Knowledge and Abilities 

Catalog for Nuclear Power 

Plant Operators

Advanced Boiling Water Reactors

Draft Report for Comment

Office of New Reactors

NUREG-2104
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Knowledge and Abilities 

Catalog for Nuclear Power 

Plant Operators

Advanced Boiling Water Reactors

Draft Report for Comment

Manuscript Completed: August 2011

Date Published: December 2011

Prepared by

R. Pelton

J. Kellum

Office of New Reactors

NUREG-2104
NUREG-2104 ii

COMMENTS ON DRAFT REPORT

Any interested party may submit comments on this report for consideration by the NRC staff. 

Comments may be accompanied by additional relevant information or supporting data. Please 

specify the report number NUREG-2104, draft, in your comments, and send them by December 

31, 2018 to the following address:

Cindy Bladey, Chief 

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Office of Administration 

Mail Stop: TWB-05-B01M 

U.S. Nuclear Regulatory Commission 

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Phone: 301-415-1028

E-mail: rick.pelton@nrc.gov

James Kellum

TWFN Mail Stop 07-D24

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Phone: 301-415-5305

E-mail: jim.kellum@nrc.gov

Please be aware that any comments that you submit to the NRC will be considered a public 

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(ADAMS). Do not provide information you would not want to be publically available.
iii NUREG-2104

ABSTRACT

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

Water Reactors (NUREG-2104, Revision 0) provides the basis for the development of contentvalid licensing examinations for reactor operators (ROs) and senior reactor operators (SROs). 

The examinations developed using the ABWR Catalog along with the Operator Licensing 

Examination Standards for Power Reactors (NUREG-1021) will sample the topics listed under 

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

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.

This is a new Knowledge and Abilities catalog developed specifically to address the General 

Electric Advanced Boiling Water Reactor.

v NUREG-2104

TABLE OF CONTENTS page

ABSTRACT iii

1.0 ORGANIZATION OF THE CATALOG 1-1

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 1-1

1.5 RO and SRO Operating Test Items 1-1

1.6 Senior Reactor Operator Limited to Fuel Handling 1-1

1.7 Organization of the ABWR Catalog 1-2

1.8 Generic Knowledge and Abilities 1-2

1.9 Plant Systems 1-3

1.10 Emergency and Abnormal Plant Evolutions 1-7

1.11 Components 1-10

1.12 Theory 1-10

1.13 Importance Ratings 1-11

1.14 Rules of Use 1-11

1.15 General Guidance 1-12

2.0 GENERIC KNOWLEDGES AND ABILITIES 2-1 

2.1 Conduct of Operations 2-3

2.2 Equipment Control 2-7

2.3 Radiation Control 2-11

2.4 Emergency Procedures / Emergency Plan 2-13

3.0 PLANT SYSTEMS 3.1-1

3.1 Safety Function 1: Reactivity Control 3.1-1

SF1CRD Control Rod Drive System 3.1-1

SF1FMCRD Fine Motion Control Rod Drive Mechanism 3.1-5

SF1RFC Recirculation Flow Control System 3.1-8

SF1RRS Reactor Recirculation System 3.1-12

SF1RCIS Rod Control and Information System 3.1-16

SF1SLC Standby Liquid Control System 3.1-20

3.2 Safety Function 2: Reactor Water Inventory Control 3.2-1

SF2HPCF High Pressure Core Flooder System 3.2-1

SF2CD Condensate System 3.2-5

SF2RCIC Reactor Core Isolation Cooling System 3.2-9

SF2FW Feedwater System 3.2-13

SF2RWCU Reactor Water Cleanup System 3.2-17

SF2FWC Feedwater Control System 3.2-21
NUREG-2104 vi

SF2RHRLPFL Residual Heat Removal System: Low Pressure Flooder

Injection Mode 3.2-24

SF2AFI Alternate Feedwater Injection System 3.2-28

3.3 Safety Function 3: Reactor Pressure Control 3.3-1

SF3ADS Automatic Depressurization System 3.3-1

SF3NBS Main and Reheat Steam System 3.3-4

SF3EHC Turbine Pressure Control/Steam Bypass and Pressure Control

System 3.3-8

SF3SRV Safety/Relief Valves 3.3-13

3.4 Safety Function 4: Heat Removal from Reactor Core 3.4-1

SF4NBS Main and Reheat Steam System 3.4-1

SF4MT Main Turbine Generator and Auxiliary Systems 3.4-5

SF4RCIC Reactor Core Isolation Cooling System 3.4-9

SF4RRS Reactor Recirculation System 3.4-13

SF4RHRSDC Residual Heat Removal System: Shutdown Cooling Mode 3.4-17

3.5 Safety Function 5: Containment Integrity 3.5-1

SF5PCS Primary Containment System and Auxiliaries 3.5-1

SF5LDIS Leak Detection and Isolation System 3.5-5

SF5RPV Reactor Vessel Internals 3.5-9

SF5HRSPC Residual Heat Removal System: Suppression Pool Cooling Mode 3.5-12

SF5RHRSPR Residual Heat Removal System: Drywell and Wetwell Spray Mode 3.5-16

SF5SEC Secondary Containment 3.5-20

3.6 Safety Function 6: Electrical 3.6-1

SF6EPDS AC Electrical Distribution System 3.6-1

SF6DC Direct Current Power Supply System 3.6-4

SF6EDGCTG Emergency Generators (Diesel/Combustion Turbine Generators) 3.6-7

SF6VAC Vital AC Power Supply System 3.6-11

SF6I&C Instrumentation and Control Power Supply System 3.6-14

3.7 Safety Function 7: Instrumentation 3.7-1

SF7APR Automatic Power Regulator System 3.7-1

SF7ATLM Automated Thermal Limit Monitor 3.7-4

SF7APRM Average Power Range Monitor/Local Power Range

Monitor System 3.7-7

SF7NBI Nuclear Boiler Instrumentation 3.7-11

SF7RAD Radiation Monitoring System 3.7-14

SF7RTIS Reactor Trip and Isolation System 3.7-17

SF7MRBM Multi-Channel Rod Block Monitor System 3.7-21

SF7RWM Rod Worth Minimizer System 3.7-24

SF7SRNM Startup Range Neutron Monitoring System 3.7-27
vii NUREG-2104

SF7ATIP Automated Traversing In-Core Probe System 3.7-30

SF7ELCS Engineered Safety Function Logic and Control System 3.7-33

SF7PICS Plant Information and Control System 3.7-36

SF7SPTM Suppression Pool Temperature Monitoring System 3.7-41

SF7RSS Remote Shutdown System 3.7-44

3.8 Safety Function 8: Plant Service Systems 3.8-1

SF8FPS Fire Protection System 3.8-1

SF8FHS Fuel Handling Equipment 3.8-4

SF8IAS Instrument Air System 3.8-7

SF8BCW Reactor Building Cooling Water System 3.8-10

SF8RSW Reactor Service Water System 3.8-14

3.9 Safety Function 9: Radioactivity Release 3.9-1

SF9OG Offgas System 3.9-1

SF9HVAC Plant Ventilation Systems 3.9-5

SF9RAD Radiation Monitoring System 3.9-8

SF9RW Radwaste System 3.9-11

SF9RPV Reactor Vessel Internals 3.9-14

SF9FPC Fuel Pool Cooling and Clean-up System 3.9-17

SF9SGTS Standby Gas Treatment System 3.9-21

SF9CRHVAC Control Room Habitability Area Heating, Ventilation, and Air

Conditioning System 3.9-24

4.0 EMERGENCY PLANT AND ABNORMAL PLANT EVOLUTIONS 4.1-1

4.1 Emergency Plant Evolutions 4.1-1

EPE1001 High Drywell Pressure 4.1-1

EPE1002 High Reactor Pressure 4.1-3

EPE1003 Suppression Pool High Water Temperature 4.1-5

EPE1004 High Drywell Temperature 4.1-6

EPE1005 High Suppression Pool Water Level 4.1-7

EPE1006 Low Suppression Pool Water Level 4.1-8

EPE1007 Reactor Low Water Level 4.1-9

EPE1008 High Secondary Containment Area Temperature 4.1-12

EPE1009 High Secondary Containment Area Radiation Levels 4.1-13

EPE1010 Reactor Building Heating, Ventilation, and Air Conditioning

Exhaust High Radiation 4.1-15

EPE1011 Secondary Containment High Differential Pressure 4.1-16

EPE1012 Secondary Containment High Floor Drain Sump/Area Water Level 4.1-17

EPE1013 Scram Condition and Reactor Power >5% or Unknown 4.1-19

EPE1014 High Off-Site Release Rate 4.1-21

4.2 Abnormal Plant Evolutions 4.2-1

APE2001 Partial or Complete Loss of Forced Core Flow Circulation 4.2-1
NUREG-2104 viii

APE2002 Loss of Main Condenser Vacuum 4.2-3

APE2003 Partial or Complete Loss of AC Power 4.2-5

APE2004 Partial or Complete Loss of DC Power 4.2-7

APE2005 Main Turbine Generator Trip 4.2-9

APE2006 Reactor Scram 4.2-11

APE 2007 High Reactor Pressure 4.2-13

APE2008 High Reactor Water Level 4.2-14

APE2009 Low Reactor Water Level 4.2-16

APE2010 High Drywell Pressure 4.2-17

APE2011 High Drywell Temperature 4.2-19

APE2012 High Suppression Pool Temperature 4.2-20

APE2013 Inadvertent Reactivity Addition 4.2-21

APE2014 Incomplete Scram 4.2-23

APE2015 Control Room Evacuation 4.2-25

APE2016 High Off-Site Release Rate 4.2-27

APE2017 Partial or Complete Loss of Reactor Building Cooling Water 4.2-29

APE2018 Partial or Complete Loss of Instrument Air 4.2-30

APE2019 Inadvertent Containment Isolation 4.2-32

APE2020 Loss of Shutdown Cooling 4.2-34

APE2021 Loss of Control Rod Drive Pumps 4.2-36

APE2022 Refueling Accidents 4.2-37

APE2023 Plant Fire On-Site 4.2-38

APE2024 Generator Voltage and Electric Grid Disturbances 4.2-40

5.0 COMPONENTS 5-1

291001 Valves 5-1

291002 Sensors and Detectors 5-2

291003 Controllers and Positioners 5-4

291004 Pumps 5-5

291005 Motors and Generators 5-6

291006 Heat Exchangers and Condensers 5-7

291007 Demineralizers and Ion Exchangers 5-8

291008 Breakers, Relays and Disconnects 5-9

6.0 THEORY 6.1-1

6.1 Reactor Theory 6.1-1

292001 Neutrons 6.1-1

292002 Neutron Life Cycle 6.1-2

292003 Reactor Kinetics and Neutron Sources 6.1-3

292004 Reactivity Coefficients 6.1-4

292005 Control Rods 6.1-5

292006 Fission Product Poisons 6.1-6

292007 Fuel Depletion and Burnable Poisons 6.1-7

292008 Reactor Operational Physics 6.1-8
ix NUREG-2104

6.2 Thermodynamics 6.2-1

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 6.2-14

1-1 NUREG-2104

1.0 ORGANIZATION OF THE CATALOG

1.1 Introduction

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

Water Reactors, NUREG-2104, 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 "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 10 CFR 55. All knowledge and abilities (K/As) in this catalog are directly linked by 

item number to 10 CFR 55. 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 RO Written Examination

The guidance for preparation of RO written examination is presented in NUREG-1021. The 

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

1.4 SRO Written Examination

The guidance for preparation of the SRO written examination is presented in NUREG-1021. In 

addition to the RO items specified in 10 CFR 55.41(b), additional items for SRO written 

examinations are presented in 10 CFR 55.43(b). 

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. The operating 

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

55.45(a).

1.6 Senior Reactor Operator Limited to Fuel Handling

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

provided in NUREG 1021. 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.
NUREG-2104 1-2

1.7 Organization of the ABWR Catalog

This catalog is organized into 6 major sections. K/As are grouped according to the major 

section to which they pertain. This organization is outlined below.

1.0 ORGANIZATION OF THE ABWR CATALOG

2.0 GENERIC KNOWLEDGE AND ABILITIES

Conduct of Operations

Equipment Control

Radiation Control

Emergency Procedures / Emergency Plan

3.0 PLANT SYSTEMS

Knowledge Categories (K1 - K6)

Ability Categories (A1 - A4)

4.0 EMERGENCY PLANT AND ABNORMAL PLANT EVOLUTIONS

Knowledge Categories (EK/AK 1 - EK/AK 3)

Ability Categories (EA/AA 1 – EA/AA 2)

5.0 COMPONENTS

Component Knowledge Categories

6.0 THEORY

Reactor Theory Knowledge Categories

Thermodynamics Knowledge Categories

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:

2.1 Conduct of Operations K/As

2.2 Equipment Control K/As

2.3 Radiation Control K/As

2.4 Emergency Operating Procedures/Plan K/As

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

operation of the facility. The types of information evaluated in this category include shift 

turnover, operator responsibilities, and procedure usage.

The K/As for "Equipment Control" are used to evaluate the applicant’s knowledge of the 

administrative issues associated with the management and control of plant systems and 

equipment. The types of information evaluated in this category include maintenance and 

temporary modifications of systems. Fuel handling and refueling K/As are organized into this 

topic area due to the equipment control aspect of fuel handling.
1-3 NUREG-2104

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

radiation protection and radiation (personnel and public). The types of information under in this 

category include radiation hazards, radiation work permits, and radiation monitoring systems.

The K/As for "Emergency Operating 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 operating procedures use. The emergency plan K/As are 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 nuclear power plant 

operation. The safety functions groups are:

Safety Function 1 Reactivity Control

Safety Function 2 Reactor Water Inventory Control

Safety Function 3 Reactor Pressure Control

Safety Function 4 Heat Removal From Reactor Core

Safety Function 5 Containment Integrity

Safety Function 6 Electrical

Safety Function 7 Instrumentation

Safety Function 8 Plant Service Systems

Safety Function 9 Radioactivity Release

Plant systems have been included in this catalog based on their relationship and importance to 

nine safety functions. Table 1 contains a list of these plant systems, arranged within each 

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

function.

Each plant system has been assigned a unique alphanumeric identifier. Plant systems K/As are 

in Section 3 of this catalog.

Table 1

Plant Systems by Safety Function

3.1 Safety Function 1: Reactivity Control

SF1CRD Control Rod Drive System

SF1FMCRD Fine Motion Control Rod and Drive Mechanism

SF1RFC Recirculation Flow Control System

SF1RRS Reactor Recirculation System

SF1RCIS Rod Control and Information System

SF1SLC Standby Liquid Control System
NUREG-2104 1-4

3.2 Safety Function 2: Reactor Water Inventory Control

SF2HPCF High Pressure Core Flooder System

SF2CD Condensate System

SF2RCIC Reactor Core Isolation Cooling System

SF2FW Feedwater System

SF2RWCU Reactor Water Cleanup System

SF2FWC Feedwater Control System

SF2RHRLPFL Residual Heat Removal: Low Pressure Flooder Injection Mode

SF2AFI Alternate Feedwater Injection System

3.3 Safety Function 3: Reactor Pressure Control

SF3ADS Automatic Depressurization System

SF3NBS Main and Reheat Steam System

SF3EHC Turbine Pressure Control/Steam Bypass and Pressure Control System

SF3SRV Safety/Relief Valves

3.4 Safety Function 4: Heat Removal From Reactor Core

SF4NBS Main and Reheat Steam System

SF4MT Main Turbine Generator and Auxiliary Systems

SF4RCIC Reactor Core Isolation Cooling System

SF4RRS Reactor Recirculation System

F3RHRSDC Residual Heat Removal System: Shutdown Cooling Mode

3.5 Safety Function 5: Containment Integrity

SF5PCS Primary Containment System and Auxiliaries

SF5LDIS Leak Detection and Isolation System

SF5RPV Reactor Vessel Internals

SF5RHRSPC Residual Heat Removal System: Suppression Pool Cooling Mode

SF5RHRSPR Residual Heat Removal System Drywell/Wetwell Spray Mode

SF5SEC Secondary Containment

3.6 Safety Function 6: Electrical

SF6EPDS AC Electrical Distribution System

SF6DC Direct Current Power Supply System

SF6DGCTG Emergency Generators (Diesel/Combustion Turbine Generators)

SF6VAC Vital AC Power Supply System

SF6I&C Instrumentation and Control Power Supply System

3.7 Safety Function 7: Instrumentation

SF7APR Automatic Power Regulator System

SF7ATLM Automated Thermal Limit Monitoring System

SF7APRM Average Power Range Monitor/Local Power Range Monitor System

SF7NBI Nuclear Boiler Instrumentation

SF7RMS Radiation Monitoring System
1-5 NUREG-2104

SF7RTIS Reactor Trip and Isolation System

SF7MRBM Multi-Channel Rod Block Monitor System

SF7RWM Rod Worth Minimizer System

SF7SRNM Startup Range Neutron Monitor System

SF7ATIP Automated Traversing In-Core Probe System

SF7ELCS Engineered Safety Function Logic and Control System

SF7PICS Plant Information and Control System

SF7SPTM Suppression Pool Temperature Monitoring System

SF7RSS Remote Shutdown System

3.8 Safety Function 8: Plant Service Systems

SF8FPS Fire Protection System

SF8FH Fuel Handling Equipment

SF8IAS Instrument Air System

SF8RBCW Reactor Building Cooling Water System

SF8RSW Reactor Service Water System

3.9 Safety Function 9: Radioactivity Release

SF9OG Offgas System

SF9HVAC Plant Ventilation Systems

SF9RMS Radiation Monitoring System

SF9RMS Radwaste System

SF9RPV Reactor Vessel Internals

SF9FPC Fuel Pool Cooling and Clean-up System

SF9SGTS Standby Gas Treatment System

SF9CRHVAC Control Room Habitability Area Heating, Ventilation, and Air Conditioning

System

1.9.2 Knowledge and Ability Stem Statements for Plant Systems

The knowledge and abilities for each plant system are organized into six types of knowledge 

and four types of ability. If there are no knowledge or ability statements following a stem 

statement, then there are no applicable knowledge or ability statements.

The applicable 10 CFR 55.41 / 43 / and 45 references 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 lists the Plant System Stem Statements:
NUREG-2104 1-6

Table 2

Knowledge and Ability Stem Statements for Plant Systems

Knowledge Stem Statements

K 1 Knowledge of the physical or control/protection logic relationships between the 

(SYSTEM) and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K 1 Contains the systems that have a connection to system XXS. The selected systems 

listed have either a plant protection/control logic relationship or physical piping 

relationship to system XXS. The electrical systems were not included in K 1 

because they are addressed in K 2.

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K 2 Lists the power supplies to system components for which knowledge of power 

supplies is testable.

K 3 Knowledge of the effect that a loss or malfunction of the (system) will have on the 

following:

(CFR: 41.7 / 45.4)

K 3 Lists the systems included in K1 that are directly affected by a loss of system XXS.

K 4 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the 

following:

(CFR: 41.7)

K 4 Contains the plant protection/control design features and interlocks.

K 5 Knowledge of the operational implications or cause-effect relationships as they apply 

to the (SYSTEM):

(CFR: 41.5 / 45.3)

K 5 Contains theoretical concepts related to the operation of the system.

K 6 Knowledge of the effect of the following plant conditions, system malfunctions or 

component malfunctions will have on the (SYSTEM):

(CFR: 41.7 / 45.7)

K 6 Lists the systems included in K1 that will have an effect on system XXS if the listed 

system is lost. It also lists the components of system XXS whose failure can affect 

the operation of the system XXS.
1-7 NUREG-2104

Ability Stem Statements

A 1 Ability to predict and/or monitor changes in parameters associated with operating the 

(system) controls including:

(CFR: 41.5 / 45.5)

A 1 Lists the parameters monitored to verify proper operation of system XXS.

A 2 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 operations:

(CFR:41.5/45.6)

A 2 Lists the ability to predict and mitigate the consequences of selected items from K 6.

A 3 Ability to monitor automatic operations of the (system) including:

(CFR: 41.7 / 45.7)

A 3 Contains the automatic features of system XXS identified in K 4 that can be 

monitored from the control room

A 4 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A 4 Contains the features of system XXS listed in A 3 that can also be manually 

performed as well as the features of system XXS system can only be manually 

performed and monitoring parameters. A4 includes system monitoring associated 

with the listed manual actions.

1.10 Emergency and Abnormal Plant Evolutions

Section 4 of this catalog contains emergency plant evolutions and abnormal plant evolutions. 

An emergency plant evolution is any condition, event, or symptom which leads to entry into the 

plant-specific emergency operating procedures. An abnormal plant evolution is any degraded 

condition, event, or symptom not directly leading to an emergency operating procedure entry 

condition, but, nonetheless, adversely affecting a safety function. The listing of emergency plant 

evolutions and abnormal plant evolutions was developed to include those integrative situations 

crossing several plant systems and/or safety functions.

The emergency plant evolution strategies described in 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 

>5% or Unknown.

3. Primary Containment Control

4. Secondary Containment Control

5. Radioactivity Release Control.
NUREG-2104 1-8

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

plant safety functions will be safely maintained. Table 3 contains a list of the emergency plant 

evolutions and abnormal plant evolutions covered by this catalog. The emergency plant and 

abnormal plant evolutions each have a unique evolution designator.

Table 3

Emergency Plant and Abnormal Plant Evolutions

Emergency Plant Evolutions

EPE1001 High Drywell Pressure

EPE1002 High Reactor Pressure

EPE1003 Suppression Pool High Water Temperature

EPE1004 High Drywell Temperature

EPE1005 High Suppression Pool Water Level

EPE1006 Low Suppression Pool Water Level

EPE1007 Reactor Low Water Level

EPE1008 High Secondary Containment Area Temperature

EPE1009 High Secondary Containment Area Radiation Levels

EPE1010 Reactor Building Heating, Ventilation, and Air Conditioning Exhaust High Radiation

EPE1011 Secondary Containment High Differential Pressure

EPE1012 Secondary Containment High Floor Drain Sump / Area Water Level

EPE1013 Scram Condition and Reactor Power >5% or Unknown

EPE1014 High Off-Site Release Rate

Abnormal Plant Evolutions

APE2001 Partial or Complete Loss of Forced Core Flow Circulation

APE2002 Loss of Main Condenser Vacuum

APE2003 Partial or Complete Loss of AC Power

APE2004 Partial or Complete Loss of DC Power

APE2005 Main Turbine Trip

APE2006 Reactor Scram

APE2007 High Reactor Pressure

APE2008 High Reactor Water Level

APE2009 Low Reactor Water Level

APE2010 High Drywell Pressure

APE2011 High Drywell Temperature

APE2012 High Suppression Pool Water Temperature

APE2013 Inadvertent Reactivity Addition

APE2014 Incomplete Scram

APE2015 Control Room Evacuation

APE2016 High Off-Site Release Rate

APE2017 Partial or Complete Loss of Reactor Building Cooling Water

APE2018 Partial or Complete Loss of Instrument Air

APE2019 Inadvertent Containment Isolation

APE2019 Loss of Shutdown Cooling

APE2021 Loss of Control Rod Drive Pumps

APE2022 Refueling Accidents

APE2023 Plant Fire on Site

APE2024 Generator Voltage and Electric Grid Disturbances
1-9 NUREG-2104

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 the written 

and operating examinations. See Table 4, below:

Table 4

Knowledge and Ability Stem Statements for

Emergency Plant and Abnormal Plant Evolutions

Knowledge Stem Statements

E/AK 1 Knowledge of the operational implications of the following concepts as they apply 

to the (Emergency Plant or Abnormal Plant Evolution):

(CFR: 41.8 to 41.10)

E/AK 1 Lists the operational implications applicable to the procedure. These items can 

come from the procedure bases, PRA, OE, procedure notes and cautions.

E/AK2 Knowledge of the interrelations between (Emergency Plant or Abnormal Plant 

Evolution) and the following:

(CFR: 41.7 / 45.8)

E/AK 2 Lists the systems required to be monitored and/or operated by the procedure.

E/AK 3 Knowledge of the reasons for the following responses as they apply to (Emergency 

Plant or Abnormal Plant Evolution):

(CFR: 41.5 / 45.6)

E/AK 3 Lists the actions and bases taken in the procedure.

Ability Stem Statements

E/AA 1 Ability to operate and / or monitor the following as they apply to (Emergency Plant 

or Abnormal Plant Evolution):

(CFR: 41.7 / 45.6)

EA 1 Lists the system and/or components required to be monitored and/or operated by 

the procedure.

E/AA 2 Ability to determine and / or interpret the following as they apply to (Emergency 

Plant or Abnormal Plant Evolution):

(CFR: 41.10 / 43.5 / 45.13)

EA 2 Lists the parameters and/or conditions that are monitored to verify successful 

implementation of the procedure.
NUREG-2104 1-10

1.11 Components

Basic components such as valves and pumps are found in many systems. NUREG-1021 lists 8 

categories of components. The eight categories of components for which additional knowledge 

statements are necessary are listed below and delineated in Section 5 of the ABWR 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 group 

has a numeric identifier and a 10 CFR 55.41(b) reference. 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)

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 lists theory items. General fundamental knowledge which underlies safe 

performance on the job is delineated in Section 6 of the ABWR Catalog. These theory 

topics represent general fundamental concepts related to plant operation. Each theory topic 

has a numeric identifier. The applicable 10 CFR 55.41(b) reference is provided for Reactor 

Theory and Thermodynamics Theory fundamental knowledge areas.

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
1-11 NUREG-2104

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, Senior Reactor Operators, and, as appropriate, for a 

combined RO/SRO (licensed operator) knowledge next to each knowledge or ability statement 

in the catalog. These ratings reflect ratings that were derived by concensus of a panel of utility 

experts. The rating scale is presented in Table 6, below.

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

A 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 not considered as appropriate content for 

NRC licensing examinations. The use of statements having importance ratings less than 2 can 

be used on an NRC licensing examination if justified based on plant-specific priorities.

1.14 Rules of Use

To ensure consistency in applying this catalog, the following terms are defined as: 

• “Parameter” any characteristic of a system and/or component that is measured.

• “Actuation” includes actuation logic, signals, blocks, bypasses, permissives, interlocks, 

and resets.
NUREG-2104 1-12

1.15 General Guidance

The following strategies and principles are utilized in this catalog:

• The use of set points is minimized. Values included are specific to titles or 

procedures. If a value included in the catalog changes, the statement is still testable 

if it meets the intent of the statement.

• K/A statement overlap in multiple sections is minimized. K/As are assigned to the 

most appropriate section.

• All importance ratings are single column format except A 2 and Generic K/As and 

fuel handling. Fuel handling is not a RO license activity and will have N/A marked in 

the RO column.
2-1 NUREG-2104

2.0 GENERIC KNOWLEDGES AND ABILITIES

2.0.1 Knowledge / Ability statements that reference Technical Specifications includes the 

Short Term Availability Controls, Core Operating Limits Report, and Offsite Dose 

Calculation Manual.

2.0.2 For Knowledge / Ability statements that reference Technical Specifications, the term 

“apply” for an RO means to perform the Technical Specifications actions.

2.0.3 Knowledge / Ability statements including the words “such as” list suggested topical 

areas as examples and are not intended to be all inclusive.

2.1 Conduct of Operations

2.1.1 Knowledge of conduct of operations requirements.

(CFR: 41.10 / 45.13)

IMPORTANCE RO 4 SRO 4

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

(CFR: 41.10 / 45.13)

IMPORTANCE RO 4 SRO 4

2.1.3 Knowledge of shift or short-term relief turnover practices.

(CFR: 41.10 / 45.13)

IMPORTANCE RO 4 SRO 4

2.1.4 Knowledge of individual licensed operator responsibilities related to shift 

staffing, such as medical requirements, “no-solo” operation, maintenance of 

active license status, 10CFR55, etc.

(CFR: 41.10 / 43.2)

IMPORTANCE RO 3 SRO 4

2.1.5 Ability to use procedures related to shift staffing, such as minimum crew 

complement, overtime limitations, etc.

(CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE RO 3 SRO 4

2.1.6 Ability to manage the control room crew during plant transients.

(CFR: 41.10 / 43.5 / 45.12 / 45.13)

IMPORTANCE RO 4 SRO 5

2.1.7 Ability to evaluate plant performance and make operational judgments based 

on operating characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5 / 43.5 / 45.12 / 45.13)

IMPORTANCE RO 4 SRO 5

2.1.8 Ability to coordinate personnel activities outside the control room.

(CFR: 41.10 / 45.5 / 45.12 / 45.13)

IMPORTANCE RO 3 SRO 4
NUREG-2104 2-2

2.1 Conduct of Operations (continued)

2.1.9 Ability to direct personnel activities inside the control room.

(CFR: 41.10 / 45.5 / 45.12 / 45.13)

IMPORTANCE RO 3 SRO 5

2.1.10 Ability to direct non-licensed personnel activities inside the control room.

(CFR: 41.10 / 43.5 / 45.9 / 45.10)

IMPORTANCE RO 3 SRO 3

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

(CFR: 41.10 / 43.5 / 45.9 / 45.10)

IMPORTANCE RO 3 SRO 3

2.1.12 Knowledge of criteria or conditions that require plant-wide announcements, 

such as pump starts, reactor trips, and mode changes, etc.

(CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE RO 3 SRO 3

2.1.13 Knowledge of administrative requirements for temporary management 

directives, such as standing orders, night orders, operations memos, etc.

(CFR: 41.10 / 45.12)

IMPORTANCE RO 3 SRO 3

2.1.14 Ability to make accurate, clear, and concise verbal reports.

(CFR: 41.10 / 45.12 / 45.13)

IMPORTANCE RO 4 SRO 4

2.1.15 Ability to make accurate, clear, and concise logs, records, status boards, and 

reports.

(CFR: 41.10 / 45.12 / 45.13)

IMPORTANCE RO 4 SRO 4

2.1.16 Ability to use Visual Display Units and other plant displays to evaluate system 

or component status.

(CFR: 41.10 / 45.12)

IMPORTANCE RO 4 SRO 4

2.1.17 Ability to use integrated control systems to operate plant systems or 

components

(CFR: 41.10 /45.8 / 45.12)

IMPORTANCE RO 4 SRO 4

2.1.18 Ability to interpret and execute procedure steps.

(CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE RO 5 SRO 5

2.1.19 Ability to verify that a copy of a controlled procedure is the proper revision.

(CFR: 41.10 / 45.10 / 45.13)

IMPORTANCE RO 4 SRO 4
2-3 NUREG-2104

2.1 Conduct of Operations (continued)

2.1.20 Ability to perform specific system and integrated plant procedures during all 

modes of plant operation.

(CFR: 41.10 / 43.5 / 45.2 / 45.6)

IMPORTANCE RO 4 SRO 4

2.1.21 Ability to interpret reference materials, such as graphs, curves, tables, etc.

(CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE RO 4 SRO 4

2.1.22 Knowledge of industrial safety procedures such as rotating equipment, 

electrical, high temperature, high pressure, caustic, chlorine, oxygen and 

hydrogen, etc.

(CFR: 41.10 / 45.12)

IMPORTANCE RO 3 SRO 4

2.1.23 Knowledge of system purpose and/or function.

(CFR: 41.7)

IMPORTANCE RO 4 SRO 4

2.1.24 Knowledge of the purpose and function of major system components and 

controls.

(CFR: 41.7)

IMPORTANCE RO 4 SRO 4

2.1.25 Knowledge of how to conduct system lineups, such as valves, breakers, 

switches, etc.

(CFR: 41.10 / 45.1 / 45.12)

IMPORTANCE RO 4 SRO 4

2.1.26 Ability to locate and operate components, including local controls.

(CFR: 41.7 / 45.7)

IMPORTANCE RO 4 SRO 4

2.1.27 Ability to locate control room switches, controls, and indications, and to 

determine that they correctly reflect the desired plant lineup.

(CFR: 41.10 / 45.12)

IMPORTANCE RO 5 SRO 4

2.1.28 Ability to explain and apply system warnings, cautions, and precautions and 

limitations.

(CFR: 41.10 / 43.2 / 45.12)

IMPORTANCE RO 4 SRO 4

2.1.29 Knowledge of reactor coolant system and balance of plant chemistry controls 

including parameters measured and reasons for the control.

(CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE RO 3 SRO 4
NUREG-2104 2-4

2.1 Conduct of Operations (continued)

2.1.30 Knowledge of the fuel-handling responsibilities of Senior Reactor Operators 

such as assessment of fuel handling equipment surveillance requirement 

acceptance criteria, prerequisites for vessel disassembly and reassembly, 

decay heat assessment, assessment of surveillance requirement for the 

refueling mode, etc.

(CFR: 41.10 / 43.7)

IMPORTANCE RO N/A SRO 4

2.1.31 Knowledge of procedures and limitations involved in core alterations.

(CFR: 41.10 / 43.6 / 45.7)

IMPORTANCE RO 3 SRO 4

2.1.32 Knowledge of procedures, guidelines, or limitations associated with reactivity 

management.

(CFR: 41.1 / 43.6 / 45.6)

IMPORTANCE RO 4 SRO 5

2.1.33 Knowledge of the station's requirements for verbal communications when 

implementing procedures.

(CFR: 41.10 / 45.13)

IMPORTANCE RO 4 SRO 4

2.1.34 Knowledge of conservative decision making practices.

(CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE RO 4 SRO 4

2.1.35 Knowledge of refueling administrative requirements such as approvals 

required to amend core loading sheets, etc.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3 SRO 4

2.1.36 Knowledge of the refueling process.

(CFR: 41.2 / 41.10 / 43.6 / 45.13)

IMPORTANCE RO 3 SRO 4

2.1.37 Knowledge of new and spent fuel movement procedures.

(CFR: 41.10 / 43.7 / 45.13)

IMPORTANCE RO 3 SRO 3

2.1.38 Ability to use procedures to determine the effects on reactivity of plant 

changes, such as reactor coolant system temperature, balance of plant, fuel 

depletion, etc.

(CFR: 41.10 / 43.6 / 45.6)

IMPORTANCE RO 4 SRO 4

2.1.39 Knowledge of Reactor Operator duties in the control room during fuel handling 

such as responding to alarms from the fuel handling area, communications 

with the refueling floor, systems operated from the control room in support of 

fueling operations, and supporting instrumentation.

(CFR: 41.10 / 43.7 / 45.12)

IMPORTANCE RO 4 SRO 4
2-5 NUREG-2104

2.1 Conduct of Operations (continued)

2.1.40 Ability to identify and interpret diverse indications to validate the response of 

another indication.

(CFR: 41.7 / 43.5 / 45.4)

IMPORTANCE RO 4 SRO 4
NUREG-2104 2-6

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: 41.5 / 41.10 / 43.5 / 43.6 / 45.1)

IMPORTANCE RO 4 SRO 4

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

shutdown and designated power levels.

(CFR: 41.6 / 41.7 / 45.2)

IMPORTANCE RO 5 SRO 4

2.2.3 (multi-unit license) Knowledge of the design, procedural, and operational 

differences between units.

(CFR: 41.5 / 41.6 / 41.7 / 41.10 / 45.12)

IMPORTANCE RO 4 SRO 4

2.2.4 (multi-unit license) Ability to explain the variations in control station/control 

room layouts, systems, instrumentation, and procedural actions between units 

at a facility.

(CFR: 41.6 / 41.7 / 41.10 / 45.1 / 45.13)

IMPORTANCE RO 4 SRO 4

2.2.5 Knowledge of the process for making design or operating changes to the 

facility such as 10 CFR 50.59 screening and evaluation processes, 

administrative process for temporary modifications, administrative processes 

for disabling annunciators, administrative processes for the installation of 

temporary instrumentation, etc.

(CFR: 41.10 / 43.3 / 45.13)

IMPORTANCE RO 2 SRO 3

2.2.6 Knowledge of the process for making changes to procedures.

(CFR: 41.10 / 43.3 / 45.13)

IMPORTANCE RO 3 SRO 4

2.2.7 Knowledge of the process for conducting special or infrequently performed 

tests or evolutions.

(CFR: 41.10 / 43.3 / 45.13)

IMPORTANCE RO 3 SRO 4

2.2.8 Knowledge of surveillance procedures.

(CFR: 41.10 / 45.13)

IMPORTANCE RO 4 SRO 4

2.2.9 Knowledge of tagging and clearance procedures.

(CFR: 41.10 / 45.13)

IMPORTANCE RO 4 SRO 4

2.2.10 Knowledge of the process for controlling equipment configuration or status.

(CFR: 41.10 / 43.3 / 45.13)

IMPORTANCE RO 4 SRO 4
2-7 NUREG-2104

2.2 Equipment Control (continued)

2.2.11 Ability to determine the expected plant configuration using design and 

configuration control documentation, such as drawings, line-ups, tag-outs, etc.

(CFR: 41.10 / 43.3 / 45.13)

IMPORTANCE RO 4 SRO 4

2.2.12 Knowledge of the process for managing maintenance activities during power 

operations, such as risk assessments, work prioritization, and coordination 

with the transmission system operator, etc.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3 SRO 4

2.2.13 Knowledge of the process for managing maintenance activities during 

shutdown operations, such as risk assessments, work prioritization, etc.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3 SRO 4

2.2.14 Knowledge of maintenance work order requirements.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 2 SRO 3

2.2.15 Knowledge of the process for managing troubleshooting activities.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3 SRO 4

2.2.16 Knowledge of pre- and post-maintenance operability requirements.

(CFR: 41.10 / 43.2)

IMPORTANCE RO 3 SRO 4

2.2.17 Knowledge of limiting conditions for operations and safety limits.

(CFR: 41.5 / 43.2 / 45.2)

IMPORTANCE RO 4 SRO 5

2.2.18 Ability to track Technical Specification limiting conditions for operations.

(CFR: 41.10 / 43.2 / 45.13)

IMPORTANCE RO 3 SRO 5

2.2.19 Knowledge of the bases in Technical Specifications for limiting conditions for 

operations and safety limits.

(CFR: 41.5 / 41.7 / 43.2)

IMPORTANCE RO N/A SRO 5

2.2.20 Ability to determine Technical Specification Mode of Operation.

(CFR: 41.7 / 41.10 / 43.2 / 45.13)

IMPORTANCE RO 4 SRO 5
NUREG-2104 2-8

2.2 Equipment Control (continued)

2.2.21 Ability to analyze the effect of maintenance activities, such as degraded power 

sources, on the status of limiting conditions for operations.

(CFR: 41.10 / 43.2 / 45.13)

IMPORTANCE RO 3 SRO 4

2.2.22 Ability to determine operability and/or availability of safety related equipment.

(CFR: 41.7 / 43.5 / 45.12)

IMPORTANCE RO N/A SRO 5

2.2.23 Knowledge of conditions and limitations in the facility license such as 

reporting requirements when the maximum licensed thermal power output is 

exceeded, administration of fire protection program requirements such as 

compensatory actions associated with inoperable sprinkler systems or fire 

doors, processes for Technical Specification or FSAR changes, the required 

actions associated for not meeting administrative controls listed in Technical 

Specification Section 5, etc

(CFR: 41.7 / 41.10 / 43.1 / 45.13)

IMPORTANCE RO 2 SRO 5

2.2.24 Knowledge of less than or equal to one hour Technical Specification action 

statements. (This Knowledge / Ability statement does not include Action 

Statements of one hour or less that follow the expiration of a completion time for a 

Technical Specification condition for which an Action Statement has already been 

entered.).

(CFR: 41.7 / 41.10 / 43.2 / 45.13)

IMPORTANCE RO 4 SRO 5

2.2.25 Ability to apply Technical Specifications with action statements of less than or 

equal to one hour.

(CFR: 41.10 / 43.2 / 43.5 / 45.3)

IMPORTANCE RO 3.4 SRO 4.7

2.2.26 Ability to determine and/or interpret Technical Specifications with action 

statements of greater than one hour.

(CFR: 43.2 / 43.5 / 45.3)

IMPORTANCE RO N/A SRO 4.7

2.2.27 Ability to apply Technical Specifications for a system, such as application of 

Required Actions and Surveillance Requirements in accordance with rules of 

application requirements, application of generic Limiting Condition for 

Operation (LCO) requirements (LCO 3.01 thru 3.0.7 and SR 3.01 thru 3.04), etc..

(CFR: 41.10 / 43.2 / 43.5 / 45.3)

IMPORTANCE RO N/A SRO 5

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

(CFR: 41.10 / 45.12 / 45.13)

IMPORTANCE RO 4 SRO 4
2-9 NUREG-2104

2.2 Equipment Control (continued)

2.2.29 Ability to recognize system parameters that are Technical Specifications entrylevel conditions.

(CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3)

IMPORTANCE RO 4 SRO 5

2.2.30 Knowledge of the process used to track inoperable alarms.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3 SRO 3

2.2.31 Ability to interpret control room indications to verify the status and operation 

of a system, and understand how operator actions and directives affect plant 

and system conditions.

(CFR: 41.5 / 43.5 / 45.12)

IMPORTANCE RO 4 SRO 4
NUREG-2104 2-10

2.3 Radiation Control

2.3.1 Knowledge of radiation exposure limits under normal or emergency 

conditions.

(CFR: 41.12 / 43.4 / 45.10)

IMPORTANCE RO 3 SRO 4

2.3.2 Ability to use radiation monitoring systems, such as fixed radiation monitors 

and alarms, portable survey instruments, personnel monitoring equipment, 

etc.

(CFR: 41.11 / 41.12 / 43.4 / 45.9)

IMPORTANCE RO 3 SRO 3

2.3.3 Ability to approve liquid release permits.

(CFR: 41.13 / 43.4 / 45.10)

IMPORTANCE RO N/A SRO 4

2.3.4 Ability to comply with radiation work permit requirements during normal or 

abnormal conditions.

(CFR: 41.12 / 45.10)

IMPORTANCE RO 4 SRO 4

2.3.5 Knowledge of plant operational thresholds which requires radiation protection 

personnel to be informed such as plant mode changes, large power changes, 

radiological alarms, dosimeter alarms, etc.

(CFR 41.12/43.4/45.10

IMPORTANCE RO 3 SRO 4

2.3.6 Ability to control radiation releases.

(CFR: 41.11 / 43.4 / 45.10)

IMPORTANCE RO 4 SRO 4

2.3.7 Knowledge of radiological safety principles pertaining to licensed operator 

duties, such as containment entry requirements, fuel handling responsibilities, 

access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12 / 45.9 / 45.10)

IMPORTANCE RO 3 SRO 4

2.3.8 Knowledge of radiological safety procedures pertaining to licensed operator 

duties, such as response to radiation monitor alarms, containment entry 

requirements, fuel handling responsibilities, access to locked high-radiation 

areas, aligning filters, etc.

(CFR: 41.12 / 43.4 / 45.9 / 45.10)

IMPORTANCE RO 3 SRO 4
2-11 NUREG-2104

2.3 Radiation Control (continued)

2.3.9 Knowledge of radiation or contamination hazards that may arise during 

normal, abnormal, or emergency conditions or activities such as analysis and 

interpretation of radiation and activity readings as they pertain to selection of 

administrative, normal, abnormal, and emergency procedures, analysis and 

interpretation of coolant activity, including comparison to emergency plan/or 

regulatory limits.

(CFR: 41.12 / 43.4 / 45.10)

IMPORTANCE RO 3 SRO 4

2.3.10 Knowledge of radiation monitoring systems, such as fixed radiation monitors 

and alarms, portable survey instruments, personnel monitoring equipment, 

etc.

(CFR: 41.12 / 43.4 / 45.9)

IMPORTANCE RO 3 SRO 3
NUREG-2104 2-12

2.4 Emergency Procedures / Emergency Plan

2.4.1 Knowledge of Emergency / Abnormal Operating Procedure entry conditions.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 5 SRO 5

2.4.2 Knowledge of system set points associated with Emergency / Abnormal 

Operating Procedure entry conditions.

(CFR: 41.7 / 45.7 / 45.8)

IMPORTANCE RO 5 SRO 5

2.4.3 Ability to identify post-accident instrumentation.

(CFR: 41.6 / 45.4)

IMPORTANCE RO 4 SRO 4

2.4.4 Ability to recognize abnormal indications for system operating parameters that 

are entry-level conditions for Emergency / Abnormal Operating Procedures.

(CFR: 41.10 / 43.2 / 45.6)

IMPORTANCE RO 5 SRO 5

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 4 SRO 4

2.4.6 Knowledge of Emergency / Abnormal Operating Procedure mitigation 

strategies.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 4 SRO 5

2.4.7 Knowledge of how abnormal operating procedures are used in conjunction 

with Emergency Operating Procedures.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 4 SRO 5

2.4.8 Knowledge of low power/shutdown implications in accident (e.g., loss of 

coolant accident or loss of residual heat removal) mitigation strategies.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 4 SRO 4

2.4.9 Knowledge of crew responsibilities during emergency / abnormal operations.

(CFR: 41.10 / 45.12)

IMPORTANCE RO 4 SRO 4

2.4.10 Knowledge of crew roles and responsibilities during Emergency / Abnormal 

Operating Procedure usage.

(CFR: 41.10 / 45.12)

IMPORTANCE RO 4 SRO 5
2-13 NUREG-2104

2.4 Emergency Procedures / Emergency Plan (continued)

2.4.11 Knowledge of general guidelines for Emergency / Abnormal Operating 

Procedure usage.

(CFR: 41.10 / 45.13)

IMPORTANCE RO 4 SRO 5

2.4.12 Knowledge of Emergency / Abnormal Operating Procedure implementation 

hierarchy and coordination with other support procedures or guidelines such 

as, operating procedures, abnormal operating procedures, and severe 

accident management guidelines, etc.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 4 SRO 4

2.4.13 Knowledge of Emergency / Abnormal Operating Procedure terms and 

definitions.

(CFR: 41.10 / 45.13)

IMPORTANCE RO 4 SRO 4

2.4.14 Knowledge of the specific bases for Emergency / Abnormal Operating 

Procedures.

(CFR: 41.10 / 43.1 / 45.13)

IMPORTANCE RO 3 SRO 4

2.4.15 Knowledge of Emergency / Abnormal Operating Procedure layout, symbols, 

and icons.

(CFR: 41.10 / 45.13)

IMPORTANCE RO 3 SRO 4

2.4.16 Knowledge of the operational implications of Emergency / Abnormal Operating 

Procedure warnings, cautions, and notes.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 4 SRO 4

2.4.17 Knowledge of the parameters and logic used to assess the status of 

Emergency / Abnormal Operating Procedure key parameters to ensure 

reactivity control, core cooling and heat removal, reactor coolant system 

integrity, containment conditions, radioactivity release control, etc.

(CFR: 41.7 / 43.5 / 45.12)

IMPORTANCE RO 4 SRO 5

2.4.18 Knowledge of the bases for prioritizing actions during emergency / abnormal 

operations.

(CFR: 41.7 / 41.10 / 43.5 / 45.12)

IMPORTANCE RO 4 SRO 4

2.4.19 Knowledge of the bases for prioritizing emergency operating procedure 

implementation.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3 SRO 4
NUREG-2104 2-14

2.4 Emergency Procedures / Emergency Plan (continued)

2.4.20 Knowledge of emergency operating procedure exit conditions such as an 

emergency condition no longer exists or severe accident guideline entry is 

required, etc.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3 SRO 4

2.4.21 Knowledge of fire protection procedures.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3 SRO 4

2.4.22 Knowledge of facility protection requirements, including fire brigade and 

portable firefighting equipment usage.

(CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE RO 3 SRO 4

2.4.23 Knowledge of procedures relating to a security event (non-safeguards 

information).

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3 SRO 4

2.4.24 Knowledge of the emergency plan including emergency plan implementing 

procedures.

(CFR: 41.10 / 43.5 / 45.11)

IMPORTANCE RO 3 SRO 4

2.4.25 Knowledge of events related to system operation/status that must be reported 

to internal organizations or external agencies, such as the State, the NRC, or 

the transmission system operator.

(CFR: 41.10 / 43.5 / 45.11)

IMPORTANCE RO 3 SRO 4

2.4.26 Knowledge of annunciator alarms, indications, or response procedures.

(CFR: 41.10 / 45.3)

IMPORTANCE RO 4 SRO 4

2.4.27 Knowledge of operator response to a loss of all annunciators.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 4 SRO 4

2.4.28 Knowledge of Reactor Operator tasks performed outside the main control 

room during an emergency and the resultant operational effects.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 4 SRO 4

2.4.29 Knowledge of non-license operator tasks during an emergency and the 

resultant operational effects.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 4 SRO 4
2-15 NUREG-2104

2.4 Emergency Procedures / Emergency Plan (continued)

2.4.30 Knowledge of the lines of authority during implementation of the emergency 

plan, emergency plan implementing procedures, emergency operating 

procedures, or severe accident guidelines.

(CFR: 41.10 / 45.13)

IMPORTANCE RO 3 SRO 4

2.4.31 Ability to take actions called for in the facility emergency plan and emergency 

plan implementing procedures, including supporting or acting as emergency 

coordinator if required.

(CFR: 41.10 / 43.5 / 45.11)

IMPORTANCE RO N/A SRO 4

2.4.32 Knowledge of Reactor Operator responsibilities in emergency plan 

implementation.

(CFR: 41.10 / 45.11)

IMPORTANCE RO 4 SRO 4

2.4.33 Knowledge of Senior Reactor Operator responsibilities in emergency plan 

implementation.

(CFR: 41.10 / 43.5 / 45.11)

IMPORTANCE RO N/A SRO 5

2.4.34 Knowledge of the emergency action level thresholds and classifications.

(CFR: 41.10 / 43.5 / 45.11)

IMPORTANCE RO N/A SRO 5

2.4.35 Knowledge of emergency response facilities.

(CFR: 41.10 / 45.11)

IMPORTANCE RO 3 SRO 4

2.4.36 Knowledge of emergency communications systems and techniques.

(CFR: 41.10 / 45.13)

IMPORTANCE RO 3 SRO 4

2.4.37 Knowledge of emergency plan protective action recommendations.

(CFR: 41.10 / 41.12 / 43.5 / 45.11)

IMPORTANCE RO N/A SRO 4

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

(CFR: 41.10 / 43.5 / 45.3 / 45.12)

IMPORTANCE RO 4 SRO 4

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

(CFR: 41.10 / 43.5 / 45.3 / 45.12)

IMPORTANCE RO 4 SRO 4
NUREG-2104 2-16

2.4 Emergency Procedures / Emergency Plan (continued)

2.4.40 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 4 SRO 4

2.4.41 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 5 SRO 4

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

alarm response manual.

(CFR: 41.10 / 43.5 / 45.3)

IMPORTANCE RO 4 SRO 4
3.1-1 NUREG-2104

3.0 PLANT SYSTEMS

3.1 Safety Function 1: Reactivity Control

System: SF1CRD Control Rod Drive System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between Control Rod Drive System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Condensate, feedwater and condensate air extraction system 3

K1.02 Makeup water condensate system 3

K1.03 Feedwater system - control rod drive system return to vessel 3

K1.04 Reactor building cooling water system 3

K1.05 Reactor trip and isolation system 3

K1.06 Instrument air system 3

K1.07 Rod control and information system 3

K1.08 Plant information and control system 2

K1.09 Reactor recirculation system 3

K1.10 AC electrical power distribution system 3

K1.11 Drywell cooling system 2

K1.12 Heating, ventilation, and air conditioning system 2

K1.13 Reactor pressure vessel system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Control rod drive pumps 3

K2.02 Scram valve solenoids 2

K2.03 Backup scram valve solenoids 4

K2.04 Alternate rod insertion valve solenoids 4

K 3 Knowledge of the effect that a loss or malfunction of the Control Rod Drive 

System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor internal pumps 3

K3.02 Reactor water level 3

K3.03 Fine motion control rod drive mechanisms 3

K3.04 Reactor water cleanup pumps 3
NUREG-2104 3.1-2

3.1 Safety Function 1: Reactivity Control

System: SF1CRD Control Rod Drive System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 Knowledge of Control Rod Drive 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 control rod drive system flow element and a

restricting orifice in the accumulator charging water line) 3

K4.02 Fine motion control rod drive mechanisms purge water flow 3

K4.03 Scramming control rods with inoperative scram solenoid

valves (back-up scram valves) 4

K4.04 Control rod scram 4

K4.05 Controlling purge water flow during fine motion control

rod drive mechanisms insertion 3

K4.06 Controlling control rod drive system flow 3

K4.07 Motor cooling 2

K4.08 Auto start of standby control rod drive pump due to low pump

discharge pressure 3

K4.09 Auto stop of running control rod drive pump due to low pump

suction pressure 3

K4.10 Auto stop of running control rod drive pump due to low lube

oil pressure 3

K4.11 Auto start of lube oil pump during control rod drive pump

running due to low lube oil pressure 3

K4.12 Controlling control rod drive pump discharge water temperature

(minimum flow bypass valve) 2

K 5 Knowledge of the operational implications of the following concepts or 

cause and effect relationships as they apply to Control Rod Drive System:

(CFR: 41.5 / 45.3)

K5.01 Reactor internal pumps purge water 3

K5.02 Fine motion control rod drive mechanisms 3

K5.03 Reactor water cleanup pump purge water 3

K5.04 Fine motion control rod drive purge water header 3
3.1-3 NUREG-2104

3.1 Safety Function 1: Reactivity Control

System: SF1CRD Control Rod Drive System (continued)

K/A NO. ABILITY IMPORTANCE

K 6 Knowledge of the effect of the following plant conditions, system

malfunctions or component malfunctions will have on the Control 

Rod Drive System:

(CFR: 41.7 / 45.7)

K6.01 Condensate system 3

K6.02 Condensate storage tanks 3

K6.03 Plant information and control system 3

K6.04 Instrument air system 3

K6.05 Reactor trip and isolation system 4

K6.06 AC electrical power distribution system 3

K6.07 Reactor building cooling water system 3

K6.08 Rod control and information system 3

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Control Rod Drive System controls including:

(CFR: 41.5 / 45.5)

A1.01 Control rod drive system flow 3

A1.02 Hydraulic control unit pressure/level 3

A1.03 Reactor water level 3

A1.04 Pump amps 2

A1.05 Fine motion control rod drive mechanisms purge water flow 3

A1.06 Fine motion control rod drive mechanisms purge water to reactor

differential pressure 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Control Rod Drive 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 / 45.5)

RO SRO

A2.01 Pumps trips 3 3

A2.02 Valve closures 3 3

A2.03 Power supply failures 3 3

A2.04 Scram conditions 4 4

A2.05 Discharge filter becoming plugged 3 3

A2 06 Suction filter becoming plugged 3 3

A2.07 Flow control valve failure 3 3

A2.08 Inadequate system flow 3 3

A2.09 Loss of applicable plant air systems 3 3

A2.10 Low hydraulic control unit accumulator pressure/high level 4 4

A2.11 Valve openings 3 3

A2.12 Low fine motion control rod drive mechanisms purge water flow 3 3
NUREG-2104 3.1-4

3.1 Safety Function 1: Reactivity Control

System: SF1CRD Control Rod Drive System (continued)

K/A NO. ABILITY IMPORTANCE

A 3 Ability to monitor automatic operations of the Control Rod Drive System

including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation 3

A3.02 Pump start 3

A3.03 System pressure 3

A3.04 System flow 3

A3.05 Reactor water level 3

A3.06 Reactor power 3

A3.07 HCU accumulator pressure/level 3

A3.08 Fine motion control rod drive mechanisms purge water flow 3

A3.09 Indications and alarms 3

A3.10 Fine motion control rod drive mechanisms purge water to reactor

differential pressure 3

A 4 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Control rod drive pumps 3

A4.02 Control rod drive system flow control valve 3
3.1-5 NUREG-2104

3.1 Safety Function 1: Reactivity Control

System: SF1FMCRD Fine Motion Control Rod Drive Mechanism

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Fine Motion Control Rod Drive Mechanism and the following 

systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Control rod drive system 3

K1.02 Rod control and information system 3

K1.03 Reactor pressure vessel system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Fine motion control rod drive mechanism motor 3

K 3 Knowledge of the effect that a loss or malfunction of the Fine Motion 

Control Rod Drive Mechanism will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor power 3

K3.02 Flux shaping 3

K3.03 Shutdown margin 4

K 4 Knowledge of Fine Motion Control Rod Drive Mechanism design feature(s) 

and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Rod drop prevention function (fine motion control rod drive latches

and rod block signal) 4

K4.02 Rod ejection accident prevention (fine motion control rod drive

brake) 3

K4.03 Detection of an uncoupled rod 4

K4.04 Slowing the drive mechanism near the end of its travel following

a scram 2

K4.05 The use of accumulator to scram the control rod 4

K4.06 Rod position indication 3

K4.07 Uncoupling the control rod from the drive mechanism 3

K4.08 Maintaining the control rod at a given location 3

K4.09 The use of fine motion control rod drive motor to auto insert control

rod upon failure to insert hydraulically on a scram signal 4

K4.10 Detection of control rod drift 4
NUREG-2104 3.1-6

3.1 Safety Function 1: Reactivity Control

System: SF1FMCRD Fine Motion Control Rod Drive Mechanism (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 5 Knowledge of the operational implications or cause and effect 

relationships as they apply to Fine Motion Control Rod Drive Mechanism:

(CFR: 41.5 / 45.3)

K5.01 Reactor pressure vessel water level 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Fine Motion 

Control Rod Drive Mechanism:

(CFR: 41.7 / 45.7)

K6.01 Control rod drive system 3

K6.02 Loss of power to fine motion control rod drive motor 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Fine Motion Control Rod Drive Mechanism controls 

including:

(CFR: 41.5 / 45.5)

A1.01 Reactor power 4

A1.02 Control rod position 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Fine Motion Control Rod 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)

RO SRO

A2.01 Stuck rod 3 4

A2.02 Uncoupled rod 4 4

A2.03 Drifting rod 3 4

A2.04 Control rod pair scram 4 4

A2.05 Reactor scram 4 4

A2.06 Loss of fine motion control rod drive charging water flow 3 3

A2.07 Loss of fine motion control rod drive purge water flow 3 3

A2.08 Low hydraulic control unit accumulator pressure/high water level 4 4

A2.09 Excessive scram time for a given drive mechanism 3 4
3.1-7 NUREG-2104

3.1 Safety Function 1: Reactivity Control

System: SF1FMCRD Fine Motion Control Rod Drive Mechanism (continued)

K/A NO. KNOWLEDGE IMPORTANCE

A 3 Ability to monitor automatic operations of the Fine Motion Control Rod 

Drive Mechanism including:

(CFR: 41.7 / 45.7)

A3.01 Fine motion control rod position 4

A3.02 Control rod position following a scram 4

A 4 Ability to manually operate and/or monitor the Fine Motion Control Rod 

Drive Mechanism in the control room:

(CFR: 41.7 / 45.5 to 45.8)

None
NUREG-2104 3.1-8

3.1 Safety Function 1: Reactivity Control

System: SF1RFC Recirculation Flow Control System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Recirculation Flow Control System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor recirculation system 4

K1.02 Steam bypass and pressure control system 3

K1.03 AC electrical power distribution system 3

K1.04 Neutron monitoring system 3

K1.05 Rod control and information system 3

K1.06 Automatic power regulator system 3

K1.07 Feedwater control system 3

K1.08 Reactor trip and isolation system 3

K1.09 Control rod drive system 4

K1.10 Plant information and control system 3

K1.11 Reactor water cleanup system 3

K1.12 Engineered Safety Function logic and control system 4

K1.13 Reactor pressure vessel instrumentation system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Reactor internal pump adjustable speed drives 3

K2.02 Reactor internal pump motor generator sets 3

K 3 Knowledge of the effect that a loss or malfunction of the will have on the 

following:

(CFR: 41.7 / 45.4)

K3.01 Core flow 4

K3.02 Reactor power 4

K3.03 Reactor water level 3

K3.04 Reactor internal pump speed 3
3.1-9 NUREG-2104

3.1 Safety Function 1: Reactivity Control

System: SF1RFC Recirculation Flow Control System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 Knowledge of Recirculation Flow Control System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Reactor internal pump speed control 3

K4.02 Signal failure detection 3

K4.03 Automatic load following 2

K4.04 Minimum and maximum pump speed setpoints 3

K4.05 Normal reactor internal pump speed runback 3

K4.06 Fast reactor internal pump speed runback 3

K4.07 Selected control rod run in 3

K4.08 Recirculation pump trip 3

K4.09 Reactor internal pump response to a momentary reactor internal

pump -adjustable speed drive voltage drop 2

K4.10 Prevention of reactor internal pump speed increase for various

core flow and/or reactor power conditions 3

K4.11 Prevention of reactor internal pump speed increase due to automated

thermal limit monitor trip 3

K 5 Knowledge of the operational implications or cause and effect 

relationships as they apply to the Recirculation Flow Control System:

(CFR: 41.5 / 45.3)

K5.01 Reactor power 4

K5.02 Reactor core flow 4

K5.03 Reactor internal pump MG set 4

K5.04 Feedwater flow 3

K5.05 Reactor water level 3

K5.06 Rod pattern 3

K5.07 Reactor internal pump-adjustable speed drives 3

K5.08 Technician interface unit 2

K 6 Knowledge of the effect of the following plant conditions, system

malfunctions or component malfunctions will have on the Recirculation 

Flow Control System:

(CFR: 41.7 / 45.7)

K6.01 Electrical power distribution system 3

K6.02 Recirculation system 3

K6.03 Feedwater control system 4

K6.04 Low reactor water level 3

K6.05 Neutron monitoring signal input 4

K6.06 Automatic power regulator system 4
NUREG-2104 3.1-10

3.1 Safety Function 1: Reactivity Control

System: SF1RFC Recirculation Flow Control System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K6.07 Steam bypass and pressure control system 3

K6.08 Reactor trip and isolation system 3

K6.09 Reactor pressure vessel instrumentation 3

A 1 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 Reactor internal pump speed 3

A1.02 MG set drive motor amps 3

A1.03 MG set generator current, power, voltage 2

A1.04 Reactor water level 3

A1.05 Reactor power 4

A1.06 Reactor core flow 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 Reactor internal pump-adjustable speed drives trip 3 3

A2.02 Reactor internal pump-adjustable speed drives normal or fast

speed runback 3 3

A2.03 Loss of AC electrical power distribution system 3 3

A2.04 Low reactor water level 3 3

A2.05 Loss of feedwater signal inputs 3 3

A 3 Ability to monitor automatic operations of the Recirculation Flow Control 

System including:

(CFR: 41.7 / 45.7)

A3.01 Indications and alarms 3

A3.02 Reactor internal pump speed 3
3.1-11 NUREG-2104

3.1 Safety Function 1: Reactivity Control

System: SF1RFC Recirculation Flow Control System (continued)

K/A NO. ABILITY IMPORTANCE

A 4 Ability to manually operate and/or monitor the Recirculation Flow Control 

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 MG sets 3

A4.02 Adjustable speed drives 3

A4.03 Indications and alarms 3

A4.04 Reactor internal pumps speed 3
NUREG-2104 3.1-12

3.1 Safety Function 1: Reactivity Control

System: SF1RRS Reactor Recirculation System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Reactor Recirculation System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor building cooling water system 3

K1.02 AC electrical power distribution system 3

K1.03 Control rod drive system 3

K1.04 Recirculation flow control system 4

K1.05 Plant information and control system 3

K1.06 Makeup water purified system 2

K1.07 Reactor pressure vessel system 3

K1.08 Radioactive drain transfer system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Reactor internal pumps 3

K2.02 Recirculation system MG sets 3

K2.03 Motor generator set oil pumps 2

K 3 Knowledge of the effect that a loss or malfunction of the Reactor 

Recirculation System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Core flow 4

K3.02 Load following capabilities 3

K3.03 Reactor power 4

K3.04 Reactor water level 4

K3.05 Reactor recirculation system motor generator sets 3

K3.06 Vessel bottom head drain temperature 3

K3.07 Primary containment integrity 3
3.1-13 NUREG-2104

3.1 Safety Function 1: Reactivity Control

System: SF1RRS Reactor Recirculation System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 Knowledge of Reactor Recirculation System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Adequate reactor internal pump NPSH 3

K4.02 Reactor internal pump motor cooling 3

K4.03 Controlled purge flow 3

K4.04 Automatic voltage/frequency regulation 3

K4.05 Motor generator set trips 3

K4.06 Pump minimum flow limit 3

K4.07 Pump start permissives 3

K4.08 Minimization of reactor vessel bottom head temperature gradients 3

K4.09 End of cycle recirculation pump trip 4

K4.10 Anticipated Transient without scram - Recirc pump trip 4

K4.11 Selected control rods run in circuitry 4

K4.12 Reactor internal pump runback 4

K4.13 Reactor internal pump startup 3

K4.14 Automatic MG set start sequencing 3

K4.15 Core flow rapid reduction logic 3

K 5 Knowledge of the operational implications or cause and effect 

relationships as they apply to the Reactor Recirculation System:

(CFR: 41.5 / 45.3)

K5.01 Reactor internal pump vibration characteristics 2

K5.02 Restart of reactor internal pumps while operating at power 3

K5.03 Core flow 4

K5.04 Reactor power 4

K5.05 Reactor moderator temperature 3

K5.06 Reactor pressure 3

K5.07 Recirculation flow control system motor-generator sets 4

K5.08 Nuclear boiler instrumentation (reactor water level/pressure/core

plate d/p) 3

K5.09 Vessel bottom head drain temperature 3

K5.10 Residual heat removal shutdown cooling mode 3

K5.11 Reactor water level 4

K5.12 Anticipated transient without scram circuitry 4

K5.13 End-of-cycle recirculation pump trip circuitry 4

K5.14 Selected control rods run in circuitry 4

K5.15 Recirculation motor inflatable shaft seal subsystem 2

K5.16 Recirculation motor cooling subsystem 3

K5.17 Reactor internal pump adjustable speed drives 3
NUREG-2104 3.1-14

3.1 Safety Function 1: Reactivity Control

System: SF1RRS Reactor Recirculation System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Reactor 

Recirculation System:

(CFR: 41.7 / 45.7)

K6.01 Reactor building cooling water systems 3

K6.02 AC electrical power distribution system 3

K6.03 Control rod drive system 3

K6.04 Recirculation system motor-generator sets 3

K6.05 Low reactor water level 3

K6.06 Recirculation motor inflatable shaft seal subsystem 3

K6.07 Makeup water purified system 2

K6.08 Reactor internal pump motor cooling subsystem 3

K6.09 Turbine trip/load rejection 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Reactor Recirculation System controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor internal pump flow 4

A1.02 Core flow 4

A1.03 Reactor water level 3

A1.04 Reactor power 4

A1.05 Reactor internal pump motor amps 3

A1.06 Reactor internal pump speed 3

A1.07 Recirculation cooling water flow 3

A1.08 Vessel bottom head drain temperature 3

A1.09 Reactor internal pump differential pressure 3

A1.10 Reactor internal pump motor temperature 2

A1.11 Reactor internal pump MG set temperatures 2

A1.12 Reactor internal pump MG drive motor amps 2

A1.13 Reactor internal pump MG set generator current, power, voltage 2

A1.14 Reactor internal pump motor purge flow 3

A1.15 Reactor internal pump vibration 2

A1.16 Core differential pressure 3
3.1-15 NUREG-2104

3.1 Safety Function 1: Reactivity Control

System: SF1RRS Reactor Recirculation System (continued)

K/A NO. ABILITY IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Reactor 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)

RO SRO

A2.01 Recirculation system leak 4 4

A2.02 Single reactor internal pump trip 4 4

A2.03 Multiple reactor internal pump trip 4 4

A2.04 Inadvertent recirculation flow increase 4 4

A2.05 Inadvertent recirculation flow decrease 4 4

A2.06 Reactor internal pump speed mismatch 3 3

A2.07 Reactor internal pump flow mismatch 3 3

A2.08 Low reactor water level 4 4

A2.09 Loss of reactor feedwater 4 4

A2.10 High reactor pressure (ATWS circuitry initiation) 4 4

A2.11 End of cycle recirculation pump trip circuitry initiation 4 4

A2.12 Selected control rods run in circuitry actuation 4 4

A2.13 Loss of motor cooling 3 3

A2.14 Loss of AC power 3 3

A2.15 Loss of reactor building cooling water 3 3

A2.16 Incomplete start sequence 3 3

A2.17 Loss of reactor internal pump purge flow 3 3

A2.18 Reactor internal pump speed runback 3 3

A2.19 Increase in reactor internal pump vibration 2 2

A 3 Ability to monitor automatic operations of the Reactor Recirculation 

System including:

(CFR: 41.7 / 45.7)

A3.01 Pump/MG set start sequence 3

A3.02 System flow 3

A3.03 Indications and alarms 3

A3.04 Pump speed 3

A3.05 Reactor internal pump trips 3

A3.06 Reactor internal pump runbacks 3

A3.07 Recirculation system motor generator set trip 3

A 4 Ability to manually operate and/or monitor the Reactor Recirculation 

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Reactor internal pumps 4

A4.02 System flow 4

A4.03 Core flow 4
NUREG-2104 3.1-16

3.1 Safety Function 1: Reactivity Control

System: SF1RCIS Rod Control and Information System 

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Rod Control and Information System and the following 

systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Neutron monitoring system 3

K1.02 Control rod drive system 4

K1.03 Recirculation flow control system 3

K1.04 Reactor trip and isolation system 3

K1.05 Plant information and control system 3

K1.06 Automatic power regulator system 3

K1.07 Refueling equipment 3

K1.08 AC electrical power distribution system 2

K1.09 Vital AC power supply system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 RCIS redundant controllers 2

K2.02 Stepping motor driver modules 3

K2.03 Rod brake controller cabinets 3

K 3 Knowledge of the effect that a loss or malfunction of the Rod Control and 

Information System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor startup 4

K3.02 Reactor shutdown 3

K3.03 Flux shaping 3

K3.04 Recirculation flow control system 3

K3.05 Refueling equipment 3

K3.06 Automatic power regulator system 3

K3.07 Control rod drive system 4

K3.08 Reactor trip and isolation system 3

K 4 Knowledge of Rod Control and Information System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Limiting the effects of a control rod accident 3

K4.02 Rod withdrawal block signals 4

K4.03 Rod insertion block signals 4

K4.04 Automatic control rod run-in following a scram 3
3.1-17 NUREG-2104

3.1 Safety Function 1: Reactivity Control

System: SF1RCIS Rod Control and Information System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K4.05 Insertion of selected control rods for core thermal-hydraulic stability

control or loss of feedwater heating event 3

K4.06 Alternate control rod insertion on a failure to scram (control rod

run-in on ARI) 3

K 5 Knowledge of the operational implications or cause and effect 

relationships as they apply to Rod Control and Information System:

(CFR: 41.5 / 45.3)

K5.01 Ganged rod withdrawal sequence 3

K5.02 Rod gangs 2

K5.03 Fine motion control rod drive mechanism 4

K5.04 Target rod pattern 3

K5.05 Low power setpoint 4

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Rod Control and 

Information System:

(CFR: 41.7 / 45.7)

K6.01 Rod position signal 3

K6.02 AC electrical power distribution system 3

K6.03 Reactor trip and isolation system 3

K6.04 Plant information and control system 3

K6.05 Neutron monitoring system 3

K6.06 Automatic power regulator system 3

K6.07 Vital AC power supply system 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Rod Control and Information System controls including:

(CFR: 41.5 / 45.5)

A1.01 First stage shell pressure/turbine load 3

A1.02 Reactor power 3

A1.03 Reactor water temperature 2
NUREG-2104 3.1-18

3.1 Safety Function 1: Reactivity Control

System: SF1RCIS Rod Control and Information System (continued)

K/A NO. ABILITY IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Rod Control and 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)

RO SRO

A2.01 High flux (neutron monitoring) 4 4

A2.02 Position indication failure 3 3

A2.03 Insert block 3 3

A2.04 Withdraw block 3 3

A2.05 Local Power Range Monitor upscale/down scale 3 3

A2.06 Accumulator fault 3 4

A2.07 Rod uncoupled 4 4

A2.08 Rod drift 4 4

A2.09 Emergency rod insertion (SCRRI, ARI, or scram-follow) 4 4

A2.10 Rod misalignment 3 3

A 3 Ability to monitor automatic operations of the Rod Control and Information 

System including:

(CFR: 41.7 / 45.7)

A3.01 Dedicated operator interface indications 4

A3.02 Rod display module indications 4

A3.03 Verification of proper functioning/operability 3

A3.04 Annunciator and alarm signals 3

A3.05 Emergency rod insertion (ARI, SCCRI, scram follow function) 4

A3.06 Rod movement in automatic mode (step/notch/continuous) 3

A3.07 Automatic self-bypass of RCIS protective features (Rod Worth

Minimizer System and Automated Thermal Limit Monitoring System) 3

A 4 Ability to manually operate and/or monitor the Rod Control and Information 

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Dedicated operator interface (switches or screen manipulations) 4

A4.02 Back panel switches or screens 3

A4.03 Initiation of SCRRI 3

A4.04 Control rods in semi-automatic or manual mode 

step/notch/continuous) 3

A4.05 Bypassing an inoperable control rod 3

A4.06 Bypassing a single channel of RCIS 3
3.1-19 NUREG-2104

3.1 Safety Function 1: Reactivity Control

System: SF1SLC Standby Liquid Control System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Standby Liquid Control System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Service air system 3

K1.02 Makeup water purified system 3

K1.03 Reactor pressure vessel system 4

K1.04 High pressure core flooder system 4

K1.05 Engineered Safety Function logic and control system 3

K1.06 Leak detection and isolation system 3

K1.07 Sampling system 2

K1.08 Neutron monitoring system 3

K1.09 AC electrical power distribution system 2

K1.10 Post accident monitoring system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Standby liquid control storage tank outlet valve 3

K2.02 Standby liquid control pumps 3

K2.03 Standby liquid control injection motor operated valves 3

K2.04 SLC tank heater power 2

K2.05 Standby liquid control lubricating pump 2

K 3 Knowledge of the effect that a loss or malfunction of the Standby Liquid 

Control System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Ability to shutdown the reactor in certain conditions 4

K 4 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 (demineralized water) 3

K4.02 Component and system testing 3

K4.03 Keeping sodium pentaborate in solution 4

K4.04 Dispersal of boron upon injection into the vessel 3

K4.05 Reactor water cleanup system isolation 4

K4.06 System initiation upon operation of SLC controls 4

K4.07 Over pressure protection 3

K4.08 Automatic standby liquid control system initiation 4
NUREG-2104 3.1-20

3.1 Safety Function 1: Reactivity Control

System: SF1SLC Standby Liquid Control System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 5 Knowledge of the operational implications and/or cause-effect 

relationships 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 3

K5.02 Chugging (as it pertains to boron mixing) 3

K5.03 Shutdown margin 3

K5.04 Tank heater operation 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Standby Liquid 

Control System:

(CFR: 41.7 / 45.7)

K6.01 Service air system 2

K6.02 Makeup water purified system 3

K6.03 AC electrical power distribution system 3

K6.04 High pressure core flooder system 3

K6.05 Engineered Safety Function logic and control system 3

K6.06 Neutron monitoring system 3

K6.07 Leak detection and isolation system 3

ABILITY

A 1 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 4

A1.02 Pump discharge pressure 4

A1.03 Valve operations 4

A1.04 Pump amps 3

A1.05 Reactor power 4

A1.06 Reactor water cleanup system lineup 4

A1.07 Standby liquid control system lineup 4

A1.08 Indications and alarms 4
3.1-21 NUREG-2104

3.1 Safety Function 1: Reactivity Control

System: SF1SLC Standby Liquid Control System (continued)

K/A NO. ABILITY IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 Standby liquid control pump trip 4 4

A2.02 AC electrical power failures 3 3

A2.03 Inadequate system flow 3 3

A2.04 Loss of standby liquid control tank heaters 3 3

A2.05 Failure to scram 4 4

A 3 Ability to monitor automatic operations of the Standby Liquid Control 

System including:

(CFR: 41.7 / 45.7)

A3.01 Pump discharge pressure 4

A3.02 Tank level 4

A3.03 Injection valve indications 4

A3.04 Reactor power 4

A3.05 Reactor water cleanup system isolation 4

A3.06 Indications and alarms 4

A3.07 System initiation 4

A 4 Ability to manually operate and/or monitor Standby Liquid Control System

in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Standby liquid control system controls 4

A4.02 Reactor water cleanup system isolation 4

A4.03 System initiation 4

3.2-1 NUREG-2104

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2HPCF High Pressure Core Flooder System 

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships between 

the High Pressure Core Flooder System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Makeup water condensate system 3

K1.02 Standby liquid control system 3

K1.03 Suppression pool cleanup system 2

K1.04 Reactor building cooling water system 2

K1.05 Reactor pressure vessel system 4

K1.06 High pressure nitrogen gas supply system 2

K1.07 Instrument air system 2

K1.08 Automatic depressurization system 3

K1.09 Remote shutdown system 3

K1.10 Engineered Safety Function logic and control system 3

K1.11 Residual heat removal system 3

K1.12 Reactor core isolation cooling system 2

K1.13 AC electrical power distribution system 3

K1.14 Plant information and control system 2

K1.15 Post accident monitoring system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 High pressure core flooder pumps 3

K2.02 High pressure core flooder test return to suppression pool valves 3

K2.03 High pressure core flooder injection valves 3

K2.04 High pressure core flooder CST suction valves 3

K2.05 High pressure core flooder suppression pool suction valves 3

K2.06 Initiation logic 3

K 3 Knowledge of the effect that a loss or malfunction of the High Pressure Core 

Flooder System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level 4

K3.02 Standby liquid control system 3

K3.03 Adequate core cooling 4

K3.04 Automatic depressurization system 3
NUREG-2104 3.2-2

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2HPCF High Pressure Core Flooder System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 Knowledge of High Pressure Core Flooder System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Prevents water hammer 3

K4.02 Prevents overfilling reactor vessel 3

K4.03 Prevents pump over heating 2

K4.04 Testable check valve operation 2

K4.05 Motor operated valve operation 2

K4.06 High pressure core flooder pump operation 4

K4.07 Override of reactor water level interlock 3

K 5 Knowledge of the operational implications and/or cause and effect

relationships as they apply to High Pressure Core Flooder System:

(CFR: 41.5 / 45.3)

K5.01 Suppression Pool 4

K5.02 Emergency core cooling system room coolers 2

K5.03 Adequate core cooling 4

K5.04 Suppression pool suction strainers 2

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the High Pressure 

Core Flooder System:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 4

K6.02 Makeup water condensate system 3

K6.03 Reactor building cooling water system 3

K6.04 Suppression pool suction strainer 3

K6.05 Suppression pool water level 3

K6.06 Engineered Safety Function logic and control system 3

K6.07 Remote shutdown system 3

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the High Pressure Core Flooder System controls including:

(CFR: 41.5 / 45.5)

A1.01 High pressure core flooder flow 4

A1.02 High pressure core flooder pressure 3

A1.03 Reactor water level 4

A1.04 Reactor pressure 3

A1.05 Suppression pool water level 3
3.2-3 NUREG-2104

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2HPCF High Pressure Core Flooder System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

A1.06 Motor amps 3

A1.07 System lineup 3

A1.08 Condensate storage tank level 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the High Pressure Core Flooder 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)

RO SRO

A2.01 System initiation 4 4

A2.02 High pressure core flooder pump trip 4 4

A2.03 AC electrical failure 3 3

A2.04 High pressure core flooder line break 3 4

A2.05 Pump seal failure 3 3

A2.06 Inadequate system flow 3 3

A2.07 Loss of room cooling 2 3

A2.08 Low suppression pool level 3 4

A2.09 High suppression pool level 3 4

A2.10 Low condensate storage tank level 3 4

A2.11 High suppression pool temperature 3 3

A2.12 Clogged suppression pool suction strainers 3 3

A 3 Ability to monitor automatic operations of the High Pressure Core Flooder 

System including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation 3

A3.02 Pump start 4

A3.03 System pressure 3

A3.04 System flow 4

A3.05 Reactor water level 4

A3.06 Indications and alarms 4

A 4 Ability to manually operate and/or monitor High Pressure Core Flooder 

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 High pressure core flooder pump 4

A4.02 High pressure core flooder suction valves 4

A4.03 High pressure core flooder injection valve 4

A4.04 High pressure core flooder minimum flow valve 3

A4.05 Manual initiation controls (PRA) 3

A4.06 High pressure core flooder testable check valve 2
NUREG-2104 3.2-4

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2HPCF High Pressure Core Flooder System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

A4.07 Line fill 3

A4.08 System flow 4

A4.09 High pressure core flooder test return valve 3

A4.10 High pressure core flooder initiation reset controls 4
3.2-5 NUREG-2104

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2CD Condensate System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships between 

the Condensate System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Main turbine 3

K1.02 Feedwater system 3

K1.03 Condensate demineralizer system 3

K1.04 Condensate filter system 3

K1.05 Control rod drive system 3

K1.06 Extraction steam system 3

K1.07 Exhaust hood spray system 2

K1.08 Instrument air system 2

K1.09 Circulating water system 3

K1.10 Turbine building cooling water system 3

K1.11 Makeup water condensate system 3

K1.12 Radwaste system 2

K1.13 Oxygen injection system 3

K1.14 Zinc injection system 2

K1.15 Hydrogen water chemistry system 3

K1.16 AC electrical power distribution system 3

K1.17 Heater drains and vent system 3

K1.18 Noble metal injection system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Condensate pumps 3

K2.02 Condensate booster pumps 3

K2.03 Condensate pump discharge valves 2

K2.04 Condensate booster pump discharge valves 2

K 3 Knowledge of the effect that a loss or malfunction of the Condensate System

will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Main turbine/main generator 3

K3.02 Control rod drive system 3

K3.03 Feedwater system 4

K3.04 Steam jet air ejectors 3

K3.05 Gland seal steam system 3

K3.06 Reactor water level 4
NUREG-2104 3.2-6

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2CD Condensate System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 Knowledge of Condensate System design feature(s) and/or interlocks which 

provide for the following:

(CFR: 41.7)

K4.01 Condensate or condensate booster pump auto start 3

K4.02 CRD pump suction 3

K4.03 Condensate or condensate booster pump protection 3

K4.04 Maintenance of water quality 3

K4.05 Maintenance of 100% system flow if a feedwater string isolates 3

K4.06 Cascading heater drains 2

K4.07 Initial main condenser vacuum 3

K4.08 Non-condensable gas removal 3

K4.09 Auto condensate pump trip due to feedwater line break detection 4

K 5 Knowledge of the operational implications and/or cause and effect

relationships as they apply to Condensate System:

(CFR: 41.5 / 45.3)

K5.01 Steam jet air ejector condenser 3

K5.02 Gland seal steam condenser 3

K5.03 Reactor water level 4

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Condensate 

System:

(CFR: 41.7 / 45.7)

K6.01 Instrument air system 3

K6.02 Circulating water system 3

K6.03 Extraction steam system 3

K6.04 AC electrical power distribution system 3

K6.05 Turbine building cooling water systems 3

K6.06 Feedwater system 3

K6.07 Makeup water condensate system 2

K6.08 Main turbine 3

K6.09 Main steam system 3

K6.10 Condensate demineralizer system 3

K6.11 Condensate filter system 3
3.2-7 NUREG-2104

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2CD Condensate System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Condensate System controls including:

(CFR: 41.5 / 45.5)

A1.01 System flow 3

A1.02 Pump amps 2

A1.03 System pressure 3

A1.04 Hotwell level 3

A1.05 Condensate storage tank level 3

A1.06 Reactor water level 4

A1.07 System lineup 3

A1.08 System water quality 3

A1.09 Feedwater temperature 3

A1.10 Condenser vacuum 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the 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)

RO SRO

A2.01 Pump trips 3 3

A2.02 Condensate pump discharge valve closures 3 3

A2.03 Condensate booster pump discharge valve closure 3 3

A2.04 Valve openings 3 3

A2.05 AC power failures 3 3

A2.06 Inadequate system flow 3 3

A2.07 Low hotwell level 3 3

A2.08 High hotwell level 3 3

A2.09 High feedwater heater level 3 3

A2.10 Low feedwater heater level 3 3

A2.11 Main turbine trip 3 3

A2.12 Loss of circulating water system 3 3

A2.13 Loss of turbine building cooling water systems 3 3

A2.14 Loss of instrument air system 3 3

A2.15 Low Condensate storage tank level 3 3

A2.16 Abnormal water quality 3 3

A2.17 High demineralizer differential pressure 3 3

A2.18 Feedwater heater string isolation 3 3

A2.19 Loss of SJAE 3 3

A2.20 Condensate filter high differential pressure 2 2
NUREG-2104 3.2-8

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2CD Condensate System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

A 3 Ability to monitor automatic operations of the Condensate System including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation 3

A3.02 Pump starts 3

A3.03 System pressure 3

A3.04 System flow 3

A3.05 Indications and alarms 3

A3.06 Hotwell level 3

A3.07 Feedwater heater level 3

A3.08 Feedwater temperature 3

A3.09 Feedwater heater drain tank level 3

A 4 Ability to manually operate and/or monitor the Condensate System in the 

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Condensate/ condensate booster pumps 3

A4.02 System motor operated valves 3

A4.03 Hotwell level controls 3
3.2-9 NUREG-2104

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2RCIC Reactor Core Isolation Cooling System 

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships between 

the Reactor Core Isolation Cooling System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Makeup water condensate system 4

K1.02 Main steam system 4

K1.03 Residual heat removal system 3

K1.04 Instrument air system 2

K1.05 Leak detection and isolation system 3

K1.06 Engineered Safety Function logic and control system 3

K1.07 Feedwater system 4

K1.08 Suppression pool suction strainer 2

K1.09 AC electrical power distribution system 2

K1.10 DC power supply system 3

K1.11 High pressure core flooder system 2

K1.12 Radioactive drain transfer system 2

K1.13 Heating ventilation and air conditioning system 2

K1.14 Post accident monitoring system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 RCIC steam admission valves 3

K2.02 Condensate storage tank suction valve 3

K2.03 Suppression pool suction valve 3

K2.04 RCIC test return to suppression pool valves 2

K2.05 RCIC initiation signals (logic) 3

K2.06 Reactor core isolation cooling drain pump 2

K 3 Knowledge of the effect that a loss or malfunction of the Reactor Core 

Isolation Cooling System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level 4

K3.02 Reactor vessel pressure 4

K3.03 Decay heat removal 4

K3.04 Adequate core cooling 4
NUREG-2104 3.2-10

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2RCIC Reactor Core Isolation Cooling System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 Knowledge of Reactor Core Isolation Cooling System design feature(s) 

and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Prevent water hammer 3

K4.02 Prevent overfilling reactor vessel 3

K4.03 Override of high reactor water level interlock 3

K4.04 Prevents pump over heating 3

K4.05 Prevents turbine damage 3

K4.06 Manual initiation 4

K4.07 Alternate supplies of water 4

K 5 Knowledge of the operational implications or cause and effect relationships 

as they apply to Reactor Core Isolation Cooling System:

(CFR: 41.5 / 45.3)

K5.01 Assist core cooling 4

K5.02 Suppression pool 4

K5.03 Main condenser 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Reactor Core 

Isolation Cooling System:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 3

K6.02 Instrument air system 2

K6.03 Suppression pool water supply 4

K6.04 Makeup water condensate system 4

K6.05 Main steam system 4

K6.06 Suppression pool suction strainer 3

K6.07 DC power supply system 3

K6.08 Engineered Safety Function logic and control system 3

K6.09 High pressure core flooder system 2

K6.10 Radioactive drain transfer system 2

K6.11 Heating ventilation and air conditioning system 2

K6.12 Feedwater system 3
3.2-11 NUREG-2104

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2RCIC Reactor Core Isolation Cooling System (continued)

K/A NO. ABILITY IMPORTANCE

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

operating the Reactor Core Isolation Cooling System controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor core isolation cooling flow 4

A1.02 Reactor core isolation cooling pressure 3

A1.03 Reactor water level 4

A1.04 Reactor pressure 4

A1.05 Reactor core isolation cooling turbine speed 4

A1.06 Condensate storage tank level 3

A1.07 Suppression pool level 3

A1.08 Suppression pool temperature 4

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Reactor Core Isolation Cooling 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)

RO SRO

A2.01 System initiation signal 4 4

A2.02 Reactor core isolation cooling turbine trips 4 4

A2.03 Injection valve closure 3 3

A2.04 AC power loss 2 2

A2.05 DC power loss 3 3

A2.06 Loss of instrument air system 2 2

A2.07 Loss of reactor core isolation cooling drain pump 2 2

A2.08 Turbine control system failures 3 3

A2.09 Inadequate system flow 3 3

A2.10 Loss of room cooling 3 3

A2.11 Steam line break 4 4

A2.12 Low condensate storage tank level 4 3

A2.13 High suppression pool level 3 3

A2.14 Low suppression pool level 3 3

A2.15 High suppression pool temperature 4 4

A2.16 High drain tank level 2 2
NUREG-2104 3.2-12

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2RCIC Reactor Core Isolation Cooling System (continued)

K/A NO. ABILITY IMPORTANCE

A 3 Ability to monitor automatic operations of the Reactor Core Isolation Cooling 

System including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation 4

A3.02 Turbine startup 4

A3.03 System pressure 4

A3.04 System flow 4

A3.05 Reactor water level 4

A3.06 Indications and alarms 4

A 4 Ability to manually operate and/or monitor the Reactor Core Isolation 

Cooling System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Reactor core isolation cooling turbine speed 4

A4.02 Turbine trip throttle valve reset 4

A4.03 System valves 3
3.2-13 NUREG-2104

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2FW Feedwater System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships between 

the Feedwater System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor pressure vessel system 4

K1.02 Reactor water cleanup system 3

K1.03 Extraction steam system 3

K1.04 Condensate system 3

K1.05 Instrument air system 3

K1.06 AC electrical power distribution system 3

K1.07 Feedwater control system 4

K1.08 Turbine building cooling water system 3

K1.09 Feedwater pump lube oil subsystem 3

K1.10 Reactor core isolation cooling system 4

K1.11 Residual heat removal system 4

K1.12 Heater drains and vent system 2

K1.13 Sampling system 2

K1.14 Control rod drive system 3

K1.15 Plant information and control system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Feedwater pump(s) 3

K2.02 Feedwater pump discharge valves 2

K2.03 Reactor feedwater pump auxiliary oil pumps 2

K 3 Knowledge of the effect that a loss or malfunction of the Feedwater System

will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level 4

K3.02 Feedwater control system 4

K3.03 Reactor water cleanup system 3

K3.04 Reactor internal pump NPSH 3

K3.05 Core inlet subcooling 3

K3.06 Condensate system 3

K3.07 Reactor core isolation cooling system 3

K3.08 Extraction steam system 3

K3.09 Residual heat removal system 3

K3.10 Reactor power 4
NUREG-2104 3.2-14

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2FW Feedwater System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 Knowledge of Feedwater System design feature(s) and/or interlocks which 

provide for the following:

(CFR: 41.7)

K4.01 Auto start of the feedwater pumps 4

K4.02 Feedwater heating 3

K4.03 Feedwater pump minimum flow 3

K4.04 Dispersal of feedwater in the reactor vessel 3

K4.05 Feedwater pump protection 3

K4.06 Feedwater pump lubrication 3

K4.07 Feedwater pump motor cooling 3

K4.08 System isolation from the reactor vessel (check valves, double valve

isolation inside/ outside containment) 3

K4.09 Feedwater pump runbacks due to ATWS 3

K4.10 Reactor internal pump speed runbacks 4

K4.11 Condensate pumps trip due to feedwater line break detection 3

K4.12 Selected control rod run-in (SCCRI) initiation 3

K4.13 Up-rate feedwater flow measurement 2

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to Feedwater System:

(CFR: 41.5 / 45.3)

K5.01 Reactor water level 4

K5.02 Thermal power calculation 2

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Feedwater System:

(CFR: 41.7 / 45.7)

K6.01 Instrument air system 3

K6.02 Condensate system 3

K6.03 AC electrical power 3

K6.04 Extraction steam 3

K6.05 Turbine building cooling water systems 3

K6.06 Feedwater control system 4

K6.07 Feedwater pump motor ventilation 2

K6.08 Feedwater pump lube oil system 3

K6.09 DC electrical power 2

K6.10 Engineered Safety Function logic and control system 3

K6.11 Heater drains 3

K6.12 Plant information and control system 3
3.2-15 NUREG-2104

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2FW Feedwater System (continued)

K/A NO. ABILITY IMPORTANCE

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Feedwater System controls including:

(CFR: 41.5 / 45.5)

A1.01 Feedwater flow/pressure 3

A1.02 Feedwater inlet temperature 3

A1.03 FP motor amps 3

A1.04 Feedwater heater level 3

K1.05 Feedwater pump speed 3

K1.06 Feedwater control valve operation 2

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the 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)

RO SRO

A2.01 Feedwater heater isolation 3 3

A2.02 Loss of condensate or condensate booster pump(s) 4 4

A2.03 Loss of extraction steam 3 3

A2.04 Loss of instrument air system 3 3

A2.05 Loss of AC electrical power 3 3

A2.06 Feedwater control system malfunctions 4 4

A2.07 Loss of DC electrical power 3 3

A2.08 Loss of turbine building cooling water system 3 3

A2.09 Loss of feedwater pump 3 3

A2.10 Loss of high pressure drain pump 3 3

A 3 Ability to monitor automatic operations of the Feedwater System including:

(CFR: 41.7 / 45.7)

A3.01 Feedwater pump auto start 3

A3.02 Feedwater pump motor amps: 2

A3.03 System flow 3

A3.04 Reactor water level 4

A3.05 Feedwater inlet temperature 3

A3.06 Pump discharge pressure 3

A3.07 Indications and alarms 3

A3.08 Pump trips 3

A3.09 Feedwater pump runbacks due to ATWS 3

A3.10 Feedwater pump speed 3

A3.11 Feedwater pump minimum flow valve position 2
NUREG-2104 3.2-16

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2FW Feedwater System (continued)

K/A NO. ABILITY IMPORTANCE

A 4 Ability to manually operate and/or monitor the Feedwater System in the 

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Manually start/control a feedwater pump 4

A4.02 Feedwater heater/drain controls 3

A4.03 System valves 3
3.2-17 NUREG-2104

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2RWCU Reactor Water Cleanup System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships between 

the Reactor Water Cleanup System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor pressure vessel system 3

K1.02 Feedwater system 3

K1.03 Reactor building cooling water system 3

K1.04 Instrument air system 3

K1.05 Service air system 2

K1.06 Low conductivity waste system 3

K1.07 Leak detection and isolation system 4

K1.08 Makeup water condensate system 3

K1.09 Residual heat removal system 3

K1.10 Sampling system 3

K1.11 Control rod drive system 3

K1.12 Feedwater control system 3

K1.13 Automatic power regulator 3

K1.14 Feedwater system 3

K1.15 Engineered Safety Function logic and control system 3

K1.16 High pressure nitrogen gas supply system 2

K1.17 Electrical power distribution system 3

K1.18 Plant information and control system 3

K1.19 Fuel pool cooling and cleanup system 2

K1.21 Post accident monitoring system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Reactor water cleanup pumps 2

K2.02 Containment isolation valves 2

K 3 Knowledge of the effect that a loss or malfunction of the Reactor Water 

Cleanup System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water quality 3

K3.02 Reactor water level 3

K3.03 Reactor building cooling water systems 2

K3.04 Reactor water temperature 3

K3.05 Area temperature 2

K3.06 Area radiation levels 3

K3.07 Drywell temperature 2

K3.08 Drywell pressure 2

K3.09 Automatic power regulator system 3
NUREG-2104 3.2-18

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2RWCU Reactor Water Cleanup System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 Knowledge of Reactor Water Cleanup System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Pump protection 3

K4.02 Piping over-pressurization protection 3

K4.03 Over temperature protection for system components 3

K4.04 System isolation upon-receipt of isolation signals 4

K4.05 Double valve isolation from the reactor 3

K4.06 Maximize plant efficiency (use of regenerative heat exchanger) 3

K4.07 Draining of reactor water to various locations 3

K4.08 Head spray to RPV vessel head for head removal prior to refueling

operation 2

K4.09 Control of RPV water level during startup and shutdown 3

K4.10 Decay heat removal 2

K4.11 Control of reactor water quality 3

K 5 Knowledge of the operational implications or cause and effect relationships 

as they apply to Reactor Water Cleanup System:

(CFR: 41.5 / 45.3)

K5.01 Main condenser 3

K5.02 Reactor water level 3

K5.03 Reactor water quality 3

K5.04 Initiation of standby liquid control system 4

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Reactor Water 

Cleanup System:

(CFR: 41.7 / 45.7)

K6.01 Reactor building cooling water systems 3

K6.02 Main condenser 2

K6.03 Radwaste 2

K6.04 Instrument air system 3

K6.05 Service air system 2

K6.06 High pressure nitrogen gas supply system 2

K6.07 AC Electrical power distribution system 3

K6.08 Feedwater system 2

K6.09 Standby liquid control system logic 3

K6.10 Leak detection and isolation system 4

K6.11 Control rod drive system 3

K6.12 Feedwater control system 3

K6.13 Engineered Safety Function logic and control system 3

K6.14 Plant information and control system 3
3.2-19 NUREG-2104

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2RWCU Reactor Water Cleanup System (continued)

K/A NO. ABILITY IMPORTANCE

A 1 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

A1.02 Component cooling water temperature 3

A1.03 Reactor water temperature 3

A1.04 System flow 3

A1.05 System pressure 3

A1.06 System temperature 3

A1.07 RWCU drain flow 3

A1.08 Main condenser hotwell level 2

A1.09 Reactor water conductivity 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 Loss of reactor building cooling water 3 3

A2.02 Flow control valve failure 3 3

A2.03 RWCU pump trips 3 3

A2.04 AC failure 3 3

A2.05 Loss of instrument air system 3 3

A2.06 Loss of service air system 2 2

A2.07 Loss of room coolers 3 3

A2.08 Inadequate system flow 3 3

A2.09 Excessive drain flow rates 3 3

A2.10 Signal received which results in a system isolation 3 3

A2.11 System high temperature 3 3

A2.12 Cleanup demineralizer high differential pressure 3 3

A2.13 Loss of purge flow to reactor water cleanup pump 3 3

A 3 Ability to monitor automatic operations of the Reactor Water Cleanup System

including:

(CFR: 41.7 / 45.7)

A3.01 Reactor water quality 3

A3.02 Response to system isolations 4

A3.03 Response to interlocks and trips designed to protect system

components 3

A3.04 Reactor water temperature 3
NUREG-2104 3.2-20

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2RWCU Reactor Water Cleanup System (continued)

K/A NO. ABILITY IMPORTANCE

A3.05 Indications and alarms 3

A3.06 Reactor water level control by feedwater control system 3

A 4 Ability to manually operate and/or monitor the Reactor Water Cleanup 

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 System pumps 3

A4.02 Valve controls 3

A4.03 Heat exchanger operation 3
3.2-21 NUREG-2104

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2FWC Feedwater Control System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships between 

the Feedwater Control System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor trip and isolation system 4

K1.02 Feedwater system 4

K1.03 Steam bypass and pressure control system 3

K1.04 Recirculation flow control system 3

K1.05 Main steam system 3

K1.06 Reactor water cleanup 3

K1.07 Plant information and control system 3

K1.08 Engineered Safety Function logic and control system 3

K1.09 Neutron monitoring system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Feedwater control system circuitry 2

K2.02 Feedwater pump adjustable speed drive 3

K 3 Knowledge of the effect that a loss or malfunction of the Feedwater Control 

System will have on the following:

(CFR: 41.7 / 45.4 to 45.8)

K3.01 Reactor water level 4

K3.02 Reactor feedwater system 4

K3.03 Recirculation flow control system 3

K3.04 Main turbine 3

K3.05 Reactor water level indication 3

K3.06 Recirculation flow control system 3

K3.07 Reactor water cleanup 3

K 4 Knowledge of Feedwater Control System design feature(s) and/or interlocks 

which provide for the following:

(CFR: 41.7)

K4. 01 Feedwater pump runout protection 3

K4.02 Reactor water level setpoint setdown following a reactor scram 3

K4.03 Control signal failure 3

K4.04 Feedwater pump speed control 4

K4.05 Single element control (reactor water level provides the only input) 3

K4.06 Three element control (main steam flow, reactor feedwater flow and

reactor water level provide input) 3

K4.07 Manual and automatic control of the system 4
NUREG-2104 3.2-22

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2FWC Feedwater Control System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K4.08 Feedwater pump speed lockup 4

K4.09 Selection of various instruments to provide reactor water level input 3

K4.10 Simultaneous Manual and Auto operation of the system

(i.e. 1 FP in Auto, 1 FP in Manual) 3

K4.11 Feedwater runback due to ATWS 4

K 5 Knowledge of the operational implications or cause and effect relationships 

as they apply to Feedwater Control System:

(CFR: 41.5 / 45.3)

K5.01 Moisture carryover 2

K5.02 Moisture carryunder 2

K5.03 Main steam flow 3

K5.04 Reactor water level 4

K5.05 Reactor feedwater flow 4

K5.06 Technician interface unit 2

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Feedwater Control 

System:

(CFR: 41.7 / 45.7)

K6.01 AC power 3

K6.02 Main steam flow input 3

K6.03 Reactor feedwater flow input 3

K6.04 Reactor water level input 4

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Feedwater Control System controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor water level 4

A1.02 Reactor feedwater flow 4

A1.03 Reactor power 4

A1.04 Reactor water level control controller indications 4

A1.05 Low flow control position. 3

A1.06 Motor driven reactor feedwater pump speed 3
3.2-23 NUREG-2104

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2FWC Feedwater Control System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Feedwater 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)

RO SRO

A2.01 Loss of any number of main steam flow inputs 3 3

A2.02 Loss of any number of reactor feedwater flow inputs 3 3

A2.03 Loss of reactor water level input 4 4

A2.04 Loss of controller signal output 3 3

A2.05 Feedwater runback due to ATWS 4 4

A 3 Ability to monitor automatic operations of the Feedwater Control System

including:

(CFR: 41.7 / 45.7)

A3.01 Runout flow control 3

A3.02 Changes in reactor water level 3

A3.03 Changes in main steam flow 3

A3.04 Changes in reactor feedwater flow 3

A3.05 Changes in reactor power 3

A3.06 Reactor water level setpoint setdown following a reactor scram 4

A3.07 FWRV lockup 4

A3.08 Motor driven feedwater pump speed lockup 4

A 4 Ability to manually operate and/or monitor the Feedwater Control System in 

the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 All individual component controllers in the manual mode 4

A4.02 All individual component controllers when transferring

from manual to automatic modes 4

A4.03 Motor driven feedwater pump lockup reset controls 3

A4.04 All individual component controllers when transferring

from automatic to manual mode 4

A4.05 Setpoint setdown reset controls 3
NUREG-2104 3.2-24

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2RHRLPFL Residual Heat Removal System: Low Pressure Flooder 

Injection Mode

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships between 

the Residual Heat Removal System: Low Pressure Flooder Injection Mode 

and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Makeup water condensate system 3

K1.02 Automatic depressurization system 4

K1.03 AC electrical power distribution system 4

K1.04 Nuclear boiler instrumentation system 4

K1.05 Instrument air 3

K1.06 Radioactive drain transfer system 2

K1.07 Reactor building cooling water system 3

K1.08 Reactor pressure vessel system 4

K1.09 Fire protection system (PRA) 3

K1.10 Remote shutdown system 3

K1.11 Reactor core isolation cooling 3

K1.12 High pressure core flooder system 3

K1.13 Fuel pool cooling and cleanup system 3

K1.14 Sampling system 2

K1.15 High pressure nitrogen gas supply system 2

K1.16 Suppression pool temperature monitoring system 3

K1.17 Engineered Safety Function logic and control system 4

K1.18 Plant information and control system 3

K1.19 Leak detection and isolation system 3

K1.20 Reactor water cleanup system 3

K1.21 Low conductivity waste system 2

K1.22 Atmosphere control system 2

K1.23 Heating, ventilation and air conditioning system 2

K1.24 Suppression pool water drainage system 2

K1.25 Post accident monitoring system 2

K1.26 Feedwater system 4

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Residual heat removal pumps 4

K2.02 Residual heat removal injection valves 3

K2.03 Residual heat removal pump minimum flow valves 2

K2.04 Residual heat removal test return valves 2

K2.05 Residual heat removal heat exchanger outlet valves 2

K2.06 Residual heat removal heat exchanger bypass valves 2

K2.07 Residual heat removal suppression pool suction valves 2

K2.08 Initiation logic 3
3.2-25 NUREG-2104

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2RHRLPFL Residual Heat Removal System: Low Pressure Flooder 

Injection Mode (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 3 Knowledge of the effect that a loss or malfunction of the Residual Heat 

Removal System: Low Pressure Flooder Injection Mode will have on the 

following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level 4

K3.02 Suppression pool level 4

K3.03 Automatic depressurization logic 4

K3.04 Adequate core cooling 4

K 4 Knowledge of Residual Heat Removal System: Low Pressure Flooder 

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

following:

(CFR: 41.7)

K4.01 Automatic system initiation/ injection 4

K4.02 Prevention of piping overpressurization 3

K4.03 Pump minimum flow protection 3

K4.04 Pump motor cooling 3

K4.05 Prevention of water hammer 3

K4.06 Adequate pump net positive suction head (interlock valve open) 4

K4.07 Emergency diesel generator load sequencing 4

K4.08 Pump operability testing 3

K4.09 Surveillance for all operable components 3

K4.10 Dedicated injection system during automatic system

initiation (injection valve interlocks) 4

K4.11 System redundancy 4

K4.12 The prevention of leakage to the environment through

Residual heat removal heat exchanger 3

K4.13 Operation from remote shutdown panel 4

K4.14 Pump runout protection 3

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to Residual Heat Removal System: Low Pressure Flooder 

Injection Mode:

(CFR: 41.5 / 45.3)

K5.01 Suppression pool 4

K5.02 Keep fill 3

K5.03 Reactor pressure 4

K5.04 Shutdown cooling 4

K5.05 Drywell or wetwell spray 4

K5.06 Drywell pressure 4

K5.07 Reactor water level 4
NUREG-2104 3.2-26

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2RHRLPFL Residual Heat Removal System: Low Pressure Flooder 

Injection Mode (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Residual Heat 

Removal System: Low Pressure Flooder Injection Mode:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power 4

K6.02 Keep fill 3

K6.03 Makeup water condensate system 3

K6.04 Instrument air system 3

K6.05 ECCS room cooling 3

K6.06 Nuclear boiler instrumentation 3

K6.07 Reactor building cooling water system 3

K6.08 Automatic depressurization system 4

K6.09 ECCS room integrity 3

K6.10 Nuclear boiler system 3

K6.11 High pressure nitrogen gas supply system 2

K6.12 Engineered Safety Function logic and control system 4

K6.13 Remote shutdown system 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Residual Heat Removal System: Low Pressure Flooder 

Injection Mode controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor water level 4

A1.02 Reactor pressure 4

A1.03 System flow 4

A1.04 System pressure 4

A1.05 Suppression pool level 4

A1.06 Motor amps 2

A1.07 Emergency diesel generator loading 3

A1.08 Reactor building cooling water systems 3
3.2-27 NUREG-2104

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2RHRLPFL Residual Heat Removal System: Low Pressure Flooder 

Injection Mode (continued)

K/A NO. ABILITY IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Residual Heat Removal System: Low 

Pressure Flooder Injection 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)

RO SRO

A2.01 Residual heat removal pump trips 4 4

A2.02 AC failures 4 4

A2.03 Pump seal failure 3 3

A2.04 Inadequate room cooling 3 3

A2.05 Inadequate system flow 3 3

A2.06 Nuclear boiler instrument failures 3 4

A2.07 Motor operated injection valve failures 3 4

A2.08 Pump runout 3 3

A2.09 Initiating logic failure 4 4

A2.10 Loss of coolant accident 4 5

A2.11 Keep fill failure 3 4

A 3 Ability to monitor auto Residual Heat Removal System: Low Pressure 

Flooder Injection Mode automatic operations including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation 4

A3.02 Pump start 4

A3.03 Pump discharge pressure 4

A3.04 System flow 4

A3.05 Reactor water level 4

A3.06 Indications and alarms 4

A3.07 System initiation sequence 4

A3.08 Emergency diesel generator load sequencing 4

A 4 Ability to manually operate and/or monitor the Residual Heat Removal 

System: Low Pressure Flooder Injection Mode in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Pumps 4

A4.02 System valves 4

A4.03 Keep fill 3

A4.04 Heat exchanger cooling flow 4

A4.05 Manual initiation controls 4

A4.06 System reset following automatic initiation 4

A4.07 Testable check valves 3
NUREG-2104 3.2-28

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2AFI Alternate Feedwater Injection System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships between 

the Alternate Feedwater Injection System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 AC electrical power distribution system 3

K1.02 Reactor feedwater system (via RWCU return line) 3

K1.03 Radioactive drain transfer system 2

K1.04 Makeup water preparation system 3

K1.06 Plant information and control system 3

K1.07 Main steam system 2

K1.08 Atmosphere control system 3

K1.09 Nuclear boiler instrumentation system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Alternate feedwater injection pump 3

K2.02 Alternate feedwater injection system motor operated injection valves 2

K 3 Knowledge of the effect that a loss or malfunction of the Alternate Feedwater 

Injection System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level 3

K3.02 Reactor pressure 3

K 4 Knowledge of Alternate Feedwater Injection System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Sufficient water capacity to maintain core covered for 24 hours

following the beyond design basis event 3

K4.02 Ability for the AFI pumps to take a suction from numerous water

sources 3

K 5 Knowledge of the operational implications or cause and effect relationships 

as they apply to Alternate Feedwater Injection System):

(CFR: 41.5 / 45.3)

K5.01 Reactor pressure vessel water level 3

K5.02 Reactor pressure vessel pressure 3
3.2-29 NUREG-2104

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2AFI Alternate Feedwater Injection System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 6 Knowledge of the effect that following plant conditions, system malfunctions 

or component malfunctions will have on the Alternate Feedwater Injection 

System:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 3

K6.02 Reactor feedwater system 3

K6.03 Radioactive drain transfer system 2

K6.04 Makeup water preparation system 3

K6.05 Main steam system 2

K6.06 Atmosphere control system 3

K6.07 Nuclear boiler instrumentation system 2

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Alternate Feedwater Injection System controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor vessel water level 4

A1.02 Reactor vessel pressure 4

A1.03 Suppression chamber pressure 3

A1.04 Suppression chamber level 3

A1.05 Demineralized water storage tank level 3

A1.06 System flow 3

A1.07 Alternate feedwater pump discharge pressure 2

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Alternate Feedwater 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)

RO SRO

A2.01 Trip of a running alternate feedwater injection pump 4 4

A2.02 Low demineralized storage tank level 3 3
NUREG-2104 3.2-30

3.2 Safety function 2: Reactor Water Inventory Control

System: SF2AFI Alternate Feedwater Injection System (continued)

K/A NO. ABILITY IMPORTANCE

A 3 Ability to monitor automatic operations of the Alternate Feedwater Injection 

System including:

(CFR: 41.7 / 45.7)

A3.01 Automatic closing of the solenoid operated vent valves when

the respective motor operated injection valve opens 3

A 4 Ability to manually operate and/or monitor the Alternate Feedwater Injection 

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

None
3.3-1 NUREG 2104

3.3 Safety Function 3: Reactor Pressure Control

System: SF3ADS Automatic Depressurization System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships between 

Automatic Depressurization System and the following systems:

(CFR: 41.2 to 41.9 /45.7 to 45.8)

K1.01 Residual heat removal system 4

K1.02 High pressure core flooder system 4

K1.03 Nuclear boiler instrumentation system 4

K1.04 High pressure nitrogen gas supply system 3

K1.05 Neutron monitoring system 3

K1.06 Engineered Safety Function logic and control system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 ADS logic 3

K2.02 ADS valve solenoids 3

K 3 Knowledge of the effect that a loss or malfunction of the Automatic 

Depressurization System will have on the 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

K3.02 Ability to rapidly depressurize the reactor 4

K 4 Knowledge of Automatic Depressurization System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Allows manual initiation of ADS logic 4

K4.02 ADS logic initiation 4

K4.03 Insures adequate nitrogen supply to ADS valves 4

K4.04 Auto inhibit of ADS with power above Average Power Range Monitor downscale 

setpoint 3

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to Automatic Depressurization System:

(CFR: 41.5 / 45.3)

K5.01 ADS logic operation 4

K5.02 Drywell/containment pressure 4

K5.03 Safety/relief valves 4

K5.04 Suppression pool 3

K5.05 Reactor pressure vessel 3
NUREG 2104 3.3-2

3.3 Safety Function 3: Reactor Pressure Control

System: SF3ADS Automatic Depressurization System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Automatic 

Depressurization System:

(CFR: 41.7 / 45.7)

K6.01 RHR pump discharge pressure 4

K6.02 High pressure core flooder pump discharge pressure 4

K6.03 Nuclear boiler instrumentation system (level indication) 4

K6.04 Nitrogen supply to ADS valves 4

K6.05 Direct current power supply system 4

K6.06 Primary containment instrumentation 3

K6.07 Average Power Range Monitor downscale signal to ADS logic 4

K6.08 Engineered Safety Function logic and control system 3

ABILITY

A 1 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

A1.02 ADS valve nitrogen supply pressure 3

A1.03 Reactor pressure 4

A1.04 Reactor water level 4

A1.05 Suppression pool temperature 4

A1.06 Average Power Range Monitor indication 3

A1.07 Suppression pool level 3

A1.08 ADS valve position indication 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 Small steam line break LOCA 4 4

A2.02 Large break LOCA 4 4

A2.03 Loss of nitrogen supply to ADS valves 3 4

A2.04 ADS failure to initiate 4 4

A2.05 Loss of DC power to ADS valves 3 4

A2.06 ADS initiation signals present 4 4

A2.07 Failure to auto inhibit 3 3
3.3-3 NUREG 2104

3.3 Safety Function 3: Reactor Pressure Control

System: SF3ADS Automatic Depressurization System (continued)

K/A NO. ABILITY IMPORTANCE

A 3 Ability to monitor automatic operations of the Automatic Depressurization 

System including:

(CFR: 41.7 / 45.7)

A3.01 ADS valve operation 4

A3.02 ADS valve tail pipe temperatures 4

A3.03 Drywell/wetwell pressure 4

A3.04 Suppression pool level 4

A3.05 Suppression pool temperature 4

A3.06 Indication and alarms 4

A3.07 Reactor pressure 4

A3.08 Reactor vessel water level 4

A 4 Ability to manually operate and/or monitor the Automatic Depressurization 

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 ADS valves (PRA) 4

A4.02 ADS logic initiation controls (PRA) 4

A4.03 ADS logic reset controls 4

A4.04 ADS inhibit controls 4
NUREG 2104 3.3-4

3.3 Safety Function 3: Reactor Pressure Control

System: SF3NBS Main and Reheat Steam System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships between 

the Main and Reheat Steam System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor pressure vessel system 3

K1.02 Main turbine 3

K1.03 Moisture separator reheaters 3

K1.04 Steam bypass and pressure control system 3

K1.05 Offgas system 3

K1.06 Condenser air removal system 3

K1.07 Steam seal/gland seal system 3

K1.08 Extraction steam system 3

K1.09 High pressure heater drains and vents 3

K1.10 Instrument air system 3

K1.11 High pressure nitrogen gas supply system 3

K1.12 Plant information and control system 3

K1.13 Process radiation monitoring system 3

K1.14 Containment system 3

K1.15 Reactor core isolation cooling system 3

K1.16 Feedwater control system 3

K1.17 Reactor trip and isolation system 4

K1.18 Leak detection and isolation system 4

K1.19 Main condenser 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Main steam isolation valve solenoids 3

K 3 Knowledge of the effect that a loss or malfunction of the Main and Reheat 

Steam System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Turbine generator 3

K3.02 Condenser 3

K3.03 Containment 3

K3.04 Decay heat removal 3

K3.05 Reactor core isolation cooling system 3

K3.06 Moisture separator reheaters 2

K3.07 Feedwater control system 4

K3.08 Safety/relief valves 4

K3.09 Reactor vessel and internals 3

K3.10 Steam jet air ejectors 3
3.3-5 NUREG 2104

3.3 Safety Function 3: Reactor Pressure Control

System: SF3NBS Main and Reheat Steam System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 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 4

K4.02 Automatic isolation and opening of drain valves 3

K4.03 Insures that steam released from a steam line break

will not bypass suppression pool 3

K4.04 Limits steam flow during a steam line rupture to 200% 3

K4.05 Steam flow measurement 3

K4.06 Over pressure control 4

K4.07 Removal of non condensable gases from reactor head area 3

K4.08 Equalization of pressure across the MSIV's before opening 3

K4.09 Moisture removal from steam lines prior to admitting steam 3

K4.10 Turbine bypass valve inhibit when MSIVs are closed 3

K 5 Knowledge of the operational implications or cause and effect relationships 

as they apply to Main and Reheat Steam System:

(CFR: 41.5 / 45.3)

K5.01 Definition and reason for steam blanketing of moisture separator

reheater 2

K5.02 Air/nitrogen operated MSIV's 3

K5.03 Decay heat removal 3

K5.04 Safety/Relief valves 4

K5.05 Head vent 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Main and Reheat 

Steam System:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 3

K6.02 Instrument air system 3

K6.03 High pressure nitrogen gas supply system 4

K6.04 Safety/relief valve safety function operability 3

K6.05 Relief valve operability 3

K6.06 Steam line integrity 4

K6.07 MSIV isolation signal 4

K6.08 Main condenser vacuum 3

K6.09 Leak detection and isolation system 4

K6.10 Plant information and control system 3

K6.11 Steam bypass and pressure control system 3
NUREG 2104 3.3-6

3.3 Safety Function 3: Reactor Pressure Control

System: SF3NBS Main and Reheat Steam System (continued)

K/A NO. ABILITY IMPORTANCE

A 1 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 4

A1.02 Main steam temperature 3

A1.03 Reheat steam pressure 2

A1.04 Reheater temperature 2

A1.05 Main steam line radiation monitors 4

A1.06 Air ejector process radiation monitor 3

A1.07 Reactor water level 4

A1.08 Reactor pressure 4

A1.09 Main steam flow 3

A1.10 Reactor power 4

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 Change in steam demand and its effect on reactor pressure and

power 4 4

A2.02 MSIV closure 4 4

A2.03 Main steam line low pressure 4 4

A2.04 Main steam line high radiation 4 4

A2.05 Main steam tunnel high temperature or differential high temperature 4 4

A2.06 Closure of one or more MSIV's at power 4 4

A2.07 Steam line break 4 4

A2.08 Leak detection and isolation system actuation 4 4

A2.09 High reactor water level 4 4

A2.10 Inadvertent initiation of HPCF (steam quality and steam flow) 3 4

A 3 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

A3.02 Opening and closing of drain valves as turbine load changes 3

A3.03 Moisture separator reheat steam supply 3

A3.04 Isolation of moisture separator reheater 3
3.3-7 NUREG 2104

3.3 Safety Function 3: Reactor Pressure Control

System: SF3NBS Main and Reheat Steam System (continued)

K/A NO. ABILITY IMPORTANCE

A 4 Ability to manually operate and/or monitor the Main and Reheat Steam 

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Main steam isolation valves 4

A4.02 Main steam line drain valves 3
NUREG 2104 3.3-8

3.3 Safety Function 3: Reactor Pressure Control

System: SF3EHC Turbine Pressure Control/Steam Bypass and Pressure Control 

System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships between 

the Turbine Pressure Control/Steam Bypass and Pressure Control System

and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor trip and isolation system 4

K1.02 AC electrical power distribution system 3

K1.03 DC power supply system 3

K1.04 Turbine building cooling water systems 3

K1.05 Recirculation flow control system 3

K1.06 Automatic power regulator system 4

K1.07 Power generation control system 3

K1.08 Plant information and control system 3

K1.09 Feedwater control system 3

K1.10 Nuclear boiler instrumentation system 3

K1.11 Main turbine 4

K1.12 Main generator 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Hydraulic power unit pumps 2

K2.02 Turbine pressure control logic 2

K2.03 Steam bypass and pressure control logic 2

K 3 Knowledge of the effect that a loss or malfunction of the Turbine Pressure 

Control/Steam Bypass and Pressure Control System will have on the 

following:

(CFR: 41.7 / 45.4)

K3.01 Reactor power 4

K3.02 Reactor pressure vessel pressure 4

K3.03 Reactor pressure vessel water level 4

K3.04 Reactor steam flow 4

K3.05 Main turbine steam flow 4

K3.06 Main turbine bypass valves 4

K3.07 Main turbine stop valves 3

K3.08 Main turbine control valves 4

K3.09 Combined intermediate valves 3

K3.10 Reactor trip and isolation system 4

K3.11 Turbine chest warming 3

K3.12 Main turbine acceleration 3

K3.13 Main turbine speed 3
3.3-9 NUREG 2104

3.3 Safety Function 3: Reactor Pressure Control

System: SF3EHC Turbine Pressure Control/Steam Bypass and Pressure Control 

System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K3.14 Main turbine inlet pressure 3

K3.15 Main turbine trip 3

K3.16 Recirculation flow control system 3

K3.17 Main generator 3

K3.18 Turbine trip testing 3

K3.19 Reactor heatup 3

K3.20 Reactor cooldown 3

K3.21 Turbine protection 3

K3.23 Turbine monitoring 2

K3.24 Automatic power regulator system 4

K3.25 Plant information and control system 3

K 4 Knowledge of Turbine Pressure Control/Steam Bypass and Pressure Control 

System design feature(s) and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Reactor pressure control 4

K4.02 Turbine speed control 3

K4.03 Turbine acceleration control 3

K4.04 Reactor scram 4

K4.05 Turbine trip 4

K4.06 Turbine chest warming 2

K4.07 Turbine trip testing 3

K4.08 Automatic hydraulic power unit pump start 3

K4.09 Reactor cooldown 3

K4.10 Turbine protection 3

K4.11 Main turbine bypass valve control 4

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to Turbine Pressure Control/Steam Bypass and Pressure Control 

System:

(CFR: 41.5 / 45.3)

K5.01 Reactor power vs. reactor pressure 4

K5.02 Turbine inlet pressure vs. reactor pressure 3

K5.03 Turbine speed measurement 2

K5.04 Reactor power 4

K5.05 Reactor pressure vessel pressure 4

K5.06 Reactor pressure vessel water level 4

K5.07 Reactor pressure vessel steam flow 4

K5.08 Main turbine steam flow 4

K5.09 Main turbine bypass valves 4

K5.10 Main turbine stop valves 4
NUREG 2104 3.3-10

3.3 Safety Function 3: Reactor Pressure Control

System: SF3EHC Turbine Pressure Control/Steam Bypass and Pressure Control 

System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K5.11 Main turbine control valves 4

K5.12 Combined intermediate valves 3

K5.13 Bearing oil 3

K5.14 Turbine chest warming 2

K5.15 Main turbine acceleration 3

K5.16 Main turbine speed 3

K5.17 Main turbine inlet pressure 3

K5.18 Main turbine trip 3

K5.19 Main condenser vacuum 3

K5.20 Reactor startup 3

K5.21 Reactor heatup 3

K5.22 Reactor cooldown 3

K5.23 Main turbine protection 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Turbine Pressure 

Control/Steam Bypass and Pressure Control System:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 3

K6.02 Turbine building cooling water system 3

K6.03 Condenser vacuum 3

K6.04 Reactor pressure vessel pressure 4

K6.05 Reactor power 4

K6.06 Main turbine steam flow 3

K6.07 Main turbine bypass valves 4

K6.08 Main turbine stop valves 3

K6.09 Main turbine control valves 3

K6.10 Combined intermediate valves 3

K6.11 Main turbine speed signal 2

K6.12 Main generator 3

K6.13 Reactor trip and isolation system 3

K6.14 Power generation control system 3

K6.15 Nuclear boiler instrumentation system 3

K6.16 Feedwater control system 3

K6.17 Automatic power regulator system 3
3.3-11 NUREG 2104

3.3 Safety Function 3: Reactor Pressure Control

System: SF3EHC Turbine Pressure Control/Steam Bypass and Pressure Control 

System (continued)

K/A NO. ABILITY IMPORTANCE

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Turbine Pressure Control/Steam Bypass and Pressure Control 

System controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor pressure vessel pressure 4

A1.02 Reactor power 4

A1.03 Reactor vessel pressure water level 4

A1.04 Main turbine inlet pressure 3

A1.05 Reactor steam flow 4

A1.06 Ma in turbine steam flow 3

A1.07 Main turbine bypass valve position 4

A1.08 Main turbine control valve position 3

A1.09 Main turbine stop valve position 3

A1.10 Combined intermediate valve position. 3

A1.11 Reactor/turbine pressure regulating system oil pressure 3

A1.12 Reactor/turbine pressure regulating system load set/reference 3

A1.13 Main turbine speed 3

A1.14 Pressure setpoint/pressure demand 3

A1.15 Maximum combined flow limit 3

A1.16 Load limit set 3

A1.17 Main condenser vacuum 3

A1.18 Reactor cooldown 3

A1.19 Main turbine vibration 3

A1.20 Main turbine eccentricity 3

A1.21 Main turbine expansion 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Turbine Pressure Control/Steam Bypass 

and Pressure 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)

RO SRO

A2.01 High reactor pressure 4 4

A2.02 Failed open/closed bypass valve(s) 4 4

A2.03 Failed open/closed main turbine control valve(s) 4 4

A2.04 Failed open/closed main turbine stop valve(s) 4 4

A2.05 Loss of main condenser vacuum 4 4

A2.06 Main turbine overspeed 3 3

A2.07 Loss of generator load 3 4

A2.08 Loss of AC electrical power 3 3
NUREG 2104 3.3-12

3.3 Safety Function 3: Reactor Pressure Control

System: SF3EHC Turbine Pressure Control/Steam Bypass and Pressure Control 

System (continued)

K/A NO. ABILITY IMPORTANCE

RO SRO

A2.09 Loss of turbine building cooling water systems 3 3

A2.10 Loss of main turbine speed feedback 2 2

A2.11 Loss of reactor pressure signal) 3 3

A2.12 Main turbine trip 4 4

A2.13 Main generator trip 4 4

A2.14 Reactor scram 4 4

A2.15 Main turbine high vibration 3 3

A2.16 Main turbine high eccentricity 3 3

A2.17 Main turbine high differential expansion 2 3

A 3 Ability to monitor automatic operations of the Turbine Pressure 

Control/Steam Bypass and Pressure Control System including:

(CFR: 41.7 / 45.7)

A3.01 Main turbine speed control 3

A3.02 Main turbine acceleration control 3

A3.03 Reactor pressure vessel pressure control 3

A3.04 Main turbine bypass valve operation 4

A3.05 Main turbine control valve operation 3

A3.06 Main turbine stop valve operation 3

A3.07 Combined intermediate valve operation 3

A3.08 Turbine trip testing 3

A3.09 Indications and alarms 3

A3.10 Main turbine startup 3

A 4 Ability to manually operate and/or monitor the Turbine Pressure 

Control/Steam Bypass and Pressure Control System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Main turbine bypass valves 4

A4.02 Turbine trip 4

A4.03 Turbine panel controls 4
3.3-13 NUREG 2104

3.3 Safety Function 3: Reactor Pressure Control

System: SF3SRV Safety/Relief Valves

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships between 

the Safety/Relief Valves and the following systems

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Main steam system 4

K1.02 SPDS 3

K1.03 Nuclear boiler instrumentation system 4

K1.04 High pressure nitrogen gas supply system 3

K1.05 Automatic depressurization system 4

K1.06 Remote shutdown system 3

K1.07 Direct current power supply system 3

K1.08 Post accident monitoring system 2

K1.09 Primary containment system 3

K1.10 Alternate feedwater system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 SRV solenoids 3

K 3 Knowledge of the effect that a loss or malfunction of the Safety/Relief Valves

will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor pressure control 4

K3.02 Reactor over pressurization 4

K3.03 Ability to rapidly depressurize the reactor 4

K 4 Knowledge of Safety/Relief Valves design feature(s) and/or interlocks which 

provide for the following:

(CFR: 41.7)

K4.01 Prevents siphoning of water into SRV discharge piping and limits

loads on subsequent actuation of SRV's 3

K4.02 Ensures even distribution of heat load to suppression pool, and 

adequate steam condensing 3

K4.03 Allows for SRV operation from more than one location 4

K4.04 Detection of valve leakage 4

K4.05 Minimum steam pressure required to keep SRV open or to open SRV 3

K4.06 Opening of the SRV from either an electrical or mechanical signal 4

K4.07 Manual opening of the SRV 4

K4.08 Methods for determining position of SRV 3
NUREG 2104 3.3-14

3.3 Safety Function 3: Reactor Pressure Control

System: SF3SRV Safety/Relief Valves (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to Safety/Relief Valves:

(CFR: 41.5 / 45.3)

K5.01 Relief function of SRV operation 3

K5.02 Safety function of SRV operation 4

K5.03 Tail pipe temperature monitoring 3

K5.04 Discharge line quencher operation 3

K5.05 Vacuum breaker operation 3

K5.06 Suppression pool 4

K5.07 Reactor pressure vessel overpressurization event 4

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Safety/Relief 

Valves:

(CFR: 41.7 / 45.7)

K6.01 Nuclear boiler instrumentation system (pressure indication) 3

K6.02 High pressure nitrogen gas supply system 3

K6.03 Direct current power supply system 3

K6.04 Discharge line vacuum breaker 3

K6.05 Remote shutdown system 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Safety/Relief Valves controls including:

(CFR: 41.5 / 45.5)

A1.01 Tail pipe temperature 3

A1.02 Nitrogen supply 3

A1.03 Reactor pressure 4

A1.04 Reactor water level 4

A1.05 Reactor power 4

A1.06 Turbine load 3

A1.07 Suppression pool water temperature 4
3.3-15 NUREG 2104

3.3 Safety Function 3: Reactor Pressure Control

System: SF3SRV Safety/Relief Valves (continued)

K/A NO. ABILITY IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Safety/Relief 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)

RO SRO

A2.01 Stuck open vacuum breakers 3 3

A2.02 Leaky SRV 3 3

A2.03 Stuck open SRV 4 4

A2.04 ADS actuation 4 4

A2.05 Low reactor pressure 3 3

A2.06 Reactor high pressure 4 4

A 3 Ability to monitor automatic operations of the Safety/Relief Valves including:

(CFR: 41.7 / 45.7)

A3.01 SRV operation after ADS actuation 4

A3.02 SRV operation on high reactor pressure 4

A3.03 Tail pipe temperatures 4

A3.04 Suppression pool temperature 4

A3.05 Reactor pressure 4

A3.06 Reactor water level 4

A3.07 Indications and alarms 4

A 4 Ability to manually operate and/or monitor the Safety/Relief Valves in the 

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 SRV's 4

3.4-1 NUREG-2104

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4NBS Main and Reheat Steam System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Main and Reheat Steam System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor pressure vessel system 3

K1.02 Main turbine 3

K1.03 Moisture separator reheaters 3

K1.04 Steam bypass and pressure control system 3

K1.05 Offgas system 3

K1.06 Condenser air removal system 3

K1.07 Steam seal/gland seal system 3

K1.08 Extraction steam system 3

K1.09 High pressure heater drains and vents 3

K1.10 Instrument air system 3

K1.11 High pressure nitrogen gas supply system 3

K1.12 Plant information and control system 3

K1.13 Process radiation monitoring system 3

K1.14 Containment system 3

K1.15 Reactor core isolation cooling system 3

K1.16 Feedwater control system 3

K1.17 Reactor trip and isolation system 4

K1.18 Leak detection and isolation system 4

K1.19 Main condenser 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Main steam isolation valve solenoids 3

K 3 Knowledge of the effect that a loss or malfunction of the Main and Reheat 

Steam System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Turbine generator 3

K3.02 Condenser 3

K3.03 Containment 3

K3.04 Decay heat removal 3

K3.05 Reactor core isolation cooling system 3

K3.06 Moisture separator reheaters 2

K3.07 Feedwater control system 4

K3.08 Safety/relief valves 4

K3.09 Reactor vessel and internals 3

K3.10 Steam jet air ejectors 3
NUREG 2104 3.4-2

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4NBS Main and Reheat Steam System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 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 4

K4.02 Automatic isolation and opening of drain valves 3

K4.03 Insures that steam released from a steam line break

will not bypass suppression pool 3

K4.04 Limits steam flow during a steam line rupture to 200% 3

K4.05 Steam flow measurement 3

K4.06 Over pressure control 4

K4.07 Removal of non condensable gases from reactor head area 3

K4.08 Equalization of pressure across the MSIV's before opening 3

K4.09 Moisture removal from steam lines prior to admitting steam 3

K4.10 Turbine bypass valve inhibit when MSIVs are closed 3

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Main and Reheat Steam System:

(CFR: 41.5 / 45.3)

K5.01 Definition and reason for steam blanketing of moisture separator

reheater 2

K5.02 Air/nitrogen operated MSIVs 3

K5.03 Decay heat removal 3

K5.04 Safety/Relief valves 4

K5.05 Head vent 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Main and Reheat 

Steam System:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 3

K6.02 Instrument air system 3

K6.03 High pressure nitrogen gas supply system 4

K6.04 Safety/relief valve safety function operability 3

K6.05 Relief valve operability 3

K6.06 Steam line integrity 4

K6.07 MSIV isolation signal 4

K6.08 Main condenser vacuum 3

K6.09 Leak detection and isolation system 4

K6.10 Plant information and control system 3

K6.11 Steam bypass and pressure control system 3
3.4-3 NUREG-2104

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4NBS Main and Reheat Steam System (continued)

K/A NO. ABILITY IMPORTANCE

A 1 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 4

A1.02 Main steam temperature 3

A1.03 Reheat steam pressure 2

A1.04 Reheater temperature 2

A1.05 Main steam line radiation monitors 4

A1.06 Air ejector process radiation monitor 3

A1.07 Reactor water level 4

A1.08 Reactor pressure 4

A1.09 Main steam flow 3

A1.10 Reactor power 4

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 Change in steam demand and its effect on reactor pressure

and power 4 4

A2.02 MSIV closure 4 4

A2.03 Main steam line low pressure 4 4

A2.04 Main steam line high radiation 4 4

A2.05 Main steam tunnel high temperature or differential high temperature 4 4

A2.06 Closure of one or more MSIV's at power 4 4

A2.07 Steam line break 4 4

A2.08 Leak detection and isolation system actuation 4 4

A2.09 High reactor water level 4 4

A2.10 Inadvertent initiation of HPCF/RCIC (steam quality and steam flow) 3 4

A 3 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

A3.02 Opening and closing of drain valves as turbine load changes 3

A3.03 Moisture separator reheat steam supply 3

A3.04 Isolation of moisture separator reheater 3
NUREG 2104 3.4-4

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4NBS Main and Reheat Steam System (continued)

K/A NO. ABILITY IMPORTANCE

A 4 Ability to manually operate and/or monitor the Main and Reheat Steam

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Main steam isolation valves 4

A4.02 Main steam line drain valves 3
3.4-5 NUREG-2104

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4MT Main Turbine Generator and Auxiliary Systems

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Main Turbine Generator and Auxiliary Systems and the 

following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 AC electrical power distribution system 3

K1.02 Condensate system 3

K1.03 Main steam system 3

K1.04 Reactor trip and isolation system 4

K1.05 Extraction steam system 3

K1.06 Turbine building cooling water system 3

K1.07 Instrument air system 3

K1.08 Steam bypass and pressure control system 3

K1.09 DC power supply system 3

K1.10 Generator cooling system 3

K1.11 Hydrogen gas cooling system 3

K1.12 Generator sealing oil system 3

K1.13 Turbine lubricating oil system 3

K1.14 Plant information and control system 3

K1.15 Turbine control system 3

K1.16 Turbine gland steam system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Generator cooling pumps 2

K2.02 Turbine lube oil pumps 2

K2.03 Generator sealing oil pumps 2

K2.04 Turbine supervisory instrumentation 2

K 3 Knowledge of the effect that a loss or malfunction of the Main Turbine 

Generator and Auxiliary Systems will have on the following:

(CFR: 41.7 / 45.4)

K3.01 AC electrical power distribution system 4

K3.02 Reactor pressure 4

K3.03 Reactor power 4

K3.04 Feedwater system (feedwater heaters) 3

K3.05 Condensate system 3

K3.06 Reactor trip and isolation system 4

K3.07 Steam bypass and pressure control system 4

K3.08 Turbine control system 4
NUREG 2104 3.4-6

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4MT Main Turbine Generator and Auxiliary Systems (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 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

K4.02 Generator cooling 2

K4.03 Sealing to prevent hydrogen leakage 3

K4.04 Hydrogen cooling 2

K4.05 Turbine protection 3

K4.06 Generator protection 3

K4.07 Generator voltage regulation 3

K4.08 Moisture removal from turbine steam 2

K4.09 Turbine control 3

K4.10 Extraction steam 3

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Main Turbine Generator and Auxiliary

Systems:

(CFR: 41.5 / 45.3)

K5.01 Turbine operation and limitations 3

K5.02 Turbine speed measurement 2

K5.03 Relief valve operation 2

K5.04 Turbine shaft sealing 3

K5.05 Generator operations and limitations 3

K5.06 Generator cooling 2

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Main Turbine 

Generator and Auxiliary Systems:

(CFR: 41.7 / 45.7)

K6.01 Gland seal 3

K6.02 Steam bypass and pressure control system 4

K6.03 Hydrogen seal oil 3

K6.04 Hydrogen gas cooling system 3

K6.05 Generator cooling water system 3

K6.06 Electrical distribution 3

K6.07 Extraction steam 2

K6.08 Main steam system 3

K6.09 Voltage regulation 2

K6.10 Turbine lube oil system 3
3.4-7 NUREG-2104

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4MT Main Turbine Generator and Auxiliary Systems (continued)

K/A NO. ABILITY IMPORTANCE

K6.11 Plant information and control system 3

K6.12 Turbine control system 3

K6.13 Moisture separator reheater 2

K6.14 Condenser vacuum 3

A 1 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 3

A1.02 Turbine speed 3

A1.03 Turbine valve position 3

A1.04 Steam flow 3

A1.05 Reactor pressure 4

A1.06 Condenser vacuum 3

A1.07 First stage turbine pressure 3

A1.08 Generator output voltage/reactive load 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 Turbine trip 4 4

A2.02 Loss of lube oil 3 4

A2.03 Loss of condenser vacuum 4 4

A2.04 Reactor scram 4 4

A2.05 Generator trip 4 4

A2.06 Loss of extraction steam 3 3

A2.07 Steam bypass and pressure control system 4 4

A2.08 Turbine rotor bow 2 3

A2.09 Turbine vibration 3 3

A2.10 Turbine pressure control system 3 3

A 3 Ability to monitor automatic operations of the Main Turbine Generator and 

Auxiliary Systems including:

(CFR: 41.7 / 45.7)

A3.01 Turbine trip 4

A3.02 Turbine roll to rated speed 3
NUREG 2104 3.4-8

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4MT Main Turbine Generator and Auxiliary Systems (continued)

K/A NO. ABILITY IMPORTANCE

A3.03 Generator megawatt output 3

A3.04 Turbine speed 3

A3.05 Control valve operation 3

A3.06 Turbine lube oil pressure 3

A3.07 Hydrogen seal oil pressure 3

A3.08 Hydrogen gas pressure 3

A3.09 Generator output voltage 3

A3.10 Stator cooling 3

A3.11 Generator lockout 2

A3.12 Turbine lube oil temperature 2

A 4 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 3

A4.02 Generator controls 3

A4.03 Stator water cooling pumps 3

A4.04 Hydrogen seal oil pumps 3

A4.05 Turbine controls 3
3.4-9 NUREG-2104

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4RCIC Reactor Core Isolation Cooling System 

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Reactor Core Isolation Cooling System and the following 

systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Makeup water condensate system 4

K1.02 Main steam system 4

K1.03 Residual heat removal system 3

K1.04 Instrument air system 2

K1.05 Leak detection and isolation system 3

K1.06 Engineered Safety Function logic and control system 3

K1.07 Feedwater system 4

K1.08 Suppression pool suction strainer 2

K1.09 AC electrical power distribution system 2

K1.10 DC power supply system 3

K1.11 High pressure core flooder system 2

K1.12 Radioactive drain transfer system 2

K1.13 Heating ventilation and air conditioning system 2

K1.14 Post accident monitoring system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 RCIC steam admission valves 3

K2.02 Condensate storage tank suction valve 3

K2.03 Suppression pool suction valve 3

K2.04 RCIC test return to suppression pool valves 2

K2.05 RCIC initiation signals (logic) 3

K2.06 Reactor core isolation cooling drain pump 2

K 3 Knowledge of the effect that a loss or malfunction of the Reactor Core 

Isolation Cooling System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level 4

K3.02 Reactor vessel pressure 4

K3.03 Decay heat removal 4

K3.04 Adequate core cooling 4
NUREG 2104 3.4-10

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4RCIC Reactor Core Isolation Cooling System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 Knowledge of Reactor Core Isolation Cooling System design feature(s) 

and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Prevent water hammer 3

K4.02 Prevent overfilling reactor vessel 3

K4.03 Override of high reactor water level interlock 3

K4.04 Prevents pump over heating 3

K4.05 Prevents turbine damage 3

K4.06 Manual initiation 4

K4.07 Alternate supplies of water 4

K 5 Knowledge of the operational implications or cause and effect 

relationships as they apply to Reactor Core Isolation Cooling System:

(CFR: 41.5 / 45.3)

K5.01 Assist core cooling 4

K5.02 Suppression pool 4

K5.03 Main condenser 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Reactor Core 

Isolation Cooling System:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 3

K6.02 Instrument air system 2

K6.03 Suppression pool water supply 4

K6.04 Makeup water condensate system 4

K6.05 Main steam system 4

K6.06 Suppression pool suction strainer 3

K6.07 DC power supply system 3

K6.08 Engineered Safety Function logic and control system 3

K6.09 High pressure core flooder system 2

K6.10 Radioactive drain transfer system 2

K6.11 Heating ventilation and air conditioning system 2

K6.12 Feedwater system 3
3.4-11 NUREG-2104

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4RCIC Reactor Core Isolation Cooling System (continued)

K/A NO. ABILITY IMPORTANCE

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

operating the Reactor Core Isolation Cooling System controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor core isolation cooling flow 4

A1.02 Reactor core isolation cooling pressure 3

A1.03 Reactor water level 4

A1.04 Reactor pressure 4

A1.05 Reactor core isolation cooling turbine speed 4

A1.06 Condensate storage tank level 3

A1.07 Suppression pool level 3

A1.08 Suppression pool temperature 4

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Reactor Core Isolation Cooling 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)

RO SRO

A2.01 System initiation signal 4 4

A2.02 RCIC turbine trips 4 4

A2.03 Injection valve closure 3 3

A2.04 AC power loss 2 2

A2.05 DC power loss 3 3

A2.06 Loss of instrument air system 2 2

A2.07 Loss of RCIC drain pump 2 2

A2.08 Turbine control system failures 3 3

A2.09 Inadequate system flow 3 3

A2.10 Loss of room cooling 3 3

A2.11 Steam line break 4 4

A2.12 Low condensate storage tank level 4 3

A2.13 High suppression pool level 3 3

A2.14 Low suppression pool level 3 3

A2.15 High suppression pool temperature 4 4

A2.16 High drain tank level 2 2

A 3 Ability to monitor automatic operations of the Reactor Core Isolation 

Cooling System including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation 4

A3.02 Turbine startup 4
NUREG 2104 3.4-12

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4RCIC Reactor Core Isolation Cooling System (continued)

K/A NO. ABILITY IMPORTANCE

A3.03 System pressure 4

A3.04 System flow 4

A3.05 Reactor water level 4

A3.06 Indications and alarms 4

A 4 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Reactor core isolation cooling turbine speed 4

A4.02 Turbine trip throttle valve reset 4

A4.03 System valves 3
3.4-13 NUREG-2104

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4RRS Reactor Recirculation System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Reactor Recirculation System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor building cooling water system 3

K1.02 AC electrical power distribution system 3

K1.03 Control rod drive system 3

K1.04 Recirculation flow control system 4

K1.05 Plant information and control system 3

K1.06 Makeup water purified system 2

K1.07 Reactor pressure vessel system 3

K1.08 Radioactive drain transfer system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Reactor internal pumps 3

K2.02 Recirculation system MG sets 3

K2.03 Motor generator set oil pumps 2

K 3 Knowledge of the effect that a loss or malfunction of the Reactor 

Recirculation System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Core flow 4

K3.02 Load following capabilities 3

K3.03 Reactor power 4

K3.04 Reactor water level 4

K3.05 Reactor recirculation system motor generator sets 3

K3.06 Vessel bottom head drain temperature 3

K3.07 Primary containment integrity 3
NUREG 2104 3.4-14

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4RRS Reactor Recirculation System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 Knowledge of Reactor Recirculation System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Adequate reactor internal pump NPSH 3

K4.02 Reactor internal pump motor cooling 3

K4.03 Controlled purge flow 3

K4.04 Automatic voltage/frequency regulation 3

K4.05 Motor generator set trips 3

K4.06 Pump minimum flow limit 3

K4.07 Pump start permissives 3

K4.08 Minimization of reactor vessel bottom head temperature gradients 3

K4.09 End of cycle recirculation pump trip 4

K4.10 Anticipated Transient without scram - Recirc pump trip 4

K4.11 Selected control rods run in circuitry 4

K4.12 Reactor internal pump runback 4

K4.13 Reactor internal pump startup 3

K4.14 Automatic MG set start sequencing 3

K4.15 Core flow rapid reduction logic 3

K 5 Knowledge of the operational implications or cause and effect 

relationships as they apply to the Reactor Recirculation System:

(CFR: 41.5 / 45.3)

K5.01 Reactor internal pump vibration characteristics 2

K5.02 Restart of reactor internal pumps while operating at power 3

K5.03 Core flow 4

K5.04 Reactor power 4

K5.05 Reactor moderator temperature 3

K5.06 Reactor pressure 3

K5.07 Recirculation flow control system motor-generator sets 4

K5.08 Nuclear boiler instrumentation (reactor water level/pressure/core

plate d/p) 3

K5.09 Vessel bottom head drain temperature 3

K5.10 Residual heat removal shutdown cooling mode 3

K5.11 Reactor water level 4

K5.12 Anticipated transient without scram circuitry 4

K5.13 End-of-cycle recirculation pump trip circuitry 4

K5.14 Selected control rods run in circuitry 4

K5.15 Recirculation motor inflatable shaft seal subsystem 2

K5.16 Recirculation motor cooling subsystem 3

K5.17 Reactor internal pump adjustable speed drives 3
3.4-15 NUREG-2104

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4RRS Reactor Recirculation System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Reactor 

Recirculation System:

(CFR: 41.7 / 45.7)

K6.01 Reactor building cooling water systems 3

K6.02 AC electrical power distribution system 3

K6.03 Control rod drive system 3

K6.04 Recirculation system motor-generator sets 3

K6.05 Low reactor water level 3

K6.06 Recirculation motor inflatable shaft seal subsystem 3

K6.07 Makeup water purified system 2

K6.08 Reactor internal pump motor cooling subsystem 3

K6.09 Turbine trip/load rejection 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Reactor Recirculation System controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor internal pump flow 4

A1.02 Core flow 4

A1.03 Reactor water level 3

A1.04 Reactor power 4

A1.05 Reactor internal pump motor amps 3

A1.06 Reactor internal pump speed 3

A1.07 Recirculation cooling water flow 3

A1.08 Vessel bottom head drain temperature 3

A1.09 Reactor internal pump differential pressure 3

A1.10 Reactor internal pump motor temperature 2

A1.11 Reactor internal pump MG set temperatures 2

A1.12 Reactor internal pump MG drive motor amps 2

A1.13 Reactor internal pump MG set generator current, power, voltage 2

A1.14 Reactor internal pump motor purge flow 3

A1.15 Reactor internal pump vibration 2

A1.16 Core differential pressure 3
NUREG 2104 3.4-16

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4RRS Reactor Recirculation System (continued)

K/A NO. ABILITY IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Reactor 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)

RO SRO

A2.01 Recirculation system leak 4 4

A2.02 Single reactor internal pump trip 4 4

A2.03 Multiple reactor internal pump trip 4 4

A2.04 Inadvertent recirculation flow increase 4 4

A2.05 Inadvertent recirculation flow decrease 4 4

A2.06 Reactor internal pump speed mismatch 3 3

A2.07 Reactor internal pump flow mismatch 3 3

A2.08 Low reactor water level 4 4

A2.09 Loss of reactor feedwater 4 4

A2.10 High reactor pressure (ATWS circuitry initiation) 4 4

A2.11 End of cycle recirculation pump trip circuitry initiation 4 4

A2.12 Selected control rods run in circuitry actuation 4 4

A2.13 Loss of motor cooling 3 3

A2.14 Loss of AC power 3 3

A2.15 Loss of reactor building cooling water 3 3

A2.16 Incomplete start sequence 3 3

A2.17 Loss of reactor internal pump purge flow 3 3

A2.18 Reactor internal pump speed runback 3 3

A2.19 Increase in reactor internal pump vibration 2 2

A 3 Ability to monitor automatic operations of the Reactor Recirculation 

System including:

(CFR: 41.7 / 45.7)

A3.01 Pump/MG set start sequence 3

A3.02 System flow 3

A3.03 Indications and alarms 3

A3.04 Pump speed 3

A3.05 Reactor internal pump trips 3

A3.06 Reactor internal pump runbacks 3

A3.07 Recirculation system motor generator set trip 3

A 4 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Reactor internal pumps 4

A4.02 System flow 4

A4.03 Core flow 4
3.4-17 NUREG-2104

3.4 Safety Function 4: Heat Removal from Reactor Core

System SF4RHRSDC Residual Heat Removal System: Shutdown Cooling Mode

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Residual Heat Removal System: Shutdown Cooling Mode and 

the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Fuel pool cooling assist 3

K1.02 Reactor building cooling water system 3

K1.03 AC electrical power distribution system 3

K1.04 Reactor water cleanup system 2

K1.05 Radioactive drain transfer system 1

K1.06 Reactor pressure vessel system 3

K1.07 Remote shutdown system 3

K1.08 Sampling system 2

K1.09 Feedwater system 3

K1.10 High pressure nitrogen gas supply system 2

K1.11 Instrument air system 2

K1.12 Plant information and control system 3

K1.13 Leak detection and isolation system 3

K1.14 Engineered Safety Function logic and control system 3

K1.15 Makeup water condensate system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Residual heat removal pumps 3

K2.02 RHR shutdown cooling suction valves 3

K 3 Knowledge of the effect that a loss or malfunction of the Residual Heat 

Removal System: Shutdown Cooling Mode will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor pressure 3

K3.02 Reactor pressure vessel water level 3

K3.03 Reactor pressure vessel temperatures (moderator, vessel, flange) 4

K 4 Knowledge of Residual Heat Removal System: Shutdown Cooling Mode

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

(CFR: 41.7)

K4.01 High RHR equipment area temperature isolation 3

K4.02 High reactor pressure vessel isolation 4

K4.03 Low reactor water level isolation 4

K4.04 Adequate pump NPSH 3
NUREG 2104 3.4-18

3.4 Safety Function 4: Heat Removal from Reactor Core

System SF4RHRSDC Residual Heat Removal System: Shutdown Cooling Mode

(continued)

K/A NO. KNOWLEDGE IMPORTANCE

K4.05 Reactor pressure vessel cooldown rate 4

K4.06 RHR pump motor cooling 2

K4.07 Pump minimum flow 3

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to Residual Heat Removal System: Shutdown Cooling Mode:

(CFR: 41.5 / 45.3)

K5.01 Reactor pressure vessel pressure 4

K5.02 Reactor water level 4

K5.03 Fuel pool cooling assist 3

K5.04 Low pressure flooder injection 4

K5.05 Reactor pressure vessel temperatures (moderator, vessel, flange) 4

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Residual Heat 

Removal System: Shutdown Cooling Mode:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 3

K6.02 Low reactor water level 4

K6.03 High reactor pressure 4

K6.04 Reactor building cooling water system 3

K6.05 High pressure nitrogen gas supply system 2

K6.06 Reactor water cleanup system 3

K6.07 Reactor internal pump failure 2

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Residual Heat Removal System: Shutdown Cooling Mode

controls including:

(CFR: 41.5 / 45.5)

A1.01 Heat exchanger cooling flow 3

A1.02 SDC/RHR pump flow 3

A1.03 SDC/RHR pump suction pressure 3

A1.04 Reactor water level 3

A1.05 Reactor pressure vessel temperatures (moderator, vessel, flange) 4

A1.06 RHR pump motor amps 2

A1.07 Heat exchanger temperatures 3

A1.08 SDC/RHR pump/system discharge pressure 3

A1.09 Throttle valve position 3
3.4-19 NUREG-2104

3.4 Safety Function 4: Heat Removal from Reactor Core

System: SF4RHRSDC Residual Heat Removal System: Shutdown Cooling Mode

(continued)

K/A NO. ABILITY IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on Residual Heat Removal System: 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)

RO SRO

A2.01 Low shutdown cooling suction pressure 3 3

A2.02 Electrical power distribution failure 3 3

A2.03 System isolation 4 4

A2.04 SDC/RHR pump trips 3 4

A2.05 Loss of RHR pump motor cooling 3 3

A2.06 Loss of heat exchanger cooling 3 4

A2.07 Reactor low water level 4 4

A2.08 Valve operation 3 3

A2.09 Reactor internal pump trips 3 3

A2.10 Inadequate system flow 3 3

A 3 Ability to monitor automatic operations of the Residual Heat Removal 

System: Shutdown Cooling Mode including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation 3

A3.02 RHR pump trips 3

A3.03 Control room indications and alarms 3

A3.04 Shutdown cooling initiation sequence 3

A 4 Ability to manually operate and/or monitor the Residual Heat Removal 

System: Shutdown Cooling Mode in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 SDC/RHR pumps 4

A4.02 SDC/RHR suction valves 4

A4.03 SDC/RHR discharge valves 4

A4.04 Heat exchanger cooling water valves 3

A4.05 Minimum flow valves 3

3.5-1 NUREG-2104

3.5 Safety Function 5: Containment Integrity

System: SF5PCS Primary Containment System and Auxiliaries

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Primary Containment System and Auxiliaries and the following 

systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Atmosphere control system 3

K1.02 Low and high conductivity waste system 3

K1.03 Residual heat removal system 4

K1.04 Suppression pool cleanup system 2

K1.05 Safety/relief valves 4

K1.06 Instrument air system 3

K1.07 Post accident sampling system 3

K1.08 High pressure core flooder system 4

K1.09 Reactor core isolation cooling system 4

K1.10 Containment and drywell atmosphere monitoring system 3

K1.11 Reactor building heating, ventilation, and air conditioning 3

K1.12 Standby gas treatment system 3

K1.13 Drywell cooling system 4

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Containment atmosphere monitoring system 2

K2.02 Drywell cooling fans 2

K 3 Knowledge of the effect that a loss or malfunction of the Primary 

Containment System and Auxiliaries will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Secondary containment 4

K3.02 Drywell/wetwell temperature 3

K3.03 Drywell/wetwell pressure 3

K3.04 Drywell/wetwell hydrogen concentration 3

K3.05 Drywell/wetwell oxygen concentration 3

K3.06 Differential pressure between secondary and primary containment 4

K3.07 Differential pressure between wetwell and drywell 3

K3.08 Pneumatically operated valves internal to drywell 3

K3.09 Reactor pressure vessel instrumentation 3

K3.10 Offsite radioactivity release 3
NUREG 2104 3.5-2

3.5 Safety Function 5: Containment Integrity

System: SF5PCS Primary Containment System and Auxiliaries (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 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 4

K4.02 Contains fission products after a LOCA 4

K4.03 Containment isolation 4

K4.04 Maintains proper wetwell to drywell differential pressure 3

K4.05 Maintains proper secondary containment to drywell differential

pressure 3

K4.06 Prevents localized heating of suppression pool (SRV steam

quenchers) 3

K4.07 Containment overpressure protection 4

K4.08 Drywell vent pipes (vertical and horizontal) 4

K4.09 Lower drywell flooder 4

K4.10 Quenching of ex-vessel core debris 3

K4.11 Containment inerted by nitrogen 3

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to Primary Containment System and Auxiliaries:

(CFR: 41.5 / 45.3)

K5.01 Vacuum breaker/relief operation 3

K5.02 Hydrogen production mechanisms 3

K5.03 Hydrogen combustibility versus hydrogen concentration and

oxygen concentration 3

K5.04 Hydrogen concentration measurement 3

K5.05 Oxygen concentration measurement 3

K5.06 Differential pressure measurement 3

K5.07 Containment isolation/integrity 4

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Primary 

Containment System and Auxiliaries:

(CFR: 41.7 / 45.7)

K6.01 Drywell cooling 4

K6.02 Suppression pool makeup 4

K6.03 Containment atmospheric control 3

K6.04 Drywell vacuum relief system 4

K6.05 AC electrical distribution 3

K6.06 DC electrical distribution 3
3.5-3 NUREG-2104

3.5 Safety Function 5: Containment Integrity

System: SF5PCS Primary Containment System and Auxiliaries (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K6.07 Atmospheric pressure control system 3

K6.08 Residual heat removal system 4

K6.09 Standby gas treatment system 3

K6.10 Instrument air system 3

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 4

A1.02 Drywell pressure 4

A1.03 Wetwell air space temperature 4

A1.04 Wetwell pressure 4

A1.05 Drywell/wetwell oxygen concentration 3

A1.06 Drywell to wetwell differential pressure 3

A1.07 Suppression pool level 4

A1.08 Suppression pool temperature 4

A1.09 Drywell leak detection system 4

A1.10 Reactor building to wetwell differential pressure 3

A1.11 Inerting flow to both the drywell and wetwell 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 Loss of coolant accident 4 4

A2.02 Steam bypass of suppression pool 4 4

A2.03 Safety/relief valve leaking or stuck open 4 4

A2.04 High drywell/wetwell hydrogen concentration 4 4

A2.05 High drywell/wetwell oxygen concentration 4 4

A2.06 High drywell pressure 4 4

A2.07 Vacuum breaker malfunction 4 4

A2.08 High drywell temperature 4 4

A2.09 Abnormal suppression pool level 4 4

A2.10 High suppression pool temperature 4 4
NUREG 2104 3.5-4

3.5 Safety Function 5: Containment Integrity

System: SF5PCS Primary Containment System and Auxiliaries (continued)

K/A NO. ABILITY IMPORTANCE

A 3 Ability to monitor automatic operations of the Primary Containment System

and Auxiliaries including:

(CFR: 41.7 / 45.7)

A3.01 Vacuum breaker/relief valve operation 3

A3.02 System indications and alarms 3

A3.03 Drywell or wetwell response during LOCA 4

A3.04 Drywell pressure 4

A3.05 Drywell/wetwell differential pressure 3

A 4 Ability to manually operate and/or monitor the Primary Containment 

System and Auxiliaries in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Containment overpressure protection system 3

A4.02 Drywell/wetwell nitrogen makeup and purge 3

A4.03 Drywell pneumatics 3

A4.04 Drywell coolers 4
3.5-5 NUREG-2104

3.5 Safety Function 5: Containment Integrity

System: SF5LDIS Leak Detection and Isolation System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Leak Detection and Isolation System and the following 

systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Main steam system 4

K1.02 Reactor water cleanup system 3

K1.03 Reactor building heating, ventilation, and air conditioning system 3

K1.04 Reactor core isolation cooling 4

K1.05 Residual heat removal system 4

K1.06 Atmosphere control system 3

K1.07 Sampling system 3

K1.08 Standby gas treatment system 3

K1.09 Automated traversing in-core probe system 3

K1.10 Radioactive drain transfer system 3

K1.11 Safety parameter display system 2

K1.12 Reactor building cooling water system 3

K1.13 Standby liquid control system 3

K1.14 Reactor trip and isolation system 3

K1.15 Process radiation monitoring system 3

K1.16 Fuel pool cooling and cleanup system 3

K1.17 Suppression pool clean-up system 2

K1.18 Heating, ventilation, and air conditioning normal cooling

water system 2

K1.19 Feedwater system 2

K1.20 Engineered Safety Function logic and control system 3

K1.21 Plant information and control system 3

K1.22 Instrumentation and control power supply system 3

K1.23 Reactor pressure vessel instrumentation system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Logic power supplies 2

K 3 Knowledge of the effect that a loss or malfunction of the Leak Detection 

and Isolation System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level 4

K3.02 Fuel cladding temperature 4

K3.03 Off-site radioactivity release 4

K3.04 Reactor building radiation level 3

K3.05 Drainage sump levels 3

K3.06 Turbine building radiation 3
NUREG 2104 3.5-6

3.5 Safety Function 5: Containment Integrity

System: SF5LDIS Leak Detection and Isolation System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K3.07 Reactor pressure 4

K3.08 Reactor vessel temperature 3

K3.09 Main steam system 3

K3.10 Reactor water cleanup system 3

K3.11 Reactor building heating, ventilation, and air conditioning system 3

K3.12 Reactor core isolation cooling 3

K3.13 Residual heat removal system 3

K3.14 Atmosphere control system 3

K3.15 Containment atmosphere sampling 3

K3.16 Standby gas treatment system 3

K3.17 Automated traversing in-core probe system 3

K3.18 Radioactive drain transfer system 3

K3.19 Reactor building cooling water systems 2

K3.20 Primary containment integrity 3

K3.21 Secondary containment integrity 3

K3.22 Process radiation monitoring system 2

K3.23 Fuel pool cooling and cleanup system 2

K3.24 Condensate system 3

K 4 Knowledge of Leak Detection and Isolation System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Redundancy 3

K4.02 Testability 3

K4.03 Manual isolation capability 4

K4.04 Single failures will not impair the function ability of the system 3

K4.05 Once initiated, system reset requires deliberate operator action 3

K4.06 Physical separation of system components (to prevent localized

environmental factors, electrical faults, and physical events from

impairing system response) 3

K4.07 Manual defeating of selected isolations during specified emergency

conditions 3

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Leak Detection and Isolation System:

(CFR: 41.5 / 45.3)

K5.01 Primary containment integrity 3

K5.02 Secondary containment integrity 3
3.5-7 NUREG-2104

3.5 Safety Function 5: Containment Integrity

System: SF5LDIS Leak Detection and Isolation System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the LEAK 

DETECTION AND ISOLATION System:

(CFR: 41.7 / 45.7)

K6.01 Instrumentation and control power supply system 3

K6.02 Process radiation monitoring system 3

K6.03 Reactor pressure vessel instrumentation 3

K6.04 Containment instrumentation 3

K6.05 Various process instrumentation 3

K6.06 Reactor trip and isolation system 4

K6.07 Engineered Safety Function logic and control system 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the LEAK DETECTION AND ISOLATION System controls 

including:

(CFR: 41.5 / 45.5)

A1.01 System status indications and alarms 4

A1.02 Valve closures 4

A1.03 Safety parameter display system 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the LEAK DETECTION AND ISOLATION 

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)

RO SRO

A2.01 Electrical power failures 3 4

A2.02 System logic failures 3 3

A2.03 Process radiation monitoring system failures 3 3

A2.04 Reactor pressure vessel instrumentation failures 3 4

A2.05 Containment instrumentation failures 3 3

A2.06 Various process instrumentation failures 3 3

A2.07 Surveillance testing 3 3

A2.08 System initiation 4 4

A2.09 Loss of coolant accidents 4 4

A2.10 Standby liquid control system initiation 4 4
NUREG 2104 3.5-8

3.5 Safety Function 5: Containment Integrity

System: SF5LDIS Leak Detection and Isolation System (continued)

K/A NO. ABILITY IMPORTANCE

A 3 Ability to monitor automatic operations of the LEAK DETECTION AND 

ISOLATION System including:

(CFR: 41.7 / 45.7)

A3.01 System status indications and alarms 3

A3.02 Valve closures 4

A3.03 Safety parameter display system 3

A3.04 Standby gas treatment system initiation 3

A3.05 Reactor building heating, ventilation, and air conditioning isolation 3

A3.06 Condensate pump trip (feedwater line break) 3

A3.07 Control room habitability area Heating, Ventilation, and Air

Conditioning initiation 3

A 4 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Valve closures 4

A4.02 Manually initiate isolations 4

A4.03 Reset isolations 4

A4.04 Safety parameter display system 3
3.5-9 NUREG-2104

3.5 Safety Function 5: Containment Integrity

System: SF5RPV Reactor Vessel Internals

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Reactor Vessel Internals and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Main steam system 3

K1.02 Reactor recirculation system 3

K1.03 Feedwater system 3

K1.04 Residual heat removal system 3

K1.05 High pressure core flooder system 3

K1.06 Reactor core isolation cooling system 3

K1.07 Control rod drive system 3

K1.08 Fine motion control rod drive mechanism 3

K1.09 Standby liquid control system 3

K1.10 Reactor water cleanup system 3

K1.11 Automatic depressurization system 3

K1.12 Loose parts monitoring system 2

K1.13 Automated Traversing In-core Probe system 3

K1.14 Neutron monitoring system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

None

K 3 Knowledge of the effect that a loss or malfunction of the Reactor Vessel 

Internals will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level 3

K3.02 Reactor pressure 3

K3.03 Reactor power 3

K3.04 Plant radiation levels 3

K3.05 Off-site radioactive release 3

K3.06 Leak detection and isolation system 3

K3.07 Nuclear boiler instrumentation 3

K 4 Knowledge of Reactor Vessel Internals design feature(s) and/or interlocks 

which provide for the following:

(CFR: 41.7)

K4.01 Separation of fluid flow paths within the vessel 3

K4.02 Core orificing 3

K4.03 Moisture removal from generated steam 3

K4.04 Natural circulation 4
NUREG 2104 3.5-10

3.5 Safety Function 5: Containment Integrity

System: SF5RPV Reactor Vessel Internals (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Reactor Vessel Internals:

(CFR: 41.5 / 45.3)

None

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Reactor Vessel 

Internals:

(CFR: 41.7 / 45.7)

K6.01 Control rod drive system 3

K6.02 Fine motion control rod drive mechanism 3

K6.03 Reactor recirculation system 3

K6.04 Feedwater system 3

K6.05 Standby Liquid Control system 3

K6.06 Safety/relief valves 3

K6.07 Reactor water cleanup system 3

K6.08 Nuclear boiler instrumentation 3

K6.09 High pressure core flooder system 3

K6.10 Residual heat removal system 3

K6.11 Reactor core isolation cooling system 3

K6.12 Automatic depressurization system 3

K6.13 Loose parts monitoring 2

K6.14 Automated traversing in-core probe system 3

K6.15 Neutron monitoring system 3

K6.16 Main steam system 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Reactor Vessel Internals controls including:

(CFR:41.5/45.5)

None
3.5-11 NUREG-2104

3.5 Safety Function 5: Containment Integrity

System: SF5RPV Reactor Vessel Internals (continued)

K/A NO. ABILITY IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 Loss of coolant accident 4 4

A2.02 Overpressurization transient 4 4

A2.03 Control rod drop accident 4 4

A2.04 Excessive heatup/cooldown rate 4 4

A2.05 Exceeding thermal limits 4 4

A2.06 Exceeding safety limits 4 4

A 3 Ability to monitor automatic operations of the Reactor Vessel Internals

including:

(CFR: 41.7 / 45.7)

None

A 4 Ability to manually operate and/or monitor the Reactor Vessel Internals in 

the control room:

(CFR: 41.7 / 45.5 to 45.8)

None
NUREG 2104 3.5-12

3.5 Safety Function 5: Containment Integrity

System: SF5RHRSPC Residual Heat Removal System: Suppression Pool Cooling

Mode

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Residual Heat Removal Systems: Suppression Pool Cooling 

Mode and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 AC electrical power distribution system 4

K1.02 Reactor building cooling water system 3

K1.03 Suppression pool temperature monitoring system 4

K1.04 Remote shutdown system 3

K1.05 Engineered Safety Function logic and control system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 RHR heat exchanger inlet and outlet valves 3

K2.02 RHR heat exchanger bypass valve 2

K2.03 Residual heat removal system pumps 3

K2.04 Valve control logic 2

K 3 Knowledge of the effect that a loss or malfunction of the Residual Heat 

Removal System: Suppression Pool Cooling Mode will have on the 

following:

(CFR: 41.7 / 45.4)

K3.01 Suppression pool temperature control 4

K3.02 Residual heat removal system drain to radwaste 3

K 4 Knowledge of Residual Heat Removal System: Suppression Pool Cooling 

Mode design feature(s) and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Redundancy 4

K4.02 Unintentional reduction in vessel injection flow during accident

conditions 4

K4.03 Pump minimum flow protection 3

K4.04 Pump motor cooling 3

K4.05 Prevention of water hammer 3

K4.06 Adequate pump net positive suction head 3

K4.07 Heat exchanger cooling 3

K4.08 Prevention of leakage to the environment through system heat

exchanger 3

K4.09 Automatic initiation of suppression pool cooling 4
3.5-13 NUREG-2104

3.5 Safety Function 5: Containment Integrity

System: SF5RHRSPC Residual Heat Removal System: Suppression Pool Cooling 

Mode (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to Residual Heat Removal System: Suppression Pool Cooling 

Mode:

(CFR: 41.5 / 45.3)

K5.01 Suppression pool 4

K5.02 Keep fill 3

K5.03 Residual heat removal system piping 4

K5.04 Residual heat removal system pumps 4

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Residual Heat 

Removal System: Suppression Pool Cooling Mode:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 3

K6.02 Keep fill 3

K6.03 Suppression pool 4

K6.04 ECCS room cooling 3

K6.06 Reactor pressure vessel instrumentation 3

K6.07 Reactor building cooling water system 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Residual Heat Removal System: Suppression Pool Cooling 

Mode controls including:

(CFR: 41.5 / 45.5)

A1.01 Suppression pool temperature 4

A1.02 System flow 4

A1.03 System pressure 3

A1.04 Suppression pool level 3

A1.05 Motor amps 2

A1.06 Emergency generator loading 3

A1.07 Wetwell air temperature 3
NUREG 2104 3.5-14

3.5 Safety Function 5: Containment Integrity

System: SF5RHRSPC Residual Heat Removal System: Suppression Pool Cooling 

Mode (continued)

K/A NO. ABILITY IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Residual Heat Removal System: 

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)

RO SRO

A2.01 Inadequate net positive suction head 3 3

A2.02 Pumps trips 3 3

A2.03 Valve closures 3 3

A2.04 Valve openings 3 3

A2.05 AC electrical power distribution system failure 3 4

A2.06 Pump seal failure 3 3

A2.07 Inadequate room cooling 3 3

A2.08 Reactor pressure vessel instrument failures 3 3

A2.09 Motor operated valve failures 3 3

A2.10 Valve logic failure 3 3

A2.11 High suppression pool temperature 4 4

A2.12 Loss of coolant accident 4 4

A2.13 Loss of, or inadequate, heat exchanger cooling flow 3 3

A2.14 High suppression pool level 3 3

A 3 Ability to monitor automatic operations of the Residual Heat Removal 

System: Suppression Pool Cooling Mode including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation 3

A3.02 Pump start 3

A3.03 Pump discharge pressure 2

A3.04 System flow 3

A3.05 Suppression pool temperature 3

A3.06 Reactor building cooling water/ Reactor building service water start

signal 3

A3.07 Control room alarms 3

A3.08 System initiation sequence 3
3.5-15 NUREG-2104

3.5 Safety Function 5: Containment Integrity

System: SF5RHRSPC Residual Heat Removal System: Suppression Pool Cooling 

Mode (continued)

K/A NO. ABILITY IMPORTANCE

A 4 Ability to manually operate and/or monitor the Residual Heat Removal 

System: Suppression Pool Cooling Mode in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Residual heat removal system pumps 4

A4.02 Valves pertaining to suppression pool cooling 4

A4.03 Keep fill 3

A4.04 Minimum flow valves 3

A4.05 The overrides for suppression pool cooling valve logic 4
NUREG 2104 3.5-16

3.5 Safety Function 5: Containment Integrity

System: SF5RHRSPR Residual Heat Removal System: Drywell and Wetwell Spray 

Mode

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

Residual Heat Removal System: Drywell and Wetwell Spray Mode and the 

following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 AC electrical power distribution system 3

K1.02 Reactor pressure vessel instrumentation 3

K1.03 Reactor building cooling water systems 3

K1.04 Fire protection system (PRA) 3

K1.05 Engineered Safety Function logic and control system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Drywell and wetwell spray motor operated valves 2

K2.02 Residual heat removal pumps 3

K2.03 Valve control logic 2

K 3 Knowledge of the effect that a loss or malfunction of the Residual Heat 

Removal System: Drywell and Wetwell Spray Mode will have on the 

following:

(CFR: 41.7 / 45.4)

K3.01 Drywell/ wetwell pressure 4

K3.02 Drywell/ wetwell temperature 4

K3.03 Drywell/ wetwell components, due to continued operation with

elevated pressure and/or temperature and/or water level 3

K 4 Knowledge of Residual Heat Removal System: Drywell and Wetwell Spray 

Mode design feature(s) and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Redundancy 3

K4.02 Reduction in vessel injection flow during accident conditions 3

K4.03 Prevention of piping overpressurization 2

K4.04 Pump minimum flow protection 3

K4.05 Residual heat removal pump motor cooling 2

K4.06 Prevention of water hammer 3

K4.07 Adequate pump net positive suction head 2

K4.08 Spray flow cooling 3

K4.09 Prevention of leakage to the environment through system heat

exchanger 3
3.5-17 NUREG-2104

3.5 Safety Function 5: Containment Integrity

System: SF5RHRSPR Residual Heat Removal System: Drywell and Wetwell Spray 

Mode (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply Residual Heat Removal System: Drywell and

Wetwell Spray Mode:

(CFR: 41.5 / 45.3)

K5.01 Evaporative cooling 2

K5.02 Convective cooling 2

K5.03 Vacuum breaker operation 3

K5.04 Suppression pool 3

K5.05 Residual heat removal system piping 4

K5.06 Residual heat removal system pumps 4

K5.07 Keep fill 3

K5.08 Drywell spray penetration 3

K5.09 Containment instrumentation 3

K5.10 Wetwell spray penetration 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Residual Heat 

Removal System: Drywell and Wetwell Spray Mode:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 3

K6.02 Keep fill 3

K6.03 Suppression pool (temperature level and pressure) 3

K6.04 ECCS room cooling 2

K6.05 Reactor pressure vessel instrumentation 3

K6.06 Wetwell to drywell vacuum breakers 3

K6.07 Reactor building cooling water system 3

K6.08 Containment integrity 3

K6.09 Suction flow path 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Residual Heat Removal System: Drywell and Wetwell Spray 

Mode controls including:

(CFR: 41.5 / 45.5)

A1.01 Drywell pressure 4

A1.02 Drywell temperature 3

A1.03 Wetwell pressure 4

A1.04 Wetwell temperature 3

A1.05 Suppression pool temperature 3
NUREG 2104 3.5-18

3.5 Safety Function 5: Containment Integrity

System: SF5RHRSPR Residual Heat Removal System: Drywell and Wetwell Spray 

Mode (continued)

K/A NO. ABILITY IMPORTANCE

A1.06 System flow 3

A1.07 System pressure 3

A1.08 Suppression pool level 3

A1.09 RHR pump motor amps 2

A1.10 Emergency generator loading 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Residual Heat Removal System: Drywell 

And Wetwell 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)

RO SRO

A2.01 Inadequate net positive suction head 2 3

A2.02 RHR pumps trips 3 3

A2.03 AC electrical power distribution system 3 3

A2.04 Pump seal failure 2 3

A2.05 Inadequate room cooling 3 3

A2.06 Reactor pressure vessel instrumentation failures 3 3

A2.07 Motor operated valve failures 3 3

A2.08 Pump runout 3 3

A2.09 Valve logic failure 3 3

A2.10 High suppression pool level 3 3

A2.11 High drywell/wetwell pressure 4 4

A2.12 Loss of, or inadequate heat exchanger cooling flow 3 3

A2.13 High drywell temperature 3 3

A2.14 Low (or negative) drywell pressure during system operation 4 4

A2.15 Low (or negative) wetwell pressure during system operation 4 4

A2.16 Loss of coolant accident 4 4

A2.17 Loss of drywell cooling system 3 3

A 3 Ability to monitor automatic operations of the Residual Heat Removal 

System: Drywell and Wetwell Spray Mode including:

(CFR: 41.7 / 45.7)

A3.01 Drywell and wetwell spray initiation sequence 3
3.5-19 NUREG-2104

3.5 Safety Function 5: Containment Integrity

System: SF5RHRSPR Residual Heat Removal System: Drywell and Wetwell Spray 

Mode (continued)

K/A NO. ABILITY IMPORTANCE

A 4 Ability to manually operate and/or monitor the Residual Heat Removal 

System: Drywell and Wetwell Spray Mode in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Residual heat removal system pumps 4

A4.02 Residual heat removal system suction valves 3

A4.03 Residual heat removal system spray valves (PRA) 4

A4.04 Keep fill 3

A4.05 Minimum flow valves 3

A4.06 Valve logic override 4
NUREG 2104 3.5-20

3.5 Safety Function 5: Containment Integrity

System: SF5SEC Secondary Containment

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Secondary Containment and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor building heating, ventilation, and air conditioning system 3

K1.02 Primary containment system 4

K1.03 Standby gas treatment system 4

K1.04 Instrument air system 3

K1.05 Reactor building 3

K1.06 Radioactive drain transfer system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

None

K 3 Knowledge of the effect that a loss or malfunction of the Secondary 

Containment will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Off-site radioactivity release 4

K3.02 Core alterations 3

K3.03 Movement of irradiated fuel in the secondary containment 3

K3.04 Operations with a potential for draining the reactor vessel (OPDRVs) 3

K 4 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 4

K4.02 Protection against over pressurization 3

K4.03 Fluid leakage collection 3

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Secondary Containment:

(CFR: 41.5 / 45.3)

None
3.5-21 NUREG-2104

3.5 Safety Function 5: Containment Integrity

System: SF5SEC Secondary Containment (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Secondary 

Containment:

(CFR: 41.7 / 45.7)

K6.01 Reactor building heating, ventilation, and air conditioning system 4

K6.02 Standby gas treatment system 4

K6.03 Primary containment system 4

K6.04 Instrument air system 3

K6.05 Reactor building 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Secondary Containment controls including:

(CFR: 41.5 / 45.5)

A1.01 High area temperature 4

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 Access doors or equipment hatch failure 3 4

A2.02 Excessive outleakage 4 4

A2.03 High area radiation 3 4

A2.04 High airborne radiation 3 4

A2.05 High area temperature 3 3

A2.06 High area water levels 3 3

A2.07 Low secondary containment differential pressure 3 3

A 3 Ability to monitor automatic operations of the Secondary Containment

including:

(CFR: 41.7 / 45.7)

A3.01 Secondary containment isolation 4

A3.02 Secondary containment differential pressure 4

A 4 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

None

3.6-1 NUREG-2104

3.6 Safety Function 6: Electrical

System: SF6EPDS AC Electrical Distribution System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the AC Electrical Distribution System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Emergency diesel generators 4

K1.02 Direct current power supply system 3

K1.03 Offsite power system 3

K1.04 Vital AC power supply system 3

K1.05 Main turbine/generator 3

K1.06 Combustion turbine generator 4

K1.07 Engineered Safety Function logic and control system 3

K1.08 Remote shutdown system 3

K1.09 Plant information and control system 3

K1.10 Instrument and control power supply system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

None

K 3 Knowledge of the effect that a loss or malfunction of the AC Electrical 

Distribution System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Major system loads 4

K3.02 Emergency diesel generators 4

K3.03 Direct current power supply system 3

K3.04 Vital AC power supply system 3

K3.05 Offsite power system 3

K3.06 Combustion turbine generator 4

K3.07 Instrumentation and control power supply system 3

K 4 Knowledge of AC Electrical Distribution System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Bus lockouts 3

K4.02 Circuit breaker automatic trips 3

K4.03 Interlocks between automatic bus transfer and breakers 3

K4.04 Protective relaying 3

K4.05 Paralleling of AC sources (syncroscope) 4

K4.06 Redundant power sources to vital buses 4
NUREG-2104 3.6-2

3.6 Safety Function 6: Electrical

System: SF6EPDS AC Electrical Distribution System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to the AC Electrical Distribution System:

(CFR: 41.5 / 45.3)

K5.01 Principle involved with paralleling two AC sources 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions, or components malfunctions will have on the AC Electrical 

Distribution System:

(CFR: 41.7 / 45.7)

K6.01 DC power 3

K6.02 Loss of off-site power 4

K6.03 Main generator trip 4

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the AC Electrical Distribution System controls including:

(CFR: 41.5 / 45.5)

A1.01 Effect on instrumentation and controls of switching power supplies 3

A1.02 Effects of loads when energizing a bus 3

A1.03 Bus voltage 3

A1.04 Load currents 3

A1.05 Breaker lineups 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the AC Electrical Distribution 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)

RO SRO

A2.01 Turbine/generator trip 3 4

A2.02 Loss of coolant accident 4 4

A2.03 Loss of off-site power 4 4

A2.04 Types of loads that, if deenergized, would degrade or hinder plant

operation 4 4

A2.05 Bus grounds 3 3

A2.06 Deenergizing a live bus 3 3

A2.07 Energizing a dead bus 3 3

A2.08 Exceeding voltage limitations 3 3
3.6-3 NUREG-2104

3.6 Safety Function 6: Electrical

System: SF6EPDS AC Electrical Distribution System (continued)

K/A NO. ABILITY IMPORTANCE

RO SRO

A2.09 Exceeding current limitations 3 3

A2.10 Degraded system voltages 3 4

A2.11 Main generator load rejection 3 3

A2.12 Station blackout 4. 4

A 3 Ability to monitor automatic operations of the AC Electrical Distribution 

System including:

(CFR: 41.7 / 45.7)

A3.01 Breaker tripping ................................................................................ 3

A3.02 Automatic bus transfer...................................................................... 3

A3.03 Load shedding .................................................................................. 3

A3.04 Load sequencing............................................................................... 3

A3.05 Synchronizing and paralleling of different AC supplies...................... 3

A 4 Ability to manually operate and/or monitor the AC Electrical Distribution 

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Available breakers and disconnects (including available switchyard) 3

A4.02 Synchroscope, including understanding of running and incoming

voltages ............................................................................................ 3

A4.03 Local operation of breakers............................................................... 3

A4.04 Synchronizing and paralleling of different AC supplies...................... 4

A4.05 Voltage, current, power, and frequency on AC buses ....................... 3

A4.06 Perform ground isolation................................................................... 2
NUREG-2104 3.6-4

3.6 Safety Function 6: Electrical

System: SF6DC Direct Current Power Supply System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Direct Current Power Supply System and the following 

systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 AC electrical power distribution system 3

K1.02 Control building heating, ventilation, and air conditioning system 3

K1.03 Control rod drive system 3

K1.04 Engineered Safety Function logic and control system 4

K1.05 Plant information and control system 4

K1.06 Reactor trip and isolation system 4

K1.07 Reactor core isolation cooling system 4

K1.08 Fuel pool cooling and cleanup system 3

K1.09 Turbine lube oil system 2

K1.10 Generator seal oil system 2

K1.11 Lighting and servicing power supply system 2

K1.12 Emergency diesel generator system 3

K1.13 Vital AC power supply system 3

K1.14 Suppression pool cleanup system 2

K1.15 Turbine control system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Alternate rod insertion valves 3

K2.02 Backup scram relay contacts to CRD air header dump valves 3

K2.03 Reactor core isolation cooling system DC valves 3

K2.04 Emergency lighting system 2

K2.05 Engineered Safety Function logic and control system 3

K2.06 Plant information and control system 3

K 3 Knowledge of the effect that a loss or malfunction of the Direct Current 

Power Supply System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Emergency diesel generators 3

K3.02 Engineered Safety Function logic and control system 3

K3.03 Reactor core isolation cooling system 3

K3.04 Reactor trip and isolation system 3

K3.05 Control rod drive system 3

K3.06 Suppression pool cleanup system 2

K3.07 Fuel pool cooling and cleanup system 2

K3.08 Turbine lube oil system 2

K3.09 Generator seal oil system 2
3.6-5 NUREG-2104

3.6 Safety Function 6: Electrical

System: SF6DC Direct Current Power Supply System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K3.10 Lighting and servicing power supply system 2

K3.12 Vital AC power supply system 3

K3.13 Plant information and control system 3

K3.14 AC electrical power distribution system 3

K3.15 Automatic depressurization system 3

K 4 Knowledge of Direct Current Power Supply System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Manual/ automatic transfers of control 3

K4.02 Breaker interlocks, permissives, bypasses and cross ties 3

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply Direct Current Power Supply System:

(CFR: 41.5 / 45.3)

K5.01 Hydrogen generation during battery charging 3

K5.02 Battery charger and battery 3

K5.03 Ground detection 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Direct Current 

Power Supply System:

(CFR: 41.7 / 45.7)

K6.01 Electrical power distribution system 3

K6.02 Battery ventilation 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Direct Current Power Supply System controls including:

(CFR: 41.5 / 45.5)

A1.01 Battery discharging rate 3
NUREG-2104 3.6-6

3.6 Safety Function 6: Electrical

System: SF6DC Direct Current Power Supply System (continued)

K/A NO. ABILITY IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Direct Current Power Supply 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)

RO SRO

A2.01 Grounds 3 3

A2.02 Loss of ventilation during charging 3 3

A2.03 Station blackout 3 3

A 3 Ability to monitor automatic operations of the Direct Current Power Supply

System including:

(CFR: 41.7 / 45.7)

A3.01 Control room indications and alarms 3

A 4 Ability to manually operate and/or monitor the Direct Current Power Supply

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Major breakers and control power fuses 3
3.6-7 NUREG-2104

3.6 Safety Function 6: Electrical

System: SF6EDGCTG Emergency Generators (Diesel/Combustion Turbine 

Generator)

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between Emergency Generators (Diesel/Combustion Turbine Generators) 

and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Electrical power distribution system 4

K1.02 Direct current power supply system 3

K1.03 Fire protection system 3

K1.04 Reactor building cooling water system 3

K1.05 Remote shutdown system 3

K1.06 Engineered Safety Function logic and control system 4

K1.07 Makeup water purified system 2

K1.08 Vital AC power supply system 3

K1.09 Reactor building heating, ventilation, and air conditioning system 3

K1.10 Plant information and control system 3

K1.11 Residual heat removal system 4

K1.12 High pressure core flooder system 4

K1.13 Grounding and lightning protection system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Air compressor 2

K2.02 Fuel oil pumps 2

K2.03 Lube oil pumps 2

K2.04 Emergency diesel generator field flash 2

K 3 Knowledge of the effect that a loss or malfunction of the Emergency 

Generators (Diesel/Combustion Turbine Generators) will have on the 

following:

(CFR: 41.7 / 45.4)

K3.01 Residual heat removal system 4

K3.02 High pressure core flooder system 4

K3.03 Electrical power distribution system 4

K 4 Knowledge of Emergency Generators (Diesel/Combustion Turbine 

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

following:

(CFR: 41.7)

K4.01 Generator trips (normal) 4

K4.02 Generator trips (emergency/Loss of coolant accident) 4

K4.03 Speed droop control 3
NUREG-2104 3.6-8

3.6 Safety Function 6: Electrical

System: SF6EDGCTG Emergency Generators (Diesel/Combustion Turbine 

Generator) (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K4.04 Field flashing 3

K4.05 Load shedding and sequencing 3

K4.06 Governor control 3

K4.07 Local operation and control 3

K4.08 Automatic startup 4

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Emergency Generators (Diesel/Combustion 

Turbine Generators):

(CFR: 41.5 / 45.3)

K5.01 Definition of frequency and synchronous frequency 2

K5.02 Reactive power control 2

K5.03 Real power control 2

K5.04 Fuel oil supply subsystem 3

K5.05 Starting air subsystem 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Emergency 

Generators (Diesel/Combustion Turbine Generators):

(CFR: 41.7 / 45.7)

K6.01 Starting air 4

K6.02 Fuel oil pumps 4

K6.03 Lube oil pumps 4

K6.04 Ignition system (combustion turbine generator) 3

K6.05 Reactor building cooling water system 4

K6.06 Electrical power distribution system 4

K6.07 DC electrical power supply system 3

K6.08 Engineered Safety Function logic and control system 4

K6.09 Makeup water purified system 3

K6.10 Loss of offsite power 3

K6.11 Loss of coolant accident 3

K6.12 Jacket cooling water 3
3.6-9 NUREG-2104

3.6 Safety Function 6: Electrical

System: SF6EDGCTG Emergency Generators (Diesel/Combustion Turbine 

Generator) (continued)

K/A NO. ABILITY IMPORTANCE

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Emergency Generators (Diesel/Combustion Turbine 

Generators controls including:

(CFR: 41.5 / 45.5)

A1.01 Lube oil temperature 3

A1.02 Fuel consumption rate 2

A1.03 Operating voltages, currents, and temperatures 3

A1.04 Crank case temperature and pressure 3

A1.05 Cylinder temperature differential 2

A1.06 Emergency generator room temperature 2

A1.07 Maintaining minimum load on generator (to prevent reverse power) 3

A1.08 Diesel generator load (MWe and frequency) 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Emergency Generators 

(Diesel/Combustion Turbine Generators); 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)

RO SRO

A2.01 Parallel operation of generator 4 4

A2.02 Unloading prior to securing generator 3 3

A2.03 Operating unloaded, lightly loaded, and highly loaded. 3 3

A2.04 Consequences of operating under/over excited 3 3

A2.05 Synchronization of the generator with other electrical supplies 4 4

A2.06 Opening normal and/or alternate power to Class 1E AC bus 3 3

A2.07 Loss of off-site power during full-load testing 4 4

A2.08 Initiation of generator room fire protection system 3 4

A2.09 Loss of electrical power distribution system 4 4

A2.10 LOCA 4 4

A2.11 Station blackout 4 4

A 3 Ability to monitor automatic operations of the Emergency Generators 

(Diesel/Combustion Turbine Generators) including:

(CFR: 41.7 / 45.7)

A3.01 Automatic starting of emergency generator 3

A3.02 Minimum time for load pick up 3

A3.03 Control room indications and alarms 3
NUREG-2104 3.6-10

3.6 Safety Function 6: Electrical

System: SF6EDGCTG Emergency Generators (Diesel/Combustion Turbine 

Generator) (continued)

K/A NO. ABILITY IMPORTANCE

A3.04 Operation of the governor control system on frequency and voltage

control 3

A3.05 Load shedding and sequencing 3

A3.06 Reactor building cooling water system operation 3

A 4 Ability to manually operate and/or monitor Emergency Generators 

(Diesel/Combustion Turbine Generator) in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Adjustment of exciter voltage 3

A4.02 Synchroscope 3

A4.03 Transfer of control between manual and automatic 3

A4.04 Manual start, loading, and stopping of generator 4

A4.05 Transfer of generator (with load) to grid 4
3.6-11 NUREG-2104

3.6 Safety Function 6: Electrical

System: SF6VAC Vital AC Power Supply System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Vital AC Power Supply System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Rod control and information system 3

K1.02 Reactor trip and isolation system 3

K1.03 Process radiation monitoring system 3

K1.04 Neutron monitoring system 3

K1.05 Standby liquid control system 3

K1.06 Plant data network 2

K1.07 Containment atmospheric monitoring system 2

K1.08 Electrical power distribution system 3

K1.09 DC power supply system 3

K1.10 Control building heating, ventilation, and air conditioning system 2

K1.11 Recirculation flow control system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

None

K 3 Knowledge of the effect that a loss or malfunction of the Vital AC Power 

Supply System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor trip and isolation system 3

K3.02 Reactor recirculation flow control system 3

K3.03 Neutron monitoring system 3

K3.04 Standby liquid control system 3

K3.05 Plant data network 2

K3.06 Containment atmospheric monitoring system 2

K3.07 Rod control and information system 3

K3.08 Control building heating, ventilation, and air conditioning system 2

K 4 Knowledge of Vital AC Power Supply System 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
NUREG-2104 3.6-12

3.6 Safety Function 6: Electrical

System: SF6VAC Vital AC Power Supply System (continued)

K/A NO. ABILITY IMPORTANCE

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Vital AC Power Supply System:

(CFR: 41.5 / 45.3)

K5.01 General principles of static inverter operation 2

K5.02 General principles of static switch operation 2

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Vital AC Power 

Supply System:

(CFR: 41.7 / 45.7)

K6.01 Electrical power distribution system 3

K6.02 DC power supply system 3

K6.03 Static inverter 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Vital AC Power Supply System controls including:

(CFR: 41.5 / 45.5)

None

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Vital AC Power Supply 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)

RO SRO

A2.01 Under voltage 3 3

A2.02 Over voltage 3 3

A2.03 Frequency changes in the system 2 3

A 3 Ability to monitor automatic operations of the Vital AC Power Supply

System including:

(CFR: 41.7 / 45.7)

A3.01 Transfer from preferred to alternate source 3
3.6-13 NUREG-2104

3.6 Safety Function 6: Electrical

System: SF6VAC Vital AC Power Supply System (continued)

K/A NO. ABILITY IMPORTANCE

A 4 Ability to manually operate and/or monitor the Vital AC Power Supply

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Transfer from alternative source to preferred source 3
NUREG-2104 3.6-14

3.6 Safety Function 6: Electrical

System: SF6I&C Instrumentation and Control Power Supply System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Instrumentation and Control Power Supply System and the 

following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Engineered Safety Function logic and control system 4

K1.02 Plant information and control system 4

K1.03 Makeup water condensate system 2

K1.04 Residual heat removal system 2

K1.05 High pressure core flooder system 2

K1.06 Reactor building cooling water system 2

K1.07 Reactor service water system 2

K1.08 Service air system 2

K1.09 Instrument air system 2

K1.10 Drywell cooling system 3

K1.11 Electrical power distribution system 3

K1.12 AC electrical power distribution system 4

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

None

K 3 Knowledge of the effect that a loss or malfunction of the Instrumentation 

and Control Power Supply System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Engineered Safety Function logic and control system 4

K3.02 Plant information and control system 4

K3.03 Makeup water condensate system 2

K3.04 Residual heat removal system 2

K3.05 High pressure core flooder system 2

K3.06 Reactor water cleanup system 2

K3.07 Reactor building cooling water system 2

K3.08 Reactor service water system 2

K3.09 Service air system 2

K3.10 Instrument air system 3

K 4 Knowledge of Instrumentation and Control Power Supply System design 

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

(CFR: 41.7)

None
3.6-15 NUREG-2104

3.6 Safety Function 6: Electrical

System: SF6I&C Instrumentation and Control Power Supply System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Instrumentation and Control Power Supply

System:

(CFR: 41.5 / 45.3)

None

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Instrumentation 

and Control Power Supply System:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 4

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Instrumentation and Control Power Supply System controls 

including:

(CFR: 41.5 / 45.5)

None

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Instrumentation and Control Power 

Supply 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)

RO SRO

A2.01 Under voltage 3 3

A2.02 Over voltage 3 3

A2.03 Distribution board feed breaker trip 3 3

A 3 Ability to monitor automatic operations of the Instrumentation and Control 

Power Supply System including:

(CFR: 41.7 / 45.7)

None
NUREG-2104 3.6-16

3.6 Safety Function 6: Electrical

System: SF6I&C Instrumentation and Control Power Supply System (continued)

K/A NO. ABILITY IMPORTANCE

A 4 Ability to manually operate and/or monitor the Instrumentation and Control 

Power Supply System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

None
3.7-1 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7APR Automatic Power Regulator System 

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships and 

between the Automatic Power Regulator System and the following 

systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Rod control and information system 4

K1.02 Neutron monitoring system 3

K1.03 Recirculation flow control system 4

K1.04 Steam bypass and pressure control system 4

K1.05 Plant information and control system 3

K1.06 Turbine control system 4

K1.07 Reactor water cleanup system 3

K1.08 Main generator 3

K1.09 Automated thermal limit monitoring system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Automatic power regulator digital controllers 2

K 3 Knowledge of the effect that a loss or malfunction of the Automatic Power 

Regulator System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Rod control and information system 4

K3.02 Recirculation flow control system 4

K3.03 Steam bypass and pressure control system 4

K3.04 Turbine control system 4

K3.05 Plant information and control system 4

K 4 Knowledge of Automatic Power Regulator System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Determination of reactor criticality when Automatic Power Regulator

is in automatic mode 3

K4.02 Trip of Automatic Power Regulator to manual when system or 

component conditions are abnormal during execution of prescribed

sequences 3
NUREG-2104 3.7-2

3.7 Safety Function 7: Instrumentation

System: SF7APR Automatic Power Regulator System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to Automatic Power Regulator System:

(CFR: 41.5 / 45.3)

K5.01 Main generator output 3

K5.02 Reactor power 4

K5.03 Rod pattern control 3

K5.04 Reactivity control 3

K5.05 Reactor water temperature during startup and shutdown 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Automatic Power 

Regulator System:

(CFR: 41.7 / 45.7)

K6.01 Plant information and control system 3

K6.02 Neutron monitoring system 3

K6.03 Reactor water cleanup system 3

K6.04 Steam bypass and pressure control system 4

K6.05 Turbine control system 3

K6.06 Main generator system 4

K6.07 Rod control and information system 4

K6.08 Recirculation flow control system 4

K6.09 Automated thermal limit monitoring system 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Automatic Power Regulator System controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor power 4

A1.02 Reactor pressure 3

A1.03 Main generator power output 3

A1.04 Reactor water temperature 3

A1.05 Power/flow operating map 3
3.7-3 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7APR Automatic Power Regulator System (continued)

K/A NO. ABILITY IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Automatic Power Regulator 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)

RO SRO

A2.01 Fault detection while in automatic mode of operation 3 3

A 3 Ability to monitor automatic operations of the Automatic Power Regulator

System including:

(CFR: 41.7 / 45.7)

A3.01 Dedicated operator interface indications 3

A3.02 Verification of proper functioning/operability 3

A3.03 Annunciator and alarm signals 3

A3.04 Reactor power 4

A3.05 Core flow 4

A3.06 Control rod position 4

A3.07 Reactor pressure 3

A3.08 Reactor water temperature 3

A3.09 Main generator output 3

A 4 Ability to manually operate and/or monitor the Automatic Power Regulator

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Console controls to set up various automatic power regulator

modes of operation 4
NUREG-2104 3.7-4

3.7 Safety Function 7: Instrumentation

System: SF7ATLM Automated Thermal Limit Monitor 

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Automated Thermal Limit Monitor and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Rod control and information system 4

K1.02 Automatic power regulator system 4

K1.03 Feedwater control system 2

K1.04 Recirculation flow control system 4

K1.05 Neutron monitoring system 3

K1.06 Plant information and control system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Automated thermal limit monitor system controllers 2

K 3 Knowledge of the effect that a loss or malfunction of the Automated 

Thermal Limit Monitor will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Rod control and information system 4

K3.02 Recirculation flow control system 4

K3.03 Automatic power regulator system 4

K 4 Knowledge of Automated Thermal Limit Monitor design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Rod withdrawal blocks/errors 4

K4.02 Bypassing an automated thermal limit monitor channel 3

K4.03 System testing 2

K4.04 Inhibiting an increase in recirculation flow 4

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to Automated Thermal Limit Monitor:

(CFR: 41.5 / 45.3)

None
3.7-5 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7ATLM Automated Thermal Limit Monitor (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 6 Knowledge of the effect of the following plant conditions, system 

malfunction or component malfunctions will have on the Automated 

Thermal Limit Monitor:

(CFR: 41.7 / 45.7)

K6.01 Recirculation flow control system 3

K6.02 Feedwater control system input (cleanup water flow, feedwater

temperature and total feedwater flow to RPV) 3

K6.03 Plant information and control system 3

K6.05 Neutron monitoring system 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Automated Thermal Limit Monitor controls including:

(CFR: 41.5 / 45.5)

A1.01 Rod position 3

A1.02 Status of control rod withdrawal blocks 3

A1.03 Status of recirculation flow increase blocks 3

A1.03 Automated thermal limit monitor channel bypass status 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Automated Thermal Limit Monitor; 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)

RO SRO

A2.01 Power supply loss 2 2

A2.02 Loss of neutron monitoring input 3 3

A2.03 Automatic self-bypass of the ATLM protective features 2 2

A 3 Ability to monitor automatic operations of the Automated Thermal Limit 

Monitor including:

(CFR: 41.7 / 45.7)

A3.01 System indications and alarms on control room panels and

backpanels 3

A3.02 Verification of proper functioning/operability 3

A3.03 Control rod withdrawal blocks 3

A3.04 Inhibit of recirculation flow increase 3

A3.05 Automatic bypass below low power setpoint 3
NUREG-2104 3.7-6

3.7 Safety Function 7: Instrumentation

System: SF7ATLM Automated Thermal Limit Monitor (continued)

K/A NO. ABILITY IMPORTANCE

A 4 Ability to manually operate and/or monitor the Automated Thermal Limit 

Monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Controls to bypass/unbypass an Automated Thermal Limit

Monitor channel 3
3.7-7 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7APRM Average Power Range Monitor/Local Power Range Monitor 

System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Average Power Range Monitor/Local Power Range Monitor

System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor trip and isolation system 4

K1.02 Multi-channel rod block monitor system 3

K1.03 Safety parameter display system 3

K1.04 Plant information and control system 3

K1.05 Rod control and information system 3

K1.06 Automated traversing incore probe system 3

K1.07 Reactor pressure vessel 3

K1.08 Automatic power regulator system 3

K1.09 Oscillation power range monitor sub-system 4

K1.10 Recirculation flow control system 3

K1.11 Engineered Safety Function logic and control system 3

K1.12 Vital AC power supply system 3

K1.13 Automated thermal limit monitor system 3

K1.14 Primary containment system 2

K1.15 Rod worth minimizer system 3

K1.16 Feedwater control system 3

K1.17 Automatic depressurization system 4

K 2 Knowledge bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Local Power Range Monitor detector channels 2

K2.02 Average Power Range Monitor channels 3

K2.03 Oscillation power range monitor channels 2

K 3 Knowledge of the effect that a loss or malfunction of the Average Power 

Range Monitor/Local Power Range Monitor System will have on the 

following:

(CFR: 41.7 / 45.4)

K3.01 Reactor trip and isolation system 4

K3.02 Recirculation flow control system 3

K3.03 Rod control and information system 3

K3.04 Reactor power indication 4

K3.05 Multichannel rod block monitor 3

K3.06 Core thermal limit calculations 4

K3.07 Automatic power regulator system 3
NUREG-2104 3.7-8

3.7 Safety Function 7: Instrumentation

System: SF7APRM Average Power Range Monitor/Local Power Range Monitor 

System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K3.08 Oscillation power range monitor system 4

K3.09 Engineered Safety Function logic and control system 3

K3.10 Automated thermal limit monitor system 3

K3.11 Rod worth minimizer system 3

K 4 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 4

K4.02 Reactor scram signals 4

K4.03 Individual Local Power Range Monitor detector replacement 2

K4.04 Alarm seal-in 2

K4.05 Effects of detector aging on Average Power Range Monitor/Local

Power Range Monitor readings 3

K4.06 Average Power Range Monitor flow biased trip setpoints 4

K4.07 Multichannel rod block monitor setpoints 4

K4.08 Sampling of overall core power in each Average Power Range

Monitor (accomplished through Local Power Range Monitor

assignments and symmetrical rod patterns) 3

K4.09 Detection of power oscillations 4

K4.10 Inhibit of automatic initiation of Automatic Depressurization System 4

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to Average Power Range Monitor/Local Power Range Monitor

System:

(CFR: 41.5 / 45.3)

K5.01 Local Power Range Monitor detector operation 3

K5.02 Effects of voids on Local Power Range Monitor indication 3

K5.03 Control rod symmetrical patterns 3

K5.04 Local Power Range Monitor detector location and core symmetry 3

K5.05 Core flow effects on Average Power Range Monitor trip setpoints 4

K5.06 Assignment of Local Power Range Monitor's to specific Average

Power Range Monitor channels 2
3.7-9 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7APRM Average Power Range Monitor/Local Power Range Monitor 

System (continued)

K/A NO. ABILITY IMPORTANCE

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Average Power 

Range Monitor/Local Power Range Monitor System:

(CFR: 41.7 / 45.7)

K6.01 Reactor trip and isolation system 4

K6.02 Automated traversing incore probe system 2

K6.03 Detectors 3

K6.04 Rod control and information system 3

K6.05 Vital AC power supply system 3

A 1 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

A1.02 Reactor trip and isolation system status 4

A1.03 Control rod block status 4

A1.04 Scram and rod block trip setpoints 4

A1.05 Indications and alarms 3

A1.06 Average Power Range Monitor (gain adjustment factor) 4

A1.07 Injection of cold water into the reactor pressure vessel 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 Power supply degraded 3 3

A2.02 Upscale or downscale trips 4 4

A2.03 Inoperative trip (all causes) 4 4

A2.04 Scram trip signals 4 4

A2.05 Rod block signals 4 4

A2.06 Loss of reactor recirculation flow signal 4 4

A2.07 Core flow channels upscale/downscale 3 4

A2.08 Faulty or erratic operation of detectors/systems 3 3
NUREG-2104 3.7-10

3.7 Safety Function 7: Instrumentation

System: SF7APRM Average Power Range Monitor/Local Power Range Monitor 

System (continued)

K/A NO. ABILITY IMPORTANCE

A 3 Ability to monitor automatic operations of the Average Power Range 

Monitor/Local Power Range Monitor System including:

(CFR: 41.7 / 45.7)

A3.01 Panel indications 3

A3.02 Annunciator and alarm signals 3

A3.03 Reactor trip and Isolation System status 4

A3.04 Control rod block status 4

A3.05 Inhibit of automatic initiation of Automatic Depressurization System 4

A 4 Ability to manually operate and/or monitor the Average Power Range 

Monitor/Local Power Range Monitor System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Average Power Range Monitor back panel switches 3

A4.02 Local Power Range Monitor back panel switches 3

A4.03 Oscillation Power Range Monitor back panel switches 3

A4.05 Trip bypasses 3

A4.06 Bypass an Average Power Range Monitor/Local Power Range

Monitor channel 3
3.7-11 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7NBI Nuclear Boiler Instrumentation

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Nuclear Boiler Instrumentation and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor trip and isolation system 4

K1.02 Neutron monitoring system 3

K1.03 Engineered Safety Function logic and control system 4

K1.04 Safety/relief valves 4

K1.05 Recirculation flow control system 3

K1.06 Feedwater control system 4

K1.07 Feedwater system 3

K1.08 Plant information and control system 3

K1.09 Reactor pressure vessel 4

K1.10 Steam bypass and pressure control system 4

K1.11 Remote shutdown system 3

K1.12 Alternate feedwater injection system 3

K1.13 Control rod drive system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

None

K 3 Knowledge of the effect that a loss or malfunction of the Nuclear Boiler 

Instrumentation will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor trip and isolation system 4

K3.02 Leak detection and isolation system 4

K3.03 Reactor core isolation cooling system 4

K3.04 High pressure core flooder system 4

K3.05 Residual heat removal 4

K3.06 Automatic depressurization system 4

K3.07 Relief/safety valves 4

K3.08 Alternate rod insertion 4

K3.09 Recirculation flow control system 3

K3.10 Feedwater control system 4

K3.11 Feedwater system 3

K3.12 Main turbine 3

K3.13 Emergency diesel generators 4

K3.14 Anticipated transient without scram logic 4
NUREG-2104 3.7-12

3.7 Safety Function 7: Instrumentation

System: SF7NBI Nuclear Boiler Instrumentation (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K3.15 Plant information and control system 3

K3.16 Reactor pressure vessel 3

K3.17 Vessel temperature monitoring 3

K3.18 Vessel level monitoring 4

K3.19 Vessel pressure monitoring 4

K3.20 Core flow monitoring 4

K3.21 Core differential pressure monitoring 4

K3.22 Loose parts detection in the primary system 3

K3.23 Reactor internal pump flow monitoring 2

K3.24 Recirculation system 3

K3.25 Steam bypass and pressure control system 3

K 4 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 4

K4.02 Physical separation of sensors 3

K4.03 Redundancy of sensors 3

K4.04 Inputs to the reactor trip and isolation system 4

K4.05 Initiation of the emergency core cooling systems 4

K4.06 Initiation of the leak detection and isolation system 4

K4.07 Protection for the main turbine from high moisture carryover 3

K4.08 Protection against filling the main steam lines from the feed system 3

K4.09 Inputs to alternate reactor shutdown system 4

K4.10 Reactor vessel overpressure protection 4

K4.11 Overpressure protection for various low-pressure systems 3

K4.13 Temperature compensation for water level indication 3

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Nuclear Boiler Instrumentation:

(CFR: 41.5 / 45.3)

K5.01 Vessel vibration measurement (loose parts monitor) 2

K5.02 Steam flow effect on reactor water level 3

K5.03 Anticipated transient without scram logic 4

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Nuclear Boiler 

Instrumentation:

(CFR: 41.7 / 45.7)

K6.01 AC electrical distribution system 3

K6.02 DC electrical distribution system 3
3.7-13 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7NBI Nuclear Boiler Instrumentation (continued)

K/A NO. ABILITY IMPORTANCE

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 Control room indications 3

A1.02 Removing or returning a transmitter from/to service 3

A1.03 Surveillance testing 3

A1.04 System venting 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 Loss of power supply 3 3

A2.02 Reactor coolant temperature 3 3

A 3 Ability to monitor automatic operations of the Nuclear Boiler 

Instrumentation including:

(CFR: 41.7 / 45.7)

A3.01 Relationship between display readings and actual parameter values 3

A 4 Ability to manually operate and/or monitor the Nuclear Boiler 

Instrumentation in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Channel select controls 3

A4.02 Process computer 3
NUREG-2104 3.7-14

3.7 Safety Function 7: Instrumentation

System: SF7RAD Radiation Monitoring System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Radiation Monitoring System and the following systems:

(CFR: 41.2 to 41.9/45.7 to 45.8)

K1.01 Main steam system 2

K1.02 Offgas system 3

K1.03 Plant stack 3

K1.04 Reactor building cooling water system 3

K1.05 Radioactive waste treatment system 3

K1.06 Reactor building heating, ventilation, and air conditioning system 3

K1.07 Fuel building heating, ventilation, and air conditioning system 3

K1.08 Service building heating, ventilation, and air conditioning system 2

K1.09 Leak detection and isolation system 4

K1.10 Turbine building heating, ventilation, and air conditioning system 3

K1.11 Radwaste building heating, ventilation, and air conditioning system 3

K1.12 Plant information and control system 3

K1.13 Emergency response information system 2

K1.14 Vital AC power supply system 2

K1.15 Instrument air system 2

K1.16 Engineered Safety Function logic and control system 3

K1.17 Standby gas treatment system 3

K1.18 Makeup water purified system 2

K1.19 Control building heating, ventilation, and air conditioning system 3

K1.20 Extraction system 3

K 2 Knowledge of bus or electrical power supplies to the following:

(CFR: 41.7)

K2.01 Main steamline radiation monitors 3

K2.02 Offgas radiation monitoring system 3

K2.03 Plant stack radiation monitoring 3

K2.04 Radwaste liquid radiation monitoring system 2

K2.05 Reactor building heating, ventilation, and air conditioning monitors 3

K2.06 Area radiation monitors 2

K2.07 Control room ventilation monitors 2

K 3 Knowledge of the effect that a loss or malfunction of the Radiation 

Monitoring System will have on the following:

(CFR: 41.5 / 45.3)

K3.01 Station liquid effluent release monitoring 3

K3.02 Station gaseous effluent release monitoring 3

K3.03 Station area radiation monitoring 3

K3.04 Offgas system 4
3.7-15 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7RAD Radiation Monitoring System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K3.05 Reactor building heating, ventilation, and air conditioning 3

K3.06 Drywell sump liquid discharge 2

K3.07 Radwaste building ventilation 3

K3.08 Control building heating, ventilation, and air conditioning system 3

K 4 Knowledge of Radiation Monitoring System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Redundancy 3

K4.02 Automatic actions to contain the radioactive release

in the event that the predetermined release rates are exceeded 4

K4.03 Fail safe tripping of process radiation monitoring

logic during conditions of instrument failure 4

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Radiation Monitoring System:

(CFR: 41.7 / 45.4)

K5.01 Hydrogen injection operation's effect on process radiation indications 3

K5.02 Drywell sump liquid discharge 2

K5.03 Turbine gland seal condenser exhaust 2

K5.04 Fuel handling area ventilation exhaust 3

K5.05 Drywell 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Radiation 

Monitoring System:

(CFR: 41.7 / 45.7)

K6.01 Vital AC power 3

K6.02 Plant information and control system 2

K6.03 Leak detection and isolation system 2

ABILITY

A 1 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 Alarms and indications associated with normal operations 3

A1.02 Alarms and indications associated with surveillance testing 3
NUREG-2104 3.7-16

3.7 Safety Function 7: Instrumentation

System: SF7RAD Radiation Monitoring System (continued)

K/A NO. ABILITY IMPORTANCE

A 2 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)

RO SRO

A2.01 Fuel element failure 4 4

A2.02 AC electrical failure 3 3

A2.03 Downscale trips 3 3

A2.04 Offgas system failure 3 3

A2.05 Low fuel pool level 3 3

A2.06 Loss of coolant accident 4 4

A2.07 Leakage and/or breaks from contaminated systems to

atmosphere or to other process systems 3 4

A2.08 Refuel floor handling accidents/operations 3 4

A2.09 Low reactor water level during refueling operations 3 4

A 3 Ability to monitor automatic operations of the Radiation Monitoring System

including:

(CFR: 41.7 / 45.7)

A3.01 Offgas system isolation indications 4

A3.02 Liquid radwaste isolation indications 3

A3.03 Radwaste handing interlocks 2

A3.04 Drywell LCW or HCW sump isolation indications 3

A3.05 Ventilation system isolation indications 3

A3.06 Display indications 3

A3.07 Meter indications 3

A3.08 Containment isolation indications 4

A3.09 Lights and alarms 3

A 4 Ability to manually operate and/or monitor the Radiation Monitoring

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4. 01 Manually trip process radiation monitor logic 3
3.7-17 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7RTIS Reactor Trip and Isolation System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Reactor Trip and Isolation System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Neutron monitoring system 4

K1.02 Nuclear boiler system 4

K1.03 Vital AC power supply system 3

K1.04 Control rod drive system 3

K1.05 Plant information and control system 3

K1.06 Turbine main steam system 3

K1.07 Suppression pool temperature monitoring system 3

K1.08 Rod control and information system 3

K1.09 Recirculation flow control system 3

K1.10 Leak detection and isolation system 3

K1.11 Engineered Safety Function logic and control system 3

K1.12 Direct current power supply system 3

K1.13 Feedwater control system 3

K1.14 Instrumentation and control power supply system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Reactor Trip and Isolation System logic channels 3

K 3 Knowledge of the effect that a loss or malfunction of the Reactor Trip and 

Isolation System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Leak detection and isolation system 4

K3.02 Reactor Protection System logic channels 4

K3.03 Scram air header solenoid operated valves 4

K3.04 Reactor power 4

K3.05 Reactor coolant primary system integrity 4

K3.06 The magnitude of heat energy that must be absorbed by the containment

during accident/transient conditions 3

K3.07 The ability of the core cooling systems to provide adequate core cooling

during loss of coolant accidents 4

K3.08 Recirculation flow control system 3

K3.09 Secondary containment integrity 3

K3.10 Plant information and control 3

K3.11 Engineered Safety Function logic and control system 3

K3.12 Feedwater control system 3
NUREG-2104 3.7-18

3.7 Safety Function 7: Instrumentation

System: SF7RTIS Reactor Trip and Isolation System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 Knowledge of Reactor Trip and Isolation System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 System redundancy and reliability 3

K4.02 The prevention of a reactor scram following a single component

failure 4

K4.03 Functional testing of the system while maintaining power operation 4

K4.04 Manual system activation 4

K4.05 Complete control rod insertion following scram signal generation 4

K4.06 Control rod insertion following RPS system electrical failure 4

K4.07 Dual-rod scram testing 3

K4.08 Operation with the neutron monitoring system selection

switch in non-coincident position 3

K4.09 Initiation of the “scram follow” function following a reactor scram signal4

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Reactor Trip and Isolation System:

(CFR: 41.5 / 45.3)

K5.01 Specific logic arrangements 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Reactor Trip and 

Isolation System:

(CFR: 41.7 / 45.7)

K6.01 Vital AC power supply system 3

K6.02 Neutron monitoring system 3

K6.03 Main steam system 3

K6.04 Main condenser vacuum 3

K6.05 Turbine main steam system 3

K6.06 Leak detection and isolation system 3

K6.07 Control rod drive system 3

K6.08 Suppression pool temperature monitoring system 3

K6.09 Direct current power supply system 3

K6.10 Instrumentation and control power supply system 3
3.7-19 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7RTIS Reactor Trip and Isolation System (continued)

K/A NO ABILITY IMPORTANCE

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Reactor Trip and Isolation System controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor power 4

A1.02 Reactor water level 3

A1.03 Reactor pressure 3

A1.04 Control rod position 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Reactor Trip and Isolation 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)

RO SRO

A2.01 RTIS power supply failure 4 4

A2.02 Neutron monitoring system failure 4 4

A2.03 RTIS logic channel failure 3 4

A2.04 High reactor power 4 4

A2.05 High reactor pressure 4 4

A2.06 Low reactor level 4 4

A2.07 High main steam line flow 4 4

A2.08 Low main steam line pressure 4 4

A2.09 High drywell pressure 4 4

A2.10 Turbine stop valve closure signal 4 4

A2.11 Control valve fast closure signal 4 4

A2.12 Main steamline isolation valve closure 4 4

A2.13 Low condenser vacuum 4 4

A2.14 Low control rod drive charging header pressure 4 4

A2.15 Changing mode switch position 4 4

A2.16 Half-scram signal 2 2

A2.17 Complete scram signal 4 4

A2.18 Half-MSIV isolation signal 2 2

A2.18 Complete MSIV isolation signal 4 4

A2.20 High main steam line tunnel temperature 4 4

A2.21 High suppression pool temperature 4 4

A2.22 Short reactor period 4 4
NUREG-2104 3.7-20

3.7 Safety Function 7: Instrumentation

System: SF7RTIS Reactor Trip and Isolation System (continued)

K/A NO ABILITY IMPORTANCE

A 3 Ability to monitor automatic operations of the Reactor Trip and Isolation

System including:

(CFR: 41.7 / 45.7)

A3.01 Reactor power 4

A3.02 Control rod position 4

A3.03 Control room indications and alarms 4

A3.04 End-of-cycle recirculation pump trip 4

A 4 Ability to manually operate and/or monitor the Reactor Trip and Isolation

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Reactor mode switch 4

A4.02 Manual scram pushbuttons 4

A4.03 Manual scram reset switch 4

A4.04 Divisional manual main steam line isolation switch 3

A4.05 CRD charging pressure trip bypass switch 4

A4.06 Divisional RPS/MSIV sensor bypass switch 3

A4.07 Divisional RPS/MSIV trip logic function trip bypass switch 3

A4.08 Divisional trip logic function auto trip test switch 3

A4.09 Main steam line isolation bypass switch 3
3.7-21 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7MRBM Multi-Channel Rod Block Monitor System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Multi-Channel Rod Block Monitor System and the following 

systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Average power range/local power range monitor sub-system 3

K1.02 Rod control and information system 3

K1.03 Plant information and control system 3

K1.04 Vital AC power supply system 3

K1.05 Automated thermal limit monitor system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Multi-channel rod block monitor channels 2

K 3 Knowledge of the effect that a loss or malfunction of the Multi-Channel Rod 

Block Monitor System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Rod control and information system 3

K 4 Knowledge of Multi-Channel Rod Block Monitor System design feature(s) 

and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Rod withdrawal blocks 3

K4.02 Allows manual or auto setup of rod block lines during power increase 3

K4.03 Automatic setdown of rod block lines during power reduction 3

K4.04 Initiation point 3

K4.05 Bypass an MRBM channel 3

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Multi-Channel Rod Block Monitor System:

(CFR: 41.5 / 45.3)

K5.01 Trip reference selection 3

K5.02 Local power range monitors 3

K5.03 Control rod selection 3
NUREG-2104 3.7-22

3.7 Safety Function 7: Instrumentation

System: SF7MRBM Multi-Channel Rod Block Monitor System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Multi-Channel 

Rod Block Monitor System:

(CFR: 41.7 / 45.7)

K6.01 Vital AC power supply system 2

K6.02 Local power range monitor detectors 3

K6.03 Automated thermal limit monitor system 3

K6.04 Core flow signal 2

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Multi-Channel Rod Block Monitor System controls including:

(CFR: 41.5 / 45.5)

A1.01 Trip reference 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Multi-Channel 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)

RO SRO

A2.01 Withdrawal of control rod in high power region of core 3 4

A2.02 Loss or reduction in core flow (flow comparator) 3 3

A2.03 Loss of associated Average Power Range Monitor channel 3 3

A2.04 Power supply loss 3 3

A2.05 Multi-channel rod block monitor upscale or inoperable 3 3

A 3 Ability to monitor automatic operations of the Multi-Channel Rod Block 

Monitor System including:

(CFR: 41.7 / 45.7)

A3.01 Control room indications and alarms 3

A3.02 Verification or proper functioning/operability 4

A3.03 Back panel indications 4

A3.04 Automatic setup when in automatic rod withdrawal mode 3

A3.05 Automatic setdown of setpoint during power reduction 3
3.7-23 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7MRBM Multi-Channel Rod Block Monitor System (continued)

K/A NO. ABILITY IMPORTANCE

A 4 Ability to manually operate and/or monitor the Multi-Channel Rod Block 

Monitor System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 MRBM back panel switches, indications and indicating lights 3

A4.02 Trip bypasses 3

A4.03 "Setup" pushbutton 3
NUREG-2104 3.7-24

3.7 Safety Function 7: Instrumentation

System: SF7RWM Rod Worth Minimizer System 

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Rod Worth Minimizer System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Rod control and information system 3

K1.02 Neutron monitoring system 3

K1.03 Reactor trip and isolation system 3

K1.04 Vital AC power supply system 3

K1.05 Plant information and control system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Rod worth minimizer circuitry 2

K 3 Knowledge of the effect that a loss or malfunction of the Rod Worth 

Minimizer System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Rod control and information system 3

K 4 Knowledge of Rod Worth Minimizer System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Insert blocks 3

K4.02 Withdraw blocks 4

K4.03 Automatic bypass above low power setpoint 3

K4.04 System testing 3

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to Rod Worth Minimizer System:

(CFR: 41.5 / 45.3)

K5.01 Low power set point 3

K5.02 Low power alarm point 3

K5.02 Rod groups and steps 3

K5.03 Withdraw block 4

K5.04 Insert block 4

K5.05 Possible fuel damage due to rod withdrawal error 3
3.7-25 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7RWM Rod Worth Minimizer System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Rod Worth 

Minimizer System:

(CFR: 41.7 / 45.7)

K6.01 Vital AC power supply system 3

K6.02 Rod control and information system 3

K6.03 Neutron monitoring system 3

K6.04 Reactor trip and isolation system 3

K6.05 Inoperable control rod 3

K6.06 Stuck control rod 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Rod Worth Minimizer System controls including:

(CFR: 41.5 / 45.5)

A1.01 Rod position 3

A1.02 Status of control rod movement blocks 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Rod Worth Minimizer 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)

RO SRO

A2.01 Power supply loss 3 3

A2.02 Inoperable control rod 3 3

A2.03 Stuck control rod 3 3

A2.04 Out of sequence rod movement 3 4

A2.05 RWM hardware/software failure 3 3

A 3 Ability to monitor automatic operations of the Rod Worth Minimizer System

including:

(CFR: 41.7 / 45.7)

A3.01 System indication 3

A3.02 Verification of proper functioning/operability 4

A3.03 Annunciator and alarm signals 3

A3.04 Control rod movement blocks 4

A3.05 Automatic bypass above the low power setpoint 3
NUREG-2104 3.7-26

3.7 Safety Function 7: Instrumentation

System: SF7RWM Rod Worth Minimizer System (continued)

K/A NO. ABILITY IMPORTANCE

A 4 Ability to manually operate and/or monitor the Rod Worth Minimizer in the 

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Bypass single channel of the rod worth minimizer circuitry 3

A4.02 Dual channel bypass for special operations 2
3.7-27 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7SRNM Startup Range Neutron Monitoring System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Startup Range Neutron Monitoring System and the following 

systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor trip and isolation system 4

K1.02 Rod control and information system 3

K1.03 Plant information and control system 3

K1.04 Reactor pressure vessel 3

K1.05 Primary containment system 3

K1.06 Engineered Safety Function logic and control system 3

K1.07 Automatic power regulator system 3

K1.08 Vital AC power supply system 3

K1.09 Alternate reactor shutdown system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Startup range neutron monitoring channels/detectors 3

K 3 Knowledge of the effect that a loss or malfunction of the Startup Range 

Neutron Monitoring System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor trip and isolation system 3

K3.02 Rod control and information system 3

K3.03 Reactor power indications 4

K3.04 Automatic power regulator system 3

K3.05 Engineered Safety Function logic and control system 3

K3.06 Plant information and control system 3

K3.07 Alternate reactor shutdown system 3

K 4 Knowledge of Startup Range Neutron Monitoring System design feature(s) 

and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Rod withdrawal blocks 4

K4.02 Reactor scram signals 3

K4.03 Gamma compensation 2

K4.04 Different power determination methods (counting and Campbelling

technique) 2

K4.05 Bypassing a startup range neutron monitoring channel 3

K4.06 SRNM indications when changing reactor mode switch position 2
NUREG-2104 3.7-28

3.7 Safety Function 7: Instrumentation

System: SF7SRNM Startup Range Neutron Monitoring System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K4.07 ATWS permissive for automatic SLC initiation 3

K4.08 Non-coincidence scram signals during initial fuel loading 2

K4.09 Alarm seal-in 2

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Startup Range Neutron Monitoring System:

(CFR: 41.5 / 45.3)

K5.01 Gamma discrimination 2

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Startup Range 

Neutron Monitoring System:

(CFR: 41.7 / 45.7)

K6.01 Reactor trip and isolation system 3

K6.02 Vital AC power supply system 3

K6.03 Startup range neutron monitoring detectors 3

K6.04 Reactor vessel 3

K6.05 Primary containment system 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Startup Range Neutron Monitoring System controls 

including:

(CFR: 41.5 / 45.5)

A1.01 Reactor power indication 4

A1.02 Reactor trip and isolation system status 3

A1.03 Control rod block status 4

A1.04 Scram, rod block, and period alarm trip setpoints 4

A1.05 Indications and alarms 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Startup Range Neutron 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)

RO SRO

A2.01 Vital AC power supply loss 3 3

A2.02 Startup range neutron monitoring inoperable condition 3 4
3.7-29 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7SRNM Startup Range Neutron Monitoring System (continued)

K/A NO. ABILITY IMPORTANCE

RO SRO

A2.03 Up scale and downscale trips 4 4

A2.04 Faulty or erratic operation of detectors/system 3 4

A 3 Ability to monitor automatic operations of the Startup Range Neutron 

Monitoring System including:

(CFR: 41.7 / 45.7)

A3.01 Control room indications 3

A3.02 Annunciator and alarm signals 3

A3.03 Reactor trip and isolation system status 4

A3.04 Control rod block status 4

A3.05 ATWS permissive for SLC initiation 3

A 4 Ability to manually operate and/or monitor the Startup Range Neutron 

Monitoring in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Startup range neutron monitoring channel bypass switches 3
NUREG-2104 3.7-30

3.7 Safety Function 7: Instrumentation

System: SF7ATIP Automated Traversing In-Core Probe System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between Automated Traversing In-Core Probe System and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Local power range monitors 3

K1.02 Plant information and control system 3

K1.03 Instrument air system 2

K1.04 Leak detection and isolation system 3

K1.05 DC power supply system 2

K1.06 Electrical power distribution system 2

K1.07 Instrumentation and control power supply system 2

K1.08 Reactor pressure vessel 3

K1.09 Primary containment system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Shear valves 2

K2.02 ATIP channels/detectors 2

K 3 Knowledge of the effect that a loss or malfunction of the Automated 

Traversing In-Core Probe System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Local power range monitor's calibration 2

K 4 Knowledge of Automated Traversing In-Core Probe System design 

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

(CFR: 41.7)

K4.01 Primary containment isolation 3

K4.02 Radiation shielding 2

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to Automated Traversing In-Core Probe System:

(CFR: 41.5 / 45.3)

K5.01 Increasing area radiation monitor indications
3.7-31 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7ATIP Automated Traversing In-Core Probe (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Automated 

Traversing In-Core Probe System:

(CFR: 41.7 / 45.7)

K6.01 DC power supply system 2

K6.02 AC electrical power distribution system 2

K6.03 Instrumentation and control power supply system 2

K6.04 Plant information and control system 3

K6.05 Leak detection and isolation system 3

K6.06 Instrument air system 2

K6.07 Nuclear boiler system 2

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Automated Traversing In-Core Probe System controls 

including:

(CFR: 41.5 / 45.5)

A1.01 Radiation levels 3

A1.02 Detector position 3

A1.03 Valve status 3

A1.04 Drive speed 2

A1.05 Detector output 2

A1.06 Radiation alarms 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Automated Traversing In-Core Probe 

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)

RO SRO

A2.01 Low reactor water level 3 3

A2.02 High drywell pressure 3 3

A2.03 Drive mechanism failure 2 2

A2.04 Electrical power distribution system 2 2

A2.05 DC power supply system 2 2

A2.06 Shear valve closures 2 3

A2.07 Failure to retract during accident conditions 3 4

A2.08 Failure to retract to shield 3 3
NUREG-2104 3.7-32

3.7 Safety Function 7: Instrumentation

System: SF7ATIP Automated Traversing In-Core Probe (continued)

K/A NO. ABILITY IMPORTANCE

A 3 Ability to monitor automatic operations of the Automated Traversing InCore Probe System including:

(CFR: 41.7 / 45.7)

A3.01 Detector position 2

A3.02 Detector drive speed 2

A3.03 Valve operation 3

A3.04 Indicating lights 2

A3.05 Detector output 2

A 4 Ability to manually operate and/or monitor the Automated Traversing InCore Probe System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Isolation valves 3
3.7-33 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7ELCS Engineered Safety Function Logic and Control System 

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Engineered Safety Function Logic and Control System and the 

following systems:

(CFR: 41.2 to 41.9/45.7 to 45.8)

K1.01 Reactor trip and isolation system 3

K1.02 Neutron monitoring system 3

K1.03 Standby liquid control system 4

K1.04 Process radiation monitoring system 3

K1.05 Plant information and control system 3

K1.06 DC power supply system 3

K1.07 Instrumentation and control power system 3

K1.08 Leak detection and isolation system 3

K1.09 Suppression pool temperature monitoring system 3

K1.10 High pressure core flooder system 4

K1.11 Reactor core isolation cooling system 4

K1.12 Residual heat removal system 4

K1.13 Automatic depressurization system 4

K1.14 Emergency diesel generators 3

K1.15 Standby gas treatments system 3

K1.16 Reactor building cooling water system 3

K1.17 Reactor service water system 3

K1.18 Heating, ventilation, and air conditioning system emergency cooling

water system 3

K1.19 High-pressure nitrogen gas supply system 3

K1.20 Alternate reactor shutdown system 3

K1.21 Feedwater system (feedwater line break circuitry) 3

K1.22 Containment atmospheric monitoring system 3

K1.23 Reactor building heating, ventilation, and air conditioning system 3

K1.24 Control building heating, ventilation, and air conditioning system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

None

K 3 Knowledge of the effect that a loss or malfunction of the Engineered Safety 

Function Logic and Control System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor trip and isolation system 3

K3.02 Neutron monitoring system 3

K3.03 Standby liquid control system 4

K3.04 Process radiation monitoring system 3
NUREG-2104 3.7-34

3.7 Safety Function 7: Instrumentation

System: SF7ELCS Engineered Safety Function Logic and Control System 

(continued)

K/A NO. KNOWLEDGE IMPORTANCE

K3.05 Plant information and control system 3

K3.06 Leak detection and isolation system 3

K3.07 Suppression pool temperature monitoring system 3

K3.08 High pressure core flooder system 4

K3.09 Reactor core isolation cooling system 4

K3.10 Residual heat removal system 4

K3.11 Automatic depressurization system 4

K3.12 Emergency diesel generators 3

K3.13 Standby gas treatment system 3

K3.14 Reactor building cooling water system 3

K3.15 Reactor service water system 3

K3.16 Heating, ventilation, and air conditioning system emergency cooling

water system 3

K3.17 High-pressure nitrogen gas supply system 3

K3.18 Alternate reactor shutdown system 3

K3.19 Feedwater system (feedwater line break circuitry) 3

K3.20 Containment atmospheric monitoring system 3

K3.21 Reactor building heating, ventilation, and air conditioning system 3

K3.22 Control building heating, ventilation, and air conditioning system 3

K 4 Knowledge of Engineered Safety Function Logic and Control System

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

(CFR: 41.7)

K4.01 Redundancy of instrumentation 3

K4.02 On-line self diagnostic testing 3

K4.03 Initiation of the emergency core cooling systems 4

K4.04 Inputs to alternate rod insertion circuitry 4

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Engineered Safety Function Logic and 

Control System:

(CFR: 41.5 / 45.3)

None

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Engineered 

Safety Function Logic and Control System:

(CFR: 41.7 / 45.7)

K6.01 Instrumentation and control power supply system 3

K6.02 DC power supply system 3
3.7-35 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7ELCS Engineered Safety Function Logic and Control System 

(continued)

K/A NO. ABILITY IMPORTANCE

A 1. Ability to predict and/or monitor changes in parameters associated with 

operating the Engineered Safety Function Logic and Control System

controls including:

(CFR: 41.5/45.5)

A1.01 Removing or returning a channel to service 3

A1.02 Surveillance testing 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 Loss of AC or DC power supply 3 3

A2.02 System initiation/isolation due to Engineered Safety Function logic and control 

actuation 3 3

A 3 Ability to monitor automatic operations of the Engineered Safety Function

Logic and Control System including:

(CFR: 41.7 / 45.7)

A3.01 System initiation/isolation 3

A 4 Ability to manually operate and/or monitor the Engineered Safety Function

Logic and Control System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Removing or returning a channel to service 3
NUREG-2104 3.7-36

3.7 Safety Function 7: Instrumentation

System: SF7PICS Plant Information and Control System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Plant Information and Control System and the following 

systems:

(CFR: 41.2 to 41.9/45.7 to 45.8)

K1.01 Main steam system 3

K1.02 Reactor recirculation system 3

K1.03 Control rod drive system 3

K1.04 Leak detection and isolation system 3

K1.05 Reactor water cleanup system 3

K1.06 Fuel pool cooling and cleanup system 2

K1.07 Suppression pool cleanup system 2

K1.08 Turbine main steam system 3

K1.09 Condensate, feedwater and condensate air extraction system 2

K1.10 High vent and drain system 2

K1.11 Main turbine 2

K1.12 Steam bypass and pressure control system 3

K1.13 Turbine gland steam system 2

K1.14 Turbine lube oil system 2

K1.15 Moisture separator reheaters 2

K1.16 Hydrogen gas cooling system 2

K1.17 Generator cooling system 2

K1.18 Generator seal oil system 2

K1.19 Main condenser 2

K1.20 Offgas system 3

K1.21 Circulating water system 2

K1.22 Makeup water purified system 2

K1.23 Turbine building cooling water system 2

K1.24 Heating, ventilation, and air conditioning system normal cooling

water system 2

K1.25 Turbine service water system 2

K1.26 Atmosphere control system 3

K1.27 Drywell cooling system 3

K1.28 Control building heating, ventilation, and air conditioning system 3

K1.29 Turbine building heating, ventilation, and air conditioning system 2

K1.30 Instrument air system 2

K1.31 AC electrical power distribution system 3

K1.32 Makeup water condensate system 2

K1.33 Neutron monitoring system 3

K1.34 Reactor trip and isolation system 3

K1.35 Engineered Safety Function logic and control system 3

K1.36 Rod control and information system 3

K1.37 Feedwater control system 3
3.7-37 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7PICS Plant Information and Control System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K1.38 Recirculation flow control system 3

K1.39 Standby liquid control system 3

K1.40 Process radiation monitoring system 3

K1.41 Area radiation monitoring system 2

K1.42 Alternate feedwater injection system 3

K1.43 Automated traversing incore probe system 2

K1.44 Automatic power regulator system 3

K1.45 Instrumentation and control power supply system 3

K1.46 Direct current power supply system 3

K1.47 Loose parts monitoring system 2

K1.48 Asset monitoring system 2

K1.49 Plant data network 2

K1.50 Containment atmospheric monitoring system 3

K1.51 Fuel servicing equipment 3

K1.52 Turbine supervisory system 3

K1.53 Combustion turbine system 3

K1.54 Emergency diesel generator system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

None

K 3 Knowledge of the effect that a loss or malfunction of the Plant Information 

and Control System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Main steam system 3

K3.02 Reactor recirculation system 3

K3.03 Control rod drive system 3

K3.04 Leak detection and isolation system 3

K3.05 Reactor water cleanup system 3

K3.06 Fuel pool cooling and cleanup system 2

K3.07 Suppression pool cleanup system 2

K3.08 Turbine main steam system 3

K3.09 Condensate, feedwater and condensate air extraction system 2

K3.10 High vent and drain system 2

K3.11 Main turbine 2

K3.12 Steam bypass and pressure control system 3

K3.13 Turbine gland steam system 2

K3.14 Turbine lube oil system 2

K3.15 Moisture separator reheaters 2

K3.16 Hydrogen gas cooling system 2

K3.17 Generator cooling system 2
NUREG-2104 3.7-38

3.7 Safety Function 7: Instrumentation

System: SF7PICS Plant Information and Control System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K3.18 Generator seal oil system 2

K3.19 Main condenser 2

K3.20 Offgas system 3

K3.21 Circulating water system 2

K3.22 Makeup water purified system 2

K3.23 Turbine building cooling water system 2

K3.24 Heating, ventilation, and air conditioning system normal cooling

water system 2

K3.25 Turbine service water system 2

K3.26 Atmosphere control system 3

K3.27 Drywell cooling system 3

K3.28 Control building heating, ventilation, and air conditioning system 3

K3.29 Turbine building heating, ventilation, and air conditioning system 2

K3.30 Instrument air system 2

K3.31 AC electrical power distribution system 3

K3.32 Makeup water condensate system 2

K3.33 Neutron monitoring system 3

K3.34 Reactor trip and isolation system 3

K3.35 Engineered Safety Function logic and control system 3

K3.36 Rod control and information system 3

K3.37 Automated thermal limit monitoring system 3

K3.38 Feedwater control system 3

K3.39 Recirculation flow control system 3

K3.40 Standby liquid control system 3

K3.41 Process radiation monitoring system 3

K3.42 Area radiation monitoring system 2

K3.43 Alternate feedwater injection system 3

K3.44 Automated traversing incore probe system 2

K3.45 Automatic power regulator system 3

K3.46 Instrumentation and control power supply system 3

K3.47 Direct current power supply system 3

K3.48 Loose parts monitoring system 2

K3.49 Asset monitoring system 2

K3.50 Plant data network 2

K3.51 Containment atmospheric monitoring system 3

K3.52 Fuel servicing equipment 2

K3.53 Turbine supervisory system 3

K3.54 Combustion turbine system 3

K3.55 Emergency diesel generator system 3
3.7-39 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7PICS Plant Information and Control System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 Knowledge of Plant Information and Control System design feature(s) 

and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Redundancy of instrumentation 2

K4.02 On-line self diagnostic testing 2

K 5 Knowledge of the operational implications or cause-effects relationships as 

they apply to Plant Information and Control System:

(CFR: 41.5 / 45.3)

K5.01 Power generation control system 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Plant Information 

and Control System:

(CFR: 41.7 / 45.7)

K6.01 Instrumentation and control power supply system 3

K6.02 DC power supply system 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Plant Information and Control System controls including:

(CFR: 41.5 / 45.5)

A1.01 Control room indications associated with normal operations 2

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Plant Information and 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)

RO SRO

A2.01 AC or DC power supply failure 3 3
NUREG-2104 3.7-40

3.7 Safety Function 7: Instrumentation

System: SF7PICS Plant Information and Control System (continued)

K/A NO. ABILITY IMPORTANCE

A 3 Ability to monitor automatic operations of Plant Information and Control 

System including:

(CFR: 41.7 / 45.7)

A3.01 Reactor startup, power operation, and shutdown of the plant in

Power Generation Control System “automatic or semi-automatic

mode of operation 3

A 4 Ability to manually operate and/or monitor the Plant Information and 

Control System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Activate appropriate breakpoint to allow continuation of Power

Generation Control System automatic operation 3
3.7-41 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7SPTM Suppression Pool Temperature Monitoring System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Suppression Pool Temperature Monitoring System and the 

following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Engineered Safety Function logic and control system 4

K1.02 Plant information and control system 3

K1.03 Reactor trip and isolation system 4

K1.04 Primary containment system (suppression pool temperature and level)3

K1.05 Remote shutdown system 3

K1.06 Residual heat removal system 4

K1.07 Vital AC power supply system 3

K1.08 Reactor building cooling water system 4

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Suppression pool temperature monitoring logic channels 2

K 3 Knowledge of the effect that a loss or malfunction of the Suppression Pool 

Temperature Monitoring System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Primary containment system (suppression pool temperature

and level) 3

K3.02 Reactor trip and isolation system 4

K3.03 Residual heat removal system 4

K3.04 Remote shutdown system 3

K3.05 Plant information and control system 3

K3.06 Reactor building cooling water system 4

K 4 Knowledge of Suppression Pool Temperature Monitoring System design 

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

(CFR: 41.7)

K4.01 System redundancy and reliability 3

K4.02 Arrangement of temperature sensors in suppression pool 2

K4.03 Method of determining average temperature of suppression pool 3

K4.04 Suppression pool temperature monitoring logic arrangement 3
NUREG-2104 3.7-42

3.7 Safety Function 7: Instrumentation

System: SF7SPTM Suppression Pool Temperature Monitoring System (continued)

K/A NO KNOWLEDGE IMPORTANCE

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Suppression Pool Temperature Monitoring 

System:

(CFR: 41.5 / 45.3)

K5.01 Low suppression pool level 3

K5.02 Safety/relief valve operation 3

K 6 Knowledge of the effect of the following plant malfunctions, system 

malfunctions or component malfunctions will have on the Suppression 

Pool Temperature Monitoring System:

(CFR: 41.7 / 45.7)

K6.01 Primary containment system (suppression pool temperature and level)3

K6.02 Vital AC power supply system 3

K6.03 Engineered Safety Function logic and control system 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Suppression Pool Temperature Monitoring System controls 

including:

(CFR: 41.5 / 45.5)

A1.01 Surveillance testing 2

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Suppression Pool Temperature 

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)

RO SRO

A2.01 High suppression pool temperature 3 3

A2.02 Low suppression pool level 3 3

A2.03 Failure or erratic operation of suppression pool temperature/level

detector 3 3
3.7-43 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7SPTM Suppression Pool Temperature Monitoring System (continued)

K/A NO ABILITY IMPORTANCE

A 3 Ability to monitor automatic operations of the Suppression Pool 

Temperature Monitoring System including:

(CFR: 41.7 / 45.7)

A3.01 Control room indications and alarms 3

A3.02 Initiations and actuations due high suppression pool temperature 3

A 4 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 SPTM backpanel switches 3
NUREG-2104 3.7-44

3.7 Safety Function 7: Instrumentation

System: SF7RSS Remote Shutdown System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Remote Shutdown System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Main steam system 3

K1.02 Nuclear Boiler Instrumentation system 3

K1.03 Residual heat removal system 4

K1.04 High pressure core flooder system 3

K1.05 Reactor building cooling water system 3

K1.06 AC electrical distribution system 3

K1.07 Reactor service water system 3

K1.08 Atmosphere control system 3

K1.09 Makeup water condensate system 2

K1.10 Emergency diesel generator system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

None

K 3 Knowledge of the effect that a loss or malfunction of the Remote Shutdown 

System will have on the following:

(CFR: 41.5 / 45.3)

K3.01 Main steam system 3

K3.02 Nuclear Boiler Instrumentation system 3

K3.03 Residual heat removal system 4

K3.04 High pressure core flooder system 3

K3.05 Reactor building cooling water system 3

K3.06 AC electrical distribution system 3

K3.07 Reactor service water system 3

K3.08 Atmosphere control system 3

K3.09 Makeup water condensate system 2

K3.10 Emergency diesel generator system 3

K 4 Knowledge of Remote Shutdown System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Ability to transfer control of interfacing system equipment from the 

main control room and override capability (manual and automatic)

of operating the interfacing equipment from the main control room 3
3.7-45 NUREG-2104

3.7 Safety Function 7: Instrumentation

System: SF7RSS Remote Shutdown System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Remote Shutdown System:

(CFR: 41.7 / 45.4)

K5.01 Heat removal mechanisms 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Remote 

Shutdown System:

(CFR: 41.7 / 45.7)

K6.01 Conditions which cause the main control room to become

inaccessible 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Remote Shutdown System controls including:

(CFR: 41.5 / 45.5)

A1.01 Reactor pressure vessel water level 3

A1.02 Reactor pressure vessel pressure 3

A1.03 Residual heat removal pump discharge pressure 3

A1.04 Residual heat removal heat exchanger inlet temperature 3

A1.05 Residual heat removal heat exchanger outlet temperature 3

A1.06 Residual heat removal system flow 3

A1.07 High pressure core flooder system flow 3

A1.08 High pressure core flooder pump discharge pressure 3

A1.09 Reactor service water system ultimate heat sink water level 3

A1.10 Reactor service water system ultimate heat sink temperature 3

A1.11 Reactor building cooling water system flow 3

A1.12 Suppression pool level 3

A1.13 Drywell temperature 3

A1.14 Drywell pressure 3

A1.15 Condensate storage tank level 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Remote Shutdown 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)

RO SRO

A2.01 Control room evacuation 3 4
NUREG-2104 3.7-46

3.7 Safety Function 7: Instrumentation

System: SF7RSS Remote Shutdown System (continued)

K/A NO. ABILITY IMPORTANCE

A 3 Ability to monitor automatic operations of the Remote Shutdown System

including:

(CFR: 41.7 / 45.7)

None

A 4 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

None
3.8-1 NUREG 2104

3.8 Safety Function 8: Plant Service Systems

System SF8SFS Fire Protection System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Fire Protection System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Main generator hydrogen system 3

K1.02 Auxiliary steam system 2

K1.03 A.C electrical power distribution system 3

K1.04 Residual heat removal system 4

K1.05 Fire detection system 2

K1.06 Makeup water preparation system 2

K1.07 Instrument air system 2

K1.08 Turbine lube oil system 2

K1.09 Fuel oil transfer system 2

K1.10 Emergency diesel generators 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Fire protection supervisory circuits 2

K2.02 Motor driven pumps 3

K2.03 Fire detection system 2

K 3 Knowledge of the effect that a loss or malfunction of the Fire Protection 

System will have on the following:

(CFR: 41.7 / 45.4)

K3.01 The ability to detect fires 3

K3.02 Personnel protection 3

K3.03 Plant protection 4

K3.04 Residual heat removal system 4

K 4 Knowledge of Fire Protection System design feature(s) and/or interlocks 

which provide for the following:

(CFR: 41.5 / 41.7 / 45.3 / 45.5 to 45.8)

K4.01 Adequate supply of water for the fire protection system 3

K4.02 Automatic system initiation 3

K4.03 Maintenance of fire header pressure 3

K4.04 Personnel safety during halon and/or carbon dioxide system actuation 4

K4.05 Fire protection capability during loss of off-site power 4

K4.06 Fire suppression capability that does not rely on the displacement

of oxygen (Halon) 3

K4.07 Diesel engine protection 3

K4.08 Ability to provide alternate source of water to the reactor pressure

vessel or primary containment 4
NUREG-2104 3.8-2

3.8 Safety Function 8: Plant Service Systems

System SF8SFS Fire Protection System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Fire Protection System:

(CFR: 41.5/45.3)

K5.01 Effect of carbon dioxide on fires 3

K5.02 Effect of Halon on fires 3

K5.03 Effect of water spray on electrical components 3

K5.04 Diesel operations 3

K5.05 Heat detection 3

K5.06 Smoke detection 3

K5.07 Reactor water level 3

K5.08 Emergency generator rooms 3

K5.09 Main generator exciter 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Fire Protection 

System:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 3

K6.02 Diesel fuel transfer system 3

K6.03 Fire detection system 2

K6.04 Makeup water preparation system 2

K6.05 Instrument air system 2

ABILITY

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 3

A1.02 System flow 2

A1.03 Fire doors 3

A1.04 Fire dampers 3

A1.05 System lineups 3
3.8-3 NUREG 2104

3.8 Safety Function 8: Plant Service Systems

System SF8SFS Fire Protection System (continued)

K/A NO. ABILITY IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 System logic failure 3 3

A2.02 AC electrical power distribution system failure 3 3

A2.03 Fire protection diesel trips 3 3

A2.04 Low fire header pressure 3 3

A2.05 Inadvertent system initiation 3 3

A2.06 Failure to actuate when required 3 3

A2.07 Pump trips 3 3

A2.08 Low diesel fuel supply 3 3

A 3 Ability to monitor automatic operations of the Fire Protection System

including:

(CFR: 41.7 / 45.7)

A3.01 Fire water pump start 3

A3.02 Fire main pressure 3

A3.03 Actuation of fire detectors 3

A3.04 System initiation 3

A3.05 Fire doors 3

A3.06 Fire dampers 3

A 4 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Electric fire pump 3

A4.02 Diesel fire pump 3
NUREG-2104 3.8-4

3.8 Safety Function 8: Plant Service Systems

System SF8FHS Fuel Handling Equipment

K/A NO. KNOWLEDGE IMPORTANCE

RO SRO

K 1 Knowledge of the physical or control/protection logic relationships 

between the Fuel Handling Equipment and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Rod control and information system 3 3

K1.02 Fuel pool ventilation 3 3

K1.03 Fuel pool cooling and cleanup system 2 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

None

K 3 Knowledge of the effect that a loss or malfunction of the Fuel Handling 

Equipment will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Rod control and information system 3 3

K3.02 Fuel handling operations 3 4

K3.03 Core modifications/alterations 3 4

K 4 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 4

K4.02 Prevention of control rod movement during core alterations 3 4

K4.03 Protection against inadvertently lifting radioactive components out

of the water 3 4

K4.04 Movement of the spent fuel cask only over designated areas 3 3

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Fuel Handling Equipment:

(CFR: 41.5 / 45.3)

K5.01 Crane/hoist operation 3 3

K5.02 Fuel handling equipment interlocks 3 4

K5.03 Water as a shield against radiation 3 3

K5.04 Spent fuel pool design 3 4

K5.05 Fuel orientation 3 4

K5.06 Fuel 3 3

K5.07 Core components 3 3
3.8-5 NUREG 2104

3.8 Safety Function 8: Plant Service Systems

System SF8FHS Fuel Handling Equipment (continued)

K/A NO. KNOWLEDGE IMPORTANCE

RO SRO

K5.08 Spent fuel cask 3 3

K5.09 Reactor vessel components 3 3

K5.10 Fuel pool configuration 3 3

K5.11 Refuel floor ventilation 3 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Fuel Handling 

Equipment

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 3 3

K6.02 Rod control and information system 3 4

K6.03 Refueling platform air system 3 4

K6.04 Fuel pool water inventory 3 3

K6.05 Refuel floor ventilation 3 3

K6.06 Fuel pool cooling and cleanup system 2 2

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 3

A1.02 Refuel floor radiation levels/airborne levels 3 4

A1.03 Core reactivity level 3 4

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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

A2.02 Loss of refueling platform air system 3 4

A2.03 Loss of electrical power 3 3
NUREG-2104 3.8-6

3.8 Safety Function 8: Plant Service Systems

System SF8FHS Fuel Handling Equipment (continued)

K/A NO. ABILITY IMPORTANCE

RO SRO

A 3 Ability to monitor automatic operations of the Fuel Handling Equipment

including:

(CFR: 41.7 / 45.7)

A3.01 Crane/refuel bridge movement 3 4

A3.02 Interlock operation 3 4

A 4 Ability to manually operate and/or monitor Fuel Handling Equipment at the 

equipment location:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Neutron monitoring system 4 4

A4.02 Control rod drive system 3 4
3.8-7 NUREG 2104

3.8 Safety Function 8: Plant Service Systems

System SF8IAS Instrument Air System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Instrument Air System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Service air system 3

K1.02 High pressure nitrogen gas supply system 3

K1.03 Reactor building cooling water system 3

K1.04 Main steam system 3

K1.05 Engineered Safety Function logic and control system 2

K1.06 Control rod drive system 3

K1.07 Automated traversing in core probe system 2

K1.08 Offgas system 2

K1.09 AC electrical power distribution system 3

K1.10 Extraction system 2

K1.11 Fire protection system 2

K1.12 Neutron monitoring system 3

K1.13 Main turbine 2

K1.14 Leak detection and isolation system 2

K1.15 Instrument and control power supply system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Instrument air compressor 3

K 3 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 Service air system 3

K3.02 Main steam system 3

K3.03 Control rod drive system 3

K3.04 Automated traversing in core probe system 2

K3.05 Offgas system 2

K3.06 Extraction system 2

K3.07 Fire protection system 2

K3.08 Neutron monitoring system 3

K3.09 Main turbine 2
NUREG-2104 3.8-8

3.8 Safety Function 8: Plant Service Systems

System SF8IAS Instrument Air System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

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 3

K4.02 Cross-over to other air systems 3

K4.03 Securing of IAS upon loss of cooling water 3

K5. Knowledge of the operational implications or cause and effect

relationships as they apply to the Instrument Air System:

(CFR: 41.5 / 45.3)

K5.01 Air compressors 3

K5.02 Service air cross-connect valve 2

K5.03 Pneumatic operated devices 2

K 6 Knowledge of the effect of the following plant conditions, plant 

malfunctions or component malfunctions will have on the Instrument Air 

System:

(CFR: 41.7 / 45.7)

K6.01 Air compressors 2

K6.02 Service air cross-connect valve 3

K6.03 Engineered Safety Function logic and control system 2

K6.04 Electrical power distribution system 3

K6.05 High pressure nitrogen gas supply system 3

K6.06 Reactor building cooling water system 2

K6.07 Instrument and control power supply system 2

ABILITY

A 1 Ability to predict and / or monitor changes in parameters associated with 

operating the Instrument Air System controls including:

(CFR: 41.5 / 45.5)

None
3.8-9 NUREG 2104

3.8 Safety Function 8: Plant Service Systems

System SF8IAS Instrument Air System (continued)

K/A NO. ABILITY IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Instrument Air System and (b) based on 

those predictions, use procedures to correct, control, or mitigate the 

consequences of those abnormal operations:

(CFR: 41.5 / 45.6)

RO SRO

A2.01 Air dryer and filter malfunctions 3 3

A 3 Ability to monitor automatic operations of the Instrument Air System

including:

(CFR: 41.7 / 45.7)

A3.01 Air pressure 3

A3.02 Air temperature 2

A 4 Ability to manually operate and/or monitor the Instrument Air System in the 

control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Instrument air compressors 3
NUREG-2104 3.8-10

3.8 Safety Function 8: Plant Service Systems

System SF8RBCW Reactor Building Cooling Water System 

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Reactor Building Cooling Water System and the following 

systems:

(CFR: 41.2 to 41.9/45.7 to 45.8)

K1.01 Reactor service water system 4

K1.02 Process radiation monitoring system 3

K1.03 Reactor recirculation system 3

K1.04 Remote shutdown system 3

K1.05 Heating, ventilation, and air conditioning system emergency cooling

water system 2

K1.06 Engineered Safety Function logic and control system 3

K1.07 Makeup water purified system 2

K1.08 Suppression pool cleanup system 2

K1.09 Instrument air system 3

K1.10 Control rod drive system 3

K1.11 Leak detection and isolation system 3

K1.12 Recirculation flow control system 3

K1.13 Residual heat removal system 3

K1.14 High pressure core flooder system 3

K1.15 Reactor water cleanup system 3

K1.16 Fuel pool cooling and cleanup system 3

K1.17 Sampling system 2

K1.18 Radioactive drain transfer system 2

K1.19 Post accident monitoring system 2

K1.20 AC electrical power distribution system 3

K1.21 Emergency diesel generator system 3

K1.22 Suppression pool temperature monitoring system 3

K1.23 Drywell cooling system 3

K1.24 Heating, ventilation and air conditioning system 3

K1.25 Containment atmospheric monitoring system 3

K1.26 Service air system 2

K1.27 Turbine building cooling water system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 RBCW pumps 3

K2.02 RBCW containment isolation valves 3
3.8-11 NUREG 2104

3.8 Safety Function 8: Plant Service Systems

System SF8RBCW Reactor Building Cooling Water System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 3 Knowledge of the effect that a loss or malfunction of the Reactor Building 

Cooling Water System will have on the following:

(CFR: 41.7 / 45.6)

K3.01 Reactor service water system 3

K3.02 Reactor recirculation system 3

K3.03 Heating, ventilation, and air conditioning system emergency cooling

water system 3

K3.04 Process radiation monitoring system 3

K3.05 Suppression pool cleanup system 2

K3.06 Instrument air system 3

K3.07 Control rod drive system 3

K3.08 Recirculation flow control system 3

K3.09 Residual heat removal system 3

K3.10 High pressure core flooder system 3

K3.11 Reactor water cleanup system 3

K3.12 Fuel pool cooling and cleanup system 2

K3.13 Sampling system 2

K3.14 Radioactive drain transfer system 2

K3.15 Emergency diesel generator system 3

K3.16 Drywell cooling system 3

K3.17 Heating, ventilation and air conditioning system 3

K3.18 Containment atmospheric monitoring system 2

K3.19 Service air system 2

K3.20 Turbine building cooling water system 2

K4. Knowledge of Reactor Building Cooling Water System design feature(s) 

and or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Automatic start of standby pump 3

K4.02 Emergency diesel generator load sequencing 3

K4.03 RBCW response to LOCA signal 3

K4.04 RBCW response to high suppression pool temperature 3

K4.05 Operation from the remote shutdown panel 3

K4.06 RBCE response to a high RBCW supply temperature 3

K5. Knowledge of the operational implications or cause-effect relationships as 

they apply to the Reactor Building Cooling Water System:

(CFR: 41.5 / 45.3)

K5.01 Chemistry control 2
NUREG-2104 3.8-12

3.8 Safety Function 8: Plant Service Systems

System SF8RBCW Reactor Building Cooling Water System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Reactor Building 

Cooling Water System:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 3

K6.02 Heating, ventilation, and air conditioning system emergency cooling

water system 2

K6.03 Makeup water purified system 2

K6.04 Plant information and control system 3

K6.05 Engineered Safety Function logic and control system 3

K6.06 Suppression pool cleanup system 2

K6.07 Instrument air system 2

K6.11 Process radiation monitoring system 2

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Reactor Building Cooling Water System controls including:

(CFR: 41.5 / 45.5)

A1.01 RBCW flow rate 3

A1.02 RBCW temperature 3

A1.03 RBCW pressure 3

A1.04 Surge tank level 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Reactor Building Cooling Water 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)

RO SRO

A2.01 Loss of RBCW pump 3 4

A2.02 High/low surge tank level 3 4

A2.03 High/low RBCW temperature 3 3

A2.04 Radiation monitoring system alarm 3 3

A2.05 Loss of AC electrical power distribution system 3 3
3.8-13 NUREG 2104

3.8 Safety Function 8: Plant Service Systems

System SF8RBCW Reactor Building Cooling Water System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

A 3 Ability to monitor automatic operations of the Reactor Building Cooling 

Water System including:

(CFR: 41.7 / 45.7)

A3.01 Setpoints on instrument signal levels for normal operations,

warnings, and trips that are applicable to the RBCW 3

A3.02 System alignment due to high suppression pool temperature 4

A3.03 Emergency diesel generator load sequencing 3

A3.04 System alignment due to LOCA signal 4

A3.05 System alignment due to loss of offsite power 3

A 4 Ability to manually operate and/or monitor the Reactor Building Cooling 

Water System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 RBCW indications and controls 3
NUREG-2104 3.8-14

3.8 Safety Function 8: Plant Service Systems

System SF8RSW Reactor Service Water System 

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Reactor Service Water System and the following systems:

(CFR: 41.2 to 41.9/45.7 to 45.8)

K1.01 Remote shutdown system 3

K1.02 Engineered Safety Function logic and control system 3

K1.03 Sampling system 2

K1.04 Radioactive drain transfer system 2

K1.05 Reactor building cooling water system 4

K1.06 Instrument air system 2

K1.07 AC electrical power distribution system 3

K1.08 Chemical storage and transfer system 2

K1.09 Turbine service water system 2

K1.10 Makeup water preparation system 2

K1.11 Plant information and control system 3

K1.12 Circulating water system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Reactor service water pumps 3

K 3 Knowledge of the effect that a loss or malfunction of the Reactor Service 

Water System will have on the following:

(CFR: 41.7 / 45.6)

K3.01 Reactor building cooling water system 4

K4. Knowledge of Reactor Service Water System design feature(s) and or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Automatic start of standby pump 3

K4.02 Emergency diesel generator load sequencing 3

K4.03 Response to loss of coolant accident signal 3

K4.04 Response to a loss of offsite power signal 3

K4.05 Response to a reactor building cooling/reactor building service water heat

exchanger room high water level signal 3

K4.06 Response to high suppression pool temperature 3

K4.07 Operation from the remote shutdown panel 3
3.8-15 NUREG 2104

3.8 Safety Function 8: Plant Service Systems

System SF8RSW Reactor Service Water System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K5. Knowledge of the operational implications or cause-effect relationships as 

they apply to the Reactor Service Water System:

(CFR: 41.5 / 45.3)

K5.01 Chemistry control 2

K5.02 Cold weather operations 2

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Reactor Service 

Water System:

(CFR: 41.7 / 45.7)

K6.01 Remote shutdown system 3

K6.02 Engineered Safety Function logic and control system 3

K6.03 Sampling system 2

K6.04 Radioactive drain transfer system 2

K6.05 Instrument air system 2

K6.06 AC electrical power distribution system 3

K6.07 Chemical storage and transfer system 2

K6.08 Turbine service water system 2

K6.09 Makeup water preparation system 2

K6.10 Plant information and control system 3

K6.11 Circulating water system 2

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Reactor Service Water System controls including:

(CFR: 41.5 / 45.5)

A1.01 RSW flow rate 3

A1.02 RSW temperature 3

A1.03 RSW header supply pressure 3

A1.04 Ultimate heat sink basin level 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Reactor Service Water 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)

RO SRO

A2.01 Loss of RSW pump 3 4

A2.02 Low ultimate heat sink water level 3 4
NUREG-2104 3.8-16

3.8 Safety Function 8: Plant Service Systems

System SF8RSW Reactor Service Water System 

K/A NO. ABILITY IMPORTANCE

RO SRO

A2.03 Loss of AC electrical power distribution system 3 3

A2.04 Loss of coolant accident 4 4

A2.05 Loss of offsite power 3 4

A2.06 High water level in the RBCW/RSW heat exchanger room 3 3

A 3 Ability to monitor automatic operations of the Reactor Service Water 

System Including:

(CFR: 41.7 / 45.7)

A3.01 System alignment due to high suppression pool temperature 4

A3.02 System alignment due to LOCA signal 4

A3.03 System alignment due to loss of offsite power 3

A3.04 Emergency diesel generator load sequencing 3

A3.05 Setpoints on instrument signal levels for normal operations,

warnings, and trips that are applicable to the RSW 3

A 4 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 /45.5 to 45.8)

A4.01 RSW indications and controls 3
3.9-1 NUREG 2104

3.9 Safety Function 9: Radioactivity Release

System: SF9OG Offgas System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Offgas System and the following systems:

(CFR: 41.2 to 41.9/45.7 to 45.8)

K1.01 Feedwater and condensate air extraction system 3

K1.02 Process radiation monitoring system 3

K1.03 Radioactive waste treatment system 2

K1.04 Instrument air system 3

K1.05 Turbine building cooling water system 3

K1.06 AC electrical distribution system 2

K1.07 Sampling system 3

K1.08 Turbine building heating, ventilation, and air conditioning system 2

K1.09 Heating steam and condensate water return system 2

K1.10 Heating, ventilation, and air conditioning system normal cooling

water system 2

K1.11 Makeup water purified system 2

K1.12 Plant information and control system 3

K1.13 Hydrogen water chemistry system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Offgas system vacuum pump 2

K 3 Knowledge of the effect that a loss or malfunction of the Offgas System will 

have on the following:

(CFR: 41.5 / 45.3)

K3.01 Condenser vacuum 4

K3.02 Off-site radioactivity release 3

K3.03 Hydrogen concentration 3

K 4 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 3

K4.02 Prevention of water entering the recombiner catalyst 3

K4.03 Maintenance of sufficient oxygen gas inventory to allow for complete

hydrogen recombination 2

K4.04 The prevention of hydrogen explosions and/or fires 3

K4.05 Redundancy 3
NUREG-2104 3.9-2

3.9 Safety Function 9: Radioactivity Release

System: SF9OG Offgas System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K4.06 Decay of fission product gases to particulate daughters 3

K4.07 Maximizing charcoal bed efficiency 3

K4.08 Automatic system isolation 3

K4.09 Filtration of radioactive particulate 3

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Offgas System:

(CFR: 41.7 / 45.4)

K5.01 Heat removal mechanisms 2

K5.02 Heat addition mechanisms 2

K5.03 Hydrogen concentration measurement 3

K5.04 Oxygen concentration measurement 3

K5.05 Catalytic recombination 3

K5.06 Radioactive decay 3

K5.07 Charcoal adsorption of fission product gases 3

K5.08 Hydrogen and oxygen recombination 3

K5.09 Decontamination factors 2

K5.10 Explain the necessity of reducing relative humidity for carbon

bed filters. 3

K5.11 Elevated release point 3

K5.12 Condenser vacuum 3

K5.13 Off-site radioactivity release 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Offgas System:

(CFR: 41.7 / 45.7)

K6.01 Instrument air system 3

K6.02 Process radiation monitoring system 3

K6.03 Turbine building cooling water system 2

K6.04 Hydrogen water chemistry system 3

K6.05 AC electrical distribution system 3

K6.06 Feedwater and condensate air extraction system 3

K6.07 Fuel cladding integrity 3

K6.08 Condenser vacuum 3

K6.09 Heating steam and condensate water return system 2

K6.10 Makeup water purified system 2

K6.11 Turbine building heating, ventilation, and air conditioning system 2

K6.12 Plant information and control system 3
3.9-3 NUREG 2104

3.9 Safety Function 9: Radioactivity Release

System: SF9OG Offgas System (continued)

K/A NO. ABILITY IMPORTANCE

A 1 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

A1.02 Station radioactive release rate 3

A1.03 Preheater discharge temperature 2

A1.04 Recombiner catalyst temperature 2

A1.05 Cooler condenser discharge temperature 2

A1.06 Filter differential pressure 2

A1.07 Charcoal bed humidity 2

A1.08 System flow 3

A1.09 Charcoal bed temperature 2

A1.10 Charcoal vault temperature 2

A1.11 Offgas condenser temperatures 2

A1.12 Process radiation monitoring indications 3

A1.13 Hydrogen gas concentration 3

A1.14 Oxygen gas concentration 3

A1.15 Steam supply pressures 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 Low condenser vacuum 3 3

A2.02 Low dilution steam flow 3 3

A2.03 Offgas system high radiation 4 4

A2.04 High charcoal bed humidity 3 3

A2.05 Offgas system holdup volume explosion/ fire 4 4

A2.06 Low oxygen injection flow 3 3

A2.07 AC electrical distribution system failures 3 3

A2.08 Offgas system high flow 3 3

A2.09 Offgas system low flow 3 3

A2.10 Recombiner high temperature 3 3

A2.11 Recombiner low temperature 2 3

A2.12 Offgas filter high differential pressure 3 3

A2.13 Air intrusion 3 3

A2.14 Loss of offgas system loop seals 3 3

A2.15 Reactor power changes 3 3
NUREG-2104 3.9-4

3.9 Safety Function 9: Radioactivity Release

System: SF9OG Offgas System (continued)

K/A NO. ABILITY IMPORTANCE

A 3 Ability to monitor automatic operations of the Offgas System including:

(CFR: 41.7 / 45.7)

A3.01 System isolations 3

A3.02 System flows 3

A3.03 System temperatures 3

A3.04 Station radioactive release rate 3

A3.05 System indications and alarms 3

A3.06 System differential pressures 3

A3.07 Process radiation monitoring system indications 3

A3.08 Startup and shutdown of the offgas system 3

A 4 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Reset system isolations 3

A4.02 Offgas system controls/components 3
3.9-5 NUREG 2104

3.9 Safety Function 9: Radioactivity Release

System: SF9HVAC Plant Ventilation Systems

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Plant Ventilation Systems and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 AC electrical distribution system 3

K1.02 Secondary containment 3

K1.03 Standby gas treatment system 4

K1.04 Atmosphere control system 3

K1.05 Process radiation monitoring system 3

K1.06 Instrument air system 3

K1.07 Heating, ventilation, and air conditioning system normal cooling

water system 2

K1.08 Heating, ventilation, and air conditioning system emergency cooling

water system 3

K1.09 Reactor building cooling water system 3

K1.10 Turbine building cooling water system 2

K1.11 Engineered Safety Function logic and control system 3

K1.12 Leak detection and isolation system 3

K1.13 Radioactive drain transfer system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Reactor building supply and exhaust fans 2

K2.02 Turbine building supply and exhaust fans 2

K2.03 Radwaste building supply and exhaust fans 2

K 3 Knowledge of the effect that a loss or malfunction of the Plant Ventilation

Systems will have on the following:

(CFR: 41.5 / 45.3)

K3.01 Secondary containment temperature 3

K3.02 Reactor building temperature 3

K3.03 Reactor building pressure 3

K3.04 Secondary containment differential pressure 3

K3.05 Turbine building temperature 2

K3.06 Turbine building differential pressure 2
NUREG-2104 3.9-6

3.9 Safety Function 9: Radioactivity Release

System: SF9HVAC Plant Ventilation Systems (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 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 4

K4.02 Secondary containment isolation 4

K4.03 Automatic starting and stopping of fans 3

K4.04 Smoke removal 3

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to PLANT VENTILATION Systems:

(CFR: 41.7 / 45.4)

K5.01 Airborne contamination control 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Plant Ventilation 

Systems:

(CFR: 41.7 / 45.7)

K6.01 AC electrical distribution system 3

K6.02 Instrument air system 3

K6.03 Heating, ventilation, and air conditioning normal cooling water

system 3

K6.04 Heating, ventilation, and air conditioning emergency cooling water

system 3

K6.05 Reactor building cooling water system 3

K6.06 Turbine building cooling water system 2

K6.07 Engineered Safety Function logic and control system 3

K6.08 Leak detection and isolation system 3

ABILITY

A 1 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

A1.02 Fan differential pressure 2

A1.03 Area temperatures 2

A1.04 Secondary containment differential pressure 3
3.9-7 NUREG 2104

3.9 Safety Function 9: Radioactivity Release

System: SF9HVAC Plant Ventilation Systems (continued)

K/A NO. KNOWLEDGE IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 High drywell pressure 3 3

A2.02 Low reactor water level 3 4

A2.03 Loss of coolant accident 4 4

A2.04 High radiation 4 4

A2.05 Secondary containment differential pressure 3 4

A 3 Ability to monitor automatic operations of the Plant Ventilation Systems

including:

(CFR: 41.7 / 45.7)

A3.01 Isolation/initiation signals 4

A 4 Ability to manually operate and/or monitor the Plant Ventilation Systems in 

the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Start and stop fans 3

A4.02 Open and close dampers 2
NUREG-2104 3.9-8

3.9 Safety Function 9: Radioactivity Release

System: SF9RAD Radiation Monitoring System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Radiation Monitoring System and the following systems:

(CFR: 41.2 to 41.9/45.7 to 45.8)

K1.01 Main steam system 3

K1.02 Offgas system 3

K1.03 Plant stack 3

K1.04 Reactor building cooling water system 3

K1.05 Radioactive waste treatment system 3

K1.06 Reactor building heating, ventilation, and air conditioning system 3

K1.07 Fuel building heating, ventilation, and air conditioning system 3

K1.08 Service building heating, ventilation, and air conditioning system 2

K1.09 Leak detection and isolation system 4

K1.10 Turbine building heating, ventilation, and air conditioning system 3

K1.11 Radwaste building heating, ventilation, and air conditioning system 3

K1.12 Plant information and control system 3

K1.13 Emergency response information system 2

K1.14 Vital AC power supply system 2

K1.15 Instrument air system 2

K1.16 Engineered Safety Function logic and control system 3

K1.17 Standby gas treatment system 3

K1.18 Makeup water purified system 2

K1.19 Control building heating, ventilation, and air conditioning system 3

K 2 Knowledge of bus or electrical power supplies to the following:

(CFR: 41.7)

K2.01 Main steamline radiation monitors 3

K2.02 Offgas radiation monitoring system 3

K2.03 Plant stack radiation monitoring 3

K2.04 Radwaste liquid radiation monitoring system 2

K2.05 Reactor building heating, ventilation, and air conditioning monitors 3

K2.06 Area radiation monitors 2

K2.07 Control room ventilation monitors 2

K 3 Knowledge of the effect that a loss or malfunction of the Radiation 

Monitoring System will have on the following:

(CFR: 41.5 / 45.3)

K3.01 Station liquid effluent release monitoring 3

K3.02 Station gaseous effluent release monitoring 3

K3.03 Station area radiation monitoring 3

K3.04 Offgas system 4
3.9-9 NUREG 2104

3.9 Safety Function 9: Radioactivity Release

System: SF9RAD Radiation Monitoring System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K3.05 Reactor building heating, ventilation, and air conditioning 3

K3.06 Drywell sump liquid discharge 2

K3.07 Radwaste building ventilation 3

K3.08 Control building heating, ventilation, and air conditioning system 3

K 4 Knowledge of Radiation Monitoring System design feature(s) and/or 

interlocks which provide for the following:

(CFR: 41.7)

K4.01 Redundancy 3

K4.02 Automatic actions to contain the radioactive release

in the event that the predetermined release rates are exceeded 4

K4.03 Fail safe tripping of process radiation monitoring

logic during conditions of instrument failure 4

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Radiation Monitoring System:

(CFR: 41.7 / 45.4)

K5.01 Hydrogen injection operation's effect on process radiation indications 3

K5.02 Drywell sump liquid discharge 2

K5.03 Turbine gland seal condenser exhaust 2

K5.04 Fuel handling area ventilation exhaust 3

K5.05 Drywell 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Radiation 

Monitoring System:

(CFR: 41.7 / 45.7)

K6.01 Vital AC power 3

K6.02 Plant information and control system 2

K6.03 Leak detection and isolation system 2

ABILITY

A 1 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 Alarms and indications associated with normal operations 3

A1.02 Alarms and indications associated with surveillance testing 3
NUREG-2104 3.9-10

3.9 Safety Function 9: Radioactivity Release

System: SF9RAD Radiation Monitoring System (continued)

K/A NO. ABILITY IMPORTANCE

A 2 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)

RO SRO

A2.01 Fuel element failure 4 4

A2.02 AC electrical failure 3 3

A2.03 Downscale trips 3 3

A2.04 Offgas system failure 3 3

A2.05 Low fuel pool level 3 3

A2.06 Loss of coolant accident 4 4

A2.07 Leakage and/or breaks from contaminated systems to atmosphere

or to other process systems 3 4

A2.08 Refuel floor handling accidents/operations 3 4

A2.09 Low reactor water level during refueling operations 3 4

A 3 Ability to monitor automatic operations of the Radiation Monitoring System

including:

(CFR: 41.7 / 45.7)

A3.01 Offgas system isolation indications 4

A3.02 Liquid radwaste isolation indications 3

A3.03 Radwaste handing interlocks 2

A3.04 Drywell LCW or HCW sump isolation indications 3

A3.05 Ventilation system isolation indications 3

A3.06 Display indications 3

A3.07 Meter indications 3

A3.08 Containment isolation indications 4

A3.09 Lights and alarms 3

A 4 Ability to manually operate and/or monitor Radiation Monitoring System in 

the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4. 01 Manually trip process radiation monitor logic 3
3.9-11 NUREG 2104

3.9 Safety Function 9: Radioactivity Release

System: SF9RW Radwaste System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Radwaste System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Makeup water condensate system 2

K1.02 Instrument air system 2

K1.03 Service air system 2

K1.04 AC electrical power distribution system 3

K1.05 Instrument and control power supply system 2

K1.06 Reactor water cleanup system 3

K1.07 Fuel pool cooling and cleanup system 3

K1.08 Residual heat removal system 2

K1.09 Turbine building service water system 2

K1.10 Process radiation monitoring system 3

K1.11 Condensate storage and transfer system 2

K1.11 Makeup water purified system 2

K1.12 Radioactive drain transfer system 2

K1.13 Solid waste system 2

K1.14 Make-up water condensate system 2

K1.15 Reactor building cooling water system 2

K1.16 Radwaste building heating, ventilation, and air conditioning system 2

K1.17 Mobile liquid radwaste processing system 2

K1.18 Mobile solid radwaste processing system 2

K1.19 Low conductivity waste system 3

K1.20 High conductivity waste system 3

K1.21 Hot shower and storm drain system 2

K1.22 Spent sludge system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

None

K 3 Knowledge of the effect that a loss or malfunction of the Radwaste System

will have on the following:

(CFR: 41.5 / 45.3)

K3.01 RWCU system 2

K3.02 Makeup water condensate system 2

K3.03 Low and high conductivity waste sumps 3

K3.04 Fuel pool cooling and cleanup system 2

K3.05 Residual heat removal system 2

K3.06 Radioactive drain transfer system 2
NUREG-2104 3.9-12

3.9 Safety Function 9: Radioactivity Release

System: SF9RW Radwaste System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 Knowledge of the Radwaste System design feature(s) and/or interlocks 

which provide for the following:

(CFR: 41.7)

None

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to the Radwaste System:

(CFR: 41.5 / 45.3)

None

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Radwaste 

System:

(CFR: 41.7)

K6.01 Instrument air system 2

K6.02 Service air system 2

K6.03 AC electrical power distribution system 3

K6.04 Instrument and control power supply system 2

K6.05 Radwaste building heating, ventilation, and air conditioning 2

K6.06 Process radiation monitoring system 3

K6.07 Makeup water purified system 2

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Radwaste System controls including:

(CFR: 41.5 / 45.5)

A1.01 Radiation level 3

A1.02 Off-site radioactivity release 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Radwaste 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)

RO SRO

A2.01 System rupture 3 3

A2.02 High turbidity water 2 3
3.9-13 NUREG 2104

3.9 Safety Function 9: Radioactivity Release

System: SF9RW Radwaste System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

A 3 Ability to monitor automatic operations of the Radwaste System including:

(CFR: 41.7 / 45.7)

None

A 4 Ability to manually operate and/or monitor the Radwaste System in the 

control room:

(CFR: 41.7 / 45.5 to 45.8)

None
NUREG-2104 3.9-14

3.9 Safety Function 9: Radioactivity Release

System: SF9RPV Reactor Vessel Internals

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Reactor Vessel Internals and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Main steam system 3

K1.02 Reactor recirculation system 3

K1.03 Feedwater system 3

K1.04 Residual heat removal system 3

K1.05 High pressure core flooder system 3

K1.06 Reactor core isolation cooling system 3

K1.07 Control rod drive system 3

K1.08 Fine motion control rod drive mechanism 3

K1.09 Standby liquid control system 3

K1.10 Reactor water cleanup system 3

K1.11 Automatic depressurization system 3

K1.12 Loose parts monitoring system 2

K1.13 Automated Traversing In-core Probe system 3

K1.14 Neutron monitoring system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

None

K 3 Knowledge of the effect that a loss or malfunction of the Reactor Vessel 

Internals will have on the following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level 3

K3.02 Reactor pressure 3

K3.03 Reactor power 3

K3.04 Plant radiation levels 3

K3.05 Off-site radioactive release 3

K3.06 Leak detection and isolation system 3

K3.07 Nuclear Boiler Instrumentation 3

K 4 Knowledge of Reactor Vessel Internals design feature(s) and/or interlocks 

which provide for the following:

(CFR: 41.7)

K4.01 Separation of fluid flow paths within the vessel 3

K4.02 Core orificing 3

K4.03 Moisture removal from generated steam 3

K4.04 Natural circulation 3
3.9-15 NUREG 2104

3.9 Safety Function 9: Radioactivity Release

System: SF9RPV Reactor Vessel Internals (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Reactor Vessel Internals:

(CFR: 41.5 / 45.3)

None

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Reactor Vessel 

Internals:

(CFR: 41.7 / 45.7)

K6.01 Control rod drive system 3

K6.02 Fine motion control rod drive mechanism 3

K6.03 Reactor recirculation system 3

K6.04 Feedwater system 3

K6.05 Standby Liquid Control system 3

K6.06 Safety/relief valves 3

K6.07 Reactor water cleanup system 3

K6.08 Nuclear Boiler Instrumentation 3

K6.09 High pressure core flooder system 3

K6.10 Residual heat removal system 3

K6.11 Reactor core isolation cooling system 3

K6.12 Automatic depressurization system 3

K6.13 Loose parts monitoring 2

K6.14 Automated traversing in-core probe system 3

K6.15 Neutron monitoring system 3

K6.16 Main steam system 3

ABILITY

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Reactor Vessel Internals controls including:

(CFR: 41.5 / 45.5)

None
NUREG-2104 3.9-16

3.9 Safety Function 9: Radioactivity Release

System: SF9RPV Reactor Vessel Internals (continued)

K/A NO. ABILITY IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 LOCA 4 4

A2.02 Overpressurization transient 4 4

A2.03 Control rod drop accident 4 4

A2.04 Excessive heatup/cooldown rate 4 4

A2.05 Exceeding thermal limits 4 4

A2.06 Exceeding safety limits 4 4

A 3 Ability to monitor automatic operations of the Reactor Vessel Internals

including:

(CFR: 41.7 / 45.7)

None

A 4 Ability to manually operate and/or monitor the Reactor Vessel Internals in 

the control room:

(CFR: 41.7 / 45.5 to 45.8)

None
3.9-17 NUREG 2104

3.9 Safety Function 9: Radioactivity Release

System: SF9FPC Fuel Pool Cooling and Cleanup System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Fuel Pool Cooling and Cleanup System and the following 

systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Residual heat removal system 3

K1.02 Makeup water condensate system 2

K1.03 Sampling system 2

K1.04 Instrument air system 2

K1.05 AC electrical power distribution system 2

K1.06 Reactor building cooling water system 3

K1.07 Low conductivity waste system 2

K1.08 Radwaste drain transfer system 3

K1.09 Suppression pool cleanup system 2

K1.10 Reactor water cleanup system 2

K1.11 Direct current power supply system 2

K1.12 Reactor pressure vessel instrumentation system 2

K1.13 Plant information and control system 3

K1.14 Spent sludge system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Fuel pool cooling and cleanup pumps 2

K 3 Knowledge of the effect that a loss or malfunction of the Fuel Pool Cooling 

and Cleanup System will have on the following:

(CFR: 41.7 /45.6)

K3.01 Fuel pool temperature 3

K3.02 Fuel pool water level 3

K3.03 Fuel pool water clarity 3

K3.04 Fuel pool water chemistry 2

K3.05 Fuel pool water fission product concentration 3

K3.06 Area radiation levels 3

K3.07 Suppression pool chemistry 2

K3.08 Refueling operations 3
NUREG-2104 3.9-18

3.9 Safety Function 9: Radioactivity Release

System: SF9FPC Fuel Pool Cooling and Cleanup System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K 4 Knowledge of Fuel Pool Cooling and Cleanup System design feature(s) 

and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Redundancy 2

K4.02 Pool clarity 2

K4.03 Maintenance of adequate pool temperature 3

K4.04 Overpressure protection for fuel pool cooling system filter 2

K4.05 Net positive suction head requirements for fuel pool cooling pumps 2

K4.06 Maintenance of adequate pool level 3

K4.07 Supplemental heat removal capability 3

K4.08 Pool cooling during loss of coolant accident 3

K4.09 Maintenance of filter/demineralizer precoat during low flow conditions 2

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Fuel Pool Cooling and Cleanup System:

(CFR: 41.5 / 45.3)

K5.01 Spent fuel decay heat generation 3

K5.02 Mechanical filtration operation 2

K5.03 Maximum normal heat load 3

K5.04 Maximum (abnormal) heat load 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Fuel Pool 

Cooling and Cleanup System:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 3

K6.02 Residual heat removal system 2

K6.03 Makeup water condensate system 3

K6.04 Reactor building cooling water system 3

K6.05 Instrument air system 2

K6.06 Radwaste drain transfer system 2

K6.07 Reactor well seal failure 3

K6.08 Direct current power supply system 2

K6.09 Reactor pressure vessel instrumentation system 2

K6.10 Plant information and control system 3

K6.11 Reactor building heating, ventilation, and air conditioning system 2

K6.12 Low conductivity waste system 2

K6.13 Suppression pool cleanup system 2
3.9-19 NUREG 2104

3.9 Safety Function 9: Radioactivity Release

System: SF9FPC Fuel Pool Cooling and Cleanup System (continued)

K/A NO. ABILITY IMPORTANCE

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

operating the Fuel Pool Cooling and Cleanup System controls including:

(CFR: 41.5 / 45.5)

A1.01 Surge tank level 3

A1.02 Pool level 3

A1.03 Pool temperature 3

A1.04 Pump discharge pressure 2

A1.05 Filter/demineralizer differential pressure 2

A1.06 System flow 3

A1.07 System temperature 3

A1.08 Pool chemistry 2

A1.09 Pool clarity 2

A1.10 Pool activity levels 2

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Fuel Pool Cooling and 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)

RO SRO

A2.01 High pool level 3 3

A2.02 Low pool level 3 3

A2.03 Low surge tank level/high level 3 3

A2.04 Pump trip 3 3

A2.05 High fuel pool temperature 3 3

A2.06 Reactor building cooling water failure 3 3

A2.07 AC electrical power distribution system failures 3 3

A2.08 Refueling bellows seal high flow 3 3

A2.09 High spent fuel pool gate drain flow 3 3

A2.10 High filter/demineralizer differential pressure 2 2

A2.11 Low filter/demineralizer differential pressure 2 2

A2.12 Low system flow 2 2

A2.13 Low pump suction pressure 2 2

A2.14 Low pool clarity 3 3

A2.15 Inadequate system/pool chemistry 3 3

A 3 Ability to monitor automatic operations of the Fuel Pool Cooling and 

Cleanup System including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation 2

A3.02 Pump trip(s) 3

A3.03 System indications and alarms 3
NUREG-2104 3.9-20

3.9 Safety Function 9: Radioactivity Release

System: SF9FPC Fuel Pool Cooling and Cleanup System (continued)

K/A NO. ABILITY IMPORTANCE

A 4 Ability to manually operate and/or monitor the Fuel Pool Cooling and 

Cleanup System in the control room:

CFR: 41.7 / 45.5 to 45.8)

A4.01 Fuel pool cooling and cleanup system pumps 3

A4.02 Fuel pool cooling and cleanup system valves 3
3.9-21 NUREG 2104

3.9 Safety Function 9: Radioactivity Release

System: SF9SGTS Standby Gas Treatment System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Standby Gas Treatment System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Reactor building heating, ventilation, and air conditioning system 3

K1.02 Plant ventilation stack 3

K1.03 Process radiation monitoring system 3

K1.04 Atmosphere control system 3

K1.05 Leak detection and isolation system 3

K1.06 Fire protection system 2

K1.07 Makeup water purified system 2

K1.08 Radioactive drain transfer system 2

K1.09 Plumbing and drainage system 2

K1.10 Engineered Safety Function logic and control system 3

K1.11 AC electrical power distribution system 3

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Standby gas treatment process and cooling fans 2

K2.02 Standby gas treatment motor operated inlet/outlet flow damper 2

K2.03 Standby gas treatment initiation logic 2

K2.04 Standby gas treatment filter train heaters 2

K2.05 Standby gas treatment inlet and outlet space heaters 2

K 3 Knowledge of the effect that a loss or malfunction of the Standby Gas 

Treatment System will have on the following:

(CFR: 41.7 /45.6)

K3.01 Secondary containment differential pressure 3

K3.02 Off-site release rate 4

K3.03 Primary containment pressure 3

K3.04 Secondary containment pressure 3

K3.05 Secondary containment radiation/contamination levels 3

K3.06 Atmosphere control system 3

K 4 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 4

K4.02 Charcoal bed decay heat removal 3

K4.03 Moisture removal 3

K4.04 Radioactive particulate filtration 3
NUREG-2104 3.9-22

3.9 Safety Function 9: Radioactivity Release

System: SF9SGTS Standby Gas Treatment System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K4.05 Fission product iodine removal 3

K4.06 Charcoal bed retention 2

K4.07 Control charcoal bed relative humidity 2

K 5 Knowledge of the operational implications or cause and effect

relationships as they apply to Standby Gas Treatment System:

(CFR: 41.5 / 45.3)

K5.01 Heat removal mechanisms 2

K5.02 Primary containment 3

K5.03 Secondary containment 3

K5.04 Wetwell 3

K5.05 Primary containment pressure 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Standby Gas 

Treatment System:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 3

K6.02 Process radiation monitoring 3

K6.03 Drywell high pressure 3

K6.04 Leak detection and isolation system 3

K6.05 Fire protection system 2

K6.06 Engineered Safety Function logic and control system 3

K6.07 Radioactive drain transfer system 2

K6.08 Makeup water purified system 2

K6.09 Plant ventilation stack 3

K6.10 Reactor building heating, ventilation, and air conditioning system 3

ABILITY

A 1 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 3

A1.02 Drywell/wetwell pressure 3

A1.03 Off-site radioactive release 3

A1.04 Secondary containment differential pressure 3

A1.05 Standby gas treatment system filter train temperature 3
3.9-23 NUREG 2104

3.9 Safety Function 9: Radioactivity Release

System: SF9SGTS Standby Gas Treatment System (continued)

K/A NO. ABILITY IMPORTANCE

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations 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)

RO SRO

A2.01 Low system flow 3 3

A2.02 High system flow 3 3

A2.03 High filter train temperature 3 3

A2.04 High filter train moisture content 3 3

A2.05 Standby gas treatment process fan trips 3 3

A2.06 Motor operated inlet/outlet flow damper closures 3 3

A2.07 AC electrical power distribution system failure 3 3

A2.08 Low reactor water level 3 3

A2.09 High drywell/wetwell pressure 3 3

A2.10 High refuel floor ventilation exhaust radiation 3 3

A2.11 High secondary containment ventilation exhaust radiation 3 4

A1.12 Refueling floor ventilation exhaust radiation 3 4

A2.13 High charcoal bed temperature 2 2

A2.14 Filter train heater trips 2 2

A 3 Ability to monitor automatic operations of the Standby Gas Treatment

System including:

(CFR: 41.7 / 45.7)

A3.01 System flow 3

A3.02 Standby gas treatment system process fan start 3

A3.03 Standby gas treatment system motor operated damper operation 3

A3.04 System temperature/humidity 3

A3.05 Secondary containment differential pressure 3

A3.06 Standby gas treatment cooling fans 3

A 4 Ability to manually operate and/or monitor the Standby Gas Treatment

System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4. 01 Standby gas treatment system fans 3

A4. 02 Standby gas treatment system motor operated dampers 3
NUREG-2104 3.9-24

3.9 Safety Function 9: Radioactivity Release

System: SF9CRHVAC Control Room Habitability Area Heating, Ventilation, and Air 

Conditioning System

K/A NO. KNOWLEDGE IMPORTANCE

K 1 Knowledge of the physical or control/protection logic relationships 

between the Control Room Habitability Area Heating, Ventilation, and Air 

Conditioning System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Process radiation monitoring system 3

K1.02 Heating, ventilation, and air conditioning emergency cooling

water system 3

K1.03 Fire protection system 3

K1.04 Makeup water purified system 2

K1.05 Engineered Safety Function logic and control system 3

K1.06 Non-radioactive drain transfer system 2

K1.07 AC electrical power distribution system 3

K1.08 Vital AC power supply system 3

K1.09 Direct current power supply system 2

K 2 Knowledge of bus or division power supplies to the following:

(CFR: 41.7)

K2.01 Control room habitability area heating, ventilation, and air

conditioning supply fans 2

K2.02 Control room habitability area heating, ventilation, and air

conditioning exhaust fans 2

K2.03 Control room habitability area heating, ventilation, and air

conditioning emergency filtration unit supply

fans 2

K2.04 Control room habitability area heating, ventilation, and air

conditioning motor operated normal supply

dampers 2

K2.05 Control room habitability area heating, ventilation, and air

conditioning emergency filtration unit air

supply dampers 2

K 3 Knowledge of the effect that a loss or malfunction of the Control Room 

Habitability Area Heating, Ventilation, and Air Conditioning System will 

have on the following:

(CFR: 41.7 /45.6)

K3.01 Control room habitability 4

K3.02 Control room temperature 3

K3.03 Control room pressure 3
3.9-25 NUREG 2104

3.9 Safety Function 9: Radioactivity Release

System: SF9CRHVAC Control Room Habitability Area Heating, Ventilation, and Air 

Conditioning System (continued)

K/A NO. KNOWLEDGE IMPORTANCE

K3.04 Control room habitability area heating, ventilation, and air

conditioning humidity 2

K3.05 Control room habitability area heating, ventilation, and air

conditioning radioactivity 3

K 4 Knowledge of Control Room Habitability Area Heating, Ventilation, and Air 

Conditioning System design feature(s) and/or interlocks which provide for 

the following:

(CFR: 41.7)

K4.01 System initiations/reconfiguration 3

K4.02 Control room temperature 2

K4.03 Smoke removal mode 3

K 5 Knowledge of the operational implications or cause-effect relationships as 

they apply to Control Room Habitability Area Heating, Ventilation, and Air 

Conditioning System:

(CFR: 41.5 / 45.3)

K5.01 Airborne contamination (e.g., radiological, toxic gas, smoke) control 3

K 6 Knowledge of the effect of the following plant conditions, system 

malfunctions or component malfunctions will have on the Control Room

Habitability Area Heating, Ventilation, and Air Conditioning System:

(CFR: 41.7 / 45.7)

K6.01 AC electrical power distribution system 3

K6.02 Vital AC power supply system 2

K6.03 Direct current power supply system 2

K6.04 Heating, ventilation, and air conditioning emergency cooling

water system 3

K6.05 Fire protection system 3

K6.06 Process radiation monitoring system 3

K6.07 Makeup water purified system 2

K6.08 Engineered Safety Function logic and control system 3

K6.09 Non-radioactive drain transfer system 2
NUREG-2104 3.9-26

3.9 Safety Function 9: Radioactivity Release

System: SF9CRHVAC Control Room Habitability Area Heating, Ventilation, and Air 

Conditioning System (continued)

K/A NO. ABILITY IMPORTANCE

A 1 Ability to predict and/or monitor changes in parameters associated with 

operating the Control Room Habitability Area Heating, Ventilation, and Air 

Conditioning System controls including:

(CFR: 41.5 / 45.5)

A1.01 Filter differential pressure 2

A1.02 Fan differential pressure 2

A1.03 Area temperatures 3

A1.04 Control room pressure 3

A1.05 Control room humidity 2

A1.05 Airborne radioactivity levels 3

A 2 Ability to (a) predict the impacts of the following system/component 

malfunctions or operations on the Control Room Habitability Area Heating, 

Ventilation, and Air Conditioning 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)

RO SRO

A2.01 Initiation/reconfiguration 3 3

A2.02 Extreme environmental conditions 3 3

A2.03 Initiation/reconfiguration failure 3 4

A2.04 Initiation/failure of fire protection system 3 3

A 3 Ability to monitor automatic operations of the Control Room Habitability 

Area Heating, Ventilation, and Air Conditioning System including:

(CFR: 41.7 / 45.7)

A3.01 Initiation/reconfiguration 3

A3.02 Initiation/failure of fire protection system 3

A 4 Ability to manually operate and/or monitor the Control Room Habitability 

Area Heating, Ventilation, and Air Conditioning System in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 Initiate/reset system 3

A4.02 Control room habitability area heating, ventilation, and air

conditioning supply and exhaust fans 3

A4.03 Control room habitability area heating, ventilation, and air

conditioning emergency filtration unit supply

fans 3

A4.04 Reposition dampers 3
4.1-1 NUREG-2104

4.0 EMERGENCY PLANT AND ABNORMAL PLANT EVOLUTIONS

4.1 Emergency Plant Evolutions

EPE: EPE1001 High Drywell Pressure

K/A NO. KNOWLEDGE IMPORTANCE

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 Primary containment integrity 4

EK2. Knowledge of the interrelations between High Drywell Pressure and the 

following:

(CFR: 41.7 / 45.8)

EK2.01 High pressure core flooder system 4

EK2.02 Reactor core isolation cooling 4

EK2.03 Residual heat removal system/Low pressure flooder mode 4

EK2.04 Reactor trip and isolation system 4

EK2.05 Emergency diesel generators 4

EK2.06 Leak detection and isolation system 4

EK2.07 Automatic depressurization system 4

EK2.08 Drywell spray 4

EK2.09 Suppression pool cooling 4

EK2.10 Wetwell spray 4

EK2.11 Safety parameter display system 3

EK2.12 Drywell cooling system 3

EK2.13 Condensate system 4

EK2.14 Containment overpressure protection system 3

EK2.16 Atmosphere control system 3

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 4

EK3.02 Wetwell spray operation 4

EK3.03 Containment overpressure protection operation 4

EK3.04 Emergency depressurization 4

EK3.05 Reactor scram 4

EK3.06 Drywell venting 4
NUREG-2104 4.1-2

4.1 Emergency Plant Evolutions

EPE: EPE1001 High Drywell Pressure (continued)

K/A NO. ABILITY IMPORTANCE

EA1. Ability to operate and/or monitor the following as they apply to High 

Drywell Pressure:

(CFR: 41.7 / 45.6)

EA1.01 High pressure core flooder system 4

EA1.02 Reactor core isolation cooling system 4

EA1.03 Residual heat removal system/Low pressure flooder mode 4

EA1.04 Reactor trip and isolation system 4

EA1.05 Emergency diesel generators 4

EA1.06 Leak detection and isolation system 4

EA1.07 Automatic depressurization system 4

EA1.08 Drywell spray 4

EA1.09 Wetwell spray 4

EA1.10 Suppression pool cooling 4

EA1.11 Drywell cooling system 3

EA1.12 Containment atmospheric monitoring 4

EA1.13 Wetwell to drywell vacuum relief breakers 3

EA1.14 Atmosphere control system 3

EA1.15 Containment overpressure protection system 3

EA2. Ability to determine and/or interpret the following as they apply to High 

Drywell Pressure:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

EA2.01 Drywell pressure 4 4

EA2.02 Drywell temperature 4 4

EA2.03 Suppression pool level 4 4

EA2.04 Wetwell pressure 4 4

EA2.05 Wetwell air-space temperature 4 4

EA2.04 Suppression pool temperature 4 4

EA2.05 Primary containment radiation levels 4 4
4.1-3 NUREG-2104

4.1 Emergency Plant Evolutions

EPE: EPE1002 High Reactor Pressure

K/A NO. KNOWLEDGE IMPORTANCE

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 4

EK1.02 Reactor pressure vessel integrity 4

EK1.03 Safety/relief valve tailpipe temperature/pressure relationships 4

EK1.04 Decay heat generation 4

EK1.05 Exceeding safety limits 4

EK1.06 Pressure effects on reactor pressure vessel water level 4

EK2. Knowledge of the interrelations between High Reactor Pressure and the 

following:

(CFR: 41.7 / 45.8)

EK2.01 Reactor trip and isolation system 4

EK2.02 Alternate reactor shutdown system 4

EK2.03 Fine motion control rod motor drive insertion function (FM Control

Rod Drive run-in) 4

EK2.04 Recirculation system 4

EK2.05 Safety/relief valves 4

EK2.06 Reactor core isolation cooling system 4

EK2.07 Steam bypass and pressure control system 4

EK2.08 Reactor power 4

EK2.09 Safety parameter display system 3

EK2.10 Reactor pressure vessel water level 4

EK2.11 ESF logic and control system 3

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

EK3.02 Reactor internal pump trip 4

EK3.03 Alternate rod insertion 4

EK3.04 Standby liquid control system initiation signal 3

EK3.05 Steam bypass and pressure control system 4

EK3.06 Feedwater control system operation (feedwater pump speed runback) 4

EK3.07 Fine motion control rod motor driven insertion function (FM Control

Rod Drive run-in) 4

EK3.08 Automatic reactor scram 4
NUREG-2104 4.1-4

4.1 Emergency Plant Evolutions

EPE: EPE1002 High Reactor Pressure (continued)

K/A NO. ABILITY IMPORTANCE

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 3

EA1.02 Steam bypass and pressure control system 4

EA1.03 Safety/relief valves 4

EA1.04 Reactor core isolation cooling system 4

EA1.05 Alternate rod insertion 4

EA1.06 Standby liquid control system 3

EA1.07 Reactor trip and isolation system 4

EA1.08 Feedwater control system (feedwater pump speed runback) 4

EA1.09 Fine motion control rod motor driven insertion function (FM Control

Rod Drive run-in) 4

EA1.10 Reactor internal pump trip 4

EA1.11 Reactor water cleanup system 3

EA2. Ability to determine and/or interpret the following as they apply to High 

Reactor Pressure:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

EA2.01 Reactor pressure vessel pressure 4 4

EA2.02 Reactor power 4 4

EA2.03 Suppression pool temperature 4 4

EA2.04 Suppression pool level 4 4

EA2.05 Reactor pressure vessel water level 4 4
4.1-5 NUREG-2104

4.1 Emergency Plant Evolutions

EPE: EPE1003 Suppression Pool High Water Temperature

K/A NO. KNOWLEDGE IMPORTANCE

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 net positive suction head 3

EK1.02 Steam condensation 4

EK1.03 Primary containment integrity 3

EK2. Knowledge of the interrelations between Suppression Pool High Water 

Temperature and the following:

(CFR: 41.7 / 45.8)

EK2.01 Suppression pool cooling 4

EK2.02 Wetwell spray 4

EK2.03 Wetwell pressure 3

EK2.04 Safety parameter display system 3

EK2.05 Suppression pool level 4

EK2.06 Suppression pool temperature monitoring system 4

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 reactor pressure vessel depressurization 4

EK3.02 Suppression pool cooling 4

EK3.03 Wetwell spray 4

EK3.04 Standby liquid control system injection 4

EK3.05 Automatic reactor scram 4

EK3.06 Reactor building cooling water system automatic initiation 4

EK3.07 Reactor service water system automatic initiation 4

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

EA1.03 Suppression pool temperature monitoring 4

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)

RO SRO

EA2.01 Suppression pool water temperature. 4 4

EA2.02 Suppression pool level 4 4

EA2.03 Reactor pressure vessel pressure 4 4
NUREG-2104 4.1-6

4.1 Emergency Plant Evolutions

EPE: EPE1004 High Drywell Temperature

K/A NO. KNOWLEDGE IMPORTANCE

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 pressure vessel water level measurement 4

EK1.02 Equipment environmental qualification 3

EK1.03 Primary containment integrity 3

EK2. Knowledge of the interrelations between High Drywell Temperature and the 

following:

(CFR: 41.7 / 45.8)

EK2.01 Drywell spray 4

EK2.02 Components internal to the drywell 3

EK2.03 Reactor pressure vessel water level indication 4

EK2.04 Drywell cooling system 4

EK2.05 Safety Parameter Display System 2

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. 4

EK3.02 Reactor pressure vessel flooding 4

EK3.03 Drywell spray operation 4

EK3.04 Increased drywell cooling 4

EK3.05 Reactor scram 4

EK3.06 Lower drywell flooder actuation 3

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 4

EA1.02 Drywell cooling system 4

EA1.03 Drywell pressure 4

EA2. Ability to determine and/or interpret the following as they apply to High 

Drywell Temperature:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

EA2.01 Drywell temperature 4 4

EA2.02 Reactor pressure vessel pressure 4 4

EA2.03 Reactor pressure vessel water level 4 4

EA2.04 Drywell pressure 4 4

EA2.05 Wetwell pressure... 4 4

EA2.06 Wetwell air space temperature 3 4
4.1-7 NUREG-2104

4.1 Emergency Plant Evolutions

EPE: EPE1005 High Suppression Pool Water Level

K/A NO. KNOWLEDGE IMPORTANCE

EK1. Knowledge of the operational implications as they apply to High 

Suppression Pool Water Level:

(CFR: 41.8 to 41.10)

EK1.01 Containment integrity 3

EK2.02 Termination of injection sources external to containment 3

EK2. Knowledge of the interrelations between High Suppression Pool Water 

Level and the following:

(CFR: 41.7 / 45.8)

EK2.01 Residual heat removal system 3

EK2.02 High pressure core flooder system 3

EK2.03 Wetwell to drywell vacuum breakers 3

EK2.04 Safety relief valves and respective discharge piping 3

EK2.05 Drywell water level 3

EK206 Reactor core isolation cooling system 3

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 4

EK3.02 Lowering suppression pool water level 4

EK3.03 Reactor scram 3

ABILITY

EA1. Ability to operate and/or monitor the following as they apply to High 

Suppression Pool Water Level:

(CFR: 41.7 / 45.6)

EK1.01 High pressure core flooder system 3

EA102 Residual heat removal system 3

EA1.03 Reactor core isolation cooling system 3

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)

RO SRO

EA2.01 Suppression pool water level 4 4

EA2.02 Reactor pressure 4 4

EA2.03 Drywell water level 3 4
NUREG-2104 4.1-8

4.1 Emergency Plant Evolutions

EPE: EPE1006 Low Suppression Pool Water Level

K/A NO. KNOWLEDGE IMPORTANCE

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 4

EK1.02 Pump net positive suction head 4

EK1.03 Heat capacity 4

EK2. Knowledge of the interrelations between Low Suppression Pool Water 

Level and the following:

(CFR: 41.7 / 45.8)

EK2.01 Reactor core isolation cooling system 4

EK2.02 Residual heat removal system/low pressure flooder mode 4

EK2.03 High pressure core flooder system 4

EK2.04 Horizontal vent submergence 4

EK2.05 SRV discharge submergence 4

EK2.06 Safety Parameter Display System 3

EK2.07 Suppression pool temperature detector submergence 3

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 4

EK3.02 Reactor core isolation cooling system 4

EK3.03 High pressure core flooder system 4

EK3.04 Reactor scram 4

EK3.05 net positive suction head considerations for Emergency Core

Cooling System pumps 4

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 Emergency Core Cooling System systems (net positive suction

head considerations) 4

EA1.02 Reactor core isolation cooling system 4

EA1.03 High pressure core flooder system 4

EA1.04 Suppression pool cleanup system 2

EA1.05 Residual heat removal system 4
4.1-9 NUREG-2104

4.1 Emergency Plant Evolutions

EPE: EPE1006 Low Suppression Pool Water Level

K/A NO. ABILITY IMPORTANCE

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)

RO SRO

EA2.01 Suppression pool level 4 4

EA2.02 Suppression pool temperature 4 4

EA2.03 Reactor pressure 4 4

EA2.04 Drywell/ suppression chamber differential pressure 4 4
NUREG-2104 4.1-10

4.1 Emergency Plant Evolutions

EPE: EPE1007 Reactor Low Water Level

K/A NO. KNOWLEDGE IMPORTANCE

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

EK1.02 Natural circulation 4

EK1.02 Water level effects on reactor power 4

EK2. Knowledge of the interrelations between Reactor Low Water Level and the 

following:

(CFR: 41.7 / 45.8)

EK2.01 Reactor pressure vessel water level indication 4

EK2.02 Reactor pressure vessel pressure. 4

EK2.03 Reactor core isolation cooling system 4

EK2.04 Residual heat removal system: Low pressure flooder mode 4

EK2.05 High pressure core flooder system 4

EK2.06 Automatic depressurization system 4

EK2.07 Recirculation system 3

EK2.08 Reactor trip and isolation system 4

EK2.09 Leak detection and isolation system 4

EK2.10 Alternate rod insertion circuitry 4

EK2.11 AC electrical power distribution system 3

EK2.12 Feedwater control system 4

EK2.13 Residual heat removal system: shutdown cooling mode 4

EK2.14 Standby liquid control system 4

EK2.15 ESF logic and control system 3

EK2.16 Safety parameter display system 2

EK2.17 Fire protection system 4

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 initiation 4

EK3.02 Core coverage 4

EK3.03 Steam cooling 4

EK3.04 Emergency depressurization 4

EK3.05 Reactor scram 4

EK3.06 Reactor core isolation cooling initiation 4

EK3.07 High pressure core flooder initiation 4

EK3.08 Residual heat removal system: Low pressure flooder mode initiation 4

EK3.09 Alternate rod insertion initiation 4
4.1-11 NUREG-2104

4.1 Emergency Plant Evolutions

EPE: EPE1007 Reactor Low Water Level (continued)

K/A NO. ABILITY IMPORTANCE

EA1. Ability to operate and/or monitor the following as they apply to Reactor 

Low Water Level:

(CFR: 41.7 / 45.6)

EA1.01 Residual heat removal system: Low pressure flooder mode 4

EK2.02 High pressure core flooder systems 4

EA1.03 Reactor core isolation system 4

EA1.04 Automatic depressurization system 4

EA1.05 Safety/relief valves 4

EA1.06 Alternate injection subsystems 4

EA1.07 Control rod drive system 4

EA1.08 Condensate system 4

EA1.09 Feedwater system 4

EA1.10 Feedwater control system 4

EA1.11 Fire protection system $

EA2. Ability to determine and/or interpret the following as they apply to Reactor 

Low Water Level:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

EA2.01 Reactor pressure vessel water level 4 4

EA2.02 Reactor power 4 4

EA2.03 Reactor pressure vessel pressure 4 4

EA2.04 Adequate core cooling 4 4
NUREG-2104 4.1-12

4.1 Emergency Plant Evolutions

EPE: EPE1008 High Secondary Containment Area Temperature

K/A NO. KNOWLEDGE IMPORTANCE

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 4

EK1.02 Radiation releases 4

EK1.03 Impact of operating environment on components 3

EK1.04 Maximum normal operating temperature 3

EK1.05 Maximum safe operating temperature 3

EK2. Knowledge of the interrelations between High Secondary Containment 

Area Temperature and the following:

(CFR: 41.7 / 45.8)

EK2.01 Area/room coolers 4

EK2.02 Reactor building HVAC system 4

EK2.03 Leak detection and isolation system 4

EK2.04 Temperature sensitive instrumentation 3

EK2.05 Systems required for safe shut-down 4

EK2.06 Systems required to suppress a fire 3

EK2.07 Systems required for adequate core cooling 3

EK2.08 Systems required to protect the containment 3

EK2.09 Primary system discharging in secondary containment 3

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 depressurization 4

EK3.02 Reactor scram 4

EK3.03 Isolating affected systems 4

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 Reactor building HVAC system 4

EA1.02 Fire protection system 3

EA1.03 Affected systems so as to isolate damaged portions 4

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)

RO SRO

EA2.01 Area temperature 4 4

EA2.02 Equipment operability 3 4

EA2.03 Cause of high area temperature 4 4
4.1-13 NUREG-2104

4.1 Emergency Plant Evolutions

EPE: EPE1009 High Secondary Containment Area Radiation Levels

K/A NO. KNOWLEDGE IMPORTANCE

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

EK1.02 Personnel protection 4

EK1.03 Radiation releases. 4

EK1.04 Maximum normal operating radiation limit 3

EK1.05 Maximum safe operating radiation limit 3

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 4

EK2.02 Process radiation monitoring system 4

EK2.03 Reactor Building HVAC system 4

EK2.04 Standby gas treatment system 4

EK2.05 Primary system discharging in to secondary containment 3

EK2.06 Systems required to suppress a fire 3

EK2.07 Systems required for adequate core cooling 3

EK2.08 Systems required to shutdown the reactor 3

EK2.09 Systems required to protect the containment 3

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

EK3.02 Reactor scram 4

EK3.03 Isolating affected systems 4

EK3.04 Personnel evacuation 4

EK3.05 Emergency plan 4

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. 4

EA1.02 Process radiation monitoring system 4

EA1.03 Reactor Building HVAC system 4

EA1.04 Standby gas treatment system 4

EA1.05 Affected systems so as to isolate damaged portions 4
NUREG-2104 4.1-14

4.1 Emergency Plant Evolutions

EPE: EPE1009 High Secondary Containment Area Radiation Levels (continued)

K/A NO. ABILITY IMPORTANCE

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)

RO SRO

EA2.01 Area radiation levels 4 4

EA2.02 Equipment operability 3 3

EA2.03 Cause of high area radiation 4 4
4.1-15 NUREG-2104

4.1 Emergency Plant Evolutions

EPE: EPE1010 Reactor Building Heating, Ventilation, and Air Conditioning

Exhaust High Radiation

K/A NO. KNOWLEDGE IMPORTANCE

EK1. Knowledge of the operational implications of the following concepts as 

they apply to Reactor Building HVAC Exhaust High Radiation:

(CFR: 41.8 to 41.10)

EK1.01 Personnel protection 4

EK1.02 Radiation releases 4

EK2. Knowledge of the interrelations between Reactor Building HVAC Exhaust 

High Radiation and the following:

(CFR: 41.7 / 45.8)

EK2.01 Process radiation monitoring system 4

EK2.02 Standby gas treatment system 4

EK2.03 Reactor building HVAC system 4

EK2.04 Leak detection and isolation system 4

EK3. Knowledge of the reasons for the following responses as they apply to 

Reactor Building HVAC Exhaust High Radiation:

(CFR: 41.5 / 45.6)

EK3.01 Isolating reactor building HVAC system 4

EK3.02 Starting standby gas treatment system 4

EK3.03 Personnel evacuation. 4

ABILITY

EA1. Ability to operate and/or monitor the following as they apply to Reactor 

Building HVAC Exhaust High Radiation:

(CFR: 41.7 / 45.6)

EA1.01 Process radiation monitoring system 4

EA1.02 Reactor building HVAC system 4

EA1.03 Standby gas treatment system 4

EA2. Ability to determine and/or interpret the following as they apply to Reactor 

Building HVAC Exhaust High Radiation:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

EA2.01 Ventilation radiation levels 4 4

EA2.02 Cause of high radiation levels 4 4
NUREG-2104 4.1-16

4.1 Emergency Plant Evolutions

EPE: EPE1011 Secondary Containment High Differential Pressure

K/A NO. KNOWLEDGE IMPORTANCE

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 4

EK1.02 Radiation release 4

EK2. Knowledge of the interrelations between Secondary Containment High 

Differential Pressure and the following:

(CFR: 41.7 / 45.8)

EK2.01 Reactor building HVAC system 4

EK2.02 Standby gas treatment system 4

EK2.03 Off-site release rate 3

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 Reactor building HVAC system response 3

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 Reactor building HVAC system 4

EA1.02 Standby gas treatment system 4

EA2. Ability to determine and/or interpret the following as they apply to 

Secondary Containment High Differential Pressure:

(CFR: 41.8 to 41.10)

RO SRO

EA2.01 Secondary containment pressure 4 4

EA2.02 Off-site release rate 3 4
4.1-17 NUREG-2104

4.1 Emergency Plant Evolutions

EPE: EPE1012 Secondary Containment High Floor Drain Sump/Area Water Level

K/A NO. KNOWLEDGE IMPORTANCE

EK1. Knowledge of the operational implications of the following concepts as 

they apply to Secondary Containment High Floor Drain Sump/Area Water 

Level:

(CFR: 41.8 to 41.10)

EK1.01 Radiation releases 3

EK1.02 Electrical ground/ circuit malfunction 3

EK1.03 Maximum normal operating limit 3

EK1.04 Maximum safe operating limit 3

EK2. Knowledge of the interrelations between Secondary Containment High 

Floor Drain Sump/Area Water Level and the following:

(CFR: 41.7 / 45.8)

EK2.01 Reactor building high conductivity and low conductivity waste drains 3

EK2.02 Radwaste system 3

EK2.03 Systems required to shutdown the reactor 3

EK2.04 Systems required to suppress a fire 3

EK2.05 Systems required for adequate core cooling 3

EK2.06 Primary system discharging to secondary containment 3

EK3. Knowledge of the reasons for the following responses as they apply to 

Secondary Containment High Floor Drain Sump/Area Water Level:

(CFR: 41.5 / 45.6)

EK3.01 Emergency depressurization 3

EK3.02 Reactor scram 3

EK3.03 Isolating affected systems (PRA) 4

EK3.04 Pumping reactor building sumps 3

ABILITY

EA1. Ability to operate and/or monitor the following as they apply to Secondary 

Containment High Floor Drain Sump/Area Water Level:

(CFR: 41.7 / 45.6)

EA1.01 Reactor building high conductivity and low conductivity waste drains 3

EA1.02 Affected systems so as to isolate damaged portions (PRA) 4

EA1.03 Radwaste systems 3
NUREG-2104 4.1-18

4.1 Emergency Plant Evolutions

EPE: EPE1012 Secondary Containment High Floor Drain Sump/Area Water Level

(continued)

K/A NO. ABILITY IMPORTANCE

EA2. Ability to determine and/or interpret the following as they apply to 

Secondary Containment High Floor Drain Sump/Area Water Level:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

EA2.01 Operability of components within the affected area 3 3

EA2.02 Water level in the affected area 3 3

EA2.03 Cause of the high water level 3 4
4.1-19 NUREG-2104

4.1 Emergency Plant Evolutions

EPE: EPE1013 Scram Condition and Reactor Power >5% or Unknown

K/A NO. KNOWLEDGE IMPORTANCE

EK1. Knowledge of the operational implications of the following concepts as 

they apply to Scram Condition and Reactor Power >5% or Unknown:

(CFR: 41.8 to 41.10)

EK1.01 Reactor pressure effects on reactor power 4

EK1.02 Reactor water level effects on reactor power 4

EK1.03 Boron effects on reactor power (Standby liquid control system) 4

EK1.04 Hot shutdown boron weight 3

EK1.05 Cold shutdown boron weight 3

EK1.06 Cooldown effects on reactor power 4

EK1.07 Shutdown margin 3

EK2. Knowledge of the interrelations between Scram Condition and Reactor 

Power >5% or Unknown and the following:

(CFR: 41.7 / 45.8)

EK2.01 Reactor trip and isolation system 4

EK2.02 Alternate reactor shutdown system 4

EK2.03 Control rod drive system 4

EK2.04 Neutron monitoring system 4

EK2.05 Safety parameter display system 3

EK2.06 Reactor pressure vessel water level 4

EK2.07 Reactor pressure vessel pressure 4

EK2.08 Rod control and information system 4

EK2.09 Alternate boron injection methods 3

EK2.10 Reactor internal pump runback and trips 4

EK2.11 Feedwater spargers 4

EK2.12 ESF logic and control system 3

EK2.13 Reactor recirculation flow control system 4

EK3. Knowledge of the reasons for the following responses as they apply to 

Scram Condition and Reactor Power >5% or Unknown:

(CFR: 41.5 / 45.6)

EK3.01 Reactor internal pump runback 4

EK3.02 Trip of reactor internal pumps 4

EK3.03 Standby liquid control system injection 4

EK3.04 Lowering of reactor pressure vessel water level (PRA) 4

EK3.05 Feedwater pump runback 4

EK3.06 Hot shutdown boron weight 2

EK3.07 Cold shutdown boron weight 3

EK3.08 Maintaining heat sinks external to the containment 4

EK3.09 Various alternate methods of control rod insertion 4
NUREG-2104 4.1-20

4.1 Emergency Plant Evolutions

EPE: EPE1013 Scram Condition and Reactor Power >5% or Unknown (continued)

K/A NO. ABILITY IMPORTANCE

EA1. Ability to operate and/or monitor the following as they apply to Scram 

Condition and Reactor Power >5% or Unknown:

(CFR: 41.7 / 45.6)

EA1.01 Reactor trip and isolation system 4

EA1.02 Initiation of alternate rod insertion function 4

EA1.03 Standby liquid control system 4

EA1.04 Control rod drive system 4

EA1.05 Neutron monitoring system 4

EA1.06 Rod control and information system 4

EA1.07 Safety parameter display system 3

EA1.08 Alternate boron injection methods 4

EA1.09 Leak detection and isolation system 4

EA1.10 Feedwater control system (PRA) 4

EA1.11 Reactor recirculation system 4

EA1.12 Reactor water cleanup system 4

EA2. Ability to determine and/or interpret the following as they apply to Scram 

Condition and Reactor Power >5% or Unknown:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

EA2.01 Reactor power 4 4

EA2.02 Reactor power oscillations 4 4

EA2.03 Reactor pressure vessel water level 4 4

EA2.04 Standby liquid control system tank level 4 4

EA2.05 Suppression pool temperature 4 4

EA2.06 Control rod position 4 4

EA2.07 Reactor pressure vessel pressure 4 4

EA2.08 Containment conditions/isolations 4 4

EA2.09 Reactor recirculation flow 4 4
4.1-21 NUREG-2104

4.1 Emergency Plant Evolutions

EPE: EPE1014 High Off-Site Release Rate

K/A NO. KNOWLEDGE IMPORTANCE

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 3

EK1.02 Protection of the general public 4

EK1.03 Meteorological effects on off-site release 3

EK2. Knowledge of the interrelations between High Off-Site Release Rate and the 

following:

(CFR: 41.7 / 45.8)

EK2.01 Radwaste system 3

EK2.02 Offgas system 4

EK2.03 Plant ventilation systems 4

EK2.04 Stack-gas monitoring system 4

EK2.05 Site emergency plan 4

EK2.06 Process radiation monitoring system 3

EK2.07 Control room habitability area HVAC system 4

EK2.08 Safety parameter display system 3

EK2.09 Post accident sample system (PASS) 3

EK2.10 Condensate air extraction system 3

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 4

EK3.02 System isolations 4

EK3.03 Control room habitability area HVAC system isolation 4

EK3.04 Emergency depressurization 4

ABILITY

EA1. Ability to operate and/or monitor the following as they apply to High OffSite Release Rate:

(CFR: 41.7 / 45.6)

EA1.01 Stack-gas monitoring system 4

EA1.02 Meteorological instrumentation 3

EA1.03 Process radiation monitoring system 4

EA1.04 Safety parameter display system 3

EA1.05 Post accident sample system 3

EA1.06 Plant ventilation 4

EA1.07 Control room habitability area HVAC system 4
NUREG-2104, Rev. 0 4.1-22

4.1 Emergency Plant Evolutions

EPE: EPE1014 High Off-Site Release Rate (continued)

K/A NO. ABILITY IMPORTANCE

EA2. Ability to determine and/or interpret the following as they apply to High OffSite Release Rate:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

EA2.01 Off-site 3 4

EA2.02 Total number of curies released 2 3

EA2.03 Radiation levels 4 4

EA2.04 Source of offsite release 4 4
4.2-1 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2001 Partial or Complete Loss of Forced Core Flow Circulation

K/A NO. KNOWLEDGE IMPORTANCE

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 4

AK1.02 Power/flow distribution 3

AK1.03 Thermal limits 4

AK1.04 Power oscillations 3

AK1.05 Selected control rod run-in initiation 4

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 Reactor recirculation system 4

AK2.02 Nuclear boiler instrumentation 3

AK2.03 Reactor pressure vessel water level 4

AK2.05 Reactor power 4

AK2.06 Core flow indication 4

AK2.07 Reactor trip and isolation system 4

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 pressure vessel water level response. 3

AK3.02 Reactor power response 4

AK3.03 Reactor scram 3

AK3.04 Reduced reactor internal pump operating requirements 3

AK3.05 Core flow indication 3
NUREG-2104 4.2-2

4.2 Abnormal Plant Evolutions

APE: APE2001 Partial or Complete Loss of Forced Core Flow Circulation

(continued)

K/A NO. ABILITY IMPORTANCE

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 Reactor recirculation system 4

AA1.02 Reactor trip and isolation system 3

AA1.03 Rod control and information system 3

AA1.04 Recirculation flow control system 3

AA1.05 Neutron monitoring system 3

AA1.06 Nuclear boiler instrumentation 3

AA1.07 Selected control rod run-in 4

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)

RO SRO

AA2.01 Power/flow map 4 4

AA2.02 Neutron monitoring 3 3

AA2.03 Actual core flow 3 3

AA2.04 Reactor internal pump operability 3 3

AA2.05 Nuclear boiler instrumentation 3 3
4.2-3 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2002 Loss of Main Condenser Vacuum

K/A NO. KNOWLEDGE IMPORTANCE

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

AK1.02 Turbine efficiency 2

AK1.03 Loss of heat sink 4

AK1.04 Offgas flow changes 3

AK2. Knowledge of the interrelations between Loss of Main Condenser Vacuum 

and the following:

(CFR: 41.7 / 45.8)

AK2.01 Main turbine 3

AK2.02 Leak detection and isolation system 4

AK2.03 Steam bypass and pressure control system 3

AK2.04 Feedwater system 3

AK2.05 Condensate system 3

AK2.06 Offgas system 3

AK2.07 Circulating water system 3

AK2.08 Seal steam 3

Ak2.09 Reactor trip and isolation system 3

AK2.10 Condensate air extraction system 2

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 Turbine trip 3

AK3.02 Turbine bypass valve closure 3

AK3.03 Main steam isolation valve closure 3

AK3.04 Air ejector flow 3

AK3.05 Decreased main generator output 2

AK3.06 Reactor power reduction 3

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 3

AA1.02 Offgas system 3

AA1.03 Reactor trip and isolation system 3

AA1.04 Leak detection and isolation system 3

AA1.05 Main turbine 3

AA1.06 Steam bypass and pressure control system 3

AA1.07 Circulating water system 3

AA1.08 Recirculation flow control system 3

AA1.09 Rod control and information system 3
NUREG-2104 4.2-4

4.2 Abnormal Plant Evolutions

APE: APE2002 Loss of Main Condenser Vacuum (continued)

K/A NO. ABILITY IMPORTANCE

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)

RO SRO

AA2.01 Condenser vacuum/absolute pressure 3 3

AA2.02 Generator output. 2 2

AA2.03 Offgas system flow 3 3
4.2-5 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2003 Partial or Complete Loss of AC Power

K/A NO. KNOWLEDGE IMPORTANCE

AK1. Knowledge of the operational implications of the following concepts as 

they apply to Partial or Complete Loss of AC Power:

(CFR: 41.8 to 41.10)

AK1.01 Effect of battery discharge rate on capacity 3

AK1.02 Load shedding 3

AK1.03 Under voltage/degraded voltage effects on electrical loads 3

AK1.04 Electrical bus divisional separation 3

AK1.05 Failsafe component design 3

AK1.06 Station blackout 4

AK2. Knowledge of the interrelations between Partial or Complete Loss of AC 

Power and the following:

(CFR: 41.7 / 45.8)

AK2.01 Station batteries 3

AK2.02 Emergency diesel generators 4

AK2.03 Combustion turbine generators 4

AK2.04 AC electrical distribution system 4

AK2.05 AC electrical loads 3

AK2.06 DC electrical loads 3

AK2.07 Reactor core isolation cooling system 4

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

Partial or Complete Loss of AC Power:

(CFR: 41.5 / 45.6)

AK3.01 Manual and auto bus transfer 3

AK3.02 Load shedding and sequencing 4

AK3.03 Ground isolation 3

AK3.04 Reactor scram 4

AK3.05 Containment isolation 4

ABILITY

AA1. Ability to operate and/or monitor the following as they apply to Partial or 

Complete Loss of AC Power:

(CFR: 41.7 / 45.6)

AA1.01 AC electrical distribution system 4

AA1.02 Emergency diesel generators 4

AA2.03 Combustion turbine generators 4

AA1.04 Systems necessary to assure safe plant shutdown 4

AA1.05 DC electrical distribution system 4
NUREG-2104 4.2-6

4.2 Abnormal Plant Evolutions

APE: APE2003 Partial or Complete Loss of AC Power (continued)

K/A NO. ABILITY IMPORTANCE

AA2. Ability to determine and/or interpret the following as they apply to Partial or 

Complete Loss of AC Power:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Cause of partial or complete loss of AC power 3 4

AA2.02 Reactor power, pressure, and level 4 4

AA2.03 Battery status 3 4

AA2.04 System lineups 4 4

AA2.05 Whether a partial or complete loss of AC power has occurred 4 4
4.2-7 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2004 Partial or Complete Loss of DC Power

K/A NO. KNOWLEDGE IMPORTANCE

AK1. Knowledge of the operational implications of the following concepts as 

they apply to Partial or Complete Loss of DC Power:

(CFR: 41.8 to 41.10)

AK1.01 Electrical bus divisional separation 3

AK1.02 Effect of battery discharge rate on capacity 3

AK1.03 Loss of breaker protection 3

AK1.04 Prevention of inadvertent system(s) actuation upon restoration of

DC power 3

AK2. Knowledge of the interrelations between Partial or Complete Loss of DC 

Power and the following:

(CFR: 41.7 / 45.8)

AK2.01 Battery charger 3

AK2.02 Batteries 3

AK2.03 Reactor core isolation cooling system 4

AK2.04 AC electrical power distribution system 3

AK2.05 Emergency diesel generators 3

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

Partial or Complete Loss of DC Power:

(CFR: 41.5 / 45.6)

AK3.01 Manual load shedding 3

AK3.02 Ground isolation/fault determination 3

AK3.03 Reactor scram 3

ABILITY

AA1. Ability to operate and/or monitor the following as they apply to Partial or 

Complete Loss of DC Power:

(CFR: 41.7 / 45.6)

AA1.01 DC electrical distribution systems 3

AA1.02 Systems necessary to assure safe plant shutdown 4

AA1.03 AC electrical power distribution system 3
NUREG-2104 4.2-8

4.2 Abnormal Plant Evolutions

APE: APE2004 Partial or Complete Loss of DC Power (continued)

K/A NO. ABILITY IMPORTANCE

AA2. Ability to determine and/or interpret the following as they apply to Partial or 

Complete Loss of DC Power:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Cause of partial or complete loss of DC power 3 4

AA2.02 Extent of partial or complete loss of DC power 4 4

AA2.03 Battery voltage 3 3

AA2.04 System lineups 3 3
4.2-9 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2005 Main Turbine Generator Trip

K/A NO. KNOWLEDGE IMPORTANCE

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

AK1.02 Core thermal limit considerations 3

AK1.03 Pressure effects on reactor pressure vessel water level 4

AK2. Knowledge of the interrelations between MAIN TURBINE GENERATOR 

TRIP and the following:

(CFR: 41.7 / 45.8)

AK2.01 Reactor trip and isolation system 4

AK2.02 Feedwater temperature 3

AK2.03 Reactor recirculation system 3

AK2.04 Main generator protection 3

AK2.05 Extraction steam system 3

AK2.06 Seal steam evaporator 2

AK2.07 Steam bypass and pressure control system 4

AK2.08 AC electrical distribution system 3

AK2.09 Turbine protection 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 4

AK3.02 Reactor internal pump trip and runback 3

AK3.03 Feedwater temperature decrease 3

AK3.04 Main generator trip 3

AK3.05 Extraction steam/moisture separator isolations 3

AK3.06 Main turbine bypass valve operation 4

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 Reactor recirculation system 3

AA1.02 Reactor trip and isolation system 4

AA1.03 Rod control and information system 3

AA1.04 Main generator controls 3

AA1.05 Steam bypass and pressure control system 4
NUREG-2104 4.2-10

4.2 Abnormal Plant Evolutions

APE: APE2005 Main Turbine Generator Trip (continued)

K/A NO. ABILITY IMPORTANCE

AA1.06 Condenser vacuum breaker 2

AA1.07 AC electrical distribution 3

AA1.08 Turbine control system 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)

RO SRO

AA2.01 Turbine speed 3 3

AA2.02 Turbine vibration 2 3

AA2.03 Turbine valve position 3 3

AA2.04 Reactor pressure vessel pressure 4 4

AA2.05 Reactor power 4 4

AA2.06 Feedwater temperature 3 3

AA2.07 Reactor pressure vessel water level 4 4

AA2.08 Electrical distribution status 3 3

AA2.09 Number of running reactor internal pumps and their speed 3 3
4.2-11 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2006 Reactor Scram

K/A NO. KNOWLEDGE IMPORTANCE

AK1. Knowledge of the operational implications of the following concepts as 

they apply to Reactor Scram:

(CFR: 41.8 to 41.10)

AK1.01 Decay heat generation and removal 4

AK1.02 Shutdown margin 3

AK1.03 Reactivity control 4

AK2. Knowledge of the interrelations between Reactor Scram and the following:

(CFR: 41.7 / 45.8)

AK2.01 Reactor trip and isolation system 4

AK2.02 Feedwater control system 4

AK2.03 Control rod drive system 4

AK2.04 Reactor power 4

AK2.05 Steam bypass and pressure control system 4

AK2.06 Recirculation flow control system 3

AK2.07 Main turbine trip 4

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

Reactor Scram:

(CFR: 41.5 / 45.6)

AK3.01 Reactor pressure vessel water level response 4

AK3.02 Reactor power response 4

AK3.03 Reactor pressure vessel pressure response 4

AK3.04 Reactor pressure vessel water level setpoint setdown 3

AK3.06 Reactor internal pump speed reduction 3

AK3.07 Scram follow function 3

ABILITY

AA1. Ability to operate and/or monitor the following as they apply to Reactor 

Scram:

(CFR: 41.7 / 45.6)

AA1.01 Reactor trip and isolation system 4

AA1.02 Feedwater control system (PRA) 4

AA1.03 Steam bypass and pressure control system 4

AA1.04 Reactor recirculation system 3

AA1.05 Neutron monitoring system 4

AA1.06 Control rod drive system 4

AA1.07 Rod control and information system 4

AA1.08 Recirculation flow control system 4
NUREG-2104 4.2-12

4.2 Abnormal Plant Evolutions

APE: APE2006 Reactor Scram (continued)

K/A NO. ABILITY IMPORTANCE

AA2. Ability to determine and/or interpret the following as they apply to Reactor 

Scram:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Reactor power 4 4

AA2.02 Control rod position 4 4

AA2.03 Reactor pressure vessel water level 4 4

AA2.04 Reactor pressure vessel pressure 4 4

AA2.05 Whether a reactor scram has occurred 4 4

AA2.06 Cause of reactor scram 4 4
4.2-13 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2007 High Reactor Pressure

K/A NO. KNOWLEDGE IMPORTANCE

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 3

AK1.02 Pressure effects on reactor power 4

AK1.03 Turbine load 3

AK2. Knowledge of the interrelations between High Reactor Pressure and the 

following:

(CFR: 41.7 / 45.8)

AK2.01 Steam bypass and pressure control system 4

AK2.02 Reactor power 4

AK2.03 Residual heat removal system/Low pressure flooder mode 3

AK2.04 Shutdown cooling 3

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

High Reactor Pressure:

(CFR: 41.5 / 45.6)

AK3.01 RCIC operation 3

AK3.02 Safety/relief valve operation 4

AK3.03 Steam bypass and pressure control system operation 4

AK3.04 Reactor internal pump trip 4

ABILITY

AA1. Ability to operate and/or monitor the following as they apply to High 

Reactor Pressure:

(CFR: 41.7 / 45.6)

AA1.01 Reactor core isolation cooling system 3

AA1.02 Safety/relief valve operation 4

AA1.03 Steam bypass and pressure control system 4

AA2. Ability to determine and/or interpret the following as they apply to High 

Reactor Pressure:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Reactor pressure vessel pressure 4 4

AA2.02 Reactor power 4 4

AA2.03 Reactor pressure vessel water level 4 4
NUREG-2104 4.2-14

4.2 Abnormal Plant Evolutions

APE: APE2008 High Reactor Water Level

K/A NO. KNOWLEDGE IMPORTANCE

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

AK1.02 Component erosion/damage 3

AK1.03 Feed flow/steam flow mismatch 3

AK2. Knowledge of the interrelations between High Reactor Water Level and the 

following:

(CFR: 41.7 / 45.8)

AK2.01 Feedwater system 4

AK2.02 Feedwater control system 4

AK2.03 Reactor core isolation cooling system 3

AK2.04 High pressure core flooder system 3

AK2.05 Main turbine 3

AK2.06 Steam bypass and pressure control system 3

AK2.07 Reactor water cleanup system (ability to drain) 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

AK3.02 Feedwater pump trip 3

AK3.03 Reactor core isolation cooling system steam supply valve closure 3

AK3.04 High pressure core flooder injection valve closure 3

ABILITY

AA1. Ability to operate and/or monitor the following as they apply to High 

Reactor Water Level:

(CFR: 41.7 / 45.6)

AA1.01 Feedwater control system 4

AA1.02 Reactor water cleanup (ability to drain) 3

AA1.03 Reactor core isolation cooling system 3

AA1.04 High pressure core flooder system 3

AA1.05 Main turbine 3

AA1.06 Feedwater system 4
4.2-15 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2008 High Reactor Water Level (continued)

K/A NO. ABILITY IMPORTANCE

AA2. Ability to determine and/or interpret the following as they apply to High 

Reactor Water Level:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Reactor pressure vessel water level 4 4

AA2.02 Steam flow/feed flow mismatch 3 3

AA2.03 Reactor water cleanup blowdown flow 3 3

AA2.04 Reactor pressure vessel water swell 3 3
NUREG-2104 4.2-16

4.2 Abnormal Plant Evolutions

APE: APE2009 Low Reactor Water Level

K/A NO. KNOWLEDGE IMPORTANCE

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 3

AK1.02 Natural circulation 3

AK2. Knowledge of the interrelations between Low Reactor Water Level and the 

following:

(CFR: 41.7 / 45.8)

AK2.01 Reactor pressure vessel water level indication 4

AK2.02 Feedwater water level control system 4

AK2.03 Reactor recirculation system 3

AK2.04 Reactor water cleanup system 3

AK2.05 Reactor trip and isolation system 4

AK3. Knowledge of the reasons for the following responses as they apply to Low 

Reactor Water Level:

(CFR: 41.5 / 45.6)

AK3.01 Reactor internal pump trip and runback 3

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 Feedwater system 4

AA1.02 Feedwater control system 4

AA1.03 Recirculation system 3

AA1.04 Reactor water cleanup system 3

AA1.05 Condensate system (PRA) 4

AA2. Ability to determine and/or interpret the following as they apply to Low 

Reactor Water Level:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Reactor pressure vessel water level 4 4

AA2.02 Steam flow/feed flow mismatch 4 4

AA2.03 Reactor water cleanup blowdown flow rate 3 3
4.2-17 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2010 High Drywell Pressure

K/A NO. KNOWLEDGE IMPORTANCE

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 Temperature increases 3

AK1.02 Dewpoint increases 2

AK2. Knowledge of the interrelations between High Drywell Pressure and the 

following:

(CFR: 41.7 / 45.8)

AK2.01 Suppression pool level 3

AK2.02 Drywell wetwell differential pressure 3

AK2.03 Atmosphere control system 3

AK2.04 Drywell cooling and ventilation 4

AK2.05 Instrument air system 3

AK2.06 High pressure nitrogen gas supply system 3

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

High Drywell Pressure:

(CFR: 41.5/45.6)

AK3.01 Drywell/wetwell venting 4

AK3.02 Increased drywell cooling 3

AK3.03 Radiation level monitoring 3

AK3.04 Leak investigation 4

AK3.05 Temperature monitoring 4

AK3.06 Termination of drywell inerting 2

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

AA1.02 High and low conductivity waste sumps 4

AA1.03 Nitrogen makeup 3

AA1.04 Sampling system 3

AA1.05 Drywell wetwell vent and purge 3

AA1.06 Leakage detection systems 3

AA1.07 Atmosphere control system 3

AA1.08 Process radiation monitoring system 3
NUREG-2104 4.2-18

4.2 Abnormal Plant Evolutions

APE: APE2010 High Drywell Pressure (continued)

K/A NO. ABILITY IMPORTANCE

AA2. Ability to determine and/or interpret the following as they apply to High 

Drywell Pressure:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Leak rates 3 4

AA2.02 Drywell pressure 4 4

AA2.03 Drywell radiation levels 3 4

AA2.04 Drywell temperature 4 4

AA2.05 Drywell dewpoint 2 2
4.2-19 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2011 High Drywell Temperature

K/A NO. KNOWLEDGE IMPORTANCE

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

AK2. Knowledge of the interrelations between High Drywell Temperature and the 

following:

(CFR: 41.7 / 45.8)

AK2.01 Drywell cooling 4

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 4

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 cooling system 4

AA2.02 Sampling system 2

AA2. Ability to determine and/or interpret the following as they apply to High 

Drywell Temperature:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Drywell temperature 4 4

AA2.02 Drywell pressure 4 4

AA2.03 Dewpoint 2 2
NUREG-2104 4.2-20

4.2 Abnormal Plant Evolutions

APE: APE2012 High Suppression Pool Temperature

K/A NO. KNOWLEDGE IMPORTANCE

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 3

AK1.02 Ambient temperature effects 2

AK1.03 Localized heating 3

AK2. Knowledge of the interrelations between High Suppression Pool 

Temperature and the following:

(CFR: 41.7 / 45.8)

AK2.01 Suppression pool cooling 4

AK2.02 Safety relief valve actuation 4

Ak2.03 Reactor core isolation cooling system 4

AK2.04 Suppression pool temperature monitoring system 4

AK2.05 ESF logic and control system 3

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 4

AK3.02 Limiting heat additions 4

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 4

AA1.02 Systems that add heat to the suppression pool 4

AA2. Ability to determine and/or interpret the following as they apply to High 

Suppression Pool Temperature:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Suppression pool temperature 4 4

AA2.02 Localized heating/stratification 3 4
4.2-21 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2013 Inadvertent Reactivity Addition

K/A NO. KNOWLEDGE IMPORTANCE

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 4

AK1.02 Reactivity anomaly 3

AK1.03 Shutdown margin 4

AK1.04 Fuel thermal limits 4

AK1.05 Abnormal reactivity additions 4

AK2. Knowledge of the interrelations between Inadvertent Reactivity Addition

and the following:

(CFR: 41.7 / 45.8)

AK2.01 Reactor trip and isolation system 4

AK2.02 Fuel thermal limits 4

AK2.03 Fuel temperature 3

AK2.04 Void concentration 3

AK2.05 Neutron monitoring system 4

AK2.06 Moderator temperature 3

AK2.07 Reactor power 4

AK2.08 Rod control and information system 3

AK2.09 Safety limits 4

AK2.10 Recirculation flow control system 4

AK2.11 Feedwater control system 3

AK2.12 Steam bypass and pressure control system 3

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

AK3.02 Control rod blocks 4

AK3.03 Selected control rod run-in 4

AK3.04 Core flow increase block 4

ABILITY

AA1. Ability to operate and/or monitor the following as they apply to Inadvertent 

Reactivity Addition:

(CFR: 41.7 / 45.6)

AA1.01 Reactor trip and isolation system 4

AA1.02 Recirculation flow control system 4

AA1.03 Rod control and information system 3
NUREG-2104 4.2-22

4.2 Abnormal Plant Evolutions

APE: APE2013 Inadvertent Reactivity Addition (continued)

K/A NO. ABILITY IMPORTANCE

AA1.04 Neutron monitoring system 4

AA1.05 Steam bypass and pressure control system 3

AA1.06 Feedwater temperature 4

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

Inadvertent Reactivity Addition:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Reactor power 4 4

AA2.02 Reactor period 4 4

AA2.03 Cause of reactivity addition 4 4

AA2.04 Violation of fuel thermal limits 4 4

AA2.05 Violation of safety limits 4 4
4.2-23 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2014 Incomplete Scram

K/A NO. KNOWLEDGE IMPORTANCE

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 4

AK1.02 Cooldown effects on reactor power 4

AK1.03 Reactivity effects 4

AK1.04 Reactor pressure 4

AK2. Knowledge of the interrelations between Incomplete Scram and the 

following:

(CFR: 41.7 / 45.8)

AK2.01 Control rod drive system 4

AK2.02 Rod control and information system 3

AK2.03 Reactor trip and isolation system 4

AK2.04 Neutron monitoring system 4

AK2.05 Safety parameter display system 3

AK2.06 Instrument air 4

AK2.07 Alternate rod insertion 4

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

ABILITY

AA1. Ability to operate and/or monitor the following as they apply to Incomplete 

Scram:

(CFR: 41.7 / 45.6)

AA1.01 Control rod drive system 4

AA1.02 Reactor trip and isolation system 4

AA1.03 Rod control and information system 3

AA1.04 Neutron monitoring system 4

AA1.05 Safety parameter display system. 3

AA1.06 Alternate rod insertion 4
NUREG-2104 4.2-24

4.2 Abnormal Plant Evolutions

APE: APE2014 Incomplete Scram (continued)

K/A NO. ABILITY IMPORTANCE

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

Incomplete Scram:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Reactor power 4 4

AA2.02 Control rod position 4 4
4.2-25 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2015 Control Room Evacuation

K/A NO. KNOWLEDGE IMPORTANCE

AK1. Knowledge of the operational implications of the following concepts as 

they apply to Control Room Evacuation:

(CFR: 41.8 to 41.10)

None

AK2. Knowledge of the interrelations between Control Room Evacuation and the 

following:

(CFR: 41.7 / 45.8)

AK2.01 Remote shutdown panel 4

AK2.02 Local control stations 4

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

Control Room Evacuation:

(CFR: 41.5 / 45.6)

AK3.01 Reactor scram 4

AK3.02 Turbine trip 4

AK3.03 Disabling control room controls 4

ABILITY

AA1. Ability to operate and/or monitor the following as they apply to Control 

Room Evacuation:

(CFR: 41.7 / 45.6)

AA1.01 Reactor trip and isolation system 4

AA1.02 AC electrical power distribution system 3

AA1.03 Reactor pressure vessel water level 4

AA1.04 Control room/local control transfer mechanisms (PRA) 4

AA1.05 Reactor pressure vessel pressure 4

AA1.06 Safety/relief valves (PRA) 3

AA1.07 Residual heat removal system (PRA) 3

AA1.08 High pressure core flooder system 3

AA1.09 Reactor building cooling water system 3

AA1.10 Reactor service water system 3

AA1.11 Atmosphere control system 3

AA1.12 Makeup water condensate system 3

AA1.13 Suppression pool temperature monitoring system 3
NUREG-2104 4.2-26

4.2 Abnormal Plant Evolutions

APE: APE2015 Control Room Evacuation (continued)

K/A NO. ABILITY IMPORTANCE

AA2. Ability to determine and/or interpret the following as they apply to Control 

Room Evacuation:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Reactor power 4 4

AA2.02 Reactor pressure vessel water level 4 4

AA2.03 Reactor pressure vessel pressure 4 4

AA2.04 Suppression pool temperature 4 4

AA2.05 Drywell pressure 4 4

AA2.06 Cooldown rate 3 4

AA2.07 Wetwell pressure 3 3

AA2.08 Reactor pressure vessel water temperature 3 3
4.2-27 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2016 High Off-Site Release Rate

K/A NO. KNOWLEDGE IMPORTANCE

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

AK1.02 Protection of the general public 4

AK1.03 Meteorological effects on off-site release 3

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 3

AK2.02 Radwaste system 3

AK2.03 Off-gas system 3

AK2.04 Plant ventilation systems 3

AK2.05 Site emergency plan 3

AK2.06 Control room habitability area ventilation system 3

AK2.07 Safety parameter display system 3

AK2.08 Condensate air extraction system 3

AK2.09 Process radiation monitoring system 3

AK2.10 Standby gas treatment system 3

AK2.11 Reactor trip and isolation system 3

AK2.12 Leak detection and isolation system 4

AK2.13 Fuel pool cooling and cleanup system 2

AK3. Knowledge of the reasons for the following responses they apply to High 

Off-Site Release Rate:

(CFR: 41.5 / 45.6)

AK3.01 System isolations 4

AK3.02 Plant ventilation 3

AK3.03 Implementation of site emergency plan 4

AK3.04 Power reduction 4

AK3.05 Control room habitability area ventilation system 3

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 system 3

AA1.02 Off-gas system 4

AA1.03 Plant ventilation systems 3

AA1.04 Safety parameter display system 3

AA1.05 Condensate air extraction system 3

AA1.06 Process radiation monitoring system 3

AA1.07 Standby gas treatment system 4

AA1.10 Reactor trip and isolation system 4

AA1.08 Leak detection and isolation system 4

AA1.09 Meteorological data 3
NUREG-2104 4.2-28

4.2 Abnormal Plant Evolutions

APE: APE2016 High Off-Site Release Rate (continued)

K/A NO. ABILITY IMPORTANCE

AA2. Ability to determine and/or interpret the following as they apply to High OffSite Release Rate:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Off-site release rate 3 4

AA2.02 Total number of curies released 2 4

AA2.03 Radiation levels 3 4

AA2.04 Source of off-site release 4 4

AA2.05 Meteorological data 3 4
4.2-29 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2017 Partial or Complete Loss of Reactor Building Cooling Water

K/A NO. KNOWLEDGE IMPORTANCE

AK1. Knowledge of the operational implications of the following concepts as 

they apply to Partial or Complete Loss of Reactor Building Cooling Water:

(CFR: 41.8 to 41.10)

AK1.01 Effects on component/system operations 4

AK2. Knowledge of the interrelations between Partial or Complete Loss of 

Reactor Building Cooling Water and the following:

(CFR: 41.7 / 45.8)

AK2.01 Reactor water cleanup system 3

AK2.02 Reactor recirculation system 3

AK2.03 Residual heat removal system 4

AK2.04 Fuel pool cooling and cleanup system 3

AK2.05 Plant operations 3

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

Partial or Complete Loss of Reactor Building Cooling Water:

(CFR: 41.5 / 45.6)

AK3.01 Isolation of non-essential heat loads 3

AK3.02 Reactor power reduction 3

AK3.03 Securing individual components (prevent equipment damage) 3

AK3.04 Starting standby pump 3

AK3.05 Placing standby heat exchanger in service 3

AK3.06 Increasing cooling water flow to heat exchangers 3

ABILITY

AA1. Ability to operate and/or monitor the following as they apply to Partial or 

Complete Loss of Reactor Building Cooling Water:

(CFR: 41.7 / 45.6)

AA1.01 System loads 3

AA1.02 Affected systems so as to isolate damaged portions 3

AA2. Ability to determine and/or interpret the following as they apply to Partial or 

Complete Loss of Reactor Building Cooling Water:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Component temperatures 3 3

AA2.02 Cooling water temperature 3 3

AA2.03 Cause for partial or complete loss 3 3

AA2.04 System flow 3 3

AA2.05 System pressure 3 3

AA2.06 Surge tank level 3 3
NUREG-2104 4.2-30

4.2 Abnormal Plant Evolutions

APE: APE2018 Partial or Complete Loss of Instrument Air

K/A NO. KNOWLEDGE IMPORTANCE

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 Control rod drive system 4

AK2.02 Reactor building cooling water system 3

AK2.03 Feedwater system 3

AK2.04 Reactor water cleanup system 3

AK2.05 Main steam system 3

AK2.06 Offgas system 3

AK2.07 Fuel pool cooling and cleanup system 3

AK2.08 Radwaste system 3

AK2.09 Service air system 3

AK2.10 Reactor core isolation cooling 3

AK2.11 Atmosphere control system 3

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)

AK301 Standby air compressor operation 4

AK3.02 Auto cross-tie of service air system to instrument air system

on lower instrument air header pressure 3

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 4

AA1.02 Instrument air compressor power supplies 3
4.2-31 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2018 Partial or Complete Loss of Instrument Air (continued)

K/A NO. ABILITY IMPORTANCE

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)

RO SRO

AA2.01 Instrument air system pressure 4 3

AA2.02 Status of instrument air system loads 3 3
NUREG-2104 4.2-32

4.2 Abnormal Plant Evolutions

APE: APE2019 Inadvertent Containment Isolation

K/A NO. KNOWLEDGE IMPORTANCE

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 4

AK1.02 Power/reactivity control 4

AK1.03 Water chemistry 2

AK1.04 Bottom head thermal stratification 3

AK1.05 Loss of drywell/containment cooling 3

AK2. Knowledge of the interrelations between Inadvertent Containment Isolation

and the following:

(CFR: 41.7 / 45.8)

AK2.01 Main steam system 4

AK2.02 Sampling system 3

AK2.03 Drywell cooling 3

AK2.04 Reactor water cleanup system 3

AK2.05 Reactor core isolation cooling system 3

AK2.06 Automated traversing in-core probe system 3

AK2.07 Residual heat removal system/shutdown cooling 3

AK2.08 Low/high conductivity waste system 3

AK2.09 Standby gas treatment system 3

AK2.10 Reactor building cooling water system 3

AK2.11 Atmosphere control system 3

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 4

AK3.02 Drywell/containment pressure response 3

AK3.03 Drywell/containment temperature response 3

AK3.04 Reactor pressure vessel pressure response 4

AK3.05 Reactor pressure vessel water level response 4

AK3.06 Suppression pool water level response. 3

AK3.07 Suppression pool temperature response 3

AK3.08 Wetwell pressure response 3

AK3.09 Safety relief valve operation 3

AK3.10 Reactor core isolation cooling operation 3
4.2-33 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2019 Inadvertent Containment Isolation (continued)

K/A NO. ABILITY IMPORTANCE

AA1. Ability to operate and/or monitor the following as they apply to Inadvertent 

Containment Isolation:

(CFR: 41.7 / 45.6)

AA1.01 Leak detection and isolation system 4

AA1.02 Drywell cooling system 3

AA1.03 Reactor building HVAC system 3

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

Inadvertent Containment Isolation:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Drywell pressure 4 4

AA2.02 Drywell temperature 3 3

AA2.03 Reactor power 4 4

AA2.04 Reactor pressure vessel pressure 4 4

AA2.05 Reactor pressure vessel water level 4 4

AA2.06 Cause of isolation 3 4
NUREG-2104 4.2-34

4.2 Abnormal Plant Evolutions

APE: APE2020 Loss of Shutdown Cooling

K/A NO. KNOWLEDGE IMPORTANCE

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 4

AK1.02 Thermal stratification 3

AK1.03 Adequate core cooling 4

AK1.04 Natural circulation 4

AK2. Knowledge of the interrelations between Loss of Shutdown Cooling and 

the following:

(CFR: 41.7 / 45.8)

AK2.01 Reactor pressure vessel water temperature 4

AK2.02 Reactor water cleanup system 3

AK2.03 Reactor building cooling water system 3

AK2.04 Fuel pool cooling and cleanup system 3

AK2.05 Reactor recirculation system 3

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 pressure vessel water level 3

AK3.02 Feeding and bleeding reactor vessel 3

AK3.03 Increasing drywell cooling 3

AK3.04 Maximizing reactor water cleanup flow 3

AK3.05 Establishing alternate decay heat removal flow paths (PRA) 4

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

AA1.02 RHR/shutdown cooling (PRA) 4

AA1.03 Reactor building cooling water systems 3

AA1.04 Alternate decay heat removal methods 4

AA1.05 Reactor recirculation system 3

AA1.06 Containment/ drywell temperature 3
4.2-35 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2020 Loss of Shutdown Cooling (continued)

K/A NO. ABILITY IMPORTANCE

AA2. Ability to determine and/or interpret the following as they apply to Loss of 

Shutdown Cooling:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Reactor pressure vessel water heatup/cooldown rate 4 4

AA2.02 RHR/shutdown cooling system flow 3 3

AA2.03 Reactor pressure vessel water level 4 4

AA2.04 Reactor pressure vessel water temperature 3 4

AA2.05 Reactor pressure vessel metal temperature 3 4

AA2.06 Reactor pressure vessel pressure 3 3

AA2.07 Reactor recirculation flow 3 3
NUREG-2104 4.2-36

4.2 Abnormal Plant Evolutions

APE: APE2021 Loss of Control Rod Drive Pumps

K/A NO. KNOWLEDGE IMPORTANCE

AK1. Knowledge of the operational implications of the following concepts as 

they apply to Loss of Control Rod Drive Pumps:

(CFR: 41.8 to 41.10)

AK1.01 Reactivity control 4

AK2. Knowledge of the interrelations between Loss of Control Rod Drive Pumps

and the following:

(CFR: 41.7 / 45.8)

AK2.01 Reactor recirculation system 3

AK2.02 Fine motion control rod mechanism 3

AK2.03 Hydraulic control unit accumulator pressures 3

AK2.04 Reactor pressure vessel water level 3

AK2.05 Reactor water cleanup system 3

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

Loss of Control Rod Drive Pumps:

(CFR: 41.5 / 45.6)

AK3.01 Reactor scram 4

ABILITY

AA1. Ability to operate and/or monitor the following as they apply to Loss of 

Control Rod Drive Pumps:

(CFR: 41.7 / 45.6)

AA1.01 Control rod drive system 3

AA1.02 Reactor trip and isolation system 4

AA1.03 Reactor recirculation system 3

AA1.04 Reactor water cleanup system 3

AA2. Ability to determine and/or interpret the following as they apply to Loss of 

Control Rod Drive Pumps:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Hydraulic control unit accumulator pressure 4 4

AA2.02 Control rod drive system status 3 3
4.2-37 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2022 Refueling Accidents

K/A NO. KNOWLEDGE IMPORTANCE

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 4

AK1.02 Shutdown margin 3

AK1.03 Inadvertent criticality 4

AK2. Knowledge of the interrelations between Refueling Accidents and the 

following:

(CFR: 41.7 / 45.8)

AK2.01 Fuel handling equipment 3

AK2.02 Fuel pool cooling and cleanup system 3

AK2.03 Radiation monitoring equipment 3

AK2.04 Rod control and information system. 3

AK2.05 Reactor building HVAC system 4

AK2.06 Standby gas treatment system 4

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 4

AK3.02 Interlocks associated with fuel handling equipment 3

AK3.03 Reactor building HVAC system isolation 3

ABILITY

AA1. Ability to operate and/or monitor the following as they apply to Refueling 

Accidents:

(CFR: 41.7 / 45.6)

AA1.01 Reactor building HVAC system 3

AA1.02 Fuel pool cooling and cleanup system 3

AA1.03 Fuel handling equipment 3

AA1.04 Radiation monitoring equipment 3

AA1.05 Neutron monitoring system 3

AA1.06 Standby gas treatment system 4

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

Refueling Accidents:

(CFR: 41.10 / 43.5 / 45.13)

RO SRO

AA2.01 Area radiation levels 4 4

AA2.02 Fuel pool level 3 4

AA2.03 Airborne contamination levels 3 4

AA2.04 Occurrence of fuel handling accident 3 4

AA2.05 Entry conditions of emergency plan 3 4
NUREG-2104 4.2-38

4.2 Abnormal Plant Evolutions

APE: EPE2023 Plant Fire On-Site

K/A NO. KNOWLEDGE IMPORTANCE

AK1 Knowledge of the operation applications of the following concepts as they 

apply to Plant Fire On-Site:

(CFR: 41.10 / 43.5 / 45.11)

AK1.01 Fire classifications by type 3

AK1.02 Fire fighting 3

AK2. Knowledge of the interrelations between Plant Fire On-Site and the 

following:

(CFR: 41.10 / 43.5 / 45.11)

AK2.01 Sensors/detectors and dampers 3

AK2.02 Controllers and positioners 2

AK2.03 Motors 3

AK2.04 Breakers/relays/disconnects/transformers 3

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

Plant Fire On-Site:

(CFR: 41.10 / 43.5 / 45.11)

AK3.01 Installation of fire detectors 2

AK3.02 Steps called out in the site fire protection plant/fire protection system

manual or fire zone manual 2

AK3.03 Fire detector surveillance test 2

AK3.04 Actions contained in the abnormal procedure for plant fire on site 3

(CFR: 41.10 / 43.5 / 45.11)

ABILITY

AA1 Ability to operate and/ or monitor the following as they apply to Plant Fire 

On-Site:

(CFR: 41.10 / 43.5 / 45.11)

AA1.01 Respirator air pack 3

AA1.02 Re-installation of fire detector 2

AA1.03 Bypass of fire zone detector 2

AA1.04 Bypass of heat detector 2

AA1.05 Plant and control room habitability area ventilation systems 3

AA1.06 Fire alarm 3

AA1.07 Fire alarm reset panel 2

AA1.08 Fire fighting equipment used on each class of fire 3

AA1.09 Plant fire zone panel (including detector location) 3
4.2-39 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: EPE2023 Plant Fire On-Site (continued)

K/A NO. ABILITY IMPORTANCE

AA2 Ability to determine and interpret the following as they apply to Plant Fire 

On-Site:

(CFR: 41.10 / 43.5 / 45.11)

RO SRO

AA2.01 Damper position 3 3

AA2.02 Fire alarm 3 3

AA2.03 The fire's extent of potential operational damage to plant equipment 3 3

AA2.04 Ventilation alignment necessary to secure affected area 3 3

AA2.05 Need for pressurizing control room (recirculating mode) 3 3

AA2.06 Need for placing control room habitability area HVAC in smoke removal

mode 4 4

AA2.07 Need for placing the reactor building HVAC system in smoke removal

mode 4 4

AA2.08 Need for placing the turbine building HVAC system in smoke removal

mode 4 4

AA2.09 Need for placing the control building safety-related equipment area

HVAC system in smoke removal mode 4 4

AA2.10 Whether malfunction is due to common-mode electrical failures 3 3

AA2.11 Time limit of long-term-breathing air system for control room 3 3

AA2.12 Time limit for use of respirators 3 3

AA2.13 Location of vital equipment within fire zone 3 4

AA2.14 Need for emergency plant shutdown 3 4

AA2.15 Equipment that will be affected by fire suppression activities in each

zone 3 4

AA2.16 Requirements for establishing a fire watch 2 4

AA2.17 Vital equipment and control systems to be maintained and operated

during a fire 3 4

AA2.18 Systems that may be affected by the fire 3 4
NUREG-2104 4.2-40

4.2 Abnormal Plant Evolutions

APE: APE2024 Generator Voltage and Electric Grid Disturbances

K/A NO. KNOWLEDGE IMPORTANCE

AK1. Knowledge of the operational implications of the following concepts as 

they apply to Generator Voltage and Electric Grid Disturbances:

(CFR: 41.4, 41.5, 41.7, 41.10 / 45.8)

AK1.01 Over-excitation 3

AK1.02 Under-excitation 3

AK2. Knowledge of the interrelations between Generator Voltage and Electric 

Grid Disturbances and the following:

(CFR: 41.4, 41.5, 41.7, 41.10 / 45.8)

AK2.01 Motors 3

AK2.02 Breakers, relays 3

AK2.03 Sensors, detectors, indicators 3

AK2.04 Controllers, positioners 3

AK2.05 Pumps 3

AK2.06 Reactor power 4

AK2.07 Turbine/generator control 4

AK2.08 Bus frequency 3

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

Generator Voltage and Electric Grid Disturbances:

(CFR: 41.4, 41.5, 41.7, 41.10 / 45.8)

AK3.01 Reactor and turbine trip criteria 4

AK3.02 Actions contained in abnormal operating procedure for voltage and

grid disturbances 4

ABILITY

AA1. Ability to operate and/or monitor the following as they apply to Generator 

Voltage and Electric Grid Disturbances:

(CFR: 41.5 and 41.10 / 45.5, 45.7, and 45.8)

AA1.01 Grid frequency and voltage 4

AA1.02 Turbine/generator controls 4

AA1.03 Voltage regulator controls 4

AA1.04 Reactor controls 4

AA1.05 Engineered safety features 4
4.2-41 NUREG-2104

4.2 Abnormal Plant Evolutions

APE: APE2024 Generator Voltage and Electric Grid Disturbances (continued)

K/A NO. ABILITY IMPORTANCE

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

Generator Voltage and Electric Grid Disturbances:

(CFR: 41.5 and 43.5 / 45.5, 45.7, and 45.8)

RO SRO

AA2.01 Operating point on the generator capability curve 4 4

AA2.02 Voltage outside the generator capability curve 4 4

AA2.03 Generator current outside the capability curve 4 4

AA2.04 VARs outside capability curve 4 4

AA2.05 Operational status of offsite circuit 3 4

AA2.06 Generator frequency limitations 3 4

AA2.07 Operational status of engineered safety features 4 4

AA2.08 Criteria to trip the turbine or reactor 4 4

AA2.09 Operational status of emergency diesel generators 4 4

AA2.10 Generator overheating and the required actions 4 4

5-1 NUREG 2104

5.0 Components

COMPONENT: 291001 Valves

(CFR: 41.3)

K/A NO. KNOWLEDGE IMPORTANCE

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-2104 5-2

COMPONENT: 291002 Sensors and Detectors

(CFR: 41.7)

K/A NO. KNOWLEDGE IMPORTANCE

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

K1.17 Applications of reed switches, magnets, LVDT, potentiometers,

and limit switches 2.3 2.4
5-3 NUREG 2104

COMPONENT: 291002 Sensors and Detectors (continued)

(CFR: 41.7)

K/A NO. KNOWLEDGE IMPORTANCE

RO SRO

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-2104 5-4

COMPONENT: 291003 Controllers and Positioners

(CFR: 41.7)

K/A NO. KNOWLEDGE IMPORTANCE

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
5-5 NUREG 2104

COMPONENT: 291004 Pumps

(CFR: 41.3)

K/A NO. KNOWLEDGE IMPORTANCE

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 2.9 2.9

Positive Displacement

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

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
NUREG-2104 5-6

COMPONENT: 291005 Motors and Generators

(CFR: 41.7)

K/A NO. KNOWLEDGE IMPORTANCE

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, AC, DC, 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
5-7 NUREG 2104

COMPONENT: 291006 Heat Exchangers and Condensers

(CFR: 41.4)

K/A NO. KNOWLEDGE IMPORTANCE

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 U-types)........ 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
NUREG-2104 5-8

COMPONENT: 291007 Demineralizers and Ion Exchangers

(CFR: 41.3)

K/A NO. KNOWLEDGE IMPORTANCE

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 demineralizer

resin bed 2.6 2.6

K1.09 Effects of demineralizer operation on water conductivity 2.7 2.7
5-9 NUREG 2104

COMPONENT: 291008 Breakers, Relays and Disconnects

(CFR: 41.7)

K/A NO. KNOWLEDGE IMPORTANCE

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-2104

6.0 Theory

6.1 Reactor Theory

(CFR: 41.1)

Reactor Theory: 292001 Neutrons

K/A NO. KNOWLEDGE IMPORTANCE

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-2104 6.1-2

6.1 Reactor Theory

(CFR: 41.1)

Reactor Theory: 292002 Neutron Life Cycle

K/A NO. KNOWLEDGE IMPORTANCE

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 the 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
6.1-3 NUREG-2104

6.1 Reactor Theory

(CFR: 41.1)

Reactor Theory: 292003 Reactor Kinetics and Neutron Sources

K/A NO. KNOWLEDGE IMPORTANCE

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-2104 6.1-4

6.1 Reactor Theory

(CFR: 41.1)

Reactor Theory: 292004 Reactivity Coefficients

K/A NO. KNOWLEDGE IMPORTANCE

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

K1.12 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
6.1-5 NUREG-2104

6.1 Reactor Theory

(CFR: 41.1)

Reactor Theory: 292005 Control Rods

K/A NO. KNOWLEDGE IMPORTANCE

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-2104 6.1-6

6.1 Reactor Theory

(CFR: 41.1)

Reactor Theory: 292006 Fission Product Poisons

K/A NO. KNOWLEDGE IMPORTANCE

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

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
6.1-7 NUREG-2104

6.1 Reactor Theory

(CFR: 41.1)

Reactor Theory: 292007 Fuel Depletion and Burnable Poisons

K/A NO. KNOWLEDGE IMPORTANCE

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
NUREG-2104 6.1-8

6.1 Reactor Theory

(CFR: 41.1)

Reactor Theory: 292008 Reactor Operational Physics

K/A NO. KNOWLEDGE IMPORTANCE

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

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
6.1-9 NUREG-2104

6.1 Reactor Theory

(CFR: 41.1)

Reactor Theory: 292008 Reactor Operational Physics (Continued)

K/A NO. KNOWLEDGE IMPORTANCE

RO SRO

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

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

6.2-1 NUREG-2104

6.2 Thermodynamics Theory

(CFR: 41.14)

Thermodynamics: 293001 Thermodynamic Units and Properties

K/A NO. KNOWLEDGE IMPORTANCE

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-2104 6.2-2

6.2 Thermodynamics Theory

(CFR: 41.14)

Thermodynamics: 293002 Basic Energy Concepts

K/A NO. KNOWLEDGE IMPORTANCE

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-2104

6.2 Thermodynamics Theory

(CFR: 41.14)

Thermodynamics: 293003 Steam

K/A NO. KNOWLEDGE IMPORTANCE

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-2104 6.2-4

6.2 Thermodynamics Theory

(CFR: 41.14)

Thermodynamics: 293004 Thermodynamic Process

K/A NO. KNOWLEDGE IMPORTANCE

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-2104

6.2 Thermodynamics Theory

(CFR: 41.14)

Thermodynamics: 293005 Thermodynamic Cycles

K/A NO. KNOWLEDGE IMPORTANCE

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-2104 6.2-6

6.2 Thermodynamics Theory

(CFR: 41.14)

Thermodynamics: 293006 Fluid Statics

K/A NO. KNOWLEDGE IMPORTANCE

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

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
6.2-7 NUREG-2104

6.2 Thermodynamics Theory

(CFR: 41.14)

Thermodynamics: 293006 Fluid Statics (continued)

K/A NO. KNOWLEDGE IMPORTANCE

RO SRO

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 Describe the methods of controlling system flow rates. 2.6 2.7
NUREG-2104 6.2-8

6.2 Thermodynamics Theory

(CFR: 41.14)

Thermodynamics: 293007 Heat Transfer and Heat Exchangers

K/A NO. KNOWLEDGE IMPORTANCE

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-2104

6.2 Thermodynamics Theory

(CFR: 41.14)

Thermodynamics: 293008 Thermal Hydraulics

K/A NO. KNOWLEDGE IMPORTANCE

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 (T vs. 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 departure from nucleate boiling 2.9 3.1

K1.09 Describe onset of transition boiling. 3.0 3.2

K1.10 Describe 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 onset of transition boiling point along a hypothetical

fuel channel, experiencing two phase flow. 2.5 2.8

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
NUREG-2104 6.2-10

6.2 Thermodynamics Theory

(CFR: 41.14)

Thermodynamics: 293008 Thermal Hydraulics (continued)

K/A NO. KNOWLEDGE IMPORTANCE

RO SRO

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 quality 2.5 2.7

K1.24 Draw the temperature profile from the centerline of a fuel

pellet o 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

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
6.2-11 NUREG-2104

6.2 Thermodynamics Theory

(CFR: 41.14)

Thermodynamics: 293008 Thermal Hydraulics (continued)

K/A NO. KNOWLEDGE IMPORTANCE

RO SRO

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-2104 6.2-12

6.2 Thermodynamics Theory

(CFR: 41.14)

Thermodynamics: 293009 Core Thermal Limits

K/A NO. KNOWLEDGE IMPORTANCE

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

Linear Heat Generation Rate (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

Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

K1.10 Define average planar linear heat generation rate (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

Minimum Critical Power Ratio (MCPR)

K1.17 Define critical power 3.3 3.7

K1.18 Define critical power ratio 3.2 3.7

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
6.2-13 NUREG-2104

6.2 Thermodynamics Theory

(CFR: 41.14)

Thermodynamics: 293009 Core Thermal Limits (continued)

K/A NO. KNOWLEDGE IMPORTANCE

RO SRO

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 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 pellet clad

interaction. 2.2 2.6

PCIOMR

K1.36 Explain the purpose for PCIOMR 2.8 3.4

K1.37 Identify how the PCIOMR rules minimize the adverse effects

of pellet clad interaction. 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
NUREG-2104 6.2-14

6.2 Thermodynamics Theory

(CFR: 41.14)

Thermodynamics: 293010 Brittle Fracture and Vessel Thermal Stress

K/A NO. KNOWLEDGE IMPORTANCE

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
BIBLIOGRAPHIC DATA SHEET

(See instructions on the reverse)

NRC FORM 335

(12-2010)

NRCMD 3.7

U.S. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER

 (Assigned by NRC, Add Vol., Supp., Rev.,

 and Addendum Numbers, if any.)

NUREG-2104

3. DATE REPORT PUBLISHED

MONTH

December

YEAR

2011

4. FIN OR GRANT NUMBER

2. TITLE AND SUBTITLE

Knowledge and Abilities Catalog for Nuclear Power Plant Operators:

Advanced Boiling Water Reactors

5. AUTHOR(S)

R. Pelton

6. TYPE OF REPORT

Technical

7. PERIOD COVERED (Inclusive Dates)

8. PERFORMING ORGANIZATION - NAME AND ADDRESS (If NRC, provide Division, Office or Region, U.S. Nuclear Regulatory Commission, and mailing address; if contractor,

Division of Construction Inspection and Operational Programs

9. SPONSORING ORGANIZATION - NAME AND ADDRESS (If NRC, type "Same as above"; if contractor, provide NRC Division, Office or Region, U.S. Nuclear Regulatory Commission, 

provide name and mailing address.)

and mailing address.)

10. SUPPLEMENTARY NOTES

11. ABSTRACT (200 words or less)

This catalog provides the basis for the development of content-valid licensing examinations for reactor operators (ROs) and

senior reactor operators (SROs). The examinations developed using this Catalog will sample the topics listed under Title 10,

Code of Federal Regulations , Part 55 (10 CFR 55). This is a new Knowledge and Abilities catalog developed specifically to

address the General Electric Advanced Boiling Water Reactor. 

This 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.

12. KEY WORDS/DESCRIPTORS (List words or phrases that will assist researchers in locating the report.)

operator licensing

examinations

reactor operator

senior reactor operator

training

task analysis

advanced boiling water reactors

14. SECURITY CLASSIFICATION

13. AVAILABILITY STATEMENT

unlimited

(This Page)

unclassified

(This Report)

unclassified

15. NUMBER OF PAGES

16. PRICE

NRC FORM 335 (12-2010)

Office of New Reactors

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

Same as above


UNITED STATES 

NUCLEAR REGULATORY COMMISSION

WASHINGTON, DC 20555-0001

--------------------

OFFICIAL BUSINESS
NUREG

-2104

Draft Report

Knowledge and Abilities Catalog for Nuclear Power Plant Operators

Advanced Boiling Water Reactors