2.3 2.4

A1.12 Process radiation monitoring indications ................................... 3.1 3.5

A1.13 Hydrogen gas concentration .............................................. 3.2 3.7

A1.14 Oxygen gas concentration ................................................ 2.7 3.0

A1.15 Steam supply pressures .................................................. 2.7 2.8

A2. Ability to (a) predict the impacts of the following on

the OFFGAS SYSTEM ; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 Low condenser vacuum .................................................. 3.1 3.3

A2.02 Low dilution steam flow ................................................. 2.9 3.1

A2.03 Main steamline high radiation ............................................ 3.5 3.8

A2.04 Offgas system high radiation ............................................. 3.7 4.1

A2.05 High charcoal bed humidity .............................................. 2.5 2.9

A2.06 Offgas system holdup volume explosion/ fire ............................... 3.5 3.9

A2.07 Low oxygen injection flow: Plant-Specific ................................. 2.7 3.3

A2.08 A.C. distribution failures ................................................ 2.5 2.7

A2.09 Valve closures ......................................................... 2.6 2.8

A2.10 Offgas system high flow ................................................. 3.1 3.3

A2.11 Offgas system low flow ................................................. 2.8 2.9
NUREG-1123, Rev. 2 3.9-10 |

SYSTEM: 271000 Offgas System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A2.12 Recombiner high temperature ............................................ 2.7 2.9

A2.13 Recombiner low temperature ............................................. 2.4 2.8

A2.14 Offgas filter high differential pressure ..................................... 2.6 2.8

A2.15 Air intrusion ........................................................... 2.7 2.9

A2.16 Loss of offgas system loop seals .......................................... 2.9 3.2

A2.17 Reactor power changes .................................................. 2.9 3.1

A3. Ability to monitor automatic operations of the OFFGAS

SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Automatic system isolations ............................................. 3.3 3.3

A3.02 System flows .......................................................... 2.9 2.8

A3.03 System temperatures .................................................... 2.8 2.8

A3.04 †Station radioactive release rate: Plant-Specific ............................ 3.0 3.8

A3.05 System indicating lights and alarms ........................................ 2.9 2.9

A3.06 System differential pressures ............................................. 2.5 2.5

A3.07 †Process radiation monitoring system indications ........................... 3.4 3.6

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Reset system isolations ................................................. 2.8 2.8

A4.02 System flows .......................................................... 2.9 2.9

A4.03 System temperatures .................................................... 2.8 2.8

A4.04 Condenser vacuum ...................................................... 3.4 3.5

A4.05 Station radioactive release rate ........................................... 3.2 3.9

A4.06 System indicating lights and alarms ........................................ 3.3 3.2

A4.07 System differential pressures ............................................. 2.4 2.5

A4.08 Process radiation monitoring system ...................................... 3.2 3.6

A4.09 Offgas system controls/components ....................................... 3.3 3.2
3.9-11 NUREG-1123, Rev. 2 |

SYSTEM: 288000 Plant Ventilation Systems

TASK: Shift ventilation lineups for various modes 

Place charcoal filters in service 

Remove charcoal filters from service 

Operate ventilation fans 

Operate air conditioning chiller units 

Operate ventilation heating units 

Monitor operation of heating, ventilation and air conditioning units

Perform main control room emergency fan and damper operability test (write in)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between PLANT VENTILATION SYSTEMS

and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 A.C. electrical ......................................................... 2.6 2.6

K1.02 Secondary containment .................................................. 3.4 3.4

K1.03 Standby gas treatment ................................................... 3.7 3.7

K1.04 Applicable component cooling water system: PlantSpecific .............................................................. 2.6 2.6

K1.05 Process radiation monitoring system ...................................... 3.3 3.6

K1.06 Plant air systems ....................................................... 2.7 2.7

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Reactor building supply and exhaust fans: PlantSpecific .............................................................. 2.4 2.4

K2.02 Auxiliary building supply and exhaust fans (turbine

building/ radwaste building): Plant-Specific ................................ 1.8* 1.9*

K3. Knowledge of the effect that a loss or malfunction of

the PLANT VENTILATION SYSTEMS will have on following:

(CFR: 41.5 / 45.3)

K3.01 Secondary containment temperature: Plant-Specific .......................... 2.8 3.0

K3.02 Reactor building temperature: Plant-Specific ............................... 2.9 3.1

K3.03 Auxiliary building temperature: Plant-Specific .............................. 2.5 2.5

K3.04 Secondary containment pressure: Plant-Specific ............................ 3.2 3.3

K3.05 Reactor building pressure: Plant-Specific .................................. 3.1 3.3

K3.06 Auxiliary building pressure: Plant-Specific ................................. 2.4* 2.4

K4. Knowledge of PLANT VENTILATION SYSTEMS design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Automatic initiation of standby gas treatment system ......................... 3.7 3.9
NUREG-1123, Rev. 2 3.9-12 |

SYSTEM: 288000 Plant Ventilation Systems

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.02 Secondary containment isolation .......................................... 3.7 3.8

K4.03 Automatic starting and stopping of fans .................................... 2.8 2.9

K5. Knowledge of the operational implications of the

following concepts as they apply to PLANT VENTILATION

SYSTEMS :

(CFR: 41.7 / 45.4)

K5.01 Airborne contamination control ........................................... 3.1 3.2

K5.02 Differential pressure control ............................................. 3.2 3.4

K5.03 Temperature control .................................................... 2.5 2.6

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the PLANT VENTILATION

SYSTEMS :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical ......................................................... 2.7 2.7

K6.02 Applicable component cooling water system: PlantSpecific .............................................................. 2.5 2.5

K6.03 Plant air systems ....................................................... 2.7 2.7

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the PLANT

VENTILATION SYSTEMS controls including:

(CFR: 41.5 / 45.5)

A1.01 Filter differential pressure ............................................... 2.2* 2.2*

A1.02 Fan differential pressure ................................................. 2.2* 2.2*

A1.03 Area temperatures ...................................................... 2.4 2.4

A2. Ability to (a) predict the impacts of the following on

the PLANT VENTILATION SYSTEMS ; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 High drywell pressure: Plant-Specific ..................................... 3.3 3.4

A2.02 Low reactor water level: Plant-Specific .................................... 3.4 3.6

A2.03 Loss of coolant accident: Plant-Specific ................................... 3.5 3.7

A2.04 High radiation: Plant-Specific ............................................ 3.7 3.8

A2.05 Extreme outside weather conditions: Plant-Specific ......................... 2.6 2.7
3.9-13 NUREG-1123, Rev. 2 |

SYSTEM: 288000 Plant Ventilation Systems

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A3. Ability to monitor automatic operations of the PLANT

VENTILATION SYSTEMS including:

(CFR: 41.7 / 45.7)

A3.01 Isolation/initiation signals ............................................... 3.8 3.8

A4. Ability to manually operate and/or monitor in the

control room:

A4.01 Start and stop fans ...................................................... 3.1 2.9

A4.02 Area temperature ....................................................... 2.8 2.8
NUREG-1123, Rev. 2 3.9-14 |

SYSTEM: 272000 Radiation Monitoring System

TASK: Perform lineups of the area radiation monitoring system

Operate area radiation monitors

Monitor area radiation

Perform lineups of process radiation monitoring system

Operate process radiation monitors

Monitor process radiation monitor operation

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between RADIATION MONITORING

SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Main steam system ..................................................... 3.6 3.8

K1.02 Offgas system (augmented offgas): Plant-Specific .......................... 3.2 3.5

K1.03 Stack gas: Plant-Specific ................................................ 3.3 3.6

K1.04 Applicable component cooling water system ................................ 2.9 2.9

| K1.05 Radwaste system ....................................................... 2.8 3.1

K1.06 Reactor building ventilation system: Plant-Specific .......................... 3.2 3.3

K1.07 Isolation condenser: Plant-Specific ....................................... 3.0 3.2

K1.08 Reactor protection system ............................................... 3.6 3.9

K1.09 Primary containment isolation system ..................................... 3.6 3.8

K1.10 Reactor building refuel floor: Plant-Specific ............................... 3.4 3.6

K1.11 Reactor building overhead crane; Plant-Specific ............................. 2.1* 2.4*

K1.12 Reactor building ........................................................ 3.1 3.2

K1.13 Turbine building ........................................................ 2.9 3.0

K1.14 Radwaste building: Plant-Specific ........................................ 2.7 2.8

K1.15 Filter building: Plant-Specific ............................................ 2.8 3.0

K1.16 Process computer ....................................................... 2.2* 2.3*

K1.17 SPDS/ERIS/CRIDS/GDS: Plant-Specific .................................. 2.4 2.7

K1.18 Primary containment/containment building: PlantSpecific .............................................................. 3.1 3.1

K1.19 Drywell ............................................................... 3.1 3.2

K1.20 †Auxiliary building: Plant-Specific ....................................... 2.8 3.0

K1.21 Circulating water: Plant-Specific ......................................... 2.3 2.4

K1.22 Fuel building: mark-III .................................................. 3.0 3.4

K1.23 Continuous air monitoring: Plant-Specific ................................. 3.0 3.3

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Main steamline radiation monitors ......................................... 2.5 2.8

K2.02 Offgas radiation monitoring system ........................................ 2.5 2.8

K2.03 Stack gas radiation monitoring system ..................................... 2.5 2.8

K2.04 Process liquid radiation monitoring system ................................. 2.3 2.5
3.9-15 NUREG-1123, Rev. 2 |

SYSTEM: 272000 Radiation Monitoring System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K2.05 Reactor building ventilation monitors: Plant-Specific

...................................................................... 2.6 2.9

K2.06 Area radiation monitors ................................................. 2.1* 2.2*

K2.07 Control room ventilation monitors: Plant-Specific .......................... 2.2* 2.4*

K3 Knowledge of the effect that a loss or malfunction of

the RADIATION MONITORING System will have on

following:

(CFR: 41.5 / 45.3)

K3.01 †Station liquid effluent release monitoring ................................. 3.2 3.8

K3.02 †Station gaseous effluent release monitoring ............................... 3.1 3.8

K3.03 Station area radiation monitoring .......................................... 3.2 3.4

K3.04 Main steam system ..................................................... 3.7 3.8

K3.05 Offgas system ......................................................... 3.5 3.7

K3.06 Reactor building ventilation: Plant-Specific ................................ 3.4 3.6

K3.07 Reactor building overhead crane operation: PlantSpecific .............................................................. 2.4* 3.0

K3.08 †Auxiliary building ventilation: Plant-Specific .............................. 2.9 3.3

K3.09 Radwaste building ventilation: Plant-Specific ............................... 2.8 3.1

K3.10 Control room ventilation: Plant-Specific .................................. 2.9 3.3

K4. Knowledge of RADIATION MONITORING System design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Redundancy ........................................................... 2.7 2.8

K4.02 Automatic actions to contain the radioactive release

in the event that the predetermined release rates are

exceeded .............................................................. 3.7 4.1

K4.03 Fail safe tripping of process radiation monitoring

logic during conditions of instrument failure ................................ 3.6 3.9

K5. Knowledge of the operational implications of the

following concepts as they apply to RADIATION

MONITORING SYSTEM :

(CFR: 41.7 / 45.4)

K5.01 Hydrogen injection operation's effect on process

radiation indications: Plant-Specific ...................................... 3.2 3.5
NUREG-1123, Rev. 2 3.9-16 |

SYSTEM: 272000 Radiation Monitoring System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6 Knowledge of the effect that a loss or malfunction of

the following will have on the RADIATION MONITORING

SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 Reactor protection system ............................................... 3.0 3.2

K6.02 D.C. power ............................................................ 2.5 2.7

K6.03 A.C. power ............................................................ 2.8 3.0

K6.04 Process computer ...................................................... 2.0* 2.2*

K6.05 SPDS/ERIS/CRID/GDS: Plant-Specific ................................... 2.1* 2.4*

K6.06 Continuous air monitoring: Plant-Specific ................................. 2.4 2.6

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the RADIATION

MONITORING SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Lights, alarms, and indications associated with normal

operations ............................................................. 3.2 3.2

A1.02 Lights, alarms, and indications associated with

surveillance testing ..................................................... 2.9 2.9

A2. Ability to (d) predict the impacts of the following on

the RADIATION MONITORING SYSTEM ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Fuel element failure .................................................... 3.7 4.1

A2.02 Reactor protection system power failure ................................... 3.3 3.6

A2.03 A.C. electrical failure ................................................... 2.9 3.1

A2.04 D.C. electrical failure ................................................... 2.7 2.8

A2.05 Loss of dilution steam .................................................. 2.5 2.6

A2.06 Downscale trips ........................................................ 2.8 2.9

A2.07 Hydrogen injection operation: Plant-Specific ............................... 2.6 2.8

A2.08 Offgas system failure ................................................... 2.9 3.1

A2.09 Low fuel pool level ..................................................... 3.1 3.3

A2.10 Loss of coolant accident ................................................. 3.9 4.1

A2.11 Leakage and/or breaks from contaminated systems to

atmosphere or to other process systems .................................... 3.4 3.7

A2.12 †Refuel floor handling accidents/operations ................................ 3.3 4.0

A2.13 Low reactor water level during refueling operations .......................... 3.3 3.8

A2.14 Loss of, or inadequate, shielding .......................................... 3.2 3.5

A2.15 Maintenance operations ................................................. 2.5 2.7
3.9-17 NUREG-1123, Rev. 2 |

SYSTEM: 272000 Radiation Monitoring System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A2.16 Instrument malfunctions ................................................. 2.7 2.9

A3. Ability to monitor automatic operations of the

RADIATION MONITORING SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Main steam isolation indications .......................................... 3.8 3.9

A3.02 Offgas system isolation indications ....................................... 3.6 3.7

A3.03 Liquid radwaste isolation indications ...................................... 3.1 3.5

A3.04 Radwaste handing interlocks ............................................. 2.3 2.8

A3.05 Refuel floor overhead crane operation interrupt:

Plant-Specific ......................................................... 3.0 3.1

A3.06 Ventilation system isolation indications .................................... 3.4 3.4 |

A3.07 Recorder indications .................................................... 2.8 2.9 |

A3.08 Meter indications ...................................................... 2.9 2.9

A3.09 Containment isolation indications ......................................... 3.6 3.5

A3.10 Lights and alarms ....................................................... 3.3 3.2

A3.11 Circulating water system blowdown isolations: PlantSpecific .............................................................. 2.6 2.7

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Recorder indications .................................................... 2.9 2.9

A4.02 Meter indications ...................................................... 3.0 3.0

A4.03 Power supply status indicators ............................................ 2.6 2.6 |

A4.04 SPDS/ERIS/CRID/GDS ................................................. 2.5* 2.7* |

A4.05 †Convert process radiation monitor readings to offsite

 release rates: Plant-Specific ............................................ 2.3* 3.7*

A4.06 †Manually trip process radiation monitor logic .............................. 2.9 3.2
NUREG-1123, Rev. 2 3.9-18 |

SYSTEM: 268000 Radwaste

TASK: Monitor the liquid radwaste system (write in)

Operate the discharge water floor drain system (write in)

Operate the drywell equipment drain pump (write in)

Monitor the liquid radwaste system (waste collection) (write in)

Startup a concentrator/evaporator

Secure a concentrator/evaporator

Perform lineups on the solid radwaste system

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between RADWASTE and the

following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Condensate system ...................................................... 2.2 2.6

K1.02 Plant air systems ........................................................ 2.1* 2.4

K1.03 Reactor building equipment drains: Plant-Specific ........................... 2.6 2.9

K1.04 Reactor building floor drains: Plant-Specific ................................ 2.7 2.9

K1.05 Drywell equipment drains ................................................ 2.9 3.2

K1.06 Drywell floor drains ..................................................... 2.9 3.2

K1.07 Reactor water cleanup ................................................... 2.8 2.9

K1.08 Fuel pool .............................................................. 2.7 2.8

K1.09 ECCS systems .......................................................... 2.6 2.8

K1.10 Auxiliary steam: Plant-Specific ........................................... 2.2 2.4

K1.11 Applicable component cooling water system ................................ 2.2 2.4

K1.12 Suppression pool ....................................................... 2.3 2.5

K1.13 Auxiliary building floor drains: Plant-Specific .............................. 2.2 2.4

K1.14 Auxiliary building equipment drains: Plant-Specific .......................... 2.0* 2.2

K1.15 Offgas system .......................................................... 2.3 2.5

K1.16 Circulating water system: Plant-Specific ................................... 2.3 2.5

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

| None

K3. Knowledge of the effect that a loss or malfunction of

the RADWASTE will have on following:

(CFR: 41.5 / 45.3)

K3.01 RWCU system ......................................................... 2.4 2.5

K3.02 Condensate system ...................................................... 2.2 2.4

K3.03 ECCS systems ......................................................... 2.2* 2.4

K3.04 Drain sumps ........................................................... 2.7 2.8

K3.05 Fuel pools: Plant-Specific ............................................... 2.1 2.4
3.9-19 NUREG-1123, Rev. 2 |

SYSTEM: 268000 Radwaste

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4. Knowledge of RADWASTE design feature(s) and/or

interlocks which provide for the following:

(CFR: 41.7)

None |

K5. Knowledge of the operational implications of the

following concepts as they apply to RADWASTE :

(CFR: 41.5 / 45.3)

K5.01 Units of radiation, dose and dose rate ...................................... 2.7 3.0

K5.02 Radiation hazards and ALARA concept ..................................... 3.1 3.6*

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the RADWASTE :

(CFR: 41.7)

K6.01 Applicable component cooling water system ................................ 2.2 2.5

K6.02 Plant air systems ........................................................ 2.3 2.6

K6.03 Building ventilation ..................................................... 2.4 2.7

K6.04 Circulating water ....................................................... 2.1* 2.3

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the RADWASTE

controls including:

(CFR: 41.5 / 45.5)

A1.01 Radiation level ......................................................... 2.7* 3.1*

A1.02 †Off-site release ....................................................... 2.6* 3.6*

A2. Ability to (a) predict the impacts of the following on

the RADWASTE ; and (b) based on those predictions, use

procedures to correct, control, or mitigate the

consequences of those abnormal conditions or

operations:

(CFR: 41.5 / 45.6)

A2.01 System rupture ......................................................... 2.9 3.5

A2.02 High turbidity water ..................................................... 2.3 2.7

A2.03 Loss of steam supply .................................................... 2.0* 2.3

SYSTEM: 268000 Radwaste
NUREG-1123, Rev. 2 3.9-20 |

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A3. Ability to monitor automatic operations of the

RADWASTE including:

(CFR: 41.7 / 45.7)

| None

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Sump integrators ........................................................ 3.4 3.6
3.9-21 NUREG-1123, Rev. 2 |

SYSTEM: 290002 Reactor Vessel Internals

TASK: Perform heatup/cooldown of reactor vessel

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between REACTOR VESSEL INTERNALS

and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Main steam system ...................................................... 3.2 3.2

K1.02 Recirculation system .................................................... 3.2 3.2

K1.03 Reactor feedwater system ................................................ 3.2 3.2

K1.04 HPCI: Plant-Specific ................................................... 3.4 3.5

K1.05 RHR: Plant-Specific .................................................... 3.1 3.2

K1.06 HPCS: Plant-Specific ................................................... 3.1 3.1

K1.07 Isolation condenser: Plant-Specific ....................................... 3.4 3.4

K1.08 RCIC: Plant-Specific ................................................... 3.1 3.1

K1.09 LPCI: Plant-Specific .................................................... 3.2 3.3

K1.10 CRD hydraulic system ................................................... 3.1 3.1

K1.11 CRD mechanism ........................................................ 2.9 2.9

K1.12 SBLC ................................................................. 3.4 3.5

K1.13 Relief/safety valves ..................................................... 3.4 3.5

K1.14 RWCU ................................................................ 2.9 3.1

K1.15 Nuclear boiler instrumentation ............................................ 3.4 3.5

K1.16 LPCS ................................................................. 3.2 3.4

K1.17 ADS .................................................................. 3.3 3.4

K1.18 Loss parts monitoring: Plant-Specific ..................................... 2.1* 2.2*

K1.19 TIP ................................................................... 2.5 2.6

K1.20 Nuclear instrumentation ................................................. 3.2 3.3

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

None |

K3. Knowledge of the effect that a loss or malfunction of

the REACTOR VESSEL INTERNALS will have on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level ...................................................... 3.2 3.3

K3.02 Reactor pressure ....................................................... 2.9 3.0

K3.03 Reactor power .......................................................... 3.3 3.4

K3.04 Plant radiation levels .................................................... 2.9 3.2

K3.05 Off-site radiation levels .................................................. 2.9 3.2

K3.06 PCIS/NSSSS ........................................................... 3.1 3.1

K3.07 Nuclear boiler instrumentation ............................................ 3.1 3.1
NUREG-1123, Rev. 2 3.9-22 |

SYSTEM: 290002 Reactor Vessel Internals

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4. Knowledge of REACTOR VESSEL INTERNALS design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 2/3 core coverage following a DBA LOCA ................................... 3.7 3.9

K4.02 Separation of fluid flow paths within the vessel ............................... 3.1 3.2

K4.03 Core orificing ........................................................... 3.2 3.3

K4.04 Moisture removal from generated steam ..................................... 2.8 2.8

K4.05 Natural circulation ....................................................... 3.3 3.5

K5. Knowledge of the operational implications of the

following concepts as they apply to REACTOR VESSEL

INTERNALS :

(CFR: 41.5 / 45.3)

K5.01 †Thermal limits ........................................................ 3.5 3.9

K5.02 Fission product poisons .................................................. 2.9 3.1

K5.03 Burnable poisons ....................................................... 2.7 3.0

K5.04 †PCIOMR Plant-Specific ................................................ 3.1 3.7

K5.05 Brittle fracture ......................................................... 3.1 3.3

K5.06 Heat transfer mechanisms ................................................ 2.8 3.2

K5.07 †Safety limits .......................................................... 3.9 4.4*

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the REACTOR VESSEL

INTERNALS :

(CFR: 41.7 / 45.7)

K6.01 CRD hydraulic system ................................................... 2.8 2.9

K6.02 CRD mechanism ........................................................ 2.9 2.9

K6.03 Recirculation system .................................................... 3.1 3.2

K6.04 Reactor feedwater system ................................................ 3.0 3.1

K6.05 SBLC ................................................................. 3.3 3.4

K6.06 Relief/safety valves ..................................................... 3.0 3.2

K6.07 RWCU ................................................................ 2.6 2.7

K6.08 Nuclear boiler instrumentation ............................................ 2.9 3.2

K6.09 LPCS ................................................................. 3.2 3.3

K6.10 HPCI: Plant-Specific ................................................... 3.0 3.3

K6.11 RHR: Plant-Specific .................................................... 3.1 3.2

K6.12 Isolation condenser: Plant-Specific ....................................... 3.0 3.2

K6.13 RCIC: Plant-Specific ................................................... 2.7 2.8

K6.14 LPCI: Plant-Specific .................................................... 3.1 3.3

K6.15 ADS .................................................................. 3.1 3.4

K6.16 Loss parts monitoring ................................................... 2.0* 2.0*

K6.17 TIP ................................................................... 2.5 2.5
3.9-23 NUREG-1123, Rev. 2 |

SYSTEM: 290002 Reactor Vessel Internals

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K6.18 Nuclear instrumentation ................................................. 3.0 3.1

K6.19 HPCS: Plant-Specific(BWR-5&6) ........................................ 3.0 3.1

K6.20 Main steam system ...................................................... 2.9 3.1

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the REACTOR

VESSEL INTERNALS controls including:

(CFR: 41.5 / 45.5)

None |

A2. Ability to (a) predict the impacts of the following on

the REACTOR VESSEL INTERNALS ; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 LOCA ................................................................. 3.7 4.0

A2.02 †Overpressurization transient ............................................. 3.6 3.9

A2.03 †Control rod drop accident ............................................... 3.6 3.9

A2.04 Excessive heatup/cooldown rate ........................................... 3.7 4.1

A2.05 †Exceeding thermal limits ................................................ 3.7 4.2

A2.06 †Exceeding safety limits ................................................. 4.0 4.5*

A3. Ability to monitor automatic operations of the REACTOR

VESSEL INTERNALS including:

(CFR: 41.7 / 45.7)

None |

|

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

None |
NUREG-1123, Rev. 2 3.9-24 |

SYSTEM: 233000 Fuel Pool Cooling and Clean-up

TASK: Lineup residual heat removal supplemental fuel pool cooling 

Monitor residual heat removal supplemental fuel pool cooling 

Startup the torus/suppression pool cleanup system (write in) 

Stop residual heat removal supplemental fuel pool cooling 

Shutdown the torus/suppression pool cleanup system (write in) 

Monitor RHR supplemental fuel pool cooling (write in) 

Perform lineups on spent fuel pool cooling system 

Fill the spent fuel pools 

Startup the spent fuel pool cooling system in different pump/heat exchanger combinations 

Perform spent fuel pool purification using filter 

Perform spent fuel pool purification using demineralizer 

Backwash spent fuel pool filter 

Change spent fuel pool filter 

Replace resin in spent fuel pool demineralizer 

Operate system between refueling pool and spent fuel pool in different lineups 

Operate the spent fuel pool skimmer loop 

Monitor spent fuel pool cooling system operation 

Perform borated water storage tank purification using filter 

Perform borated water storage tank purification using demineralizer

Recirculate the spent fuel pool 

Lower refueling pool level 

Fill and vent the spent fuel pool purification system 

Perform spent fuel pool leakage test 

Fill the fuel transfer canal 

Drain the fuel transfer canal 

Perform fuel transfer canal purification 

Recirculate fuel transfer canal 

Perform decay heat removal using the spent fuel cooling system 

Shutdown the spent fuel pool cooling system 

Fill the dryer-separator pit 

Drain the dryer-separator pit 

Conduct nitrogen mixing of spent fuel pool cooling demineralizer resin

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between FUEL POOL COOLING AND

CLEAN-UP and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Shutdown cooling system: Plant-Specific .................................. 2.6 2.9

K1.02 Residual heat removal system: Plant-Specific ............................... 2.9 3.0

K1.03 Condensate storage tank ................................................. 2.3 2.3

K1.04 Process sampling system ................................................. 2.0* 2.0*
3.9-25 NUREG-1123, Rev. 2 |

SYSTEM: 233000 Fuel Pool Cooling and Clean-up

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.05 Plant air systems ........................................................ 2.2 2.2

K1.06 A.C. electrical power .................................................... 2.3 2.3

K1.07 Condensate system: Plant-Specific ........................................ 2.1 2.2

K1.08 Condensate transfer ..................................................... 2.5 2.5

K1.09 Component cooling water systems ......................................... 2.6 2.6

K1.10 Containment drainage system: Plant-Specific ............................... 2.2 2.3

K1.11 Reactor building drainage system: Plant-Specific ............................ 2.3 2.4

K1.12 Radwaste system ........................................................ 2.5 2.6

K1.13 Suppression pool cleanup system: Plant-Specific ............................ 2.3 2.6

K1.14 Reactor building ventilation .............................................. 2.5 2.5

K1.15 Storage pools .......................................................... 2.9 2.9

K1.16 Emergency cooling water systems: Plant-Specific ........................... 2.7 2.8

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Fuel pool cooling pumps ................................................. 2.1* 2.2*

K2.02 RHR pumps ............................................................ 2.8* 2.9*

K3. Knowledge of the effect that a loss or malfunction of

the FUEL POOL COOLING AND CLEAN-UP will have on

following:

(CFR: 41.7 /45.6)

K3.01 Fuel pool temperature ................................................... 3.2 3.4

K3.02 Fuel pool water level .................................................... 3.1 3.2

K3.03 Fuel pool water clarity ................................................... 2.6 2.8

K3.04 Fuel pool water chemistry ................................................ 2.4* 2.6

K3.05 Fuel pool water fission product concentration ............................... 2.6 2.8

K3.06 Area radiation levels ..................................................... 2.9 3.2

K3.07 Suppression pool chemistry: Plant-Specific ................................ 2.3 2.9

K3.08 †Refueling operations ................................................... 2.9 3.5

K4. Knowledge of FUEL POOL COOLING AND CLEAN-UP design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Redundancy ............................................................ 2.4 2.6

K4.02 Pool clarity ............................................................ 2.4 2.6

K4.03 Maintenance of adequate pool temperature .................................. 2.8 3.1

K4.04 Overpressure protection for fuel pool cooling system

filter .................................................................. 2.0* 2.1

K4.05 Net positive suction head requirements for fuel pool

cooling pumps .......................................................... 2.1* 2.2*

K4.06 Maintenance of adequate pool level ........................................ 2.9 3.2
NUREG-1123, Rev. 2 3.9-26 |

SYSTEM: 233000 Fuel Pool Cooling and Clean-up

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K4.07 Supplemental heat removal capability ...................................... 2.7 2.9

K4.08 Pool cooling during loss of coolant accident: BWR-6 ........................ 2.6* 2.8

K4.09 Maintenance of filter/demineralizer precoat during low

flow conditions ......................................................... 2.1* 2.4*

K5. Knowledge of the operational implications of the

following concepts as they apply to FUEL POOL COOLING

AND CLEAN-UP :

(CFR: 41.5 / 45.3)

K5.01 Heat removal mechanisms ................................................ 2.5 2.7

K5.02 Pump cavitation ........................................................ 2.1* 2.2*

K5.03 Spent fuel decay heat generation ........................................... 2.6 2.8

K5.04 Demineralizer ion exchange .............................................. 2.0* 2.2*

K5.05 Mechanical filtration operation ........................................... 2.1* 2.2*

K5.06 Maximum normal heat load ............................................... 2.5 2.7

K5.07 Maximum (abnormal) heat 102d ........................................... 2.5 2.8

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the FUEL POOL COOLING AND

CLEAN-UP :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical power .................................................... 2.5 2.7

K6.02 Shutdown cooling system: Plant-Specific .................................. 2.2* 2.5*

K6.03 Residual heat removal: Plant-Specific ..................................... 2.3 2.7

K6.04 Condensate transfer ..................................................... 2.5 2.6

K6.05 Condensate system ...................................................... 2.1* 2.3

K6.06 Condensate storage tanks ................................................. 2.4 2.4

K6.07 Component cooling water systems ......................................... 2.7 2.8

K6.08 Plant air systems ....................................................... 2.4 2.4

K6.09 Radwaste system ........................................................ 2.2 2.4

K6.10 Reactor cavity seal failure ................................................ 2.9 3.3

K6.11 NSSSS/PCIS: Plant-Specific ............................................. 2.3 2.6*

ABILITY

Al. Ability to predict and/or monitor changes in

parameters associated with operating the FUEL POOL

COOLING AND CLEAN-UP controls including:

(CFR: 41.5 / 45.5)

A1.01 Surge tank level ........................................................ 2.6 2.9

Al.02 Pool level ............................................................. 2.9 3.1

Al.03 Pool temperature ....................................................... 3.1 3.3

Al.04 Pump discharge pressure ................................................. 2.4 2.5

| Al.05 Filter/ demineralize differential pressure ................................... 2.4* 2.3*
3.9-27 NUREG-1123, Rev. 2 |

SYSTEM: 233000 Fuel Pool Cooling and Clean-up

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

Al.06 System flow ........................................................... 2.5 2.4

Al.07 System temperature ..................................................... 2.7 2.8

Al.08 Pool chemistry ......................................................... 2.1* 2.4* |

Al.09 Pool clarity ............................................................ 2.4 2.6

A1.10 Pool activity levels ...................................................... 2.4 2.6*

A1.11 Suppression pool chemistry: BWR-6 ...................................... 2.4 2.9

A2. Ability to (a) predict the impacts of the following on

the FUEL POOL COOLING AND CLEAN-UP ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 High pool level ......................................................... 2.7 2.9

A2.02 Low pool level ......................................................... 3.1 3.3

A2.03 Low surge tank level/high level ............................................ 2.8 3.0

A2.04 Pump trip .............................................................. 2.6 2.7

A2.05 Valve closures .......................................................... 2.5 2.5

A2.06 Valve openings ......................................................... 2.5 2.5

A2.07 High fuel pool temperature ............................................... 3.0 3.2

A2.08 Closed cooling water failure .............................................. 2.9 3.1

A2.09 A.C. electrical power failures ............................................. 2.7 2.9

A2.10 Refueling bellows seal high flow .......................................... 2.9 3.3

A2.11 Fuel pool gate seal high flow.............................................. 2.9 3.2

A2.12 High filter/ demineralizer differential pressure .............................. 2.4* 2.4

A2.13 Low filter/ demineralizer differential pressure ............................... 2.2* 2.2* |

A2.14 Low system flow ....................................................... 2.3 2.3

A2.15 High system temperature ................................................. 2.8 2.9

A2.16 Loss of coolant accident signal ........................................... 2.5 2.8

A2.17 Fuel transfer tube drain tank high level/low level:

BWR-6 ............................................................... 2.8 2.8 |

A2.18 Low pool clarity ........................................................ 2.5 2.7

A2.19 Inadequate system/pool chemistry ......................................... 2.5 2.8

A3. Ability to monitor automatic operations of the FUEL

POOL COOLING AND CLEAN-UP including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation ......................................................... 2.4 2.5

A3.02 Pump trip(s) ........................................................... 2.6 2.6

A3.03 System indicating lights and alarms ........................................ 2.6 2.6
NUREG-1123, Rev. 2 3.9-28 |

SYSTEM: 233000 Fuel Pool Cooling and Clean-up

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 System lights and alarms ................................................. 2.6 2.6

A4.02 System lineups ......................................................... 2.3 2.5

A4.03 System flow ........................................................... 2.2 2.4

A4.04 Pool level ............................................................. 2.9* 3.1

A4.05 Pool temperature ....................................................... 2.7* 3.1*

A4.06 System temperature ..................................................... 2.5* 2.6*

A4.07 System pressures ....................................................... 2.2* 2.3*

A4.08 System differential pressures ............................................. 2.2* 2.2*

A4.09 Pump operation ......................................................... 2.2* 2.2*

A4.10 Tank levels ............................................................. 2.5 2.6

A4.11 Closed cooling water temperature ......................................... 2.5 2.5
3.9-29 NUREG-1123, Rev. 2 |

SYSTEM: 261000 Standby Gas Treatment System

TASK: Perform lineups on the standby gas treatment system

Place the standby gas treatment system in standby readiness

Place the standby gas treatment system in service manually

Monitor the standby gas treatment system following automatic initiation

Remove one standby gas treatment (SGTS) train from service after automatic initiation

Secure the standby gas treatment system (SGTS)

Perform standby gas treatment manual bypass valve operation, and simulated auto act test

Perform standby gas treatment system logic system functional test

Perform one circuit of standby gas treatment system inoperable test

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between STANDBY GAS TREATMENT

SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor building ventilation system ........................................ 3.4 3.6

K1.02 Drywell ............................................................... 3.2 3.4

K1.03 Suppression pool ....................................................... 2.9 3.1

K1.04 High radiation sampling system ........................................... 2.5 2.8

K1.05 Radwaste system: Plant-Specific .......................................... 2.3 2.4

K1.06 High pressure coolant injection system: PlantSpecific ............................................................... 3.0 3.1

K1.07 Elevated release stack ................................................... 3.1 3.2

K1.08 Process radiation monitoring system ....................................... 2.8 3.1

K1.09 Primary containment isolation system ...................................... 3.2 3.4

K1.10 Plant air systems ........................................................ 2.2* 2.3

K1.11 Primary containment pressure ............................................ 3.2 3.3

K1.12 Primary containment purge system: Plant-Specific ........................... 3.1 3.2

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Fan power ............................................................. 2.1* 2.3*

K2.02 Valve power ............................................................ 1.9* 2.0*

K2.03 Initiation logic ......................................................... 2.3* 2.5*

K2.04 Heater power ........................................................... 1.7* 1.9*

K3. Knowledge of the effect that a loss or malfunction of

the STANDBY GAS TREATMENT SYSTEM will have on

following:

(CFR: 41.7 /45.6)

K3.01 Secondary containment and environment differential

pressure .............................................................. 3.3 3.6

K3.02 Off-site release rate ..................................................... 3.6 3.9
NUREG-1123, Rev. 2 3.9-30 |

SYSTEM: 261000 Standby Gas Treatment System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K3.03 Primary containment pressure: Mark-I&II .................................. 3.2 3.4

K3.04 High pressure coolant injection system: PlantSpecific ............................................................... 3.1 3.1

| K3.05 Secondary containment radiation/ contamination levels ....................... 3.2 3.5

| K3.06 Primary containment oxygen content: Mark-I&II ............................ 3.0 3.3

K4. Knowledge of STANDBY GAS TREATMENT SYSTEM design

feature(s) and/or interlocks which provide for the

following:

(CFR: 41.7)

K4.01 Automatic system initiation .............................................. 3.7 3.8

K4.02 Charcoal bed decay heat removal .......................................... 2.6 2.8

K4.03 Moisture removal ....................................................... 2.5 2.7

K4.04 Radioactive particulate filtration .......................................... 2.7 2.9

K4.05 Fission product gas removal .............................................. 2.6 2.8

K4.06 Charcoal bed retention ................................................... 2.4* 2.6

K5. Knowledge of the operational implications of the

following concepts as they apply to STANDBY GAS

TREATMENT SYSTEM :

(CFR: 41.5 / 45.3)

K5.01 Heat removal mechanisms ................................................ 2.3* 2.6*

K5.02 Air operated valves: Plant-Specific ........................................ 2.3* 2.5*

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the STANDBY GAS TREATMENT

SYSTEM :

(CFR: 41.7 / 45.7)

K6.01 A.C. electrical distribution ............................................... 2.9 3.0

K6.02 D.C. electrical distribution ............................................... 2.4* 2.6*

K6.03 Emergency diesel generator system ........................................ 3.0 3.1

K6.04 Process radiation monitoring ............................................. 2.9 3.1

K6.05 Reactor protection system: Plant-Specific .................................. 3.1 3.2

K6.06 Plant air systems ........................................................ 2.4 2.6

K6.07 Primary containment atmosphere sampling system:

Plant-Specific .......................................................... 2.2* 2.4

K6.08 Reactor vessel level: Plant-Specific ....................................... 3.1 3.1

K6.09 Primary containment high pressure: Plant-Specific .......................... 3.1 3.3
3.9-31 NUREG-1123, Rev. 2 |

SYSTEM: 261000 Standby Gas Treatment System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the STANDBY GAS

TREATMENT SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 System flow ........................................................... 2.9 3.1

A1.02 Primary containment pressure ............................................ 3.1 3.2

A1.03 †Off-site release levels .................................................. 3.2 3.8

A1.04 Secondary containment differential pressure ................................ 3.0 3.3

A1.05 Primary containment oxygen level: Mark-I&II ............................... 2.7* 2.9*

A1.06 Drywell and suppression chamber differential pressure:

Mark-I ................................................................ 2.7 3.0

A1.07 SBGTS train temperature ................................................. 2.8 2.9

A2. Ability to (a) predict the impacts of the following on

the STANDBY GAS TREATMENT SYSTEM ; and (b) based on

those predictions, use procedures to correct, control,

or mitigate the consequences of those abnormal

conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Low system flow ....................................................... 2.9 3.1

A2.02 High system flow ....................................................... 2.9 3.1

A2.03 High train temperature ................................................... 2.9 3.2

A2.04 High train moisture content ............................................... 2.5 2.7

A2.05 Fan trips ............................................................... 3.0 3.1

A2.06 Valve closures .......................................................... 2.9* 2.9*

A2.07 A.C. electrical failure ................................................... 2.7* 2.8

A2.08 D.C. electrical failure ................................................... 2.4* 2.7*

A2.09 Plant air system failure .................................................. 2.4* 2.6*

A2.10 Low reactor water level: Plant-Specific .................................... 3.1 3.2

A2.11 High containment pressure ............................................... 3.2 3.3

A2.12 High fuel pool ventilation radiation: Plant-Specific. .......................... 3.2 3.4

A2.13 High secondary containment ventilation exhaust

radiation ............................................................... 3.4 3.7

A2.14 High system pressure: Plant-Specific ...................................... 3.0 3.2

A2.15 High area radiation by refuel bridge: Plant-Specific. .......................... 3.0 3.4

A3. Ability to monitor automatic operations of the STANDBY

GAS TREATMENT SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 System flow ........................................................... 3.2 3.3

A3.02 Fan start ............................................................... 3.2 3.1
NUREG-1123, Rev. 2 3.9-32 |

SYSTEM: 261000 Standby Gas Treatment System

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A3.03 Valve operation ......................................................... 3.0 2.9

A3.04 System temperature ..................................................... 3.0 3.1

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 †Off-site release levels: Plant-Specific .................................... 3.2* 4.0*

A4.02 Suction valves .......................................................... 3.1 3.1

A4.03 Fan ................................................................... 3.0 3.0

A4.04 Primary containment pressure ............................................ 3.3 3.4

A4.05 Drywell to suppression chamber/torus differential

pressure: Mark-I,II ...................................................... 2.9 3.2

A4.06 Reactor building differential pressure ...................................... 3.3 3.6

A4.07 System flow ........................................................... 3.1 3.2

A4.08 System temperature ..................................................... 2.6 2.7

A4.09 Ventilation valves/dampers ............................................... 2.7 2.7
3.9-33 NUREG-1123, Rev. 2 |

SYSTEM: 290003 Control Room HVAC

TASK: Perform system lineups

Place system in standby operating mode

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1. Knowledge of the physical connections and/or causeeffect relationships between CONTROL ROOM HVAC and the

following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Radiation monitors ...................................................... 3.4 3.5

K1.02 Chlorine amonia detectors: Plant-Specific .................................. 2.9 3.1

K1.03 Remote air intakes: Plant-Specific ........................................ 2.8 2.9

K1.04 Nuclear steam supply shut off system (NSSSS/PCIS):

Plant-Specific .......................................................... 3.2 3.3

K1.05 Component cooling water systems ......................................... 2.8 3.0

K1.06 Plant air systems ........................................................ 2.6 2.7

K1.07 Fire protection ......................................................... 2.9 3.0

K2. Knowledge of electrical power supplies to the

following:

(CFR: 41.7)

K2.01 Fans .................................................................. 2.2* 2.4*

K2.02 Chiller units ........................................................... 2.4* 2.4*

K2.03 Motor operated valves: Plant-Specific ..................................... 1.9* 2.0*

K3. Knowledge of the effect that a loss or malfunction of

the CONTROL ROOM HVAC will have on following:

(CFR: 41.7 /45.6)

K3.01 Control room habitability ................................................ 3.5 3.8

K3.02 Computer/instrumentation: Plant-Specific .................................. 3.3 3.6

K3.03 Control room temperature ................................................ 2.9 3.1

K3.04 Control room pressure ................................................... 2.8* 2.9

K4. Knowledge of CONTROL ROOM HVAC design feature(s)

and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 System initiations/reconfiguration: Plant-Specific ........................... 3.1 3.2

K4.02 Control room temperatures ............................................... 2.4* 2.6

K5. Knowledge of the operational implications of the

following concepts as they apply to CONTROL ROOM HVAC

(CFR: 41.5 / 45.3)

K5.01 Airborne contamination (e.g., radiological, toxic gas,

smoke) control ......................................................... 3.2 3.5

K5.02 Differential pressure control ............................................. 2.8 2.8
NUREG-1123, Rev. 2 3.9-34 |

SYSTEM: 290003 Control Room HVAC

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K5.03 Temperature control ..................................................... 2.6 2.7

K6. Knowledge of the effect that a loss or malfunction of

the following will have on the CONTROL ROOM HVAC :

(CFR: 41.7 / 45.7)

K6.01 Electrical power ........................................................ 2.7 2.9

K6.02 Component cooling water systems ......................................... 2.7 2.9

K6.03 Plant air systems ........................................................ 2.4 2.6

K6.04 Fire protection: Plant-Specific ........................................... 2.6 2.8

ABILITY

A1. Ability to predict and/or monitor changes in

parameters associated with operating the CONTROL ROOM

HVAC controls including:

(CFR: 41.5 / 45.5)

A1.01 Filter differential pressure ............................................... 2.1* 2.1*

A1.02 Fan differential pressure ................................................. 2.1* 2.1*

Al.03 Area temperatures ...................................................... 2.6 2.6

A1.04 Control room pressure ................................................... 2.5 2.8

A1.05 Radiation monitoring (control room) ....................................... 3.2 3.3

A2. Ability to (a) predict the impacts of the following on

the CONTROL ROOM HVAC ; and (b) based on those

predictions, use procedures to correct, control, or

mitigate the consequences of those abnormal conditions

or operations:

(CFR: 41.5 / 45.6)

A2.01 Initiation/reconfiguration ................................................ 3.1 3.2

A2.02 Extreme environmental conditions ......................................... 3.1 3.4

A2.03 Initiation/reconfiguration failure .......................................... 3.4 3.6

A2.04 Initiation/failure of fire protection system .................................. 3.1 3.3

A3. Ability to monitor automatic operations of the CONTROL

ROOM HVAC including:

(CFR: 41.7 / 45.7)

A3.01 Initiation/reconfiguration ................................................ 3.3 3.5

A3.02 Initiation/failure of fire protection system .................................. 3.0 3.4
3.9-35 NUREG-1123, Rev. 2 |

SYSTEM: 290003 Control Room HVAC

Tasks as noted previously

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

A4. Ability to manually operate and/or monitor in the

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Initiate/reset system ..................................................... 3.2 3.2

A4.02 Fans .................................................................. 2.8 2.8

A4.03 Reposition dampers ..................................................... 2.8 2.8

A4.04 Environmental conditions ................................................ 2.8 3.0
4.1-1 NUREG-1123, Rev. 2 |

4.1 Emergency Plant Evolutions page

295024 High Drywell Pressure 4.1-3

295025 High Reactor Pressure 4.1-5

295026 Suppression Pool High Water Temperature 4.1-7

295027 High Containment Temperature (Mark III Containment Only) 4.1-8

295028 High Drywell Temperature 4.1-9

295029 High Suppression Pool Water Level 4.1-11

295030 Low Suppression Pool Water Level 4.1-12

295031 Reactor Low Water Level 4.1-14

295032 High Secondary Containment Area Temperature 4.1-16

295033 High Secondary Containment Area Radiation Levels 4.1-18

295034 Secondary Containment Ventilation High Radiation 4.1-20

295035 Secondary Containment High Differential Pressure 4.1-22

295036 Secondary Containment High Sump / Area Water Level 4.1-23

295037 SCRAM Condition Present and Reactor Power Above APRM 4.1-24

Downscale or unknown

295038 High Off-Site Release Rate 4.1-26

500000 High Containment Hydrogen Concentration 4.1-28
NUREG-1123, Rev. 2 4.1-2 |

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4.1-3 NUREG-1123, Rev. 2 |

EPE: 295024 High Drywell Pressure

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK1. Knowledge of the operational implications of the

following concepts as they apply to HIGH DRYWELL

PRESSURE :

(CFR: 41.8 to 41.10)

EK1.01 Drywell integrity: Plant-Specific.................... 4.1 4.2*

EK1.02 Containment building integrity: Mark-III............. 3.9 4.1

EK2. Knowledge of the interrelations between HIGH DRYWELL

PRESSURE and the following:

(CFR: 41.7 / 45.8) 

EK2.01 HPCI (FWCI): Plant-Specific.......................... 3.9 4.0

EK2.02 HPCS: Plant-Specific................................. 3.7 3.7

EK2.03 LPCS: Plant-Specific................................. 3.8 3.8

EK2.04 RHR/LPCI.............................................. 3.9 3.9

EK2.05 RPS................................................... 3.9 4.0

EK2.06 Emergency generators.................................. 3.9 4.0

EK2.07 PCIS/NSSSS............................................ 3.9 3.9

EK2.08 ADS: Plant-Specific.................................. 4.0 4.1

EK2.09 Suppression pool makeup: Plant-Specific.............. 2.9 3.1

EK2.10 A.C. distribution..................................... 3.5 3.5

EK2.11 Drywell spray (RHR) logic: Mark-I&II................. 4.2 4.2*

EK2.12 Suppression pool cooling.............................. 3.5 3.5

EK2.13 Suppression pool spray: Plant-Specific............... 3.8 3.8

EK2.14 Containment pressure: Mark-III....................... 3.9 3.9

EK2.15 Containment spray logic: Plant-Specific.............. 3.8 3.9

EK2.16 SPDS/ERIS/CRIDS: Plant-Specific...................... 3.2 3.2

EK2.17 Auxiliary building isolation logic: Plant-Specific... 3.0 3.3

EK2.18 Ventilation........................................... 3.3 3.4

EK2.19 Feedwater and condensate: Plant-Specific............. 2.9 2.9

EK2.20 D.C. distribution: Plant-Specific.................... 2.8 2.9

EK3. Knowledge of the reasons for the following responses

as they apply to HIGH DRYWELL PRESSURE :

(CFR: 41.5 / 45.6)

EK3.01 Drywell spray operation: Mark-I&II................... 3.6 4.0

EK3.02 Suppression pool spray operation: Plant-Specific..... 3.5 3.8

EK3.03 Containment venting: Mark-III........................ 3.6 4.1

EK3.04 †Emergency depressurization............................ 3.7 4.1

EK3.05 †RPV flooding.......................................... 3.5 3.8

EK3.06 Reactor SCRAM......................................... 4.0* 4.1

EK3.07 Drywell venting....................................... 3.5 4.0

EK3.08 Containment spray: Plant-Specific.................... 3.7 4.1 |

EK3.09 Auxiliary building isolation: Plant-Specific......... 3.1 3.6
NUREG-1123, Rev. 2 4.1-4 |

EPE: 295024 High Drywell Pressure

IMPORTANCE 

K/A NO. ABILITY RO SRO

EA1. Ability to operate and/or monitor the following as

they apply to HIGH DRYWELL PRESSURE:

(CFR: 41.7 / 45.6)

EA1.01 HPCI (FWCI): Plant-Specific.......................... 4.1* 4.0

EA1.02 HPCS: Plant-Specific................................. 3.8 3.7

EA1.03 LPCS: Plant-Specific................................. 4.0 3.9

EA1.04 RHR/LPCI.............................................. 4.1 3.9

EA1.05 RPS................................................... 3.9 4.0

EA1.06 Emergency generators.................................. 3.7 3.7

EA1.07 PCIS/NSSSS............................................ 3.8 3.9

EA1.08 ADS: Plant-Specific.................................. 3.9 3.9

EA1.09 Suppression pool makeup: Plant-Specific.............. 2.9 3.0

EA1.10 A.C. distribution..................................... 3.4 3.6

EA1.11 Drywell spray: Mark-I&II............................. 4.2* 4.2*

EA1.12 Suppression pool spray: Mark-I&II.................... 3.8 3.8

EA1.13 Suppression pool cooling.............................. 3.6 3.6

EA1.14 Drywell ventilation system............................ 3.4 3.5

EA1.15 Containment/drywell atmospheric monitoring............ 3.6 3.7

EA1.16 Containment/drywell vacuum breakers................... 3.4 3.4

EA1.17 Containment spray: Plant-Specific.................... 3.9 3.9

EA1.18 Containment ventilation system: Mark-III............. 3.6 3.6

EA1.19 Containment atmosphere control: Plant-Specific....... 3.3 3.4

EA1.20 Standby gas treatment/FRVS: Plant-Specific........... 3.5 3.6

EA1.21 Recirculation system (LPCI loop select logic):

Plant-Specific........................................ 3.4 3.8

EA1.22 D.C. distribution: Plant-Specific.................... 2.7 2.9

EA2. Ability to determine and/or interpret the following as

they apply to HIGH DRYWELL PRESSURE:

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 Drywell pressure...................................... 4.2* 4.4*

EA2.02 Drywell temperature................................... 3.9 4.0

EA2.03 Suppression pool level................................ 3.8 3.8

EA2.04 Suppression chamber pressure: Plant-Specific.......... 3.9 3.9

EA2.05 Suppression chamber air-space temperature: Plant-

| Specific.............................................. 3.6 3.7

EA2.06 Suppression pool temperature.......................... 4.1 4.1

EA2.07 Containment radiation levels: Mark-III................ 3.4 3.9

EA2.08 Drywell radiation levels.............................. 3.6 4.0

EA2.09 Containment pressure: Mark-III........................ 4.0* 4.1*

EA2.10 Containment temperature: Mark-III..................... 3.7 3.9
4.1-5 NUREG-1123, Rev. 2 |

EPE: 295025 High Reactor Pressure

IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK1. Knowledge of the operational implications of the

following concepts as they apply to HIGH REACTOR

PRESSURE :

(CFR: 41.8 to 41.10)

EK1.01 Pressure effects on reactor power..................... 3.9 4.0

EK1.02 Reactor vessel integrity.............................. 4.1 4.2

EK1.03 Safety/relief valve tailpipe temperature/pressure

relationships........................................ 3.6 3.8

EK1.04 Decay heat generation................................ 3.6 3.9

EK1.05 †Exceeding safety limits.............................. 4.4* 4.7*

EK1.06 Pressure effects on reactor water level.............. 3.5 3.6

EK2. Knowledge of the interrelations between HIGH REACTOR

PRESSURE and the following:

(CFR: 41.7 / 45.8) 

EK2.01 RPS................................................... 4.1* 4.1

EK2.02 Isolation condenser: Plant-Specific.................. 4.2* 4.5*

EK2.03 RRCS: Plant-Specific.................................. 4.0 4.3

EK2.04 ARI/RPT/ATWS: Plant-Specific......................... 3.9 4.1*

EK2.05 Safety/relief valves: Plant-Specific................. 4.1* 4.2

EK2.06 HPCI: Plant-Specific................................. 3.8 3.8

EK2.07 RCIC: Plant-Specific................................. 3.7 3.7

EK2.08 Reactor/turbine pressure regulating system: PlantSpecific.............................................. 3.7 3.7

EK2.09 Reactor power......................................... 3.9 3.9

EK2.10 SPDS/ERIS/CRIDS/GDS: Plant-Specific.................. 2.9 3.2

EK2.11 Reactor water level................................... 3.5 3.6

EK3. Knowledge of the reasons for the following responses

as they apply to HIGH REACTOR PRESSURE :

(CFR: 41.5 / 45.6)

EK3.01 Safety/relief valve opening........................... 4.2 4.3*

EK3.02 Recirculation pump trip: Plant-Specific.............. 3.9 4.1

EK3.03 HPCI operation: Plant-Specific....................... 3.8 3.8

EK3.04 Isolation condenser initiation: Plant-Specific....... 4.5* 4.7*

EK3.05 RCIC operation: Plant-Specific....................... 3.6 3.7

EK3.06 Alternate rod insertion: Plant-Specific.............. 4.2* 4.4*

EK3.07 †RRCs initiation: Plant-Specific...................... 3.3 3.7

EK3.08 Reactor/turbine pressure regulating system operation.. 3.5 3.5

EK3.09 Low-low set initiation: Plant-Specific............... 3.7 3.7
NUREG-1123, Rev. 2 4.1-6 |

EPE: 295025 High Reactor Pressure

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

EA1. Ability to operate and/or monitor the following as

 they apply to HIGH REACTOR PRESSURE:

(CFR: 41.7 / 45.6)

EA1.01 Main steam line drains................................ 2.9 3.0

EA1.02 Reactor/turbine pressure regulating system............ 3.8 3.8

EA1.03 Safety/relief valves: Plant-Specific................. 4.4* 4.4*

EA1.04 HPCI: Plant-Specific................................. 3.8 3.9

EA1.05 RCIC: Plant-Specific................................. 3.7 3.7

EA1.06 Isolation condenser: Plant-Specific.................. 4.5* 4.5*

EA1.07 ARI/RPT/ATWS: Plant-Specific......................... 4.1 4.1

EA1.08 †RRCS: Plant-Specific................................. 3.3 3.7*

EA2. Ability to determine and/or interpret the following as

they apply to HIGH REACTOR PRESSURE:

(CFR: 41.10 / 43.5 / 45.13)

| EA2.01 Reactor pressure...................................... 4.3* 4.3*

EA2.02 Reactor power......................................... 4.2* 4.2

EA2.03 Suppression pool temperature.......................... 3.9 4.1

EA2.04 Suppression pool level................................ 3.9 3.9

EA2.05 Decay heat generation................................. 3.4 3.6

EA2.06 Reactor water level................................... 3.7 3.8
4.1-7 NUREG-1123, Rev. 2 |

EPE: 295026 Suppression Pool High Water Temperature

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK1. Knowledge of the operational implications of the

following concepts as they apply to SUPPRESSION POOL

HIGH WATER TEMPERATURE :

(CFR: 41.8 to 41.10)

EK1.01 Pump NPSH............................................. 3.0 3.4

EK1.02 Steam condensation.................................... 3.5 3.8

EK2. Knowledge of the interrelations between SUPPRESSION

POOL HIGH WATER TEMPERATURE and the following:

(CFR: 41.7 / 45.8) 

EK2.01 Suppression pool cooling.............................. 3.9 4.0

EK2.02 Suppression pool spray: Plant-Specific............... 3.6 3.8

EK2.03 Suppression chamber pressure: Mark-I&II.............. 3.2 3.6

EK2.04 SPDS/ERIS/CRIDS/GDS: Plant-Specific.................. 2.5 2.8

EK2.05 Containment pressure: Mark-III....................... 3.0 3.3

EK2.06 Suppression pool level................................ 3.5 3.7

EK3. Knowledge of the reasons for the following responses

as they apply to SUPPRESSION POOL HIGH WATER

TEMPERATURE:

(CFR: 41.5 / 45.6)

EK3.01 Emergency/normal depressurization..................... 3.8 4.1

EK3.02 Suppression pool cooling.............................. 3.9 4.0

EK3.03 Suppression pool spray: Plant-Specific............... 3.5 3.8

EK3.04 †SBLC injection........................................ 3.7 4.1*

EK3.05 Reactor SCRAM......................................... 3.9 4.1

ABILITY

EA1. Ability to operate and/or monitor the following as

they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:

(CFR: 41.7 / 45.6)

EA1.01 Suppression pool cooling.............................. 4.1 4.1

EA1.02 Suppression pool spray: Plant-Specific............... 3.6 3.8

EA1.03 Temperature monitoring................................ 3.9* 3.9

EA2. Ability to determine and/or interpret the following as

they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 Suppression pool water temperature.................... 4.1* 4.2*

EA2.02 Suppression pool level................................ 3.8 3.9

EA2.03 Reactor pressure...................................... 3.9 4.0
NUREG-1123, Rev. 2 4.1-8 |

EPE: 295027 High Containment Temperature (Mark III Containment Only)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK1. Knowledge of the operational implications of the

following concepts as they apply to HIGH CONTAINMENT

TEMPERATURE (MARK III CONTAINMENT ONLY) :

(CFR: 41.8 to 41.10)

EK1.01 Equipment environmental qualifications: Mark-III..... 2.5 2.7

EK1.02 Reactor water level measurement: Mark-III............ 3.0 3.2

EK1.03 Containment integrity: Mark-III...................... 3.8 3.8

EK2. Knowledge of the interrelations between HIGH

CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY)

and the following:

(CFR: 41.7 / 45.8) 

EK2.01 Containment spray: Plant-Specific.................... 3.2 3.4

EK2.02 Components internal to the containment: Mark-III..... 3.2 3.3

EK2.03 Containment ventilation/cooling: Mark-III............ 3.5 3.7

EK2.04 SPDS/ERIS/CRIDS/GDS: Mark-III........................ 2.6 3.2

EK3. Knowledge of the reasons for the following responses

as they apply to HIGH CONTAINMENT TEMPERATURE (MARK

III CONTAINMENT ONLY) :

(CFR: 41.5 / 45.6)

EK3.01 Emergency depressurization: Mark-III................. 3.7 3.8

EK3.02 Containment spray: Plant-Specific.................... 3.2 3.2

EK3.03 Reactor SCRAM: Mark-III.............................. 3.7 3.7

ABILITY

EA1. Ability to operate and/or monitor the following as

they apply to HIGH CONTAINMENT TEMPERATURE (MARK III

CONTAINMENT ONLY) :

(CFR: 41.7 / 45.6)

EA1.01 Containment spray: Plant-Specific.................... 3.2 3.4

EA1.02 Containment ventilation/cooling: Mark-III............ 3.5 3.5

EA1.03 Emergency depressurization: Mark-III................. 3.5 3.8

EA2. Ability to determine and/or interpret the following as

they apply to HIGH CONTAINMENT TEMPERATURE (MARK III

CONTAINMENT ONLY) :

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 Containment temperature: Mark-III.................... 3.7 3.7

EA2.02 Containment pressure: Mark-III....................... 3.7 3.7

EA2.03 Reactor pressure: Mark-III........................... 3.3 3.3

EA2.04 Containment radiation levels: Mark-III............... 3.3 3.7
4.1-9 NUREG-1123, Rev. 2 |

EPE: 295028 High Drywell Temperature

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK1. Knowledge of the operational implications of the

following concepts as they apply to HIGH DRYWELL

TEMPERATURE :

(CFR: 41.8 to 41.10)

EK1.01 Reactor water level measurement....................... 3.5 3.7

EK1.02 Equipment environmental qualification................. 2.9 3.1

EK2. Knowledge of the interrelations between HIGH DRYWELL

TEMPERATURE and the following:

(CFR: 41.7 / 45.8) 

EK2.01 †Drywell spray: Mark-I&II............................. 3.7 4.1

EK2.02 Components internal to the drywell.................... 3.2 3.3

EK2.03 Reactor water level indication........................ 3.6 3.8

EK2.04 Drywell ventilation................................... 3.6 3.6

EK2.05 SPDS/ERIS/CRIDS/GDS: Plant-Specific.................. 2.3* 2.5

EK3. Knowledge of the reasons for the following responses

as they apply to HIGH DRYWELL TEMPERATURE :

(CFR: 41.5 / 45.6)

EK3.01 Emergency depressurization............................ 3.6 3.9

EK3.02 RPV flooding.......................................... 3.5 3.8

EK3.03 †Drywell spray operation: Mark-I&II................... 3.6 3.9

EK3.04 Increased drywell cooling............................. 3.6 3.8

EK3.05 Reactor SCRAM......................................... 3.6 3.7

EK3.06 ADS................................................... 3.4 3.7

ABILITY

EA1. Ability to operate and/or monitor the following as

they apply to HIGH DRYWELL TEMPERATURE :

(CFR: 41.7 / 45.6)

EA1.01 Drywell spray: Mark-I&II............................. 3.8 3.9

EA1.02 Drywell ventilation system............................ 3.9 3.8

EA1.03 Drywell cooling system................................ 3.9 3.9

EA1.04 Drywell pressure...................................... 3.9 4.0

EA1.05 ADS................................................... 3.7 3.7

EA2. Ability to determine and/or interpret the following as

they apply to HIGH DRYWELL TEMPERATURE :

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 Drywell temperature................................... 4.0* 4.1*

EA2.02 Reactor pressure...................................... 3.8 3.9

EA2.03 Reactor water level................................... 3.7 3.9
NUREG-1123, Rev. 2 4.1-10 |

EPE: 295028 High Drywell Temperature

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

EA2.04 Drywell pressure...................................... 4.1 4.2

EA2.05 Torus/suppression chamber pressure: Plant-Specific... 3.6 3.8

EA2.06 Torus/suppression chamber air space temperature:

Plant-Specific........................................ 3.4 3.7
4.1-11 NUREG-1123, Rev. 2 |

EPE: 295029 High Suppression Pool Water Level

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK1. Knowledge of the operational implications of the

following concepts as they apply to HIGH SUPPRESSION

POOL WATER LEVEL :

(CFR: 41.8 to 41.10)

EK1.01 Containment integrity................................. 3.4 3.7

EK2. Knowledge of the interrelations between HIGH

SUPPRESSION POOL WATER LEVEL and the following:

(CFR: 41.7 / 45.8) 

EK2.01 RHR/LPCI.............................................. 3.0 3.3

EK2.02 HPCI: Plant-Specific................................. 3.4 3.6

EK2.03 HPCS: Plant-Specific................................. 3.3 3.5

EK2.04 Suppression pool cleanup system: Plant-Specific...... 2.4* 2.4*

EK2.05 Containment/drywell vacuum breakers................... 3.1 3.3

EK2.06 SRV's and discharge piping............................ 3.4 3.5

EK2.07 Drywell/containment water level....................... 3.1 3.2

EK2.08 Drywell/suppression chamber ventilation............... 2.6 2.9

EK2.09 RCIC: Plant-Specific................................. 3.1 3.2

EK3. Knowledge of the reasons for the following responses

as they apply to HIGH SUPPRESSION POOL WATER LEVEL :

(CFR: 41.5 / 45.6)

EK3.01 Emergency depressurization............................ 3.5 3.9*

EK3.02 Lowering suppression pool water level................. 3.6 4.0

EK3.03 Reactor SCRAM......................................... 3.4 3.5

ABILITY

EA1. Ability to operate and/or monitor the following as

they apply to HIGH SUPPRESSION POOL WATER LEVEL :

(CFR: 41.7 / 45.6)

EA1.01 HPCI: Plant-Specific................................. 3.4* 3.5

EA1.02 HPCS: Plant-Specific................................. 3.1 3.1

EA1.03 RHR/LPCI.............................................. 2.9 3.0

EA1.04 RCIC: Plant-Specific................................. 3.4 3.5

EA2. Ability to determine and/or interpret the following as

they apply to HIGH SUPPRESSION POOL WATER LEVEL :

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 Suppression pool water level.......................... 3.9* 3.9* |

EA2.02 Reactor pressure...................................... 3.5 3.6

EA2.03 Drywell/containment water level....................... 3.4 3.5
NUREG-1123, Rev. 2 4.1-12 |

EPE: 295030 Low Suppression Pool Water Level

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK1. Knowledge of the operational implications of the

following concepts as they apply to LOW SUPPRESSION

POOL WATER LEVEL:

(CFR: 41.8 to 41.10)

EK1.01 Steam condensation.................................... 3.8* 4.1*

EK1.02 Pump NPSH............................................. 3.5 3.8

EK1.03 Heat capacity......................................... 3.8 4.1*

EK2. Knowledge of the interrelations between LOW

SUPPRESSION POOL WATER LEVEL and the following:

(CFR: 41.7 / 45.8) 

EK2.01 HPCI: Plant-Specific................................. 3.8 3.9

EK2.02 RCIC: Plant-Specific................................. 3.7 3.8

EK2.03 LPCS.................................................. 3.8 3.9

EK2.04 RHR/LPCI.............................................. 3.7 3.8

EK2.05 HPCS: Plant-Specific................................. 3.8 3.9

EK2.06 Suppression pool make-up: Mark-III................... 3.9* 3.9*

EK2.07 Downcomer/ horizontal vent submergence................ 3.5 3.8

EK2.08 SRV discharge submergence............................. 3.5 3.8

EK2.09 SPDS/ERIS/CRIDS/GDS: Plant-Specific.................. 2.5 2.8

EK3. Knowledge of the reasons for the following responses

as they apply to LOW SUPPRESSION POOL WATER LEVEL:

(CFR: 41.5 / 45.6)

EK3.01 Emergency depressurization............................ 3.8 4.1

EK3.02 HPCI operation: Plant-Specific....................... 3.5 3.7

EK3.03 RCIC operation: Plant-Specific....................... 3.6 3.7

EK3.04 HPCS operation: Plant-Specific....................... 3.5 3.5

EK3.05 Suppression pool make-up operation: Mark-III......... 3.6 3.6

EK3.06 Reactor SCRAM......................................... 3.6 3.8

EK3.07 NPSH considerations for ECCS pumps.................... 3.5 3.8

ABILITY

EA1. Ability to operate and/or monitor the following as

they apply to LOW SUPPRESSION POOL WATER LEVEL:

(CFR: 41.7 / 45.6)

EA1.01 ECCS systems (NPSH considerations): Plant-Specific... 3.6 3.8

EA1.02 RCIC: Plant-Specific................................. 3.4 3.5

EA1.03 HPCS: Plant-Specific................................. 3.4 3.4

EA1.04 Suppression pool make-up system: Mark-III............ 4.0 4.0

EA1.05 HPCI.................................................. 3.5 3.5
4.1-13 NUREG-1123, Rev. 2 |

EPE: 295030 Low Suppression Pool Water Level

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

EA1.06 Condensate storage and transfer (make-up to the

suppression pool): Plant-Specific.................... 3.4 3.4

EA2. Ability to determine and/or interpret the following as

they apply to LOW SUPPRESSION POOL WATER LEVEL :

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 Suppression pool level................................ 4.1* 4.2*

EA2.02 Suppression pool temperature.......................... 3.9 3.9

EA2.03 Reactor pressure...................................... 3.7 3.9

EA2.04 Drywell/ suppression chamber differential pressure:

Mark-I&II............................................. 3.5 3.7
NUREG-1123, Rev. 2 4.1-14 |

EPE: 295031 Reactor Low Water Level

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK1. Knowledge of the operational implications of the

following concepts as they apply to REACTOR LOW WATER

LEVEL :

(CFR: 41.8 to 41.10)

EK1.01 Adequate core cooling................................. 4.6* 4.7*

EK1.02 Natural circulation: Plant-Specific.................. 3.8 4.1

EK1.03 Water level effects on reactor power.................. 3.7 4.1

EK2. Knowledge of the interrelations between REACTOR LOW

WATER LEVEL and the following:

(CFR: 41.7 / 45.8) 

EK2.01 Reactor water level indication........................ 4.4* 4.4*

EK2.02 Reactor pressure...................................... 3.8 3.9

EK2.03 Low pressure core spray............................... 4.2 4.3*

EK2.04 Reactor core isolation cooling: Plant-Specific....... 4.0 4.1

EK2.05 Low pressure coolant injection (RHR).................. 4.2 4.3

EK2.06 High pressure (feedwater) coolant injection

(FWCI/HPCI): Plant-Specific.......................... 4.1 4.2

EK2.07 High pressure core spray: Plant-Specific............. 4.0 4.1

EK2.08 Automatic depressurization system..................... 4.2* 4.3*

EK2.09 Recirculation system: Plant-Specific................. 3.3 3.4

EK2.10 Redundant reactivity control: Plant-Specific......... 4.0 4.0

EK2.11 Reactor protection system............................. 4.4* 4.4*

EK2.12 Primary containment isolation system/ Nuclear steam

supply shutoff........................................ 4.5* 4.5*

EK2.13 ARI/RPT/ATWS: Plant-Specific......................... 4.1 4.2

EK2.14 Emergency generators.................................. 3.9 4.0

EK2.15 A.C. distribution: Plant-Specific.................... 3.2 3.2

EK2.16 Reactor water level control........................... 4.1* 4.1

EK3. Knowledge of the reasons for the following responses

as they apply to REACTOR LOW WATER LEVEL :

(CFR: 41.5 / 45.6)

EK3.01 Automatic depressurization system actuation........... 3.9 4.2*

EK3.02 Core coverage......................................... 4.4* 4.7*

EK3.03 Spray cooling......................................... 4.1 4.4*

EK3.04 Steam cooling......................................... 4.0 4.3*

EK3.05 Emergency depressurization............................ 4.2* 4.3*
4.1-15 NUREG-1123, Rev. 2 |

EPE: 295031 Reactor Low Water Level

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EA1. Ability to operate and/or monitor the following as

they apply to REACTOR LOW WATER LEVEL :

(CFR: 41.7 / 45.6)

EA1.01 Low pressure coolant injection (RHR): Plant-Specific. 4.4* 4.4*

EA1.02 High pressure (feedwater) coolant injection: PlantSpecific.............................................. 4.5* 4.5*

EA1.03 Low pressure core spray............................... 4.4* 4.4*

EA1.04 High pressure core spray: Plant-Specific............. 4.3* 4.2

EA1.05 Reactor core isolation system: Plant-Specific........ 4.3* 4.3*

EA1.06 Automatic depressurization system..................... 4.4* 4.4*

EA1.07 Safety/relief valves.................................. 3.7* 3.7*

EA1.08 Alternate injection systems: Plant-specific.......... 3.8 3.9

EA1.09 Isolation condenser: Plant-Specific.................. 3.3* 3.5*

EA1.10 Control rod drive..................................... 3.6 3.7

EA1.11 Condensate............................................ 4.1 4.1

EA1.12 Feedwater............................................. 3.9 4.1*

EA1.13 Reactor water level control........................... 4.3* 4.3*

EA2. Ability to determine and/or interpret the following

as they apply to REACTOR LOW WATER LEVEL :

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 Reactor water level............................ 4.6* 4.6*

EA2.02 Reactor power.................................. 4.0 4.2*

EA2.03 Reactor pressure............................... 4.2* 4.2*

EA2.04 Adequate core cooling.......................... 4.6* 4.8*
NUREG-1123, Rev. 2 4.1-16 |

EPE: 295032 High Secondary Containment Area Temperature

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK1. Knowledge of the operational implications of the

following concepts as they apply to HIGH SECONDARY

CONTAINMENT AREA TEMPERATURE: 

(CFR: 41.8 to 41.10)

EK1.01 Personnel protection.................................. 3.6 3.8

EK1.02 †Radiation releases.................................... 3.6 4.0

EK1.03 Secondary containment leakage detection: PlantSpecific.............................................. 3.5? 3.9?

EK1.04 Impact of operating environment on components......... 3.1 3.6

EK2. Knowledge of the interrelations between HIGH SECONDARY

CONTAINMENT AREA TEMPERATURE and the following:

(CFR: 41.7 / 45.8) 

EK2.01 Area/room coolers..................................... 3.5 3.6

EK2.02 Secondary containment ventilation..................... 3.6 3.7

EK2.03 Fire protection system................................ 3.3 3.4

EK2.04 PCIS/NSSSS............................................ 3.6 3.8

EK2.05 Temperature sensitive instrumentation................. 3.2 3.4

EK2.06 Area temperature monitoring system.................... 3.3 3.4

EK2.07 Leak detection system concept: Plant-Specific........ 3.6 3.8

EK2.08 Systems required for safe shut-down................... 3.8 3.9

EK3. Knowledge of the reasons for the following responses

as they apply to HIGH SECONDARY CONTAINMENT AREA

TEMPERATURE :

(CFR: 41.5 / 45.6)

EK3.01 Emergency/normal depressurization..................... 3.5 3.8

EK3.02 Reactor SCRAM......................................... 3.6 3.8

EK3.03 Isolating affected systems............................ 3.8 3.9*

ABILITY

EA1. Ability to operate and/or monitor the following as

they apply to HIGH SECONDARY CONTAINMENT AREA

TEMPERATURE :

(CFR: 41.7 / 45.6)

EA1.01 Area temperature monitoring system.................... 3.6 3.7

EA1.02 Leak detection system concept: Plant-Specific........ 3.4 3.5

EA1.03 Secondary containment ventilation..................... 3.7 3.7

EA1.04 Fire protection system................................ 3.3 3.4

EA1.05 Affected systems so as to isolate damaged portions.... 3.7 3.9
4.1-17 NUREG-1123, Rev. 2 |

EPE: 295032 High Secondary Containment Area Temperature

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

EA2. Ability to determine and/or interpret the following as

they apply to HIGH SECONDARY CONTAINMENT AREA

TEMPERATURE :

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 Area temperature...................................... 3.8* 3.8

EA2.02 Equipment operability................................. 3.3 3.5

EA2.03 Cause of high area temperature........................ 3.8 4.0
NUREG-1123, Rev. 2 4.1-18 |

EPE: 295033 High Secondary Containment Area Radiation Levels

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK1. Knowledge of the operational implications of the

following concepts as they apply to HIGH SECONDARY

CONTAINMENT AREA RADIATION LEVELS :

(CFR: 41.8 to 41.10)

EK1.01 Component environmental qualifications................ 2.4 2.8*

EK1.02 Personnel protection.................................. 3.9 4.2*

EK1.03 †Radiation releases.................................... 3.9 4.2*

EK2. Knowledge of the interrelations between HIGH SECONDARY

CONTAINMENT AREA RADIATION LEVELS and the following:

(CFR: 41.7 / 45.8) 

EK2.01 Area radiation monitoring system...................... 3.8 4.0

EK2.02 Process radiation monitoring system................... 3.8 4.1

EK2.03 Secondary containment ventilation: Plant-Specific.... 3.7 3.9

EK2.04 Standby gas treatment system/FRVS..................... 3.9 4.2

EK3. Knowledge of the reasons for the following responses

as they apply to HIGH SECONDARY CONTAINMENT AREA

RADIATION LEVELS :

(CFR: 41.5 / 45.6)

EK3.01 Emergency depressurization............................ 3.3 3.5

EK3.02 Reactor SCRAM......................................... 3.5 3.6

EK3.03 Isolating affected systems............................ 3.8 3.9

EK3.04 Personnel evacuation.................................. 4.0 4.4*

EK3.05 Emergency plan........................................ 3.6 4.5*

 ABILITY

EA1. Ability to operate and/or monitor the following as

 they apply to HIGH SECONDARY CONTAINMENT AREA

RADIATION LEVELS :

(CFR: 41.7 / 45.6)

EA1.01 Area radiation monitoring system...................... 3.9 4.0

EA1.02 Process radiation monitoring system................... 3.7 3.8

EA1.03 Secondary containment ventilation..................... 3.8 3.8

EA1.04 SBGT/FRVS............................................. 4.2* 4.2

EA1.05 Affected systems so as to isolate damaged portions.... 3.9 4.0

EA1.06 Portable radiation monitoring instruments............. 2.9* 3.1*

EA1.07 Personnel dosimetry................................... 3.5 3.6

EA1.08 Control room ventilation: Plant-Specific............. 3.6 3.8
4.1-19 NUREG-1123, Rev. 2 |

EPE: 295033 High Secondary Containment Area Radiation Levels

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

EA2. Ability to determine and/or interpret the following as

they apply to HIGH SECONDARY CONTAINMENT AREA

RADIATION LEVELS :

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 Area radiation levels................................. 3.8 3.9

EA2.02 Equipment operability................................. 3.1 3.2

EA2.03 †Cause of high area radiation......................... 3.7 4.2
NUREG-1123, Rev. 2 4.1-20 |

EPE: 295034 Secondary Containment Ventilation High Radiation

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK1. Knowledge of the operational implications of the

following concepts as they apply to SECONDARY

CONTAINMENT VENTILATION HIGH RADIATION :

(CFR: 41.8 to 41.10)

EK1.01 Personnel protection.................................. 3.8 4.1

EK1.02 †Radiation releases.................................... 4.1 4.4*

EK2. Knowledge of the interrelations between SECONDARY

CONTAINMENT VENTILATION HIGH RADIATION and the

following:

(CFR: 41.7 / 45.8) 

EK2.01 Process radiation monitoring system................... 3.9 4.2

EK2.02 Area radiation monitoring system...................... 3.8 3.9

EK2.03 SBGT/FRVS: Plant-Specific............................ 4.3* 4.5*

EK2.04 Secondary containment ventilation..................... 3.9 3.9

EK2.05 Fuel building ventilation: Mark-III.................. 3.5 3.7

EK2.06 PCIS/NSSSS: Plant-Specific........................... 3.9 4.2

EK3. Knowledge of the reasons for the following responses

as they apply to SECONDARY CONTAINMENT VENTILATION

HIGH RADIATION :

(CFR: 41.5 / 45.6)

EK3.01 Isolating secondary containment ventilation........... 3.8 4.1

EK3.02 Starting SBGT/FRVS: Plant-Specific................... 4.1 4.1

EK3.03 Personnel evacuation.................................. 4.0* 4.4*

EK3.04 Fuel building ventilation: Plant-Specific............ 3.7 3.8

| EK3.05 Manual SCRAM and depressurization: Plant-Specific.... 3.6 3.9

 ABILITY

EA1. Ability to operate and/or monitor the following as

they apply to SECONDARY CONTAINMENT VENTILATION HIGH

RADIATION :

(CFR: 41.7 / 45.6)

EA1.01 Area radiation monitoring system...................... 3.8 3.8

EA1.02 Process radiation monitoring system................... 3.9 4.0

EA1.03 Secondary containment ventilation..................... 4.0 3.9

EA1.04 SBGT/FRVS: Plant-Specific............................ 4.1* 4.2*

EA1.05 Fuel building ventilation: Plant-Specific............ 3.8 3.8
4.1-21 NUREG-1123, Rev. 2 |

EPE: 295034 Secondary Containment Ventilation High Radiation

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

EA2. Ability to determine and/or interpret the following as

they apply to SECONDARY CONTAINMENT VENTILATION HIGH

RADIATION :

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 Ventilation radiation levels.......................... 3.8 4.2

EA2.02 Cause of high radiation levels........................ 3.7 4.2*
NUREG-1123, Rev. 2 4.1-22 |

EPE: 295035 Secondary Containment High Differential Pressure

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK1. Knowledge of the operational implications of the

following concepts as they apply to SECONDARY

CONTAINMENT HIGH DIFFERENTIAL PRESSURE :

(CFR: 41.8 to 41.10)

EK1.01 Secondary containment integrity....................... 3.9 4.2*

EK1.02 †Radiation release..................................... 3.7 4.2

EK2. Knowledge of the interrelations between SECONDARY

CONTAINMENT HIGH DIFFERENTIAL PRESSURE and the

following:

(CFR: 41.7 / 45.8) 

EK2.01 Secondary containment ventilation..................... 3.6 3.6

EK2.02 SBGT/FRVS............................................. 3.6 3.8

EK2.03 †Off-site release rate................................. 3.3 4.1

EK2.04 Blow-out panels: Plant-Specific...................... 3.3 3.7

EK3. Knowledge of the reasons for the following responses

as they apply to SECONDARY CONTAINMENT HIGH

DIFFERENTIAL PRESSURE :

(CFR: 41.5 / 45.6)

EK3.01 Blow-out panel operation: Plant-Specific............. 2.8 3.1

EK3.02 Secondary containment ventilation response............ 3.3 3.5

 ABILITY

EA1. Ability to operate and/or monitor the following as

they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL

PRESSURE:

(CFR: 41.7 / 45.6)

EA1.01 Secondary containment ventilation system.............. 3.6 3.6

EA1.02 SBGT/FRVS............................................. 3.8 3.8

EA2. Ability to determine and/or interpret the following as

they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL

PRESSURE:

(CFR: 41.8 to 41.10)

EA2.01 Secondary containment pressure: Plant-Specific....... 3.8 3.9

EA2.02 †Off-site release rate: Plant-Specific................ 2.8* 4.1
4.1-23 NUREG-1123, Rev. 2 |

EPE: 295036 Secondary Containment High Sump/Area Water Level

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK1. Knowledge of the operational implications of the

following concepts as they apply to SECONDARY

CONTAINMENT HIGH SUMP/AREA WATER LEVEL :

(CFR: 41.8 to 41.10)

EK1.01 Radiation releases.................................... 2.9 3.1

EK1.02 Electrical ground/ circuit malfunction................ 2.6* 2.8*

EK2. Knowledge of the interrelations between SECONDARY

CONTAINMENT HIGH SUMP/AREA WATER LEVEL and the

following:

(CFR: 41.7 / 45.8) 

EK2.01 Secondary containment equipment and floor drain system 3.1 3.2

EK2.02 Post-accident sampling system: Plant-Specific........ 2.6 2.9

EK2.03 Radwaste.............................................. 2.8 3.1

EK3. Knowledge of the reasons for the following responses

as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA

WATER LEVEL :

(CFR: 41.5 / 45.6)

EK3.01 Emergency depressurization............................ 2.6 2.8

EK3.02 Reactor SCRAM......................................... 2.8 2.8

EK3.03 Isolating affected systems............................ 3.5 3.6

EK3.04 Pumping secondary containment sumps................... 3.1 3.4

 ABILITY

EA1. Ability to operate and/or monitor the following as

they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA

WATER LEVEL :

(CFR: 41.7 / 45.6)

EA1.01 Secondary containment equipment and floor drain

systems............................................... 3.2 3.3

EA1.02 Affected systems so as to isolate damaged portions.... 3.5 3.6

EA1.03 Radwaste.............................................. 2.8 3.0

EA1.04 Radiation monitoring: Plant-Specific................. 3.1 3.4

EA2. Ability to determine and/or interpret the following as

they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA

WATER LEVEL :

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 Operability of components within the affected area.. 3.0 3.2

EA2.02 Water level in the affected area.................... 3.1 3.1

EA2.03 Cause of the high water level....................... 3.4 3.8
NUREG-1123, Rev. 2 4.1-24 |

EPE: 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale

 or Unknown

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK1. Knowledge of the operational implications of the

following concepts as they apply to SCRAM CONDITION

PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR

UNKNOWN :

(CFR: 41.8 to 41.10)

EK1.01 Reactor pressure effects on reactor power............. 4.1* 4.3*

EK1.02 Reactor water level effects on reactor power.......... 4.1* 4.3*

EK1.03 Boron effects on reactor power (SBLC)................. 4.2 4.4*

EK1.04 Hot shutdown boron weight: Plant-Specific............ 3.4 3.6

EK1.05 Cold shutdown boron weight: Plant-Specific........... 3.4 3.6

EK1.06 Cooldown effects on reactor power..................... 4.0* 4.2*

EK1.07 Shutdown margin....................................... 3.4 3.8

EK2. Knowledge of the interrelations between SCRAM

CONDITION PRESENT AND REACTOR POWER ABOVE APRM

DOWNSCALE OR UNKNOWN and the following:

(CFR: 41.7 / 45.8) 

| EK2.01 RPS................................................... 4.2* 4.3*

EK2.02 RRCS: Plant-Specific................................. 4.0 4.2

| EK2.03 ARI/RPT/ATWS: Plant-Specific......................... 4.1 4.2*

| EK2.04 SBLC system........................................... 4.4* 4.5*

EK2.05 CRD hydraulic system.................................. 4.0 4.1

EK2.06 CRD mechanisms........................................ 3.5 3.6

| EK2.07 Neutron monitoring system............................. 4.0* 4.0

EK2.08 SPDS/ERIS/CRIDS/GDS: Plant-Specific.................. 2.7 3.1

EK2.09 Reactor water level................................... 4.0 4.2

EK2.10 Reactor pressure...................................... 3.8 4.1

EK2.11 RMCS: Plant-Specific................................. 3.8 3.9

EK2.12 Rod control and information system: Plant-Specific... 3.6 3.8

EK2.13 Alternate boron injection methods: Plant-Specific.... 3.4 4.1

EK2.14 RPIS: Plant-Specific................................. 3.6 3.9

EK3. Knowledge of the reasons for the following responses

as they apply to SCRAM CONDITION PRESENT AND REACTOR

POWER ABOVE APRM DOWNSCALE OR UNKNOWN :

(CFR: 41.5 / 45.6)

EK3.01 Recirculation pump trip/runback: Plant-Specific...... 4.1 4.2

EK3.02 SBLC injection........................................ 4.3* 4.5*

EK3.03 Lowering reactor water level.......................... 4.1* 4.5*

EK3.04 Hot shutdown boron weight: Plant-Specific............ 3.2 3.7
4.1-25 NUREG-1123, Rev. 2 |

EPE: 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale

 or Unknown

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK3.05 Cold shutdown boron weight: Plant-Specific........... 3.2 3.7

EK3.06 Maintaining heat sinks external to the containment.... 3.8 4.1

EK3.07 Various alternate methods of control rod insertion:

Plant-Specific........................................ 4.2 4.3*

EK3.08 ATWS circuitry: Plant-Specific....................... 3.6* 3.9*

 ABILITY

EA1. Ability to operate and/or monitor the following as

 they apply to SCRAM CONDITION PRESENT AND REACTOR

POWER ABOVE APRM DOWNSCALE OR UNKNOWN :

(CFR: 41.7 / 45.6)

EA1.01 Reactor Protection System............................. 4.6* 4.6*

EA1.02 RRCS: Plant-Specific................................. 3.8 4.0

EA1.03 ARI/RPT/ATWS: Plant-Specific......................... 4.1* 4.1*

EA1.04 SBLC.................................................. 4.5* 4.5*

EA1.05 CRD hydraulics systems................................ 3.9 4.0

EA1.06 Neutron monitoring system............................. 4.1* 4.1

EA1.07 RMCS: Plant-Specific................................. 3.9 4.0

EA1.08 Rod control and information system: Plant-Specific... 3.6 3.6

EA1.09 SPDS/ERIS/CRIDS/GDS: Plant-Specific.................. 2.8* 3.0

EA1.10 Alternate boron injection methods: Plant-Specific.... 3.7 3.9

EA1.11 PCIS/NSSSS............................................ 3.5 3.6

EA2. Ability to determine and/or interpret the following as

they apply to SCRAM CONDITION PRESENT AND REACTOR

POWER ABOVE APRM DOWNSCALE OR UNKNOWN :

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 Reactor power......................................... 4.2* 4.3*

EA2.02 Reactor water level................................... 4.1* 4.2*

EA2.03 SBLC tank level....................................... 4.3* 4.4*

EA2.04 Suppression pool temperature.......................... 4.0* 4.1*

EA2.05 Control rod position.................................. 4.2* 4.3*

EA2.06 Reactor pressure...................................... 4.0 4.1

EA2.07 Containment conditions/isolations..................... 4.0 4.2*
NUREG-1123, Rev. 2 4.1-26 |

EPE: 295038 High Off-Site Release Rate

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

EK1. Knowledge of the operational implications of the

following concepts as they apply to HIGH OFF-SITE

RELEASE RATE :

(CFR: 41.8 to 41.10)

EK1.01 Biological effects of radioisotope ingestion.......... 2.5 3.1

EK1.02 †Protection of the general public...................... 4.2* 4.4*

EK1.03 †Meteorological effects on off-site release............ 2.8 3.8

EK2. Knowledge of the interrelations between HIGH OFF-SITE

RELEASE RATE and the following:

(CFR: 41.7 / 45.8) 

EK2.01 Radwaste.............................................. 3.1 3.4

EK2.02 Offgas system......................................... 3.6 3.8

EK2.03 Plant ventilation systems............................. 3.6 3.8

EK2.04 Stack-gas monitoring system: Plant-Specific.......... 3.9 4.2

EK2.05 †Site emergency plan................................... 3.7 4.7*

EK2.06 Process liquid radiation monitoring system............ 3.4 3.7

EK2.07 Control room ventilation.............................. 3.5 3.7

EK2.08 SPDS/ERIS/CRIDS/GDS: Plant-Specific.................. 2.6 3.1

EK2.09 Post accident sample system (PASS): Plant-Specific... 2.9* 3.5*

EK2.10 Condenser air removal system.......................... 3.2 3.4

EK2.11 MSIV leakage control: Plant-Specific................. 3.1 3.4

EK2.12 Feedwater leakage control: BWR-6..................... 3.5 3.8

EK3. Knowledge of the reasons for the following responses

as they apply to HIGH OFF-SITE RELEASE RATE:

(CFR: 41.5 / 45.6)

EK3.01 †Implementation of site emergency plan................. 3.6 4.5*

EK3.02 System isolations..................................... 3.9 4.2

EK3.03 Control room ventilation isolation: Plant-Specific... 3.7 3.9

EK3.04 †Emergency depressurization............................ 3.6 3.9

 ABILITY

EA1. Ability to operate and/or monitor the following as

 they apply to HIGH OFF-SITE RELEASE RATE :

(CFR: 41.7 / 45.6)

EA1.01 Stack-gas monitoring system: Plant-Specific.......... 3.9 4.2

EA1.02 †Meteorological instrumentation........................ 3.0* 3.8

EA1.03 Process liquid radiation monitoring system............ 3.7 3.9

EA1.04 SPDS/ERIS/CRIDS/GDS: Plant-Specific.................. 2.8 3.2

EA1.05 Post accident sample system (PASS): Plant-Specific... 3.0* 3.5*

EA1.06 Plant ventilation..................................... 3.5 3.6

EA1.07 Control room ventilation: Plant-Specific............. 3.6 3.8
4.1-27 NUREG-1123, Rev. 2 |

EPE: 295038 High Off-Site Release Rate

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

EA2. Ability to determine and/or interpret the following as

they apply to HIGH OFF-SITE RELEASE RATE :

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 †Off-site............................................... 3.3* 4.3*

EA2.02 †Total number of curies released......................... 2.5* 3.3*

EA2.03 †Radiation levels........................................ 3.5* 4.3*

EA2.04 Source of off-site release............................. .................................. 4.1* 4.5*
NUREG-1123, Rev. 2 4.1-28 |

EPE: 500000 High Containment Hydrogen Concentration

 

 IMPORTANCE 

K/A NO. Knowledge RO SRO

EK1. Knowledge of the operational implications of the 

following concepts as they apply to HIGH CONTAINMENT

HYDROGEN CONCENTRATIONS:

(CFR: 41.8 to 41.10)

EK1.01 Containment integrity ................................................... 3.3 3.9

EK2. Knowledge of the interrelations between HIGH

CONTAINMENT HYDROGEN CONCENTRATIONS the following:

(CFR: 41.7 / 45.8) 

EK2.01 Containment hydrogen monitoring systems ................................. 3.1 3.5

EK2.02 Containment oxygen monitoring systems ................................... 3.1 3.5

EK2.03 Containment Atmosphere Control System .................................. 3.3 3.4

EK2.04 Drywell recirculating fan ................................................. 2.7 2.9

EK2.05 Hydrogen and oxygen recombiners ........................................ 3.2 3.3

EK2.06 Wetwell Spray system ................................................... 3.0 3.4

EK2.07 Drywell vent system ..................................................... 3.2 3.7

EK2.08 Wet Well vent system ................................................... 3.2 3.6

EK2.09 Drywell nitrogen purge system ............................................ 3.0 3.3

EK3. Knowledge of the reasons for the following responses as

they apply to HIGH PRIMARY CONTAINMENT HYDROGEN 

CONCENTRATIONS:

(CFR: 41.5 / 45.6)

EK3.01 Initiation of containment atmosphere control system ......................... 2.9 3.3

EK3.02 Operation of drywell recirculating fans ..................................... 2.8 3.0

EK3.03 Operation of hydrogen and oxygen recombiners .............................. 3.0 3.5

EK3.04 Emergency depressurization .............................................. 3.1 3.9

EK3.05 Operation of wet well (suppression pool) sprays ............................. 2.9 3.4

EK3.06 Operation of wet well vent ................................................ 3.1 3.7

EK3.07 Operation of drywell vent ................................................ 3.1 3.7

EK3.08 Operation of drywell nitrogen purge system ................................. 3.1 3.6

EA1. Ability to operate and monitor the following as they apply

to HIGH CONTAINMENT HYDROGEN CONTROL:

(CFR: 41.7 / 45.6)

EA1.01 Primary containment hydrogen instrumentation .............................. 3.4 3.3

EA1.02 Primary containment oxygen instrumentation ................................ 3.3 3.2

EA1.03 Containment atmosphere control system .................................... 3.4 3.2

EA1.04 Drywell recirculating fans ................................................ 2.9 2.9

EA1.05 Wetwell sprays ......................................................... 3.3 3.3

EA1.06 Drywell sprays ......................................................... 3.3 3.4

EA1.07 Nitrogen purge system ................................................... 3.4 3.3
4.1-29 NUREG-1123, Rev. 2 |

EPE: 500000 High Containment Hydrogen Concentration

 

 IMPORTANCE 

K/A NO. Knowledge RO SRO

EA2 Ability to determine and / or interpret the following 

as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS:

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 Hydrogen monitoring system availability ................................... 3.1 3.5

EA2.02 Oxygen monitoring system availability ..................................... 3.0 3.5

EA2.03 Combustible limits for drywell ............................................ 3.3 3.8

EA2.04 Combustible limits for wetwell ........................................... 3.3 3.3
NUREG-1123, Rev. 2 4.1-30 |

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4.2-1 NUREG-1123, Rev. 2 |

4.2 Abnormal Plant Evolutions page

295001 Partial or Complete Loss of Forced Core Flow Circulation 4.2-3

295002 Loss of Main Condenser Vacuum 4.2-5

295003 Partial or Complete Loss of A.C. Power 4.2-7

295004 Partial or Complete Loss of D.C. Power 4.2-9

295005 Main Turbine Trip 4.2-10

295006 SCRAM 4.2-12

295007 High Reactor Pressure 4.2-14

295008 High Reactor Water Level 4.2-16

295009 Low Reactor Water Level 4.2-18

295010 High Drywell Pressure 4.2-19

295011 High Containment Temperature (Mark III Containment Only) 4.2-21

295012 High Drywell Temperature 4.2-22

295013 High Suppression Pool Water Temperature 4.2-23

295014 Inadvertent Reactivity Addition 4.2-24

295015 Incomplete SCRAM 4.2-26

295016 Control Room Abandonment 4.2-28

295017 High Off-Site Release Rate 4.2-29

295018 Partial or Complete Loss of Component Cooling Water 4.2-31

295019 Partial or Complete Loss of Instrument Air 4.2-33

295020 Inadvertent Containment Isolation 4.2-35

295021 Loss of Shutdown Cooling 4.2-37

295022 Loss of Control Rod Drive Pumps 4.2-39

295023 Refueling Accidents 4.2-40

600000 Plant Fire On Site 4.2-42
NUREG-1123, Rev. 2 4.2-2 |

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4.2-3 NUREG-1123, Rev. 2 |

APE: 295001 Partial or Complete Loss of Forced Core Flow Circulation

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to PARTIAL OR

COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION :

(CFR: 41.8 to 41.10)

AK1.01 Natural circulation................................... 3.5 3.6

AK1.02 Power/flow distribution............................... 3.3 3.5

AK1.03 †Thermal limits........................................ 3.6 4.1

AK1.04 †Limiting cycle oscillation: Plant-Specific........... 2.5 3.3

AK2. Knowledge of the interrelations between PARTIAL OR

COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION and the

following:

(CFR: 41.7 / 45.8) 

AK2.01 Recirculation system.................................. 3.6 3.7

AK2.02 Nuclear boiler instrumentation........................ 3.2 3.3

AK2.03 Reactor water level................................... 3.6 3.7

AK2.04 Reactor/turbine pressure regulating system: PlantSpecific.............................................. 3.3 3.3

AK2.05 LPCI loop select logic: Plant-Specific............... 3.2 3.6

AK2.06 Reactor power......................................... 3.8 3.8

AK2.07 Core flow indication.................................. 3.4 3.4

AK2.08 Standby liquid control: BWR-1........................ 2.5* 2.8

AK3. Knowledge of the reasons for the following responses

as they apply to PARTIAL OR COMPLETE LOSS OF FORCED

CORE FLOW CIRCULATION :

(CFR: 41.5 / 45.6)

AK3.01 Reactor water level response.......................... 3.4 3.6

AK3.02 Reactor power response................................ 3.7 3.8

AK3.03 Idle loop flow........................................ 2.8 2.9

AK3.04 Reactor SCRAM......................................... 3.4 3.6

AK3.05 Reduced loop operating requirements: Plant-Specific.. 3.2 3.6

AK3.06 Core flow indication.................................. 2.9 3.0

 ABILITY

AA1. Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE

LOSS OF FORCED CORE FLOW CIRCULATION :

(CFR: 41.7 / 45.6)

AA1.01 Recirculation system.................................. 3.5 3.6

AA1.02 RPS................................................... 3.3 3.3
NUREG-1123, Rev. 2 4.2-4 |

APE: 295001 Partial or Complete Loss of Forced Core Flow Circulation

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

AA1.03 RMCS: Plant-Specific................................. 2.6 2.7

AA1.04 Rod control and information system: BWR-5&6.......... 2.6 2.8

AA1.05 Recirculation flow control system..................... 3.3 3.3

AA1.06 Neutron monitoring system............................. 3.3 3.4

AA1.07 Nuclear boiler instrumentation system................. 3.1 3.2

AA1.08 Standby liquid control: BWR-1........................ 2.5* 2.8

AA2. Ability to determine and/or interpret the following as

they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE

FLOW CIRCULATION :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Power/flow map........................................ 3.5 3.8

AA2.02 Neutron monitoring.................................... 3.1 3.2

AA2.03 Actual core flow...................................... 3.3 3.3

AA2.04 Individual jet pump flows: Not-BWR-1&2............... 3.0 3.1

AA2.05 Jet pump operability: Not-BWR-1&2.................... 3.1 3.4

AA2.06 Nuclear boiler instrumentation........................ 3.2 3.3
4.2-5 NUREG-1123, Rev. 2 |

APE: 295002 Loss of Main Condenser Vacuum

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to LOSS OF MAIN

CONDENSER VACUUM :

(CFR: 41.8 to 41.10)

AK1.01 Plant efficiency...................................... 2.1* 2.5

AK1.02 Turbine efficiency.................................... 2.2* 2.5

AK1.03 Loss of heat sink..................................... 3.6 3.8

AK1.04 Increased offgas flow................................. 3.0 3.3

AK2. Knowledge of the interrelations between LOSS OF MAIN

CONDENSER VACUUM and the following:

(CFR: 41.7 / 45.8) 

AK2.01 RPS................................................... 3.5 3.5

AK2.02 Main turbine.......................................... 3.1 3.2

AK2.03 PCIS/NSSSS............................................ 3.5 3.6

AK2.04 Reactor/turbine pressure regulating system............ 3.2 3.3

AK2.05 Feedwater system...................................... 2.7 2.7

AK2.06 Condensate system..................................... 2.6 2.7

AK2.07 Offgas system......................................... 3.1 3.1

AK2.08 Condenser circulating water system.................... 3.1 3.2

AK2.09 Vacuum drag (low conductivity drain): Plant-Specific. 2.4 2.4

AK2.10 Reactor recirculation system: Plant-Specific......... 2.4* 2.5

AK2.11 Seal steam: Plant-Specific............................. 2.6 2.7

AK3. Knowledge of the reasons for the following responses

as they apply to LOSS OF MAIN CONDENSER VACUUM :

(CFR: 41.5 / 45.6)

AK3.01 Reactor SCRAM: Plant-Specific........................ 3.7 3.8

AK3.02 Turbine trip.......................................... 3.4 3.4

AK3.03 Reactor feedpump turbine trip: Plant-Specific........ 3.3 3.3

AK3.04 Bypass valve closure.................................. 3.4 3.6

AK3.05 Main steam isolation valve: Plant-Specific........... 3.4 3.4

AK3.06 Air ejector flow...................................... 2.9 2.9

AK3.07 Decreased main generator output....................... 2.4 2.5

AK3.08 Recirculation system run-backs: Plant-Specific....... 2.8 2.9

AK3.09 Reactor power reduction............................... 3.2 3.2
NUREG-1123, Rev. 2 4.2-6 |

APE: 295002 Loss of Main Condenser Vacuum

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

 ABILITY

AA1. Ability to operate and/or monitor the following as

 they apply to LOSS OF MAIN CONDENSER VACUUM :

(CFR: 41.7 / 45.6)

AA1.01 Condensate system 2.6 2.6

AA1.02 Offgas system ........................................ . 2.9 2.9

AA1.03 RPS. .................................................. 3.4 3.5

AA1.04 PCIS/NSSSS ............................................ 3.3 3.4

AA1.05 Main turbine .......................................... 3.2 3.2

AA1.06 Reactor/turbine pressure regulating system ............ 3.0 3.1

AA1.07 Condenser circulating water system .................... 3.1 2.9

AA1.08 Recirculating flow control system ..................... 2.6 2.7

AA1.09 Reactor manual control/rod control and information

system............................................. ... 2.4 2.4

AA1.10 Feedwater system: Plant-Specific ..................... 2.7 2.7

AA2. Ability to determine and/or interpret the following as

they apply to LOSS OF MAIN CONDENSER VACUUM :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Condenser vacuum/absolute pressure.................... 2.9 3.1

AA2.02 Reactor power: Plant-Specific........................ 3.2 3.3

AA2.03 Generator output...................................... 2.3 2.4

AA2.04 Offgas system flow.................................... 2.8 2.9
4.2-7 NUREG-1123, Rev. 2 |

APE: 295003 Partial or Complete Loss of A.C. Power

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to PARTIAL OR

COMPLETE LOSS OF A.C. POWER :

(CFR: 41.8 to 41.10)

AK1.01 Effect of battery discharge rate on capacity.......... 2.7 2.9

AK1.02 Load shedding......................................... 3.1 3.4

AK1.03 Under voltage/degraded voltage effects on electrical

loads................................................. 2.9 3.2

AK1.04 Electrical bus divisional separation.................. 3.1 3.2

AK1.05 Failsafe component design............................. 2.6 2.7

AK1.06 Station blackout: Plant-Specific..................... 3.8 4.0*

AK2. Knowledge of the interrelations between PARTIAL OR

COMPLETE LOSS OF A.C. POWER and the following:

(CFR: 41.7 / 45.8) 

AK2.01 Station batteries..................................... 3.2 3.3

AK2.02 Emergency generators.................................. 4.1* 4.2*

AK2.03 A.C. electrical distribution system................... 3.7 3.9

AK2.04 A.C. electrical loads................................. 3.4 3.5

AK2.05 Isolation condenser: Plant-Specific.................. 3.8* 4.0

AK2.06 D.C. electrical loads................................. 3.4 3.5

AK3. Knowledge of the reasons for the following responses

as they apply to PARTIAL OR COMPLETE LOSS OF A.C.

POWER :

(CFR: 41.5 / 45.6)

AK3.01 Manual and auto bus transfer.......................... 3.3 3.5

AK3.02 Selective tripping.................................... 2.9 3.1

AK3.03 Load shedding......................................... 3.5 3.6

AK3.04 Ground isolation...................................... 3.0 3.2

AK3.05 Reactor SCRAM......................................... 3.7 3.7

AK3.06 Containment isolation................................. 3.7 3.7

AK3.07 Initiation of isolation condenser: Plant-Specific.... 3.8* 4.0*

 ABILITY

AA1. Ability to operate and/or monitor the following as

 they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER :

(CFR: 41.7 / 45.6)

AA1.01 A.C. electrical distribution system................... 3.7 3.8

AA1.02 Emergency generators.................................. 4.2* 4.3*

AA1.03 Systems necessary to assure safe plant shutdown....... 4.4* 4.4*
NUREG-1123, Rev. 2 4.2-8 |

APE: 295003 Partial or Complete Loss of A.C. Power

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

AA1.04 D.C. electrical distribution system................... 3.6 3.7

AA2. Ability to determine and/or interpret the following as

they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Cause of partial or complete loss of A.C. power....... 3.4 3.7

AA2.02 Reactor power / pressure / and level.................... 4.2* 4.3*

AA2.03 Battery status: Plant-Specific....................... 3.2 3.5

AA2.04 System lineups........................................ 3.5 3.7

AA2.05 Whether a partial or complete loss of A.C. power has

occurred.............................................. 3.9* 4.2*
4.2-9 NUREG-1123, Rev. 2 |

APE: 295004 Partial or Complete Loss of D.C. Power

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to PARTIAL OR

COMPLETE LOSS OF D.C. POWER :

(CFR: 41.8 to 41.10)

AK1.01 †Automatic load shedding: Plant-Specific.............. 2.9 3.2

AK1.02 Redundant D.C. power supplies: Plant-Specific........ 3.2 3.4

AK1.03 Electrical bus divisional separation.................. 2.9 2.9

AK1.04 Effect of battery discharge rate on capacity.......... 2.8 2.9

AK1.05 Loss of breaker protection............................ 3.3 3.4

AK1.06 Prevention of inadvertent system(s) actuation upon

restoration of D.C. power............................. 3.3 3.6

AK2. Knowledge of the interrelations between PARTIAL OR

COMPLETE LOSS OF D.C. POWER and the following:

(CFR: 41.7 / 45.8) 

AK2.01 Battery charger....................................... 3.1 3.1

AK2.02 Batteries............................................. 3.0 3.1

AK2.03 D.C. bus loads........................................ 3.3 3.3

AK3. Knowledge of the reasons for the following responses

as they apply to PARTIAL OR COMPLETE LOSS OF D.C.

POWER :

(CFR: 41.5 / 45.6)

AK3.01 †Load shedding: Plant-Specific........................ 2.6 3.1

AK3.02 Ground isolation/fault determination.................. 2.9 3.3

AK3.03 Reactor SCRAM: Plant-Specific........................ 3.1 3.5

 ABILITY

AA1. Ability to operate and/or monitor the following as

 they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER :

(CFR: 41.7 / 45.6)

AA1.01 D.C. electrical distribution systems.................. 3.3 3.4

AA1.02 Systems necessary to assure safe plant shutdown....... 3.8 4.1

AA1.03 A.C. electrical distribution.......................... 3.4 3.6

AA2. Ability to determine and/or interpret the following as

they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Cause of partial or complete loss of D.C. power....... 3.2 3.6

AA2.02 Extent of partial or complete loss of D.C. power...... 3.5 3.9

AA2.03 Battery voltage....................................... 2.8 2.9

AA2.04 System lineups........................................ 3.2 3.3
NUREG-1123, Rev. 2 4.2-10 |

APE: 295005 Main Turbine Generator Trip

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to MAIN TURBINE

GENERATOR TRIP :

(CFR: 41.8 to 41.10)

AK1.01 Pressure effects on reactor power.................... 4.0 4.1

AK1.02 †Core thermal limit considerations.................... 3.2 3.6

AK1.03 Pressure effects on reactor level.................... 3.5 3.7

AK2. Knowledge of the interrelations between MAIN TURBINE

GENERATOR TRIP and the following:

(CFR: 41.7 / 45.8) 

AK2.01 RPS................................................... 3.8 3.9

AK2.02 Feedwater temperature................................. 2.9 3.0

AK2.03 Recirculation system.................................. 3.2 3.3

AK2.04 Main generator protection............................. 3.3 3.3

AK2.05 Extraction steam system............................... 2.6 2.7

AK2.06 Seal steam evaporator: Plant-Specific................ 1.9* 1.9*

AK2.07 Reactor pressure control.............................. 3.6 3.7

AK2.08 A.C. electrical distribution.:........................ 3.2 3.3

AK2.09 Feedwater - HPCI: BWR-2.............................. 4.0 4.3

AK3. Knowledge of the reasons for the following responses

as they apply to MAIN TURBINE GENERATOR TRIP:

(CFR: 41.5 / 45.6)

AK3.01 Reactor SCRAM........................................ 3.8 3.8

AK3.02 Recirculation pump downshift/trip: Plant-Specific... 3.4 3.5

AK3.03 Feedwater temperature decrease....................... 2.8 3.0

AK3.04 Main generator trip.................................. 3.2 3.2

AK3.05 Extraction steam/moisture separator isolations....... 2.5 2.6

AK3.06 Realignment of electrical distribution............... 3.3 3.3

AK3.07 Bypass valve operation............................... 3.8 3.8

AK3.08 Feedwater - HPCI actuation: BWR-2................... 4.0 4.3

 ABILITY

AA1. Ability to operate and/or monitor the following as

 they apply to MAIN TURBINE GENERATOR TRIP :

(CFR: 41.7 / 45.6)

AA1.01 Recirculation system: Plant-Specific................. 3.1 3.3

AA1.02 RPS................................................... 3.6 3.6

AA1.03 Reactor manual control/Rod control and information

system................................................ 2.7 2.8

AA1.04 Main generator controls............................... 2.7 2.8
4.2-11 NUREG-1123, Rev. 2 |

APE: 295005 Main Turbine Generator Trip

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AA1.05 Reactor/turbine pressure regulating system............ 3.6 3.6

AA1.06 Condenser vacuum breaker.............................. 2.4 2.6

AA1.07 A.C. electrical distribution.......................... 3.3 3.3

AA2. Ability to determine and/or interpret the following as

they apply to MAIN TURBINE GENERATOR TRIP :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Turbine speed......................................... 2.6 2.7

AA2.02 Turbine vibration..................................... 2.4 2.7

AA2.03 Turbine valve position................................ 3.1 3.1

AA2.04 Reactor pressure...................................... 3.7 3.8

AA2.05 Reactor power......................................... 3.8 3.9

AA2.06 Feedwater temperature................................. 2.6 2.7

AA2.07 Reactor water level................................... 3.5 3.6

AA2.08 Electrical distribution status........................ 3.2 3.3
NUREG-1123, Rev. 2 4.2-12 |

APE: 295006 SCRAM

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to SCRAM :

(CFR: 41.8 to 41.10)

AK1.01 Decay heat generation and removal..................... 3.7 3.9

AK1.02 Shutdown margin....................................... 3.4 3.7

AK1.03 Reactivity control.................................... 3.7 4.0

AK2. Knowledge of the interrelations between SCRAM and the

following:

(CFR: 41.7 / 45.8) 

AK2.01 RPS................................................... 4.3* 4.4*

AK2.02 Reactor water level control system.................... 3.8 3.8

AK2.03 CRD hydraulic system.................................. 3.7 3.8

AK2.04 Turbine trip logic: Plant-Specific.................... 3.6 3.7

AK2.05 CRD mechanism......................................... 3.1 3.3

AK2.06 Reactor power......................................... 4.2* 4.3*

AK2.07 Reactor pressure control.............................. 4.0 4.1

AK3. Knowledge of the reasons for the following responses

as they apply to SCRAM :

(CFR: 41.5 / 45.6)

AK3.01 Reactor water level response.......................... 3.8 3.9

AK3.02 Reactor power response................................ 4.1* 4.2*

AK3.03 Reactor pressure response............................. 3.8 3.9*

AK3.04 Reactor water level setpoint setdown: Plant-Specific.. 3.1 3.3

AK3.05 Direct turbine generator trip: Plant-Specific......... 3.8 4.0

AK3.06 Recirculation pump speed reduction: Plant-Specific.... 3.2 3.3

 ABILITY

AA1. Ability to operate and/or monitor the following as

 they apply to SCRAM :

(CFR: 41.7 / 45.6)

AA1.01 RPS................................................... 4.2* 4.2*

AA1.02 Reactor water level control system.................... 3.9 3.8

AA1.03 Reactor/turbine pressure regulating system............ 3.7 3.7

AA1.04 Recirculation system.................................. 3.1 3.2

AA1.05 Neutron monitoring system............................. 4.2* 4.2*

AA1.06 CRD hydraulic system.................................. 3.5 3.6

AA1.07 Control rod position.................................. 4.1 4.1
4.2-13 NUREG-1123, Rev. 2 |

APE: 295006 SCRAM

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

AA2. Ability to determine and/or interpret the following as 

they apply to SCRAM :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Reactor power......................................... 4.5* 4.6*

AA2.02 Control rod position.................................. 4.3* 4.4*

AA2.03 Reactor water level................................... 4.0 4.2*

AA2.04 Reactor pressure...................................... 4.1 4.1*

AA2.05 Whether a reactor SCRAM has occurred.................. 4.6* 4.6*

AA2.06 Cause of reactor SCRAM................................ 3.5 3.8
NUREG-1123, Rev. 2 4.2-14 |

APE: 295007 High Reactor Pressure

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to HIGH REACTOR

PRESSURE :

(CFR: 41.8 to 41.10)

AK1.01 Pump shutoff head..................................... 2.9 3.2

AK1.02 Decay heat generation................................. 3.1 3.4

AK1.03 Pressure effects on reactor power..................... 3.8 3.9

AK1.04 Turbine load.......................................... 2.7 2.8

AK2. Knowledge of the interrelations between HIGH REACTOR

PRESSURE and the following:

(CFR: 41.7 / 45.8) 

AK2.01 Reactor/turbine pressure regulating system............ 3.5 3.7

AK2.02 Reactor power......................................... 3.8 3.8

AK2.03 RHR/LPCI: Plant-Specific............................. 3.1 3.2

AK2.04 LPCS.................................................. 3.2 3.3

AK2.05 Shutdown cooling: Plant-Specific..................... 2.9 3.1

AK2.06 PCIS/NSSSS: Plant-Specific........................... 3.5 3.7

AK3. Knowledge of the reasons for the following responses

as they apply to HIGH REACTOR PRESSURE :

(CFR: 41.5 / 45.6)

AK3.01 Isolation condenser operation: Plant-Specific........ 4.0 4.2

AK3.02 HPCI operation: Plant-Specific....................... 3.7 3.8*

AK3.03 RCIC operation: Plant-Specific....................... 3.4 3.5

AK3.04 Safety/relief valve operation: Plant-Specific........ 4.0 4.1*

AK3.05 Low pressure system isolation......................... 3.0 3.2

AK3.06 Reactor/turbine pressure regulating system operation.. 3.7 3.8

 ABILITY

AA1. Ability to operate and/or monitor the following as

 they apply to HIGH REACTOR PRESSURE :

(CFR: 41.7 / 45.6)

AA1.01 Isolation condenser: Plant-Specific.................. 4.0 4.2

AA1.02 HPCI: Plant-Specific................................. 3.5 3.7*

AA1.03 RCIC: Plant-Specific................................. 3.4 3.5

AA1.04 Safety/relief valve operation: Plant-Specific........ 3.9 4.1*

AA1.05 Reactor/turbine pressure regulating system............ 3.7 3.8
4.2-15 NUREG-1123, Rev. 2 |

APE: 295007 High Reactor Pressure

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AA2. Ability to determine and/or interpret the following as

they apply to HIGH REACTOR PRESSURE :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Reactor pressure...................................... 4.1* 4.1*

AA2.02 Reactor power......................................... 4.1* 4.1*

AA2.03 Reactor water level................................... 3.7 3.7
NUREG-1123, Rev. 2 4.2-16 |

APE: 295008 High Reactor Water Level

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to HIGH REACTOR 

WATER LEVEL :

(CFR: 41.8 to 41.10)

AK1.01 Moisture carryover.................................... 3.0 3.2

AK1.02 Component erosion/damage.............................. 2.8 2.8

AK1.03 Feed flow/steam flow mismatch......................... 3.2 3.2

AK1.04 Containment integrity: Alis-Chalmers................. 4.0 4.3*

AK2. Knowledge of the interrelations between HIGH REACTOR

WATER LEVEL and the following:

(CFR: 41.7 / 45.8) 

AK2.01 RPS: Plant-Specific.................................. 3.7 3.8

AK2.02 Reactor feedwater system.............................. 3.6 3.8

AK2.03 Reactor water level control........................... 3.6 3.7

AK2.04 PCIS/NSSSS: Plant-Specific............................ 3.1 3.3

AK2.05 HPCI: Plant-Specific................................. 3.8 3.9

AK2.06 RCIC: Plant-Specific................................. 3.4 3.6

AK2.07 HPCS: Plant-Specific................................. 2.9 3.0

AK2.08 Main turbine: Plant-Specific......................... 3.4 3.5

AK2.09 Reactor water cleanup system (ability to drain):

Plant-Specific........................................ 3.1 3.1

AK2.10 RHR (ability to drain): Plant-Specific............... 2.7 2.8

AK2.11 Main steam............................................ 3.1 3.3

AK3. Knowledge of the reasons for the following responses

as they apply to HIGH REACTOR WATER LEVEL :

(CFR: 41.5 / 45.6)

AK3.01 Main turbine trip..................................... 3.4 3.5

AK3.02 Reactor SCRAM: Plant-Specific........................ 3.6* 3.9*

AK3.03 PCIS/NSSSS initiation: Plant-Specific................ 2.9 3.1

AK3.04 Reactor feed pump trip: Plant-Specific............... 3.3 3.5

AK3.05 HPCI turbine trip: Plant-Specific.................... 3.5 3.6

AK3.06 RCIC turbine trip: Plant-Specific.................... 3.4 3.5

AK3.07 HPCS isolation: Plant-Specific....................... 3.2 3.3

AK3.08 RCIC steam supply valve closure: Plant-Specific...... 3.4 3.5

AK3.09 HPCS injection valve closure: Plant-Specific......... 3.3 3.4
4.2-17 NUREG-1123, Rev. 2 |

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

AA1. Ability to operate and/or monitor the following as

 they apply to HIGH REACTOR WATER LEVEL :

(CFR: 41.7 / 45.6)

AA1.01 Reactor water level control: Plant-Specific.......... 3.7 3.7

AA1.02 Reactor water cleanup (ability to drain): PlantSpecific.............................................. 3.3 3.3

AA1.03 Main steam system: Plant-Specific.................... 3.1 3.1

AA1.04 HPCI: Plant-Specific................................. 3.5 3.5

AA1.05 RCIC: Plant-Specific................................. 3.3 3.3

AA1.06 HPCS: Plant-Specific................................. 2.8 2.8

AA1.07 Main turbine: Plant-Specific......................... 3.4 3.4

AA1.08 Feedwater system...................................... 3.5 3.5

AA1.09 Ability to drain: Plant-Specific..................... 3.3 3.3

AA2. Ability to determine and/or interpret the following as

they apply to HIGH REACTOR WATER LEVEL :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Reactor water level................................... 3.9 3.9

AA2.02 Steam flow/feedflow mismatch.......................... 3.4 3.4

AA2.03 Reactor water cleanup blowdown flow................... 2.9 3.0

AA2.04 Heatup rate: Plant-Specific......................... 3.1 3.3

AA2.05 Swell................................................. 2.9 3.1
NUREG-1123, Rev. 2 4.2-18 |

APE: 295009 Low Reactor Water Level

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to LOW REACTOR WATER

LEVEL :

(CFR: 41.8 to 41.10)

AK1.01 Steam carryunder...................................... 2.7 2.9

AK1.02 Recirculation pump net positive suction head: PlantSpecific.............................................. 3.0 3.1

AK1.03 Jet pump net positive suction head: Not-BWR-1&2...... 2.7 2.7

AK1.04 Jet pump efficiency: Not-BWR-1&2..................... 2.4 2.4

AK1.05 Natural circulation................................... 3.3 3.4

AK2. Knowledge of the interrelations between LOW REACTOR

WATER LEVEL and the following:

(CFR: 41.7 / 45.8) 

AK2.01 Reactor water level indication........................ 3.9 4.0

AK2.02 Reactor water level control........................... 3.9 3.9

AK2.03 Recirculation system.................................. 3.1 3.2

AK2.04 Reactor water cleanup................................. 2.6 2.6

AK3. Knowledge of the reasons for the following responses

as they apply to LOW REACTOR WATER LEVEL :

(CFR: 41.5 / 45.6)

AK3.01 Recirculation pump run back: Plant-Specific.......... 3.2 3.3

AK3.02 Reactor feedpump runout flow control: Plant-Specific. 2.7 2.8

 ABILITY

AA1. Ability to operate and/or monitor the following as

they apply to LOW REACTOR WATER LEVEL :

(CFR: 41.7 / 45.6)

AA1.01 Reactor feedwater..................................... 3.9 3.9

AA1.02 Reactor water level control........................... 4.0 4.0

AA1.03 Recirculation system: Plant-Specific................. 3.0 3.1

AA1.04 Reactor water cleanup................................. 2.7 2.7

AA2. Ability to determine and/or interpret the following as

they apply to LOW REACTOR WATER LEVEL :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Reactor water level................................... 4.2 4.2

AA2.02 Steam flow/feed flow mismatch......................... 3.6 3.7

AA2.03 Reactor water cleanup blowdown rate................... 2.9 2.9
4.2-19 NUREG-1123, Rev. 2 |

APE: 295010 High Drywell Pressure

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to HIGH DRYWELL

PRESSURE :

(CFR: 41.8 to 41.10)

AK1.01 Downcomer submergence: Mark-I&II..................... 3.0 3.4

AK1.02 Submergence vent control: Mark-III................... 2.8 3.1*

AK1.03 Temperature increases................................. 3.2 3.4

AK2. Knowledge of the interrelations between HIGH DRYWELL

PRESSURE and the following:

(CFR: 41.7 / 45.8) 

AK2.01 Suppression pool level................................ 3.2 3.3

AK2.02 Drywell/suppression chamber differential pressure:

Mark-I&II............................................. 3.3 3.5

AK2.03 Drywell/containment differential pressure: Mark-III.. 3.0 3.1

AK2.04 Nitrogen makeup system: Plant-Specific............... 2.6 2.8

AK2.05 Drywell cooling and ventilation....................... 3.7 3.8

AK3. Knowledge of the reasons for the following responses

as they apply to HIGH DRYWELL PRESSURE :

(CFR: 41.5 / 45.6)

AK3.01 Drywell venting....................................... 3.8 4.0*

AK3.02 Increased drywell cooling............................. 3.4 3.4

AK3.03 Radiation level monitoring............................ 3.2 3.5

AK3.04 Leak investigation.................................... 3.5 3.8

AK3.05 Temperature monitoring................................ 3.5 3.4

AK3.06 Termination of drywell inerting: Plant-Specific...... 2.4* 2.8

 ABILITY

AA1. Ability to operate and/or monitor the following as

 they apply to HIGH DRYWELL PRESSURE :

(CFR: 41.7 / 45.6)

AA1.01 Drywell ventilation/cooling........................... 3.4 3.5

AA1.02 Drywell floor and equipment drain sumps............... 3.6 3.6

AA1.03 Nitrogen makeup: Plant-Specific...................... 2.6 2.6

AA1.04 Drywell sampling system............................... 3.1 3.0

AA1.05 Drywell/suppression vent and purge.................... 3.1 3.4

AA1.06 Leakage detection systems............................. 3.3 3.5

AA1.07 Containment (drywell) atmosphere control.............. 3.2 3.4
NUREG-1123, Rev. 2 4.2-20 |

APE: 295010 High Drywell Pressure

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

AA2. Ability to determine and/or interpret the following as

they apply to HIGH DRYWELL PRESSURE :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 †Leak rates............................................ 3.4 3.8

AA2.02 Drywell pressure..................................... 3.8 3.9

AA2.03 Drywell radiation levels............................. 3.3 3.6

AA2.04 Drywell humidity: Plant-Specific..................... 2.8 3.0

| AA2.05 Drywell air cooler drain flow: BWR-6................. 3.3 3.3

| AA2.06 Drywell temperature.................................. 3.6 3.6
4.2-21 NUREG-1123, Rev. 2 |

APE: 295011 High Containment Temperature (Mark III Containment Only)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the 

following concepts as they apply to HIGH CONTAINMENT 

TEMPERATURE (MARK III CONTAINMENT ONLY) :

(CFR: 41.8 to 41.10)

AK1.01 Containment pressure: Mark-III....................... 4.0* 4.1*

AK2. Knowledge of the interrelations between HIGH

CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY)

and the following:

(CFR: 41.7 / 45.8) 

AK2.01 Containment ventilation/cooling: Mark-III............ 3.7 4.0

AK3. Knowledge of the reasons for the following responses

as they apply to HIGH CONTAINMENT TEMPERATURE (MARK

III CONTAINMENT ONLY) :

(CFR: 41.5 / 45.6)

AK3.01 Increased containment cooling: Mark-III.............. 3.6 3.9

 ABILITY

AA1. Ability to operate and/or monitor the following as

they apply to HIGH CONTAINMENT TEMPERATURE (MARK III

CONTAINMENT ONLY) :

(CFR: 41.7 / 45.6)

AA1.01 Containment ventilation/cooling system: Mark-III..... 3.6 3.9

AA2. Ability to determine and/or interpret the following as

they apply to HIGH CONTAINMENT TEMPERATURE (MARK III

CONTAINMENT ONLY) : (CFR: 41.10 / 43.5 / 45.13)

AA2.01 Containment temperature: Mark-III.................... 3.6 3.9

AA2.02 Containment pressure: Mark-III....................... 4.0* 4.1*

AA2.03 Containment humidity: Mark-III....................... 2.8 3.2
NUREG-1123, Rev. 2 4.2-22 |

APE: 295012 High Drywell Temperature

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the 

following concepts as they apply to HIGH DRYWELL 

TEMPERATURE :

(CFR: 41.8 to 41.10)

AK1.01 Pressure/temperature relationship..................... 3.3 3.5

AK1.02 Reactor power level control........................... 3.1 3.2

AK2. Knowledge of the interrelations between HIGH DRYWELL

TEMPERATURE and the following:

(CFR: 41.7 / 45.8) 

AK2.01 Drywell ventilation................................... 3.4 3.5

AK2.02 Drywell cooling....................................... 3.6 3.7

AK3. Knowledge of the reasons for the following responses

as they apply to HIGH DRYWELL TEMPERATURE :

(CFR: 41.5 / 45.6)

AK3.01 Increased drywell cooling............................. 3.5 3.6

 ABILITY

AA1. Ability to operate and/or monitor the following as

they apply to HIGH DRYWELL TEMPERATURE :

(CFR: 41.7 / 45.6)

AA1.01 Drywell ventilation system............................ 3.5 3.6

AA1.02 Drywell cooling system................................ 3.8 3.8

AA2. Ability to determine and/or interpret the following as

they apply to HIGH DRYWELL TEMPERATURE :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Drywell temperature................................... 3.8 3.9

AA2.02 Drywell pressure...................................... 3.9 4.1

AA2.03 Drywell humidity: Plant-Specific..................... 2.8 3.1
4.2-23 NUREG-1123, Rev. 2 |

APE: 295013 High Suppression Pool Temperature

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to HIGH SUPPRESSION

POOL TEMPERATURE :

(CFR: 41.8 to 41.10)

AK1.01 Pool stratification................................... 2.5 2.6

AK1.02 Ambient temperature effects........................... 2.4 2.5

AK1.03 Localized heating..................................... 3.0 3.3

AK1.04 Complete condensation................................. 2.9 3.2

AK2. Knowledge of the interrelations between HIGH

SUPPRESSION POOL TEMPERATURE and the following:

(CFR: 41.7 / 45.8) 

AK2.01 Suppression pool cooling.............................. 3.6 3.7

AK3. Knowledge of the reasons for the following responses

as they apply to HIGH SUPPRESSION POOL TEMPERATURE :

(CFR: 41.5 / 45.6)

AK3.01 Suppression pool cooling operation.................... 3.6 3.8

AK3.02 Limiting heat additions............................... 3.6 3.8

 ABILITY

AA1. Ability to operate and/or monitor the following as

 they apply to HIGH SUPPRESSION POOL TEMPERATURE :

(CFR: 41.7 / 45.6)

AA1.01 Suppression pool cooling.............................. 3.9 3.9

AA1.02 Systems that add heat to the suppression pool......... 3.9 3.9

AA2. Ability to determine and/or interpret the following as

they apply to HIGH SUPPRESSION POOL TEMPERATURE :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Suppression pool temperature.......................... 3.8 4.0

AA2.02 Localized heating/stratification...................... 3.2 3.5
NUREG-1123, Rev. 2 4.2-24 |

APE: 295014 Inadvertent Reactivity Addition

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to INADVERTENT

REACTIVITY ADDITION :

(CFR: 41.8 to 41.10)

AK1.01 Prompt critical....................................... 3.7 3.8

AK1.02 Reactivity anomaly.................................... 3.3 3.7

AK1.03 Shutdown margin....................................... 3.7 4.0

AK1.04 PCIOMR: Plant-Specific............................... 3.0 3.4

AK1.05 †Fuel thermal limits................................... 3.7 4.2*

AK1.06 Abnormal reactivity additions......................... 3.8 3.9

AK2. Knowledge of the interrelations between INADVERTENT

REACTIVITY ADDITION and the following:

(CFR: 41.7 / 45.8) 

AK2.01 RPS................................................... 3.9 4.1

AK2.02 †Fuel thermal limits................................... 3.7 4.2*

AK2.03 Fuel temperature...................................... 3.3 3.4

AK2.04 Void concentration.................................... 3.2 3.3

AK2.05 Neutron monitoring system............................. 4.0 4.1*

AK2.06 Moderator temperature................................. 3.4 3.5

AK2.07 Reactor power......................................... 3.9 3.9

AK2.08 RMCS: Plant-Specific................................. 3.4 3.5

AK2.09 Rod control and information system: Plant-Specific... 3.4 3.6

AK2.10 Safety limits......................................... 4.1 4.5*

AK2.11 Recirculation flow control............................ 3.6 3.7

AK3. Knowledge of the reasons for the following responses

as they apply to INADVERTENT REACTIVITY ADDITION:

(CFR: 41.5 / 45.6)

AK3.01 Reactor SCRAM......................................... 4.1* 4.1

AK3.02 Control rod blocks.................................... 3.7 3.7

 ABILITY

AA1. Ability to operate and/or monitor the following as

 they apply to INADVERTENT REACTIVITY ADDITION:

(CFR: 41.7 / 45.6)

AA1.01 RPS................................................... 4.0 4.1*

AA1.02 Recirculation flow control system..................... 3.6 3.8

AA1.03 RMCS: Plant-Specific................................. 3.5 3.5

AA1.04 Rod control and information system: Plant-Specific... 3.2 3.3

AA1.05 Neutron monitoring system............................. 3.9 3.9

AA1.06 Reactor/turbine pressure regulating system............ 3.3 3.4
4.2-25 NUREG-1123, Rev. 2 |

APE: 295014 Inadvertent Reactivity Addition

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AA1.07 Cold water injection.................................. 4.0 4.1

AA2. Ability to determine and/or interpret the following as

they apply to INADVERTENT REACTIVITY ADDITION :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Reactor power......................................... 4.1* 4.2*

AA2.02 Reactor period........................................ 3.9 3.9

AA2.03 Cause of reactivity addition.......................... 4.0 4.3*

AA2.04 †Violation of fuel thermal limits...................... 4.1 4.4*

AA2.05 †Violation of safety limits 4.2* 4.6* |
NUREG-1123, Rev. 2 4.2-26 |

APE: 295015 Incomplete SCRAM

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to INCOMPLETE SCRAM :

(CFR: 41.8 to 41.10)

AK1.01 Shutdown margin....................................... 3.6* 3.9*

AK1.02 Cooldown effects on reactor power..................... 3.9 4.1

AK1.03 Reactivity effects.................................... 3.8 3.9

AK1.04 Reactor pressure: Plant-Specific..................... 3.8 3.8

AK2. Knowledge of the interrelations between INCOMPLETE

SCRAM and the following:

(CFR: 41.7 / 45.8) 

AK2.01 CRD hydraulics........................................ 3.8 3.9

AK2.02 RMCS: Plant-Specific................................. 3.6 3.7

AK2.03 Rod control and information system: Plant-Specific... 3.2 3.6

AK2.04 RPS................................................... 4.0 4.1

AK2.05 Rod worth minimizer: Plant-Specific.................. 2.6 2.8

AK2.06 RSCS: Plant-Specific................................. 2.6 2.8

AK2.07 CRD mechanism......................................... 3.3 3.4

AK2.08 Neutron monitoring system............................. 3.6 3.7

AK2.09 RPIS.................................................. 3.5 3.6

AK2.10 SPDS/ERIS/CRIDS/GDS: Plant-Specific.................. 2.8 3.0

AK2.11 Instrument air........................................ 3.5 3.7

AK3. Knowledge of the reasons for the following responses

as they apply to INCOMPLETE SCRAM :

(CFR: 41.5 / 45.6)

AK3.01 Bypassing rod insertion blocks........................ 3.4 3.7

 ABILITY

AA1. Ability to operate and/or monitor the following as

 they apply to INCOMPLETE SCRAM :

(CFR: 41.7 / 45.6)

AA1.01 CRD hydraulics........................................ 3.8 3.9

AA1.02 RPS................................................... 4.0 4.2*

AA1.03 RMCS: Plant-Specific................................. 3.6 3.8

AA1.04 Rod control and information system: Plant-Specific... 3.4 3.7

AA1.05 Rod worth minimizer: Plant-Specific.................. 2.5* 2.8*

AA1.06 RSCS: Plant-Specific................................. 2.7 2.9
4.2-27 NUREG-1123, Rev. 2 |

APE: 295015 Incomplete SCRAM

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

AA1.07 Neutron monitoring system............................. 3.6 3.7

AA1.08 Process computer/SPDS/ERIS/CRIDS/GDS: Plant-Specific. 2.7 2.9

AA2. Ability to determine and/or interpret the following as

they apply to INCOMPLETE SCRAM :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Reactor power......................................... 4.1* 4.3*

AA2.02 Control rod position.................................. 4.1* 4.2*
NUREG-1123, Rev. 2 4.2-28 |

APE: 295016 Control Room Abandonment

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to CONTROL ROOM

ABANDONMENT :

(CFR: 41.8 to 41.10)

| None

AK2. Knowledge of the interrelations between CONTROL ROOM

ABANDONMENT and the following:

(CFR: 41.7 / 45.8) 

AK2.01 Remote shutdown panel: Plant-Specific................ 4.4* 4.5*

AK2.02 Local control stations: Plant-Specific............... 4.0* 4.1*

AK2.03 Control room HVAC..................................... 2.9* 3.1*

AK3. Knowledge of the reasons for the following responses

as they apply to CONTROL ROOM ABANDONMENT :

(CFR: 41.5 / 45.6)

AK3.01 Reactor SCRAM......................................... 4.1* 4.2*

AK3.02 Turbine trip.......................................... 3.7* 3.8*

AK3.03 Disabling control room controls....................... 3.5 3.7*

 ABILITY

AA1. Ability to operate and/or monitor the following as

 they apply to CONTROL ROOM ABANDONMENT :

(CFR: 41.7 / 45.6)

AA1.01 RPS................................................... 3.8 3.9

AA1.02 Reactor/turbine pressure regulating system............ 2.9* 3.1*

AA1.03 RPIS.................................................. 3.0* 3.1

AA1.04 A.C. electrical distribution.......................... 3.1 3.2

AA1.05 D.C. electrical distribution.......................... 2.8 2.9

AA1.06 Reactor water level................................... 4.0 4.1

AA1.07 Control room/local control transfer mechanisms........ 4.2* 4.3*

AA1.08 Reactor pressure...................................... 4.0 4.0

AA1.09 Isolation/emergency condenser(s): Plant-Specific..... 4.0 4.0

AA2. Ability to determine and/or interpret the following as

they apply to CONTROL ROOM ABANDONMENT :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Reactor power......................................... 4.1* 4.1*

AA2.02 Reactor water level................................... 4.2* 4.3*

AA2.03 Reactor pressure...................................... 4.3* 4.4*

AA2.04 Suppression pool temperature.......................... 3.9 4.1

AA2.05 Drywell pressure...................................... 3.8 3.9

AA2.06 Cooldown rate......................................... 3.3 3.5

AA2.07 Suppression chamber pressure.......................... 3.2 3.4
4.2-29 NUREG-1123, Rev. 2 |

APE: 295017 High Off-Site Release Rate

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to HIGH OFF-SITE

RELEASE RATE :

(CFR: 41.8 to 41.10)

AK1.01 Biological effects of radioisotope ingestion.......... 2.2* 2.5

AK1.02 †Protection of the general public...................... 3.8* 4.3*

AK1.03 †Meteorological effects on off-site release............ 2.7 3.4

AK2. Knowledge of the interrelations between HIGH OFF-SITE

RELEASE RATE and the following:

(CFR: 41.7 / 45.8) 

AK2.01 Fission product production versus reactor power....... 2.8 3.3

AK2.02 Radwaste.............................................. 2.8 3.1

AK2.03 Off-gas system........................................ 3.3 3.5

AK2.04 Plant ventilation systems............................. 3.1 3.3

AK2.05 Stack-gas monitoring system: Plant-Specific.......... 3.4 3.5 |

AK2.06 †Site emergency plan................................... 3.4 4.6*

AK2.07 Control room ventilation.............................. 3.2 3.4

AK2.08 SPDS/ERIS/CRIDS/GDS................................... 2.8 3.3

AK2.09 Condenser air removal system: Plant-Specific......... 2.8 2.9

AK2.10 Process radiation monitoring system................... 3.3 3.6

AK2.11 MSIV leakage control: Plant-Specific................. 3.1 3.2

AK2.12 Standby gas treatment/FRVS............................ 3.4 3.7

AK2.13 RPS................................................... 3.4 3.7

AK2.14 PCIS/NSSSS............................................ 4.0 4.1

AK3. Knowledge of the reasons for the following responses

as they apply to HIGH OFF-SITE RELEASE RATE :

(CFR: 41.5 / 45.6)

AK3.01 System isolations..................................... 3.6 3.9

AK3.02 Plant ventilation..................................... 3.3 3.5

AK3.03 †Implementation of site emergency plan................. 3.3 4.5*

AK3.04 Power reduction....................................... 3.6 3.8

AK3.05 Control room ventilation: Plant-Specific............. 3.3 3.6

 ABILITY

AA1. Ability to operate and/or monitor the following as

 they apply to HIGH OFF-SITE RELEASE RATE :

(CFR: 41.7 / 45.6)

AA1.01 Radwaste.............................................. 2.7* 3.1

AA1.02 Off-gas system........................................ 3.5 3.7

AA1.03 Plant ventilation systems............................. 3.4 3.4

AA1.04 Stack-gas monitoring system: Plant-Specific.......... 3.6 3.8

AA1.05 SPDS/ERIS/CRIDS/GDS: Plant-Specific.................. 2.7 3.2
NUREG-1123, Rev. 2 4.2-30 |

APE: 295017 High Off-Site Release Rate

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

AA1.06 Condenser air removal system: Plant-Specific......... 3.2 3.2

AA1.07 Process radiation monitoring system................... 3.4 3.6

AA1.08 MSIV leakage control: Plant-Specific................. 3.1 3.4

AA1.09 Standby gas treatment/FRVS............................ 3.6 3.8

AA1.10 RPS................................................... 3.6 3.7

AA1.11 PCIS/NSSSS............................................ 3.9 4.1

AA1.12 †Meteorological data................................... 2.5* 3.9

AA2. Ability to determine and/or interpret the following as

they apply to HIGH OFF-SITE RELEASE RATE :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 †Off-site release rate: Plant-Specific................ 2.9* 4.2*

AA2.02 †Total number of curies released: Plant-Specific...... 2.4* 3.5*

AA2.03 †Radiation levels: Plant-Specific..................... 3.1 3.9

AA2.04 †Source of off-site release............................ 3.6 4.3*

AA2.05 †Meteorological data................................... 2.5 3.8
4.2-31 NUREG-1123, Rev. 2 |

APE: 295018 Partial or Complete Loss of Component Cooling Water

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to PARTIAL OR

COMPLETE LOSS OF COMPONENT COOLING WATER :

(CFR: 41.8 to 41.10)

AK1.01 Effects on component/system operations................ 3.5 3.6

AK2. Knowledge of the interrelations between PARTIAL OR

COMPLETE LOSS OF COMPONENT COOLING WATER and the

following:

(CFR: 41.7 / 45.8) 

AK2.01 System loads.......................................... 3.3 3.4

AK2.02 Plant operations...................................... 3.4 3.6

AK3. Knowledge of the reasons for the following responses

as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT

COOLING WATER :

(CFR: 41.5 / 45.6)

AK3.01 Isolation of non-essential heat loads: Plant-Specific 2.9 3.2

AK3.02 Reactor power reduction............................... 3.3 3.4

AK3.03 Securing individual components (prevent equipment

damage)............................................... 3.1 3.3

AK3.04 Starting standby pump................................. 3.3 3.3

AK3.05 Placing standby heat exchanger in service............. 3.2 3.3

AK3.06 Increasing cooling water flow to heat exchangers...... 3.3 3.3

AK3.07 Cross-connecting with backup systems.................. 3.1 3.2

 ABILITY

AA1. Ability to operate and/or monitor the following as

 they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT

COOLING WATER :

(CFR: 41.7 / 45.6)

AA1.01 Backup systems........................................ 3.3 3.4

AA1.02 System loads.......................................... 3.3 3.4

AA1.03 Affected systems so as to isolate damaged portions.... 3.3 3.4
NUREG-1123, Rev. 2 4.2-32 |

APE: 295018 Partial or Complete Loss of Component Cooling Water

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

AA2. Ability to determine and/or interpret the following as

they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT 

COOLING WATER :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Component temperatures................................ 3.3 3.4

AA2.02 Cooling water temperature............................. 3.1 3.2

AA2.03 Cause for partial or complete loss.................... 3.2 3.5

AA2.04 System flow........................................... 2.9 2.9

AA2.05 System pressure....................................... 2.9 2.9
4.2-33 NUREG-1123, Rev. 2 |

APE: 295019 Partial or Complete Loss of Instrument Air

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to PARTIAL OR

COMPLETE LOSS OF INSTRUMENT AIR :

(CFR: 41.8 to 41.10)

None |

AK2. Knowledge of the interrelations between PARTIAL OR

COMPLETE LOSS OF INSTRUMENT AIR and the following:

(CFR: 41.7 / 45.8) 

AK2.01 CRD hydraulics........................................ 3.8 3.9

AK2.02 Component cooling water............................... 2.9 3.0

AK2.03 Reactor feedwater..................................... 3.2 3.3

AK2.04 Reactor water cleanup................................. 2.8 2.8

AK2.05 Main steam system..................................... 3.4 3.4

AK2.06 Offgas system......................................... 2.8 2.9

AK2.07 Condensate system..................................... 3.2 3.2

AK2.08 Plant ventilation..................................... 2.8 2.9

AK2.09 Containment........................................... 3.3 3.3

AK2.10 Fuel pool cooling..................................... 2.8 2.8

AK2.11 Radwaste.............................................. 2.5 2.6

AK2.12 Standby gas treatment/FRVS............................ 3.3 3.4

AK2.13 Isolation condenser: Plant-Specific.................. 3.2* 3.2*

AK2.14 Plant air systems..................................... 3.2 3.2

AK2.15 Standby liquid control system......................... 2.3* 2.6

AK2.16 Reactor core isolation cooling........................ 2.8 2.8

AK2.17 High pressure coolant injection: Plant-Specific...... 2.7 2.7

AK2.18 ADS: Plant-Specific.................................. 3.5 3.5

AK2.19 RHR/LPCI: Plant-Specific............................. 2.7 2.8

AK3. Knowledge of the reasons for the following responses

as they apply to PARTIAL OR COMPLETE LOSS OF

INSTRUMENT AIR :

(CFR: 41.5 / 45.6)

AK3.01 Backup air system supply: Plant-Specific............. 3.3 3.4

AK3.02 Standby air compressor operation...................... 3.5 3.4

AK3.03 Service air isolations: Plant-Specific............... 3.2 3.2

 ABILITY

AA1. Ability to operate and/or monitor the following as

they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT

AIR :

(CFR: 41.7 / 45.6)

AA1.01 Backup air supply..................................... 3.5 3.3
NUREG-1123, Rev. 2 4.2-34 |

APE: 295019 Partial or Complete Loss of Instrument Air

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

AA1.02 Instrument air system valves: Plant-Specific......... 3.3 3.1

AA1.03 Instrument air compressor power supplies.............. 3.0 3.0

AA1.04 Service air isolations valves: Plant-Specific........ 3.3 3.2

AA2. Ability to determine and/or interpret the following as

they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT

AIR :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Instrument air system pressure........................ 3.5 3.6

AA2.02 Status of safety-related instrument air system loads

(see AK2.1 - AK2.19).................................. 3.6 3.7
4.2-35 NUREG-1123, Rev. 2 |

APE: 295020 Inadvertent Containment Isolation

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

 following concepts as they apply to INADVERTENT

 CONTAINMENT ISOLATION :

(CFR: 41.8 to 41.10)

AK1.01 Loss of normal heat sink.............................. 3.7 3.9

AK1.02 Power/reactivity control.............................. 3.5 3.8

AK1.03 Water chemistry....................................... 2.3 2.5

AK1.04 Bottom head thermal stratification.................... 2.5 2.8

AK1.05 Loss of drywell/containment cooling................... 3.3 3.6

AK2. Knowledge of the interrelations between INADVERTENT

CONTAINMENT ISOLATION and the following:

(CFR: 41.7 / 45.8) 

AK2.01 Main steam system..................................... 3.6 3.7 |

AK2.02 Sampling system....................................... 2.6 2.8

AK2.03 Drywell/containment ventilation/cooling: PlantSpecific.............................................. 3.1 3.3

AK2.04 RWCU system........................................... 3.1 3.1

AK2.05 Isolation condenser: Plant-Specific.................. 4.2* 4.2

AK2.06 HPCI: Plant-Specific................................. 3.8 3.8

AK2.07 RCIC: Plant-Specific................................. 3.4 3.4

AK2.08 Traversing in-core probes: Plant-Specific............ 2.5* 2.6

AK2.09 RHR/shutdown cooling: Plant-Specific................. 3.1 3.3

AK2.10 Drywell equipment/floor drain sumps................... 2.9 3.1

AK2.11 Standby gas treatment system/FRVS: Plant-Specific.... 3.2 3.4

AK2.12 Instrument air/nitrogen: Plant-Specific.............. 3.1 3.2

AK3. Knowledge of the reasons for the following responses

as they apply to INADVERTENT CONTAINMENT ISOLATION:

(CFR: 41.5 / 45.6)

AK3.01 Reactor SCRAM........................................... 3.8 3.8

AK3.02 Drywell/containment pressure response................... 3.3 3.5

AK3.03 Drywell/containment temperature response................ 3.2 3.2

AK3.04 Reactor pressure response............................... 4.1 4.1

AK3.05 Reactor water level response............................ 3.8 3.9

AK3.06 Suppression pool water level response................... 3.3 3.4

AK3.07 Suppression pool temperature response................... 3.4 3.6

AK3.08 Suppression chamber pressure response................... 3.3 3.5
NUREG-1123, Rev. 2 4.2-36 |

APE: 295020 Inadvertent Containment Isolation

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

AA1. Ability to operate and/or monitor the following as 

they apply to INADVERTENT CONTAINMENT ISOLATION :

(CFR: 41.7 / 45.6)

AA1.01 PCIS/NSSSS............................................ 3.6 3.6

AA1.02 Drywell ventilation/cooling system.................... 3.2 3.2

AA1.03 Containment ventilation system: Plant-Specific....... 2.9 3.1

AA2. Ability to determine and/or interpret the following as

they apply to INADVERTENT CONTAINMENT ISOLATION :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Drywell/containment pressure.......................... 3.6 3.7

AA2.02 Drywell/containment temperature....................... 3.3 3.4

AA2.03 Reactor power......................................... 3.7 3.7

AA2.04 Reactor pressure...................................... 3.9 3.9

AA2.05 Reactor water level................................... 3.6 3.6

AA2.06 Cause of isolation.................................... 3.4 3.8
4.2-37 NUREG-1123, Rev. 2 |

APE: 295021 Loss of Shutdown Cooling

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to LOSS OF SHUTDOWN

COOLING :

(CFR: 41.8 to 41.10)

AK1.01 Decay heat............................................ 3.6 3.8

AK1.02 Thermal stratification................................ 3.3 3.4

AK1.03 Adequate core cooling................................. 3.9 3.9

AK1.04 Natural circulation................................... 3.6 3.7

AK2. Knowledge of the interrelations between LOSS OF

SHUTDOWN COOLING and the following:

(CFR: 41.7 / 45.8) 

AK2.01 Reactor water temperature............................. 3.6 3.7

AK2.02 Reactor water cleanup................................. 3.2 3.3

AK2.03 RHR/shutdown cooling.................................. 3.6 3.6

AK2.04 Component cooling water systems: Plant-Specific...... 3.0 3.1

AK2.05 Fuel pool cooling and cleanup system.................. 2.7 2.8

AK2.06 Reactor vessel headspray: Plant-Specific............. 2.5 2.6

AK2.07 Reactor recirculation................................. 3.1 3.2

AK3. Knowledge of the reasons for the following responses

as they apply to LOSS OF SHUTDOWN COOLING :

(CFR: 41.5 / 45.6)

AK3.01 Raising reactor water level........................... 3.3 3.4

AK3.02 Feeding and bleeding reactor vessel................... 3.3 3.4

AK3.03 Increasing drywell cooling............................ 2.9 2.9

AK3.04 Maximizing reactor water cleanup flow................. 3.3 3.4

AK3.05 Establishing alternate heat removal flow paths........ 3.6 3.8

 ABILITY

AA1. Ability to operate and/or monitor the following as

 they apply to LOSS OF SHUTDOWN COOLING :

(CFR: 41.7 / 45.6)

AA1.01 Reactor water cleanup system.......................... 3.4 3.4

AA1.02 RHR/shutdown cooling.................................. 3.5 3.5

AA1.03 Component cooling water systems: Plant-Specific...... 3.1 3.1

AA1.04 Alternate heat removal methods........................ 3.7 3.7

AA1.05 Reactor recirculation................................. 3.0 3.0

AA1.06 Containment/ drywell temperature...................... 2.8 3.0
NUREG-1123, Rev. 2 4.2-38 |

APE: 295021 Loss of Shutdown Cooling

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

AA2. Ability to determine and/or interpret the following as

they apply to LOSS OF SHUTDOWN COOLING :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Reactor water heatup/cooldown rate .................... 3.5 3.6

AA2.02 RHR/shutdown cooling system flow .................... 3.4 3.4

| AA2.03 Reactor water level ................................... 3.5 3.5

| AA2.04 Reactor water temperature ............................. 3.6 3.6

| AA2.05 Reactor vessel metal temperature ...................... 3.4 3.5

AA2.06 Reactor pressure ...................................... 3.2 3.3

AA2.07 Reactor recirculation flow ............................ 2.9 3.1
4.2-39 NUREG-1123, Rev. 2 |

APE: 295022 Loss of CRD Pumps

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the 

following concepts as they apply to LOSS OF CRD PUMPS:

(CFR: 41.8 to 41.10)

AK1.01 Reactor pressure vs. rod insertion capability......... 3.3 3.4

AK1.02 Reactivity control.................................... 3.6 3.7

AK2. Knowledge of the interrelations between LOSS OF CRD

PUMPS and the following:

(CFR: 41.7 / 45.8) 

AK2.01 Recirculation system: Plant-Specific................. 2.8 3.0

AK2.02 CRD mechanism......................................... 3.1 3.1

AK2.03 Accumulator pressures................................. 3.4 3.4

AK2.04 Reactor water level................................... 2.5 2.7

AK2.05 Reactor water cleanup: Plant-Specific................ 2.4 2.5

AK2.06 Shared components with other units: Plant-Specific... 2.6 2.8

AK2.07 Reactor pressure (SCRAM assist): Plant-Specific...... 3.4 3.6

AK3. Knowledge of the reasons for the following responses

as they apply to LOSS OF CRD PUMPS:

(CFR: 41.5 / 45.6)

AK3.01 Reactor SCRAM......................................... 3.7* 3.9*

AK3.02 CRDM high temperature................................. 2.9 3.1

 ABILITY

AA1. Ability to operate and/or monitor the following as

 they apply to LOSS OF CRD PUMPS:

(CFR: 41.7 / 45.6)

AA1.01 CRD hydraulic system.................................. 3.1 3.2

AA1.02 RPS................................................... 3.6 3.6

AA1.03 Recirculation system: Plant-Specific................. 2.7 2.8

AA1.04 Reactor water cleanup system: Plant-Specific......... 2.5 2.6

AA2. Ability to determine and/or interpret the following as

they apply to LOSS OF CRD PUMPS :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Accumulator pressure.................................. 3.5 3.6

AA2.02 CRD system status..................................... 3.3 3.4

AA2.03 CRD mechanism temperatures............................ 3.1 3.2
NUREG-1123, Rev. 2 4.2-40 |

APE: 295023 Refueling Accidents

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1. Knowledge of the operational implications of the

following concepts as they apply to REFUELING

ACCIDENTS :

(CFR: 41.8 to 41.10)

AK1.01 Radiation exposure hazards............................ 3.6 4.1

AK1.02 Shutdown margin....................................... 3.2 3.6

AK1.03 Inadvertent criticality............................... 3.7 4.0

AK2. Knowledge of the interrelations between REFUELING

ACCIDENTS and the following:

(CFR: 41.7 / 45.8) 

AK2.01 Fuel handling equipment............................... 3.3 3.7

AK2.02 Fuel pool cooling and cleanup system.................. 2.9 3.2

AK2.03 Radiation monitoring equipment........................ 3.4 3.6

AK2.04 RMCS/Rod control and information system............... 3.2 3.4

AK2.05 Secondary containment ventilation..................... 3.5 3.7

AK2.06 Containment ventilation: Mark-III.................... 3.4 3.8

AK2.07 Standby gas treatment/FRVS............................ 3.6 3.9

AK3. Knowledge of the reasons for the following responses

as they apply to REFUELING ACCIDENTS :

(CFR: 41.5 / 45.6)

AK3.01 Refueling floor evacuation............................ 3.6 4.3*

AK3.02 Interlocks associated with fuel handling equipment.... 3.4 3.8

AK3.03 Ventilation isolation................................. 3.3 3.6

AK3.04 Non-coincident SCRAM function......................... 3.0 3.5

AK3.05 Initiation of SLC/shut-down cooling: PlantSpecific(BWR-1)....................................... 3.5 4.0

 ABILITY

AA1. Ability to operate and/or monitor the following as

they apply to REFUELING ACCIDENTS :

(CFR: 41.7 / 45.6)

AA1.01 Secondary containment ventilation..................... 3.3 3.5

AA1.02 Fuel pool cooling and cleanup system.................. 2.9 3.1

AA1.03 Fuel handling equipment............................... 3.3 3.6

AA1.04 Radiation monitoring equipment........................ 3.4 3.7

AA1.05 Fuel transfer system: Plant-Specific................. 2.8 3.5

AA1.06 Neutron monitoring.................................... 3.3 3.4

AA1.07 Standby gas treatment/FRVS............................ 3.6 3.6

AA1.08 †Containment building ventilation: Mark-III......... 3.3 3.4
4.2-41 NUREG-1123, Rev. 2 |

APE: 295023 Refueling Accidents

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

AA2. Ability to determine and/or interpret the following as

they apply to REFUELING ACCIDENTS :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Area radiation levels................................. 3.6 4.0

AA2.02 Fuel pool level....................................... 3.4 3.7

AA2.03 Airborne contamination levels......................... 3.3* 3.8*

AA2.04 †Occurrence of fuel handling accident.................. 3.4 4.1

AA2.05 †Entry conditions of emergency plan.................... 3.2 4.6*
NUREG-1123, Rev. 2 4.2-42 |

APE: 600000 Plant Fire On Site

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

AK1 Knowledge of the operation applications of the 

following concepts as they apply to Plant Fire On Site:

AK1.01 Fire Classifications by type .............................................. 2.5 2.8 

AK1.02 Fire Fighting ........................................................... 2.9 3.1

AK2. Knowledge of the interrelations between PLANT FIRE 

ON SITE and the following: 

AK2.01 Sensors / detectors and valves ............................................ 2.6 2.7

AK2.02 Controllers and positioners .............................................. 2.4 2.5

AK2.03 Motors ............................................................... 2.5 2.6

AK2.04 Breakers / relays / and disconnects ......................................... 2.5 2.6

AK3 Knowledge of the reasons for the following responses

as they apply to PLANT FIRE ON SITE:

AK3.01 Installation of fire detectors .............................................. 2.0 2.1

AK3.02 Steps called our in the site fire protection plant /

fire protection system manual / and fire zone manual ......................... 2.2 2.8

AK3.03 Fire detector surveillance test ............................................. 2.0 2.2

AK3.04 Actions contained in the abnormal procedure for plant

fire on site ............................................................. 2.8 3.4
4.2-43 NUREG-1123, Rev. 2 |

APE: 600000 Plant Fire On Site

 

 IMPORTANCE 

K/A NO. ABILITY RO SRO

AA1 Ability to operate and / or monitor the following as 

theyapply to PLANT FIRE ON SITE: 

AA1.01 Respirator air pack ...................................................... 3.0 2.9

AA1.02 Re-installation of fire detector ............................................ 1.8 1.9

AA1.03 Bypass of fire zone detector .............................................. 1.8 2.2

AA1.04 Bypass of heat detector .................................................. 1.9 2.2

AA1.05 Plant and control room ventilation systems .................................. 3.0 3.1

AA1.06 Fire alarm ............................................................. 3.0 3.0

AA1.07 Fire alarm reset panel .................................................... 2.3 2.4

AA1.08 Fire fighting equipment used on each class of fire ............................ 2.6 2.9

AA1.09 Plant fire zone panel (including detector location) ............................ 2.5 2.7

AA2 Ability to determine and interpret the following as they 

apply to PLANT FIRE ON SITE:

AA2.01 Gas treatment system ................................................... 2.2 2.3

AA2.02 Damper position ........................................................ 2.8 2.9

AA2.03 Fire alarm ............................................................. 2.8 3.2

AA2.04 The fire's extent of potential operational damage

to plant equipment ...................................................... 2.8 3.1

AA2.05 Ventilation alignment necessary to secure 

affected area ........................................................... 2.9 3.0

AA2.06 Need for pressurizing control room 

(recirculating mode) .................................................... 2.5 2.8

AA2.07 Whether malfunction is due to common-mode electrical

failures ................................................................ 2.6 3.0

AA2.08 Limits of affected area

AA2.09 That a failed fire alarm detector exists ...................................... 2.4 2.8

AA2.10 Time limit of long-term-breathing air system for 

control room ........................................................... 2.9 3.1

AA2.11 Time limit for use of respirators .......................................... 2.9 3.0

AA2.12 Location of vital equipment within fire zone ................................. 3.1 3.5

AA2.13 Need for emergency plant shutdown ....................................... 3.2 3.8

AA2.14 Equipment that will be affected by fire suppression

activities in each zone ................................................... 3.0 3.6

AA2.15 Requirements for establishing a fire watch .................................. 2.3 3.5

AA2.16 Vital equipment and control systems to be maintained

and operated during a fire ................................................ 3.0 3.5

AA2.17 Systems that may be affected by the fire .................................... 3.1 3.6
NUREG-1123, Rev. 2 4.2-44 |

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5-1 NUREG-1123, Rev. 2 |

5 Components page

291001 Valves 5-3

291002 Sensors and Detectors 5-4

291003 Controllers and Positioners 5-6

291004 Pumps 5-7

291005 Motors and Generators 5-9

291006 Heat Exchangers and Condensers 5-10

291007 Demineralizers and Ion Exchangers 5-11

291008 Breakers, Relays and Disconnects 5-12
NUREG-1123, Rev. 2 5-2 |

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5-3 NUREG-1123, Rev. 2 |

COMPONENT: 291001 Valves

 (CFR: 41.3)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 The operation of safety valves 3.4 3.5

K1.02 The operation of relief valves 3.4 3.6

K1.03 The relationship of valve position to flow rate and

back pressure 2.7 2.8

K1.04 Valve design for a given failed-valve position (open,

closed, and as-is positions; spring loaded valves;

hydraulic, pneumatically controlled valves; electric

motor-driven valves) 2.7 2.8

K1.05 The significance of stem position (valve status) for

gate valves 2.9 2.8

K1.06 Safety concerns in the use of gate valves (protect

valves seals, open slowly) 2.7 2.7

K1.07 Cautions for placing a valve controller in manual mode 3.4 3.4

K1.08 Emergency operation of MOV with motor inoperable 3.4 3.5

K1.09 The stroke test for a valve, including the use of a

stopwatch 2.7 2.7

K1.10 Principles of operation and purpose of check valves 3.1 3.1

K1.11 Operation of manual valves and verification of

position with indicator lights 3.2 3.2

K1.12 Reason for using globe valves versus gates valves for

throttling 2.6 2.8
NUREG-1123, Rev. 2 5-4 |

COMPONENT: 291002 Sensors/Detectors

(CFR: 41.7)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

 Flow

K1.01 Operation of venturis and orifices 2.4 2.5

K1.02 Temperature compensation requirements 2.4 2.5

K1.03 Effects of gas or steam on liquid flow rate

indications (erroneous reading) 2.5 2.6

K1.04 Modes of failure 2.9 3.1

K1.05 Operation of a flow D/P cell type flow detector 3.1 3.1

 Level

K1.06 Temperature/pressure compensation requirements 2.8 2.9

K1.07 Operation of a differential pressure level detector 3.2 3.2

K1.08 Effects of operating environment (pressure,

temperature, and radiation) 2.8 2.9

K1.09 Modes of failure 3.3 3.3

 Pressure

K1.10 Theory of operation of bourdon tubes, diaphragms,

bellows, and pressure detectors 2.4 2.5

K1.11 Effects of operating environment (pressure,

temperature, radiation) 2.3 2.5

K1.12 Operation of a pressure D/P cell 2.8 2.9

K1.13 Modes of failure 2.9 3.1

 Temperature

K1.14 Theory of operation of T/C, RTD, thermostats,

thermometers (expanding fluid) 2.3* 2.4

K1.15 Indications of failure modes of T/C, RTD, thermometers 2.6 2.8

 Position Detector_

K1.16 Failure modes of reed switches, LVDT, limit switches, 

and potentiometers 2.5 2.7
5-5 NUREG-1123, Rev. 2 |

COMPONENT: 291002 Sensors/Detectors

(CFR: 41.7)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.17 Applications of reed switches, magnets, LVDT,

potentiometers, and limit switches 2.3* 2.4

Electrical

K1.18 Applications of voltmeters, ammeters, frequency, and

ground detectors 2.2* 2.4

Nuclear Instrumentation

K1.19 Operation of fission chambers, ion chambers 3.0 3.1

K1.20 Neutron monitoring indication units 3.2 3.2

K1.21 Effects of voltage changes on neutron detector

performance 2.8 2.9

K1.22 Failure modes of fission chambers, ion chambers, and

proportional counters 3.0 3.1

Radiation Detection

K1.23 Operation of ion chambers, G-M tubes and scintillation

detectors 2.8 2.9

K1.24 Use of portable radiation monitoring instruments 3.1 3.2
NUREG-1123, Rev. 2 5-6 |

COMPONENT: 291003 Controllers and Positioners

(CFR: 41.7)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Function and operation of flow controller in manual

and automatic modes 3.5 3.7

K1.02 Function and operation of a speed controller 3.5 3.6

K1.03 Operation of a valve controller, including seal-in

features 3.3 3.4

K1.04 Function and operation of pressure and temperature

controllers, including pressure and temperature

control valves 3.3 3.3

K1.05 Function and characteristics of valve positioners 2.8 2.8

K1.06 Function and characteristics of governors and other

mechanical controllers 2.5 2.6

K1.07 Safety precautions with respect to the operation of

controllers and positioners 2.8 2.8

K1.08 Theory of operation of the following types of

controllers: electronic, electrical, and pneumatic 2.2* 2.2*

K1.09 Effects on operation of controllers due to

proportional, proportional and reset, and proportional

and integral features 2.0* 2.2*
5-7 NUREG-1123, Rev. 2 |

COMPONENT: 291004 Pumps

(CFR: 41.3)

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

 Centrifugal

K1.01 Identification, symptoms, and consequences of

cavitation 3.2 3.2

K1.02 Reasons for venting a centrifugal pump 2.8 2.8

K1.03 Consequences of air binding 2.8 2.9

K1.04 Consequences of operating a pump dead headed or for

extended recirculation times 3.0 3.1

K1.05 Discuss relationships among head, flow, speed, and

power 2.8 2.9

K1.06 Need for net positive suction head (NPSH); effects of

loss of suction 3.3 3.3

K1.07 Starting current and operating current interpretation 2.8 2.8

K1.08 Purpose of starting a pump with discharge valve closed 2.8 2.8

K1.09 Pressure and flow relationship of pumps in parallel 2.3* 2.4*

K1.10 Pressure and flow relationship of pumps in series 2.3* 2.4*

K1.11 Definition of pump shutoff head 2.4 2.5

K1.12 "Runout" of a centrifugal pump (definition,

indications, causes, effects, and corrective measures) 2.8 2.8

K1.13 Principles of operation of a centrifugal pump 2.6 2.7

K1.14 Relationship between flow from a pump and suction

heads 2.5 2.5

K1.15 Purpose of pump minimum flow requirements

Positive Displacement 2.9 2.9

K1.16 Discuss relationship among head, flow, speed, and

power 2.5 2.7

K1.17 Net positive suction head (NSPH) requirements for a

positive displacement pump 2.5 2.6

K1.18 Consequences of operating a positive displacement pump

 against a closed flow path 3.3 3.3
NUREG-1123, Rev. 2 5-8 |

COMPONENT: 291004 Pumps

(CFR: 41.3)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.19 Functions and characteristics of positive displacement 

pumps 2.6 2.6

K1.20 Reason for starting a positive displacement pump with 

the discharge valve open; need to clear the flow path 3.1 3.1

K1.21 Safety procedures and precautions associated with 

positive displacement pumps 3.1 3.0
5-9 NUREG-1123, Rev. 2 |

COMPONENT: 291005 Motors and Generators

(CFR: 41.7)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Locked motor rotor, recognition from motor parameters 2.6 2.6

K1.02 Potential consequences of overheating motor insulation

or motor bearings 2.6 2.7

K1.03 Causes of excessive current in motors, such as low

voltage, overloading , and mechanical binding 2.6 2.7

K1.04 Relationship between pump motor current (ammeter

reading) and the following: pump fluid flow, head,

speed, and stator temperature 2.7 2.7

K1.05 Explain the difference between starting current and

operating (running) current in a motor 2.6 2.7

K1.06 Reason for limiting the number of motor starts in a

given time period 2.9 3.1

K1.07 Electrical units: volts, amps, A.C., D.C., and hertz 2.6 2.6

K1.08 Consequences of overexcited/underexcited 2.5 2.6

K1.09 †Interrelations of the following: VARs, Watts, Amps,

Volts, Power factor 2.3* 2.6
NUREG-1123, Rev. 2 5-10 |

COMPONENT: 291006 Heat Exchangers and Condensers

(CFR: 41.4)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Startup/shutdown of a heat exchanger 2.7 2.7

K1.02 Proper filling of a shell-and-tube heat exchanger 2.6 2.6

K1.03 Basic heat transfer in a heat exchanger 2.4 2.6

K1.04 Effects of heat exchanger flow rates that are too high

or too low 2.8 2.8

K1.05 Flow paths for the heat exchanger (counterflow and Utypes) 2.2* 2.3*

K1.06 Components of a heat exchanger (shells, tubes, plates,

etc.) 2.3* 2.3*

K1.07 Control of heat exchanger temperatures 2.7 2.8

K1.08 Relationship between flow rates and temperatures 2.9 3.0

K1.09 Definition of thermal shock 2.7 2.8

K1.10 Principle of operation of condensers 2.8 2.8

K1.11 Relationship between condenser vacuum and backpressure 2.8 2.8

K1.12 Causes of natural circulation 2.9 3.0

K1.13 Use of steam tables to determine saturation pressure

for a given temperature and vice versa 2.7 2.9

K1.14 Fluid hammer and methods of prevention 3.1 3.2

K1.15 Effects of heat exchanger tube fouling 2.6 2.8

K1.16 Effects of scaling on heat exchanger operation 2.5 2.6

K1.17 Consequences of heat exchanger tube failure 2.7 2.8

K1.18 Reasons for non-condensible gas removal 2.8 2.9
5-11 NUREG-1123, Rev. 2 |

COMPONENT: 291007 Demineralizers and Ion Exchangers

(CFR: 41.3)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Effect of excessive differential pressure on 

demineralizer performance 2.6 2.7

K1.02 Reason for sampling inlet and outlet of demineralizer 2.5 2.6 |

K1.03 Effects of channeling in a demineralizer 2.8 2.9 |

K1.04 Purpose of a demineralizer 2.8 2.9 |

K1.05 Purpose of demineralizer D/P gauge 2.4 2.5

K1.06 Reason for demineralizer temperature and flow limits 2.7 2.7

K1.07 Principles of demineralizer operation 2.3* 2.5

K1.08 Demineralizer D/P to determine condition of 2.6 2.6 |

demineralizer resin bed

K1.09 Effects of demineralizer operation on water

conductivity 2.7 2.7
NUREG-1123, Rev. 2 5-12 |

COMPONENT: 291008 Breakers, Relays and Disconnects

(CFR: 41.7)

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Purpose for racking out breakers (de-energize

components and associated control and indication

circuits) 3.6 3.6

K1.02 Local indication that breaker is open, closed or

tripped 3.4 3.5

K1.03 Meaning of power supply circuit breaker indicator

lights and capability to remotely open and close 3.3 3.4

K1.04 Operation of various push buttons, switches and

handles and the resulting action on breakers 3.3 3.3

K1.05 Function of thermal overload protection device 3.0 3.1

K1.06 Interpreting one-line diagram of control circuitry 3.2 3.6

K1.07 Safety procedures and precautions associated with

breakers, including MCC bus breakers, high, medium and

low voltage breakers, relays and disconnects 3.5* 3.7

K1.08 Effects of closing breakers with current out of phase,

different frequencies, high voltage differential, low

current, or too much load 3.4 3.5

K1.09 Effect of racking out breakers on control and

indicating circuits and removal of control power on

breaker operation 3.4 3.5

K1.10 Function, control, and precautions associated with

disconnects 3.3* 3.4
6.1-1 NUREG-1123, Rev. 2 |

6 Theory page

6.1 Reactor Theory

292001 Neutrons 6.1-3

292002 Neutron Life Cycle 6.1-4

292003 Reactor Kinetics and Neutron Sources 6.1-5

292004 Reactivity Coefficients 6.1-6

292005 Control Rods 6.1-7

292006 Fission Product Poisons 6.1-8

292007 Fuel Depletion and Burnable Poisons 6.1-10

292008 Reactor Operational Physics 6.1-11

6.2 Thermodynamics Theory

293001 Thermodynamic Units and Properties 6.2-1

293002 Basic Energy Concepts 6.2-2

293003 Steam 6.2-3

293004 Thermodynamic Process 6.2-4

293005 Thermodynamic Cycles 6.2-5

293006 Fluid Statics 6.2-6

293007 Heat Transfer and Heat Exchangers 6.2-8

293008 Thermal Hydraulics 6.2-9

293009 Core Thermal Limits 6.2-12

293010 Brittle Fracture and Vessel Thermal Stress 6.2-15
NUREG-1123, Rev. 2 6.1-2 |

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6.1-3 NUREG-1123, Rev. 2 |

6.1 Reactor Theory

 (CFR: 41.1)

REACTOR THEORY: 292001 Neutrons

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Define fast, intermediate, and slow neutrons. 2.0* 2.1*

K1.02 Define prompt and delayed neutrons. 3.0 3.1

K1.03 Define thermal neutrons. 2.7 2.7

K1.04 Describe neutron moderation. 3.2 3.2

K1.05 Identify characteristics of good moderators. 2.4* 2.6*

K1.06 Define neutron lifetime. 1.9* 1.9*

K1.07 Define neutron generation time. 1.9* 1.9*

K1.08 Describe fast flux, thermal flux, and flux

distribution. 2.2* 2.4
NUREG-1123, Rev. 2 6.1-4 |

REACTOR THEORY: 292002 Neutron Life Cycle

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

Describe the neutron life cycle using the following

terms:

K1.01 --fast fission factor. 1.9* 1.9*

K1.02 --fast non-leakage probability factor. 1.9* 1.9*

K1.03 --resonance escape probability factor. 2.0* 2.1*

K1.04 --thermal non-leakage probability factor. 1.9* 2.0*

K1.05 --thermal utilization factor. 1.9* 2.0*

K1.06 --reproduction factor. 1.9* 1.9*

K1.07 Define critical, subcritical, and supercritical with

respect to a reactor. 3.5* 3.5

K1.08 Define effective multiplication factor and discuss its

relationship to the state of d reactor. 2.7 2.8

K1.09 Define K-excess. 2.4* 2.6

K1.10 Define shutdown margin. 3.2 3.5

K1.11 Define reactivity. 3.2 3.3

K1.12 State the relationship between reactivity and

effective multiplication factor. 2.4 2.5

K1.13 †Calculate shutdown margin using procedures and given

| plant parameters 1.8* 2.4*

K1.14 †Evaluate change in shutdown margin due to changes in

plant parameters 2.6 2.9
6.1-5 NUREG-1123, Rev. 2 |

REACTOR THEORY: 292003 Reactor Kinetics and Neutron Sources

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Explain the concept of subcritical multiplication. 2.9 3.0

K1.02 Given the simplified formula for subcritical

multiplication, perform calculations involving steady

state count rate and source count rate. 2.1* 2.3*

K1.03 Describe the production of delayed neutrons. 2.4 2.4

K1.04 Define delayed neutron fraction and effective delayed

neutron fraction; state the reasons for variation. 2.5 2.5

K1.05 Define reactor period. 3.7 3.7

K1.06 Explain the effect of delayed neutrons on reactor

period. 3.7 3.7

K1.07 Explain prompt critical, prompt jump, and prompt drop. 3.3 3.3

K1.08 Given the power equation, solve problems for power

changes and period. 2.7 2.8

K1.09 Define doubling time and calculate it using the power

equation. 2.5* 2.6*

K1.10 Explain the necessity for installed neutron sources in

a reactor core. 2.4* 2.4

K1.11 Explain why installed sources are not needed after one

cycle of core operation. 2.4 2.4
NUREG-1123, Rev. 2 6.1-6 |

REACTOR THEORY: 292004 Reactivity Coefficients

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Define the temperature coefficient of reactivity. 3.2 3.2

K1.02 Describe the effect on the magnitude of the

temperature coefficient of reactivity from changes in

moderator temperature and core age. 2.5* 2.6*

K1.03 Explain resonance absorption. 2.6 2.7

K1.04 Explain doppler broadening and self-shielding. 2.6 2.7

K1.05 Define the doppler coefficient of reactivity. 2.9 2.9

Describe the effect on the magnitude of the doppler

coefficient of reactivity for changes in the

following:

K1.06 --Moderator temperature 2.1* 2.2*

K1.07 --Core void fraction 2.1* 2.2*

K1.08 --Fuel temperature 2.2* 2.4*

K1.09 --Core age 1.9* 2.1*

K1.10 Define the void coefficient of reactivity. 3.2 3.2

Describe the effect on the magnitude of void

coefficient from changes in the following:

K1.11 --Core void fraction 2.5 2.6

Kl. 12 --Fuel temperature 2.2* 2.3*

K1.13 --Core age 2.1* 2.2*

K1.14 Compare the relative magnitudes of the temperature,

doppler, and void coefficients of reaCtivitY. 3.3 3.3
6.1-7 NUREG-1123, Rev. 2 |

REACTOR THEORY: 292005 Control Rods

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Relate notch and rod position. 3.2* 3.3*

K1.02 Name the material used for thermal neutron absorption

in control rods. 2.5 2.6

K1.03 Describe nuclear properties of active material in the

rod. 1.9* 1.9*

K1.04 Predict direction of change in reactor power for a

change in control rod position. 3.5 3.5

K1.05 Define rod density. 2.5* 2.6

K1.06 Define reactor scram. 3.7* 3.8*

K1.07 Define control rod worth, differential control rod

worth, and integral control rod worth. 2.4 2.6

K1.08 Explain the shape of curves for differential and

integral CRW versus rod position. 2.1* 2.3

K1.09 Explain direction of change in the magnitude of CRW

for a change in moderator temperature, void fraction,

and control rod density, and Xenon. 2.5* 2.6

K1.10 †State the purpose of flux shaping and rod sequencing. 2.8 3.3

K1.11 Define deep rods, and shallow rods. 2.4* 2.5*

K1.12 †Describe effects of deep, and shallow control rods on 

axial and radial flux distribution. 2.6 2.9
NUREG-1123, Rev. 2 6.1-8 |

REACTOR THEORY: 292006 Fission Product Poisons

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Define fission product poison. 2.7 2.8

K1.02 State the characteristics of Xenon-135 as a fission

product poison. 3.1 3.1

K1.03 Describe the production of Xenon-135. 2.9 2.9

K1.04 Describe the removal of Xenon-135. 2.9 2.9

Describe the following processes and state their

effect on reactor operations:

K1.05 --Equilibrium Xenon 2.9 2.9

K1.06 --Maneuvering Xenon 2.7 2.7

K1.07 --Xenon following a scram 3.2 3.2

K1.08 †Describe the effects that Xenon concentration has on

flux shape and control rod patterns. 2.8 3.2

Plot the curve and explain the reasoning for the

reactivity insertion by Xenon-135 versus time for the

following:

K1.09 --Initial reactor startup and ascension to rated

power. 2.5 2.5

K1.10 --Reactor startup with Xenon-135 already present in

the core 2.9 2.9

K1.11 --Power changes from steady-state power to another. 2.6 2.7

K1.12 --Reactor scram. 2.8 2.3

K1.13 --Reactor shutdown. 2.6* 2.6

K1.14 Explain the process and reasons for the Reactor

Operator to compensate for the time dependent behavior

of Xenon-135 concentration in the reactor. 3.1 3.2

K1.15 State the characteristics of Samarium-149 as a fission

| product poison. 2.1* 2.1*

K1.16 Describe the production of Samarium-149. 1.8* 1.9*

K1.17 Describe the removal of Samarium-149. 1.9* 1.9*
6.1-9 NUREG-1123, Rev. 2 |

REACTOR THEORY: 292006 Fission Product Poisons

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.18 Define equilibrium samarium. 1.8* 1.8*

Plot the curve and explain the reasoning for

reactivity insertion by Samarium-149 versus time for

the following:

K1.19 --Initial reactor startup and ascension to rated

power. 1.7* 1.8*

K1.20 --Reactor shutdown. 1.6* 1.7*

K1.21 Describe effects of power changes on samarium

concentration. 1.7* 1.8*

K1.22 Compare effects of Samarium-149 on reactor operation

with those of Xenon-135. 2.4* 2.4
NUREG-1123, Rev. 2 6.1-10 |

REACTOR THEORY: 292007 Fuel Depletion And Burnable Poisons

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Define burnable poison and state its use in the

reactor. 2.9 3.1

K1.02 Describe and explain distribution of burnable poisons

in the core. 1.8* 2.0*

K1.03 †Given a curve of K-effective versus core age, state

the reasons for maximum, minimum, and inflection

points. 2.4* 2.7
6.1-11 NUREG-1123, Rev. 2 |

REACTOR THEORY: 292008 Reactor Operational Physics

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

 Startup and Approach to Criticality

K1.01 List parameters which should be monitored and

controlled during the approach to criticality. 3.8 3.9*

K1.02 List reactivity control mechanisms which exist for

plant conditions during the approach to criticality. 3.8 3.8

K1.03 Describe count rate and period response which should

be observed for rod withdrawal during the approach to

criticality. 4.1 4.0

K1.04 Relate the concept of subcritical multiplication to

predicted count rate and period response for control

rod withdrawal during the approach to critical. 3.3 3.4

K1.05 Explain characteristics to be observed when the

reactor is very close to criticality. 4.3* 4.3*

 Criticality

K1.06 List parameters which should be monitored and

controlled upon reaching initial criticality. 4.2* 4.2

K1.07 Define criticality as related to a reactor startup. 3.9 3.9

K1.08 Describe reactor power and period response once

criticality is reached. 4.1 4.1

 Intermediate Range Operation

K1.09 List parameters which should be monitored and

controlled during the intermediate phase of startup. 3.9* 3.9*

K1.10 Explain procedures for adjusting reactor period during

the intermediate phase of startup. 3.6 3.6

K1.11 Discuss the concept of the point of adding heat (POAH)

and its impact on reactor power. 3.7 3.8

K1.12 Describe reactor power and period response prior to

reaching the POAH. 3.6 3.7

K1.13 Explain characteristics to look for when the POAH is

reached. 3.8 3.9
NUREG-1123, Rev. 2 6.1-12 |

REACTOR THEORY: 292008 Reactor Operational Physics

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

 Heatup Operation

K1.14 Describe three parameters to be monitored and

controlled during heatup. 3.5 3.5

K1.15 Describe reactor power and period response after

reaching the point of adding heat. 3.7 3.7

K1.16 Explain procedures for establishing and controlling

heatup rate. 3.6 3.7

 Power Operation

K1.17 Describe three parameters to be monitored and

controlled during power operation. 3.6 3.6

K1.18 Describe means by which reactor power will be

increased to rated power. 3.8 3.8

K1.19 Explain transient and steady-state effects of a

control rod withdrawal on reactor power and void

fraction content. 3.1 3.2

K1.20 Explain transient and steady-state effects of an

increase in core flow on reactor power and void

fraction. 3.3 3.4

K1.21 Explain the relationship between steam production rate

and reactor power given specific conditions. 2.9 3.0

K1.22 Explain the effect that opening steam bypass valves,

during power operation, will have on reactor power. 3.5 3.6

K1.23 †Explain the necessity for rod pattern exchanges. 2.6 3.1

K1.24 †Describe the parameters to be monitored and controlled

during rod pattern exchanges. 2.8 3.2

 Reactor Response on a Scram

K1.25 Explain the shape of a curve of reactor power versus

time after a scram. 2.8 2.9

 Normal Reactor Shutdown

K1.26 Explain reactor power response to a decrease in core

flow. 3.4 3.7
6.1-13 NUREG-1123, Rev. 2 |

REACTOR THEORY: 292008 Reactor Operational Physics

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.27 Explain reactor power response to a control rod

insertion. 3.4 3.5

K1.28 Explain the necessity for inserting control rods in a

predetermined sequence during normal shutdown. 3.4 3.7

K1.29 Define decay heat. 3.4 3.6

K1.30 Explain the relationship between decay heat generation

and: a) power level history, b) power production, and

c) time since reaction shut down. 3.2 3.5
NUREG-1123, Rev. 2 6.1-14 |

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6.2-1 NUREG-1123, Rev. 2 |

6.2 THERMODYNAMICS

(CFR: 41.14)

THERMODYNAMICS: 293001 Thermodynamic Units and Properties

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Convert between absolute and relative pressure and

vacuum scales. 2.2* 2.3*

K1.02 Recognize the difference between absolute and relative

temperature scales. 2.1* 2.1*

K1.03 Describe how common pressure and level sensing

instruments work. 2.5* 2.7

K1.04 Explain relationships between work, power, and energy. 1.8* 1.9*
NUREG-1123, Rev. 2 6.2-2 |

THERMODYNAMICS: 293002 Basic Energy Concepts

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Identify energy and work forms. 1.6* 1.7*

K1.02 Explain the law of conservation of energy. 1.9* 1.9*

K1.03 Explain the difference between state and phase of a

working substance. 1.6* 1.7*

K1.04 Explain the application of enthalpy in the monitoring

of plant processes. 2.1* 2.4*

K1.05 Identify the relationship between heat flow during a

process and a T-s diagram representation of the

process. 2.0* 2.2*

K1.06 Define specific heat. 1.8* 2.1*

K1.07 Apply specific heat in solving heat transfer problems. 1.5* 1.6*
6.2-3 NUREG-1123, Rev. 2 |

THERMODYNAMICS: 293003 Steam

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Describe effects of pressure on density or specific

volume of a liquid. 2.3* 2.4

K1.02 Distinguish between liquids, vapors, gases, and fluids. 2.2* 2.3*

K1.03 Define latent heat of vaporization 2.3 2.4

K1.04 Define vaporization line 2.0* 2.1*

K1.05 Define critical point 1.8* 1.8*

K1.06 Define vapor dome 1.8* 2.0*

K1.07 Define saturated liquid 2.7 2.8

K1.08 Define wet vapor 1.8* 1.9*

K1.09 Define saturated vapor 2.5* 2.6*

K1.10 Define vapor pressure 1.8* 1.9*

K1.11 Define moisture content 2.3* 2.3*

K1.12 Define quality 2.5 2.6

K1.13 Define superheated vapor 2.3* 2.4*

K1.14 Define supersaturated vapor 1.8* 1.8*

K1.15 Define subcooled and compressed liquids 2.4* 2.4*

K1.16 Define subcooling 2.8 2.8

K1.17 Define specific heat 1.9* 2.1*

Identify the following terms on a T-s diagram:

K1.18 --Critical point 1.7* 1.7*

K1.19 --Saturated liquid line 2.1* 2.2*

K1.20 --Saturated vapor line 2.2* 2.3*

K1.21 --Solid, liquid, gas, vapor, and fluid regions 2.1* 2.2*

K1.22 Explain the usefulness of steam tables to the Control

Room Operator. 2.9 3.2

K1.23 Use saturated and superheated steam tables. 2.8* 3.1*
NUREG-1123, Rev. 2 6.2-4 |

THERMODYNAMICS: 293004 Thermodynamic Processes

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Explain the relationship between real and ideal

processes. 1.6* 1.7*

K1.02 Explain the shape of the T-s diagram process line for

a typical boiler. 1.8* 1.9*

Nozzles

K1.03 Describe the functions of nozzles in flow restrictors. 2.2* 2.2*

K1.04 Describe the functions of nozzles in air ejectors. 2.5 2.6

K1.05 Describe the principles of operation of a jet pump 2.7 2.7

 Turbines

K1.06 Explain the function of nozzles, fixed blading, and

moving blading in the turbine. 1.9* 2.1*

K1.07 Explain the reason turbines are multistages. 2.1* 2.2*

K1.08 Define turbine efficiency. 2.0* 2.1*

K1.09 Explain the difference between actual turbine

performance and ideal thermal efficiency. 1.7* 1.8*

Pumps

K1.10 Define pump efficiency. 1.8* 1.9*

K1.11 Explain the difference between ideal and real pumping

processes. 1.7* 1.8*

Condensers

K1.12 Discuss subcooling. 2.9 3.1

K1.13 Explain vacuum formation in condenser processes. 2.5 2.6

K1.14 Explain the condensing process. 2.6 2.7

 Throttling and the Throttling Process

K1.15 Define throttling. 2.2* 2.3*

K1.16 Explain the reduction of process pressure from

throttling. 2.1* 2.3*
6.2-5 NUREG-1123, Rev. 2 |

THERMODYNAMICS: 293005 Thermodynamic Cycles

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Define thermodynamic cycle. 1.7* 1.8*

K1.02 Define thermodynamic cycle efficiency in terms of net

work produced and energy applied. 1.7* 1.7*

Kl.03 Describe the moisture effects on turbine integrity and

efficiency. 2.6 2.7

K1.04 Explain steam quality effects on nuclear turbine

design. 2.3* 2.4*

K1.05 State the advantages of moisture separators/reheaters

and feedwater heaters for a typical steam cycle. 2.7 2.8
NUREG-1123, Rev. 2 6.2-6 |

THERMODYNAMICS: 293006 Fluid Statics

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 Distinguish between fluids and other substances. 1.7* 1.8*

K1.02 Distinguish between static pressure, dynamic pressure,

and total pressure. 2.0* 2.2*

K1.03 Define head loss. 2.4 2.5

K1.04 Discuss operational considerations of viscosity as

related to head loss. 1.7* 1.9*

K1.05 Explain operational implications of fluid hammer 3.2 3.3

 Pumps and Pump Characteristics

K1.06 --State the purpose of a pump. 2.5* 2.6*

K1.07 --Discuss pump head. 2.5 2.6

K1.08 --Discuss relationship between pump speed, head, flow,

and power without using formulas or calculations. 2.5 2.6

K1.09 --Define cavitation. 2.8 2.9

K1.10 --Define net positive suction head (NPSH). 2.7 2.8

K1.11 --Define pump shut-off head, pump runout, and axial

thrust. 2.4 2.5

K1.12 --Explain the importance of proper system venting for

pump operations. 2.9 2.9

K1.13 --Explain the results of putting centrifugal pumps in

parallel or series combinations. 2.6 2.7

K1.14 --Given the characteristic curve for a typical

centrifugal pump, explain the reason for its shape. 2.2* 2.3*

K1.15 --Using a centrifugal pump characteristic curve and a

system characteristic curve, illustrate how the system

operating point changes due to system changes. 2.3* 2.4*

K1.16 --Describe how a centrifugal pump characteristic curve

will change with pump speed. 2.1* 2.3*

K1.17 --Explain how operating a centrifugal pump at shutoff

head may cause overheating of the pump and describe

methods used to avoid overheating. 2.6 2.7
6.2-7 NUREG-1123, Rev. 2 |

THERMODYNAMICS: 293006 Fluid Statics

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.18 --Discuss the characteristic curve for a typical

positive displacement pump and explain the reason for

its shape. 1.9* 2.1*

K1.19 --Describe the problems that will occur in emergency

core cooling systems if the pumps are operated at

lower than design flow for extended periods of time. 2.7 2.9

K1.20 Define or explain mass flow rate 2.4 2.4

K1.21 Define or explain two-phase flow 2.4* 2.6

K1.22 Define or explain pressure spike 2.2* 2.3*

K1.23 Define or explain gas binding 2.2* 2.3*

K1.24 Define or explain recirculation ratio 2.1* 2.3*

K1.25 Define or explain pipe whip 2.1* 2.2*

K1.26 Explain why flow measurements must be corrected for

density changes. 2.3 2.4

K1.27 Explain the relationship between pressure head and

velocity head in a fluid system. 1.8* 2.0*

K1.28 Discuss the velocity profiles for laminar flow and

tubulent flow. 1.7* 1.8*

K1.29 Describe the methods of controlling system flow rates. 2.6 2.7
NUREG-1123, Rev. 2 6.2-8 |

THERMODYNAMICS: 293007 Heat Transfer and Heat Exchanges

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

 Heat Transfer

K1.01 Describe three mechanisms of heat transfer. 3.2 3.2

K1.02 Describe thermal conductivity. 2.4 2.6

K1.03 Explain the manner in which fluid films affects heat

transfer. 2.7 2.8

Heat Exchangers

K1.04 Discuss parallel-flow heat exchangers. 1.9* 2.2*

K1.05 Discuss counter-flow heat exchangers. 2.0* 2.2*

K1.06 Discuss the factors which affect heat transfer rate in

a heat exchanger. 2.7 2.8

K1.07 Describe how the presence of gases or steam can affect

heat transfer and fluid flow in heat exchangers. 2.7 2.9

 Condenser Applications of Heat Transfer

K1.08 List functions of the main condenser in a power plant. 3.0 3.1

K1.09 Discuss operational implications of condensate

depression. 2.5 2.7

Core Thermal Power

K1.10 Define core thermal power. 2.7* 2.9*

K1.11 †Explain methods of calculating core thermal power. 2.6 3.1

K1.12 Define percent reactor power. 2.6* 2.7*

K1.13 †Calculate core thermal power using a simplified heat

balance. 2.3* 2.9*
6.2-9 NUREG-1123, Rev. 2 |

THERMODYNAMICS: 293008 Thermal Hydraulics

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

 Boiling Heat Transfer

K1.01 Distinguish between boiling processes and other heat

transfer mechanisms. 2.6 2.8

K1.02 Describe surface or cavity nucleation. 2.2* 2.3*

K1.03 List factors affecting bubble formation in a cavity. 1.9* 2.1*

K1.04 Describe means by which boiling improves convection

heat transfer. 2.6 2.7

K1.05 Describe microconvection. 1.4* 1.5*

 Pool Boiling Curve (Tvs. Q/A)

K1.06 Define a natural convection heat transfer. 2.5 2.6

K1.07 Define nucleate boiling, subcooled nucleate boiling,

and bulk boiling. 2.8 3.0

K1.08 Describe DNB (departure from nucleate boiling). 2.9 3.1

K1.09 Describe OTB (onset of transition boiling). 3.0 3.2

K1.10 Describe CHF (critical heat flux). 2.9 3.0

K1.11 Describe transition (partial film) boiling. 2.7 2.8

K1.12 Describe stable film boiling. 2.7 2.8

K1.13 Describe burnout and burnout heat flux. 2.3* 2.3*

 Two Phase Flow

K1.14 Classify slug flow region along a fuel channel,

experiencing two phase flow. 2.0* 2.1*

K1.15 Describe annular flow region along a hypothetical fuel

channel, experiencing two phase flow. 2.2* 2.3

K1.16 Describe dryout region or mist flow region along a

hypothetical fuel channel, experiencing two phase

flow. 2.2* 2.3

K1.17 Describe OTB point along a hypothetical fuel channel,

experiencing two phase flow. 2.5 2.8
NUREG-1123, Rev. 2 6.2-10 |

THERMODYNAMICS: 293008 Thermal Hydraulics

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.18 Describe effects of flowrate and phase change on the

heat transfer coefficient. 2.2* 2.4

 Core Inlet Subcooling

K1.19 Define core inlet subcooling. 2.6 2.8

K1.20 Define carryunder. 2.4 2.6

 Voids and Void Fraction

K1.21 Define void fraction. 3.0 3.0

K1.22 Explain the term void as applied to core operations 2.9 3.0

K1.23 Define qualilty 2.5 2.7

K1.24 Draw the temperature profile from the centerline of a

fuel pellet to the centerline of the channel. 2.4 2.5

 Recirculation System

K1.25 Explain the reason for forced core recirculation. 3.2 3.2

K1.26 Explain the jet pump operating principle. 2.9 3.1

K1.27 Explain the necessity of determining core coolant

flow. 2.9 3.0

K1.28 Describe the factors affecting single- and two-phase

flow resistance. 2.3* 2.5*

 Core Orificing

K1.29 Describe the effects of increasing bundle power on

bundle flow resistance. 2.8 3.0

K1.30 Compare the flow resistance through high powered

bundles to that of low powered bundles. 2.7 2.7

K1.31 Explain the necessity of core orificing. 2.9 3.0

K1.32 Describe core bypass flow. 2.5 2.6

K1.33 Explain the need for adequate core bypass flow.

Natural Circulation 2.4 2.6
6.2-11 NUREG-1123, Rev. 2 |

THERMODYNAMICS: 293008 Thermal Hydraulics

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.34 Explain the causes of natural circulation in BWR's. 2.9 3.1

K1.35 Describe problems that thermal stratification can

cause. 3.1 3.3

K1.36 Describe means by which the operator can determine if

natural circulation flow exists. 3.1 3.3

K1.37 Describe means by which the operator can enhance

natural circulation. 3.2 3.4

Sketch the axial temperature and enthalpy profiles for

a typical reactor coolant channel and describe how

they are affected by the following:

K1.38 --Onset of nucleate boiling 1.8* 2.1*

K1.39 --Axial core flux 1.8* 1.9*

K1.40 --Inlet temperature 1.8* 1.9*

K1.41 --Heat generation rate 1.8* 2.0*

K1.42 --Flow rate in the channel 1.8* 1.9*

K1.43 Sketch the temperature profile in the axial and radial

directions for a typical fuel rod and explain the

reason for its shape. 2.0* 2.2*
NUREG-1123, Rev. 2 6.2-12 |

THERMODYNAMICS: 293009 Core Thermal Limits

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 †Explain radial peaking factor (RPF) 2.1* 2.5*

K1.02 †Explain axial peaking factor(APF) 2.2* 2.6

K1.03 †Explain local peaking factor(LPF) 2.1* 2.5*

K1.04 †Explain total peaking factor(TPF) 2.2* 2.6

K1.05 State the reason thermal limits are necessary. 3.3 3.5

 LHGR

K1.06 †Define LHGR. 3.4 3.8

K1.07 †Explain the basis of the limiting condition of LHGR. 2.8 3.6

K1.08 †Describe the mode of fuel failure for LHGR. 3.0 3.4

K1.09 †Define FLPD and MFLPD. 3.1 3.7

 MAPLHGR

K1.10 †Define APLHGR 3.3 3.7

K1.11 †Explain the basis of the limiting condition for

APLGHR. 2.8 3.6

K1.12 †Describe the mode of fuel failure for APLHGR. 2.9 3.5

K1.13 †Define MAPLHGR 3.1 3.6

K1.14 †Explain the mechanisms most limiting for each region

of the MAPLHGR limit curves. 2.2* 2.7

K1.15 †Describe conditions under which radiative heat

transfer becomes the significant method of heat

transfer within a fuel bundle. 2.6 3.1

K1.16 †Discuss how changes in the heat generation rate and

thermal conductivity of the fuel rod affect fuel

centerline temperature 2.4 2.8

 MCPR

K1.17 †Define critical power. 3.3 3.7

K1.18 †Define critical power ratio. 3.2 3.7
6.2-13 NUREG-1123, Rev. 2 |

THERMODYNAMICS: 293009 Core Thermal Limits

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.19 †Explain the basis of the limiting condition for CPR. 2.8 3.6

K1.20 †Describe the mode of fuel failure for CPR. 3.1 3.6

K1.21 †Define MCPR. 3.1 3.6

K1.22 †Describe the effects of subcooling on critical power. 2.9 3.3

K1.23 †Describe the effects of mass flow on critical power. 2.8 3.2

K1.24 †Describe the effects of pressure on critical power. 2.7 3.2

K1.25 †Describe the effects of local power distribution on

 critical power. 2.7 3.2

K1.26 †Describe the effects of axial power distribution on

 critical power. 2.6 3.1

K1.27 †Explain the purpose of the flow biasing correlation

 factor, (K ), as it relates to MCPR limits. 2.7 3.3

K1.28 †Define FLCPR. 3.0 3.5

Thermal Time Constant

K1.29 Define fuel thermal time constant. 2.4* 2.7

K1.30 †Relate thermal time constant to transient operating

 condition. 2.3 2.7

Pellet Clad Interaction

K1.31 Describe pellet-clad interaction (PCI). 3.0 3.4

K1.32 List the causes of PCI. 2.9 3.3

K1.33 Describe the purpose of the pellet to clad gap. 2.4 2.8

K1.34 Identify the possible effects of fuel densification. 2.3* 2.6

K1.35 Describe the effects of iodine and cadmium on PCI. 2.2* 2.6*

 PCIOMR

K1.36 †Explain the purpose for PCIOMR (Plant Specific). 2.8 3.4
NUREG-1123, Rev. 2 6.2-14 |

THERMODYNAMICS: 293009 Core Thermal Limits

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.37 †Identify how the PCIOMR rules minimize the adverse

effects of PCI (Plant Specific). 2.6 3.3

K1.38 †State the items measured for each of the three core

thermal limits. 2.7 3.1

For the following plant operating or accident

conditions, identify which of the three core thermal

limits are most limiting:

K1.39 Full power operation 2.8 3.2

K1.40 Loss of reactor coolant 2.8 3.3

K1.41 Increase in core flow 2.8 3.3

K1.42 Increase in reactor pressure 2.8 3.3

K1.43 Cold water addition 2.9 3.4
6.2-15 NUREG-1123, Rev. 2 |

THERMODYNAMICS: 293010 Brittle Fracture and Vessel Thermal Stress

 

 IMPORTANCE 

K/A NO. KNOWLEDGE RO SRO

K1.01 State the brittle fracture mode of failure. 2.4* 2.8

K1.02 †State the definition of Nil-Ductility Transition

Temperature. 2.2* 2.7

K1.03 Define reference temperature. 2.0* 2.5

K1.04 †State how the possibility of brittle fracture is

minimized by operating limitations. 2.9 3.2

K1.05 †State the effect of fast neutron irradiation on

reactor vessel metals. 2.5 2.8
NUREG-1123, Rev. 2 6.2-16 |

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