Standard Technical 

Specifications

Babcock and Wilcox Plants

Revision 4.0

Volume 1, Specifications

Office of Nuclear Reactor Regulation

NUREG-1430

Volume 1

Revision 4.0

Standard Technical 

Specifications

Babcock and Wilcox Plants

Revision 4.0

Volume 1, Specifications

Manuscript Completed: October 2011

Date Published: April 2012

Office of Nuclear Reactor Regulation

NUREG-1430

Volume 1

Revision 4.0
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Babcock & Wilcox STS iii Rev. 4.0 

ABSTRACT 

This NUREG contains the improved Standard Technical Specifications (STS) for Babcock and 

Wilcox (B&W) plants. The changes reflected in Revision 4 result from the experience gained 

from plant operation using the improved STS and extensive public technical meetings and 

discussions among the Nuclear Regulatory Commission (NRC) staff and various nuclear power 

plant licensees and the Nuclear Steam Supply System (NSSS) Owners Groups.

The improved STS were developed based on the criteria in the Final Commission Policy 

Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 

1993 (58 FR 39132), which was subsequently codified by changes to Section 36 of Part 50 of 

Title 10 of the Code of Federal Regulations (10 CFR 50.36) (60 FR 36953). Licensees are 

encouraged to upgrade their technical specifications consistent with those criteria and 

conforming, to the practical extent, to Revision 4 to the improved STS. The Commission 

continues to place the highest priority on requests for complete conversions to the improved 

STS. Licensees adopting portions of the improved STS to existing technical specifications 

should adopt all related requirements, as applicable, to achieve a high degree of standardization 

and consistency. 

Users may access the STS NUREGs in the PDF format at (http://www.nrc.gov). Users may print 

or download copies from the NRC Web site. 

PAPERWORK REDUCTION ACT STATEMENT 

The information collections contained in this NUREG are covered by the requirements of 

10 CFR Part 50, which were approved by the Office of Management and Budget, approval 

number 3150-0011.

PUBLIC PROTECTION NOTIFICATION 

If a means used to impose an information collection does not display a currently valid OMB 

control number, the NRC may not conduct or sponsor, and a person is not required to respond 

to, the information collection.

Babcock & Wilcox STS v Rev. 4.0 

TABLE OF CONTENTS / REVISION SUMMARY Page Rev.

1.0 USE AND APPLICATION 

1.1 Definitions .....................................................................................................1.1-1 4.0

1.2 Logical Connectors .......................................................................................1.2-1 4.0

1.3 Completion Times ........................................................................................1.3-1 4.0

1.4 Frequency ....................................................................................................1.4-1 4.0

2.0 SAFETY LIMITS (SLs) .......................................................................................2.0-1 4.0

2.1 SLs 

2.2 SL Violations 

3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ..................3.0-1 4.0

3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ................................. 3.0-4 4.0

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.1 SHUTDOWN MARGIN (SDM) ..................................................................3.1.1-1 4.0

3.1.2 Reactivity Balance .....................................................................................3.1.2-1 4.0

3.1.3 Moderator Temperature Coefficient (MTC) ...............................................3.1.3-1 4.0

3.1.4 CONTROL ROD Group Alignment Limits .................................................3.1.4-1 4.0

3.1.5 Safety Rod Insertion Limits .......................................................................3.1.5-1 4.0

3.1.6 AXIAL POWER SHAPING ROD (APSR) Alignment Limits .......................3.1.6-1 4.0

3.1.7 Position Indicator Channels .......................................................................3.1.7-1 4.0

3.1.8 PHYSICS TESTS Exceptions - MODE 1 ..................................................3.1.8-1 4.0

3.1.9 PHYSICS TESTS Exceptions - MODE 2 ..................................................3.1.9-1 4.0

3.2 POWER DISTRIBUTION LIMITS 

3.2.1 Regulating Rod Insertion Limits ................................................................3.2.1-1 4.0

3.2.2 AXIAL POWER SHAPING ROD (APSR) Insertion Limits .........................3.2.2-1 4.0

3.2.3 AXIAL POWER IMBALANCE Operating Limits .........................................3.2.3-1 4.0

3.2.4 QUADRANT POWER TILT (QPT) ............................................................3.2.4-1 4.0

3.2.5 Power Peaking Factors .............................................................................3.2.5-1 4.0

3.3 INSTRUMENTATION 

(Section 3.3 Specifications with an "A" suffix include setpoints. Specifications with a "B" suffix 

reflect a Setpoint Control Program.) 

3.3.1A Reactor Protection System (RPS) Instrumentation ................................. 3.3.1A-1 4.0

3.3.1B Reactor Protection System (RPS) Instrumentation ................................. 3.3.1B-1 4.0

3.3.2 Reactor Protection System (RPS) Manual Reactor Trip ...........................3.3.2-1 4.0

3.3.3A Reactor Protection System (RPS) - Reactor Trip Module (RTM) ............3.3.3A-1 4.0

3.3.3B Reactor Protection System (RPS) - Reactor Trip Module (RTM) ............3.3.3B-1 4.0

3.3.4A CONTROL ROD Drive (CRD) Trip Devices ............................................3.3.4A-1 4.0

3.3.4B CONTROL ROD Drive (CRD) Trip Devices ............................................3.3.4B-1 4.0

3.3.5A Engineered Safety Feature Actuation System (ESFAS) 

 Instrumentation ..................................................................................3.3.5A-1 4.0

3.3.5B Engineered Safety Feature Actuation System (ESFAS) 

 Instrumentation ..................................................................................3.3.5B-1 4.0

3.3.6 Engineered Safety Feature Actuation System (ESFAS) Manual 

 Initiation ...............................................................................................3.3.6-1 4.0

3.3.7 Engineered Safety Feature Actuation System (ESFAS) Automatic 

 Actuation Logic ....................................................................................3.3.7-1 4.0
Babcock & Wilcox STS vi Rev. 4.0 

TABLE OF CONTENTS / REVISION SUMMARY Page Rev.

3.3 INSTRUMENTATION (continued) 

3.3.8A Emergency Diesel Generator (EDG) Loss of Power Start (LOPS) .........3.3.8A-1 4.0

3.3.8B Emergency Diesel Generator (EDG) Loss of Power Start (LOPS) .........3.3.8B-1 4.0

3.3.9A Source Range Neutron Flux ....................................................................3.3.9A-1 4.0

3.3.9B Source Range Neutron Flux ....................................................................3.3.9B-1 4.0

3.3.10A Intermediate Range Neutron Flux .........................................................3.3.10A-1 4.0

3.3.10B Intermediate Range Neutron Flux .........................................................3.3.10B-1 4.0

3.3.11A Emergency Feedwater Initiation and Control (EFIC) System 

 Instrumentation ................................................................................3.3.11A-1 4.0

3.3.11B Emergency Feedwater Initiation and Control (EFIC) System 

 Instrumentation ................................................................................3.3.11B-1 4.0

3.3.12 Emergency Feedwater Initiation and Control (EFIC) Manual 

 Initiation .............................................................................................3.3.12-1 4.0

3.3.13 Emergency Feedwater Initiation and Control (EFIC) Logic .....................3.3.13-1 4.0

3.3.14 Emergency Feedwater Initiation and Control (EFIC) - Emergency 

 Feedwater (EFW) - Vector Valve Logic .............................................3.3.14-1 4.0

3.3.15A Reactor Building (RB) Purge Isolation - High Radiation ........................3.3.15A-1 4.0

3.3.15B Reactor Building (RB) Purge Isolation - High Radiation ........................3.3.15B-1 4.0

3.3.16A Control Room Isolation - High Radiation ...............................................3.3.16A-1 4.0

3.3.16B Control Room Isolation - High Radiation ...............................................3.3.16B-1 4.0

3.3.17 Post Accident Monitoring (PAM) Instrumentation ....................................3.3.17-1 4.0

3.3.18 Remote Shutdown System ......................................................................3.3.18-1 4.0

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate 

 Boiling (DNB) Limits ............................................................................3.4.1-1 4.0

3.4.2 RCS Minimum Temperature for Criticality .................................................3.4.2-1 4.0

3.4.3 RCS Pressure and Temperature (P/T) Limits ...........................................3.4.3-1 4.0

3.4.4 RCS Loops - MODES 1 and 2 ...................................................................3.4.4-1 4.0

3.4.5 RCS Loops - MODE 3 ...............................................................................3.4.5-1 4.0

3.4.6 RCS Loops - MODE 4 ...............................................................................3.4.6-1 4.0

3.4.7 RCS Loops - MODE 5, Loops Filled ..........................................................3.4.7-1 4.0

3.4.8 RCS Loops - MODE 5, Loops Not Filled ...................................................3.4.8-1 4.0

3.4.9 Pressurizer ................................................................................................3.4.9-1 4.0

3.4.10 Pressurizer Safety Valves .......................................................................3.4.10-1 4.0

3.4.11 Pressurizer Power Operated Relief Valve (PORV) ................................. 3.4.11-1 4.0

3.4.12 Low Temperature Overpressure Protection (LTOP) System ..................3.4.12-1 4.0

3.4.13 RCS Operational LEAKAGE ...................................................................3.4.13-1 4.0

3.4.14 RCS Pressure Isolation Valve (PIV) Leakage .........................................3.4.14-1 4.0

3.4.15 RCS Leakage Detection Instrumentation ................................................3.4.15-1 4.0

3.4.16 RCS Specific Activity ...............................................................................3.4.16-1 4.0

3.4.17 Steam Generator (SG) Tube Integrity .....................................................3.4.17-1 4.0

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.1 Core Flood Tanks (CFTs) ..........................................................................3.5.1-1 4.0

3.5.2 ECCS - Operating .....................................................................................3.5.2-1 4.0

3.5.3 ECCS - Shutdown .....................................................................................3.5.3-1 4.0

3.5.4 Borated Water Storage Tank (BWST) .......................................................3.5.4-1 4.0
Babcock & Wilcox STS vii Rev. 4.0 

TABLE OF CONTENTS / REVISION SUMMARY Page Rev.

3.6 CONTAINMENT SYSTEMS 

3.6.1 Containment ..............................................................................................3.6.1-1 4.0

3.6.2 Containment Air Locks ..............................................................................3.6.2-1 4.0

3.6.3 Containment Isolation Valves ....................................................................3.6.3-1 4.0

3.6.4 Containment Pressure ...............................................................................3.6.4-1 4.0

3.6.5 Containment Air Temperature ...................................................................3.6.5-1 4.0

3.6.6 Containment Spray and Cooling Systems .................................................3.6.6-1 4.0 

3.6.7 Spray Additive System ..............................................................................3.6.7-1 4.0

3.7 PLANT SYSTEMS 

3.7.1 Main Steam Safety Valves (MSSVs) .........................................................3.7.1-1 4.0

3.7.2 Main Steam Isolation Valves (MSIVs) .......................................................3.7.2-1 4.0

3.7.3 [Main Feedwater Stop Valves (MFSVs), Main Feedwater Control 

 Valves (MFCVs), and Associated Startup Feedwater Control 

 Valves (SFCVs) ] .................................................................................3.7.3-1 4.0

3.7.4 Atmospheric Vent Valves (AVVs) ..............................................................3.7.4-1 4.0

3.7.5 Emergency Feedwater (EFW) System ......................................................3.7.5-1 4.0

3.7.6 Condensate Storage Tank (CST) ..............................................................3.7.6-1 4.0

3.7.7 Component Cooling Water (CCW) System ...............................................3.7.7-1 4.0

3.7.8 Service Water System (SWS) ...................................................................3.7.8-1 4.0

3.7.9 Ultimate Heat Sink (UHS) ..........................................................................3.7.9-1 4.0

3.7.10 Control Room Emergency Ventilation System (CREVS) ........................3.7.10-1 4.0

3.7.11 Control Room Emergency Air Temperature Control System 

 (CREATCS) .......................................................................................3.7.11-1 4.0

3.7.12 Emergency Ventilation System (EVS) .....................................................3.7.12-1 4.0

3.7.13 Fuel Storage Pool Ventilation System (FSPVS) ......................................3.7.13-1 4.0

3.7.14 Fuel Storage Pool Water Level ...............................................................3.7.14-1 4.0

[ 3.7.15 Spent Fuel Pool Boron Concentration .....................................................3.7.15-1 4.0 ] 

[ 3.7.16 Spent Fuel Pool Storage .........................................................................3.7.16-1 4.0 ] 

3.7.17 Secondary Specific Activity .....................................................................3.7.17-1 4.0

3.7.18 Steam Generator Level ...........................................................................3.7.18-1 4.0

3.8 ELECTRICAL POWER SYSTEMS 

3.8.1 AC Sources - Operating ............................................................................3.8.1-1 4.0

3.8.2 AC Sources - Shutdown ............................................................................3.8.2-1 4.0

3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air .................................................3.8.3-1 4.0

3.8.4 DC Sources - Operating ............................................................................3.8.4-1 4.0

3.8.5 DC Sources - Shutdown ............................................................................3.8.5-1 4.0

3.8.6 Battery Parameters ...................................................................................3.8.6-1 4.0

3.8.7 Inverters - Operating .................................................................................3.8.7-1 4.0

3.8.8 Inverters - Shutdown .................................................................................3.8.8-1 4.0 

3.8.9 Distribution Systems - Operating ...............................................................3.8.9-1 4.0

3.8.10 Distribution Systems - Shutdown ............................................................3.8.10-1 4.0

3.9 REFUELING OPERATIONS 

3.9.1 Boron Concentration .................................................................................3.9.1-1 4.0

3.9.2 Nuclear Instrumentation ............................................................................3.9.2-1 4.0

3.9.3 Containment Penetrations .........................................................................3.9.3-1 4.0 
Babcock & Wilcox STS viii Rev. 4.0 

TABLE OF CONTENTS / REVISION SUMMARY Page Rev.

3.9 REFUELING OPERATIONS (continued) 

3.9.4 Decay Heat Removal (DHR) and Coolant Circulation – High Water 

 Level ....................................................................................................3.9.4-1 4.0

3.9.5 Decay Heat Removal (DHR) and Coolant Circulation – Low Water 

 Level ....................................................................................................3.9.5-1 4.0

3.9.6 Refueling Canal Water Level .....................................................................3.9.6-1 4.0

4.0 DESIGN FEATURES .........................................................................................4.0-1 4.0

4.1 Site Location 

4.2 Reactor Core 

4.3 Fuel Storage 

5.0 ADMINISTRATIVE CONTROLS 

5.1 Responsibility ...............................................................................................5.1-1 4.0

5.2 Organization ................................................................................................. 5.2-1 4.0

5.3 Unit Staff Qualifications ................................................................................5.3-1 4.0

5.4 Procedures ..................................................................................................5.4-1 4.0

5.5 Programs and Manuals ...............................................................................5.5-1 4.0

5.6 Reporting Requirements .............................................................................5.6-1 4.0

5.7 High Radiation Area .....................................................................................5.7-1 4.0
Definitions 

1.1

Babcock & Wilcox STS 1.1-1 Rev. 4.0 

1.0 USE AND APPLICATION 

1.1 Definitions 

------------------------------------------------------------NOTE-----------------------------------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these 

Technical Specifications and Bases. 

-------------------------------------------------------------------------------------------------------------------------------

Term Definition 

ACTIONS ACTIONS shall be that part of a Specification that prescribes 

Required Actions to be taken under designated Conditions 

within specified Completion Times. 

ALLOWABLE THERMAL ALLOWABLE THERMAL POWER shall be the maximum 

POWER reactor core heat transfer rate to the reactor coolant permitted 

by consideration of the number and configuration of reactor 

coolant pumps (RCPs) in operation. 

AXIAL POWER IMBALANCE AXIAL POWER IMBALANCE shall be the power in the top half 

of the core, expressed as a percentage of RATED THERMAL 

POWER (RTP), minus the power in the bottom half of the 

core, expressed as a percentage of RTP. 

AXIAL POWER SHAPING APSRs shall be control components used to control the axial 

RODS (APSRs) power distribution of the reactor core. The APSRs are 

positioned manually by the operator and are not trippable. 

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as 

necessary, of the channel output such that it responds within 

the necessary range and accuracy to known values of the 

parameter that the channel monitors. The CHANNEL 

CALIBRATION shall encompass all devices in the channel 

required for channel OPERABILITY and the CHANNEL 

FUNCTIONAL TEST. Calibration of instrument channels with 

resistance temperature detector (RTD) or thermocouple 

sensors may consist of an inplace qualitative assessment of 

sensor behavior and normal calibration of the remaining 

adjustable devices in the channel. The CHANNEL 

CALIBRATION may be performed by means of any series of 

sequential, overlapping, or total channel steps. 

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by 

observation, of channel behavior during operation. This 

determination shall include, where possible, comparison of the 

channel indication and status to other indications or status 

derived from independent instrument channels measuring the 

same parameter. 
Definitions 

1.1

Babcock & Wilcox STS 1.1-2 Rev. 4.0 

1.1 Definitions 

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a 

simulated or actual signal into the channel as close to the 

sensor as practicable to verify OPERABILITY of all devices in 

the channel required for channel OPERABILITY. 

The ESFAS CHANNEL FUNCTIONAL TEST shall also include 

testing of ESFAS safety related bypass functions for each 

channel affected by bypass operation. The CHANNEL 

FUNCTIONAL TEST may be performed by means of any 

series of sequential, overlapping, or total steps. 

CONTROL RODS CONTROL RODS shall be all full length safety and regulating 

rods that are used to shut down the reactor and control power 

level during maneuvering operations. 

CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle 

REPORT (COLR) specific parameter limits for the current reload cycle. These 

cycle specific limits shall be determined for each reload cycle 

in accordance with Specification 5.6.3. Plant operation within 

these limits is addressed in individual Specifications. 

DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 

(microcuries/gram) that alone would produce the same thyroid 

dose as the quantity and isotopic mixture of I-131, I-132, I-133, 

I-134, and I-135 actually present. The thyroid dose conversion 

factors used for this calculation shall be those listed in 

[Table III of TID-14844, AEC, 1962, "Calculation of Distance 

Factors for Power and Test Reactor Sites," or those listed in 

Table E-7 of Regulatory Guide 1.109, Rev. 1, NRC, 1977, or 

ICRP 30, Supplement to Part 1, page 192-212, table titled, 

"Committed Dose Equivalent in Target Organs or Tissues per 

Intake of Unit Activity"]. 

Ē - AVERAGE Ē shall be the average (weighted in proportion to the 

DISINTEGRATION ENERGY concentration of each radionuclide in the reactor coolant at the 

time of sampling) of the sum of the average beta and gamma 

energies per disintegration (in MeV) for isotopes, other than 

iodines, with half lives > [15] minutes, making up at least 95% 

of the total noniodine activity in the coolant.
Definitions 

1.1

Babcock & Wilcox STS 1.1-3 Rev. 4.0 

1.1 Definitions 

EMERGENCY FEEDWATER The EFIC RESPONSE TIME shall be that time interval from 

INITIATION AND CONTROL when the monitored parameter exceeds its EFIC actuation 

(EFIC) RESPONSE TIME setpoint at the channel sensor until the emergency feedwater 

equipment is capable of performing its function (i.e., valves 

travel to their required positions, pumps discharge pressures 

reach their required values, etc.). Times shall include diesel 

generator starting and sequence loading delays, where 

applicable. The response time may be measured by means of 

any series of sequential, overlapping, or total steps so that the 

entire response time is measured. 

ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval from 

FEATURE (ESF) RESPONSE when the monitored parameter exceeds its ESF actuation 

TIME setpoint at the channel sensor until the ESF equipment is 

capable of performing its safety function (i.e., the valves travel 

to their required positions, pump discharge pressures reach 

their required values, etc.). Times shall include diesel 

generator starting and sequence loading delays, where 

applicable. The response time may be measured by means of 

any series of sequential, overlapping, or total steps so that the 

entire response time is measured. 

LEAKAGE LEAKAGE shall be: 

a. Identified LEAKAGE 

1. LEAKAGE, such as that from pump seals or valve 

packing (except RCP seal water injection or 

leakoff), that is captured and conducted to 

collection systems or a sump or collecting tank, 

2. LEAKAGE into the containment atmosphere from 

sources that are both specifically located and 

known either not to interfere with the operation of 

leakage detection systems or not to be pressure 

boundary LEAKAGE, or 

3. Reactor Coolant System (RCS) LEAKAGE through 

a steam generator to the Secondary System 

(primary to secondary LEAKAGE), 

b. Unidentified LEAKAGE 

 All LEAKAGE (except RCP seal water injection or 

leakoff) that is not identified LEAKAGE, and 
Definitions 

1.1

Babcock & Wilcox STS 1.1-4 Rev. 4.0 

1.1 Definitions 

LEAKAGE (continued) 

c. Pressure Boundary LEAKAGE 

 LEAKAGE (except primary to secondary LEAKAGE) 

through a nonisolable fault in an RCS component body, 

pipe wall, or vessel wall. 

MODE A MODE shall correspond to any one inclusive combination of 

core reactivity condition, power level, average reactor coolant 

temperature, and reactor vessel head closure bolt tensioning 

specified in Table 1.1-1 with fuel in the reactor vessel. 

NUCLEAR HEAT FLUX HOT FQ(Z) shall be the maximum local linear power density in the 

CHANNEL FACTOR FQ(Z) core divided by the core average fuel rod linear power density, 

assuming nominal fuel pellet and fuel rod dimensions. 

NUCLEAR ENTHALPY RISE 

N FH

 shall be the ratio of the integral of linear power along the 

HOT CHANNEL FACTOR 

N FH

fuel rod on which minimum departure from nucleate boiling 

ratio occurs, to the average fuel rod power.

OPERABLE – OPERABILITY A system, subsystem, train, component, or device shall be 

OPERABLE or have OPERABILITY when it is capable of 

performing its specified safety function(s) and when all 

necessary attendant instrumentation, controls, normal or 

emergency electrical power, cooling and seal water, 

lubrication, and other auxiliary equipment that are required for 

the system, subsystem, train, component, or device to perform 

its specified safety function(s) are also capable of performing 

their related support function(s). 

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure 

the fundamental nuclear characteristics of the reactor core and 

related instrumentation. 

These tests are: 

a. Described in Chapter [14, Initial Test Program] of the 

FSAR, 

b. Authorized under the provisions of 10 CFR 50.59, or

c. Otherwise approved by the Nuclear Regulatory 

Commission. 
Definitions 

1.1

Babcock & Wilcox STS 1.1-5 Rev. 4.0 

1.1 Definitions 

PRESSURE AND The PTLR is the unit specific document that provides the 

TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including 

REPORT (PTLR) heatup and cooldown rates, for the current reactor vessel 

fluence period. These pressure and temperature limits shall 

be determined for each fluence period in accordance with 

Specification 5.6.4. 

QUADRANT POWER TILT QPT shall be defined by the following equation and is 

expressed as a percentage of the Power in any Core Quadrant 

(Pquad) to the Average Power of all Quadrants (Pavg).

 QPT = 100 [ (Pquad / Pavg) - 1 ]

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the 

(RTP) reactor coolant of [2544] MWt. 

REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval from 

SYSTEM (RPS) RESPONSE when the monitored parameter exceeds its RPS trip setpoint at 

TIME the channel sensor until electrical power is interrupted at the 

control rod drive trip breakers. The response time may be 

measured by means of any series of sequential, overlapping, 

or total steps so that the entire response time is measured. 

SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which 

the reactor is subcritical or would be subcritical from its 

present condition assuming: 

a. All full length CONTROL RODS (safety and regulating) 

are fully inserted except for the single CONTROL ROD 

of highest reactivity worth, which is assumed to be fully 

withdrawn. However, with all CONTROL RODS verified 

fully inserted by two independent means, it is not 

necessary to account for a stuck CONTROL ROD in the 

SDM calculation. With any CONTROL ROD not capable 

of being fully inserted, the reactivity worth of these 

CONTROL RODS must be accounted for in the 

determination of SDM, 

b. In MODES 1 and 2, the fuel and moderator temperatures 

are changed to the [nominal zero power design level], 

and

c. There is no change in APSR position. 
Definitions 

1.1

Babcock & Wilcox STS 1.1-6 Rev. 4.0 

1.1 Definitions 

[ STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of 

one of the systems, subsystems, channels, or other 

designated components during the interval specified by the 

Surveillance Frequency, so that all systems, subsystems, 

channels, or other designated components are tested during n

Surveillance Frequency intervals, where n is the total number 

of systems, subsystems, channels, or other designated 

components in the associated function. ]

THERMAL POWER THERMAL POWER shall be the total reactor core heat 

transfer rate to the reactor coolant. 
Definitions 

1.1

Babcock & Wilcox STS 1.1-7 Rev. 4.0 

Table 1.1-1 (page 1 of 1)

MODES 

MODE TITLE

REACTIVITY

CONDITION

(keff)

% RATED

THERMAL

POWER(a)

AVERAGE

REACTOR COOLANT

TEMPERATURE

(F)

1 Power Operation  0.99 > 5 NA

2 Startup  0.99  5 NA

3 Hot Standby < 0.99 NA  [330]

4 Hot Shutdown(b) < 0.99 NA [330] > Tavg > [200]

5 Cold Shutdown(b) < 0.99 NA  [200]

6 Refueling(c) NA NA NA

(a) Excluding decay heat. 

(b) All reactor vessel head closure bolts fully tensioned. 

(c) One or more reactor vessel head closure bolts less than fully tensioned.

Logical Connectors 

1.2

Babcock & Wilcox STS 1.2-1 Rev. 4.0 

1.0 USE AND APPLICATION 

1.2 Logical Connectors 

PURPOSE The purpose of this section is to explain the meaning of logical 

connectors. 

Logical connectors are used in Technical Specifications (TS) to 

discriminate between, and yet connect, discrete Conditions, Required 

Actions, Completion Times, Surveillances, and Frequencies. The only 

logical connectors that appear in TS are AND and OR. The physical 

arrangement of these connectors constitutes logical conventions with 

specific meanings. 

BACKGROUND Several levels of logic may be used to state Required Actions. These 

levels are identified by the placement (or nesting) of the logical 

connectors and by the number assigned to each Required Action. The 

first level of logic is identified by the first digit of the number assigned to a 

Required Action and the placement of the logical connector in the first 

level of nesting (i.e., left justified with the number of the Required Action). 

The successive levels of logic are identified by additional digits of the 

Required Action number and by successive indentations of the logical 

connectors. 

When logical connectors are used to state a Condition, Completion Time, 

Surveillance, or Frequency, only the first level of logic is used, and the 

logical connector is left justified with the statement of the Condition, 

Completion Time, Surveillance, or Frequency. 

EXAMPLES The following examples illustrate the use of logical connectors. 
Logical Connectors 

1.2

Babcock & Wilcox STS 1.2-2 Rev. 4.0 

1.2 Logical Connectors 

EXAMPLES (continued) 

EXAMPLE 1.2-1 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. LCO not met. A.1 Verify . . .

AND

A.2 Restore . . .

In this example the logical connector AND is used to indicate that when in 

Condition A, both Required Actions A.1 and A.2 must be completed.
Logical Connectors 

1.2

Babcock & Wilcox STS 1.2-3 Rev. 4.0 

1.2 Logical Connectors 

EXAMPLES (continued) 

EXAMPLE 1.2-2 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. LCO not met. A.1 Trip . . .

OR

A.2.1 Verify . . .

AND

A.2.2.1 Reduce . . .

OR

A.2.2.2 Perform . . .

OR

A.3 Align . . .

This example represents a more complicated use of logical connectors. 

Required Actions A.1, A.2, and A.3 are alternative choices, only one of 

which must be performed as indicated by the use of the logical connector 

OR and the left justified placement. Any one of these three Actions may 

be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be 

performed as indicated by the logical connector AND. Required 

Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented 

position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are 

alternative choices, only one of which must be performed. 

Completion Times 

1.3

Babcock & Wilcox STS 1.3-1 Rev. 4.0 

1.0 USE AND APPLICATION 

1.3 Completion Times 

PURPOSE The purpose of this section is to establish the Completion Time 

convention and to provide guidance for its use. 

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements 

for ensuring safe operation of the unit. The ACTIONS associated with an 

LCO state Conditions that typically describe the ways in which the 

requirements of the LCO can fail to be met. Specified with each stated 

Condition are Required Action(s) and Completion Time(s). 

DESCRIPTION The Completion Time is the amount of time allowed for completing a 

Required Action. It is referenced to the time of discovery of a situation 

(e.g., inoperable equipment or variable not within limits) that requires 

entering an ACTIONS Condition unless otherwise specified, providing the 

unit is in a MODE or specified condition stated in the Applicability of the 

LCO. Required Actions must be completed prior to the expiration of the 

specified Completion Time. An ACTIONS Condition remains in effect and 

the Required Actions apply until the Condition no longer exists or the unit 

is not within the LCO Applicability. 

If situations are discovered that require entry into more than one 

Condition at a time within a single LCO (multiple Conditions), the 

Required Actions for each Condition must be performed within the 

associated Completion Time. When in multiple Conditions, separate 

Completion Times are tracked for each Condition starting from the time of 

discovery of the situation that required entry into the Condition. 

Once a Condition has been entered, subsequent trains, subsystems, 

components, or variables expressed in the Condition, discovered to be 

inoperable or not within limits, will not result in separate entry into the 

Condition, unless specifically stated. The Required Actions of the 

Condition continue to apply to each additional failure, with Completion 

Times based on initial entry into the Condition. 

However, when a subsequent train, subsystem, component, or variable, 

expressed in the Condition, is discovered to be inoperable or not within 

limits, the Completion Time(s) may be extended. To apply this 

Completion Time extension, two criteria must first be met. The 

subsequent inoperability: 

a. Must exist concurrent with the first inoperability and 

b. Must remain inoperable or not within limits after the first inoperability 

is resolved. 
Completion Times 

1.3

Babcock & Wilcox STS 1.3-2 Rev. 4.0 

1.3 Completion Times 

DESCRIPTION (continued) 

The total Completion Time allowed for completing a Required Action to 

address the subsequent inoperability shall be limited to the more 

restrictive of either: 

a. The stated Completion Time, as measured from the initial entry into 

the Condition, plus an additional 24 hours or 

b. The stated Completion Time as measured from discovery of the 

subsequent inoperability. 

The above Completion Time extensions do not apply to those 

Specifications that have exceptions that allow completely separate reentry into the Condition (for each train, subsystem, component, or 

variable expressed in the Condition) and separate tracking of Completion 

Times based on this re-entry. These exceptions are stated in individual 

Specifications. 

The above Completion Time extension does not apply to a Completion 

Time with a modified "time zero." This modified "time zero" may be 

expressed as a repetitive time (i.e., "once per 8 hours," where the 

Completion Time is referenced from a previous completion of the 

Required Action versus the time of Condition entry) or as a time modified 

by the phrase "from discovery . . ." 

EXAMPLES The following examples illustrate the use of Completion Times with 

different types of Conditions and changing Conditions.

EXAMPLE 1.3-1 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

B. Required 

Action and 

associated 

Completion 

Time not met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 5.

6 hours

36 hours

Condition B has two Required Actions. Each Required Action has its own 

separate Completion Time. Each Completion Time is referenced to the 

time that Condition B is entered.
Completion Times 

1.3

Babcock & Wilcox STS 1.3-3 Rev. 4.0 

1.3 Completion Times 

EXAMPLES (continued) 

The Required Actions of Condition B are to be in MODE 3 within 6 hours 

AND in MODE 5 within 36 hours. A total of 6 hours is allowed for 

reaching MODE 3 and a total of 36 hours (not 42 hours) is allowed for 

reaching MODE 5 from the time that Condition B was entered. If MODE 3 

is reached within 3 hours, the time allowed for reaching MODE 5 is the 

next 33 hours because the total time allowed for reaching MODE 5 is 

36 hours. 

If Condition B is entered while in MODE 3, the time allowed for reaching 

MODE 5 is the next 36 hours. 

EXAMPLE 1.3-2 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One pump 

inoperable.

A.1 Restore pump to 

OPERABLE status.

7 days

B. Required 

Action and 

associated 

Completion 

Time not met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 5.

6 hours

36 hours

When a pump is declared inoperable, Condition A is entered. If the pump 

is not restored to OPERABLE status within 7 days, Condition B is also 

entered and the Completion Time clocks for Required Actions B.1 

and B.2 start. If the inoperable pump is restored to OPERABLE status 

after Condition B is entered, Conditions A and B are exited, and therefore, 

the Required Actions of Condition B may be terminated.

When a second pump is declared inoperable while the first pump is still 

inoperable, Condition A is not re-entered for the second pump. 

LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for 

more than one inoperable pump. The Completion Time clock for 

Condition A does not stop after LCO 3.0.3 is entered, but continues to be 

tracked from the time Condition A was initially entered. 
Completion Times 

1.3

Babcock & Wilcox STS 1.3-4 Rev. 4.0 

1.3 Completion Times 

EXAMPLES (continued) 

While in LCO 3.0.3, if one of the inoperable pumps is restored to 

OPERABLE status and the Completion Time for Condition A has not 

expired, LCO 3.0.3 may be exited and operation continued in accordance 

with Condition A.

While in LCO 3.0.3, if one of the inoperable pumps is restored to 

OPERABLE status and the Completion Time for Condition A has expired, 

LCO 3.0.3 may be exited and operation continued in accordance with 

Condition B. The Completion Time for Condition B is tracked from the 

time the Condition A Completion Time expired. 

On restoring one of the pumps to OPERABLE status, the Condition A 

Completion Time is not reset, but continues from the time the first pump 

was declared inoperable. This Completion Time may be extended if the 

pump restored to OPERABLE status was the first inoperable pump. A 

24 hour extension to the stated 7 days is allowed, provided this does not 

result in the second pump being inoperable for > 7 days. 
Completion Times 

1.3

Babcock & Wilcox STS 1.3-5 Rev. 4.0 

1.3 Completion Times 

EXAMPLES (continued) 

EXAMPLE 1.3-3 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One 

Function X 

train 

inoperable.

A.1 Restore Function X 

train to OPERABLE 

status.

7 days

B. One 

Function Y 

train 

inoperable.

B.1 Restore Function Y 

train to OPERABLE 

status.

72 hours

C. One 

Function X 

train 

inoperable.

AND

One 

Function Y 

train 

inoperable.

C.1 Restore Function X 

train to OPERABLE 

status.

OR

C.2 Restore Function Y 

train to OPERABLE 

status.

72 hours

72 hours
Completion Times 

1.3

Babcock & Wilcox STS 1.3-6 Rev. 4.0 

1.3 Completion Times 

EXAMPLES (continued) 

When one Function X train and one Function Y train are inoperable, 

Condition A and Condition B are concurrently applicable. The Completion 

Times for Condition A and Condition B are tracked separately for each 

train starting from the time each train was declared inoperable and the 

Condition was entered. A separate Completion Time is established for 

Condition C and tracked from the time the second train was declared 

inoperable (i.e., the time the situation described in Condition C was 

discovered). 

If Required Action C.2 is completed within the specified Completion Time, 

Conditions B and C are exited. If the Completion Time for Required 

Action A.1 has not expired, operation may continue in accordance with 

Condition A. The remaining Completion Time in Condition A is measured 

from the time the affected train was declared inoperable (i.e., initial entry 

into Condition A).

It is possible to alternate between Conditions A, B, and C in such a 

manner that operation could continue indefinitely without ever restoring 

systems to meet the LCO. However, doing so would be inconsistent with 

the basis of the Completion Times. Therefore, there shall be 

administrative controls to limit the maximum time allowed for any 

combination of Conditions that result in a single contiguous occurrence of 

failing to meet the LCO. These administrative controls shall ensure that 

the Completion Times for those Conditions are not inappropriately 

extended. 
Completion Times 

1.3

Babcock & Wilcox STS 1.3-7 Rev. 4.0 

1.3 Completion Times 

EXAMPLES (continued)

EXAMPLE 1.3-4 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more 

valves 

inoperable.

A.1 Restore valve(s) to 

OPERABLE status.

4 hours

B. Required 

Action and 

associated 

Completion 

Time not met.

B.1 Be in MODE 3..

AND

B.2 Be in MODE 4

6 hours

12 hours

A single Completion Time is used for any number of valves inoperable at 

the same time. The Completion Time associated with Condition A is 

based on the initial entry into Condition A and is not tracked on a per 

valve basis. Declaring subsequent valves inoperable, while Condition A 

is still in effect, does not trigger the tracking of separate Completion 

Times. 

Once one of the valves has been restored to OPERABLE status, the 

Condition A Completion Time is not reset, but continues from the time the 

first valve was declared inoperable. The Completion Time may be 

extended if the valve restored to OPERABLE status was the first 

inoperable valve. The Condition A Completion Time may be extended for 

up to 4 hours provided this does not result in any subsequent valve being 

inoperable for > 4 hours. 

If the Completion Time of 4 hours (plus the extension) expires while one 

or more valves are still inoperable, Condition B is entered. 
Completion Times 

1.3

Babcock & Wilcox STS 1.3-8 Rev. 4.0 

1.3 Completion Times 

EXAMPLES (continued) 

EXAMPLE 1.3-5 

ACTIONS 

---------------------------------------------NOTE--------------------------------------------

Separate Condition entry is allowed for each inoperable valve. 

--------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more 

valves 

inoperable.

A.1 Restore valve to 

OPERABLE status.

4 hours

B. Required 

Action and 

associated 

Completion 

Time not met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 4.

6 hours

12 hours

The Note above the ACTIONS Table is a method of modifying how the 

Completion Time is tracked. If this method of modifying how the 

Completion Time is tracked was applicable only to a specific Condition, 

the Note would appear in that Condition rather than at the top of the 

ACTIONS Table. 

The Note allows Condition A to be entered separately for each inoperable 

valve, and Completion Times tracked on a per valve basis. When a valve 

is declared inoperable, Condition A is entered and its Completion Time 

starts. If subsequent valves are declared inoperable, Condition A is 

entered for each valve and separate Completion Times start and are 

tracked for each valve. 

If the Completion Time associated with a valve in Condition A expires, 

Condition B is entered for that valve. If the Completion Times associated 

with subsequent valves in Condition A expire, Condition B is entered 

separately for each valve and separate Completion Times start and are 

tracked for each valve. If a valve that caused entry into Condition B is 

restored to OPERABLE status, Condition B is exited for that valve. 
Completion Times 

1.3

Babcock & Wilcox STS 1.3-9 Rev. 4.0 

1.3 Completion Times 

EXAMPLES (continued) 

Since the Note in this example allows multiple Condition entry and 

tracking of separate Completion Times, Completion Time extensions do 

not apply.

EXAMPLE 1.3-6 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One channel 

inoperable.

A.1 Perform SR 3.x.x.x.

OR

A.2 Reduce THERMAL 

POWER to 

 50% RTP.

Once per 8 hours

8 hours

B. Required 

Action and 

associated 

Completion 

Time not met.

B.1 Be in MODE 3. 6 hours

Entry into Condition A offers a choice between Required Action A.1 

or A.2. Required Action A.1 has a "once per" Completion Time, which 

qualifies for the 25% extension, per SR 3.0.2, to each performance after 

the initial performance. The initial 8 hour interval of Required Action A.1 

begins when Condition A is entered and the initial performance of 

Required Action A.1 must be complete within the first 8 hour interval. If 

Required Action A.1 is followed and the Required Action is not met within 

the Completion Time (plus the extension allowed by SR 3.0.2), 

Condition B is entered. If Required Action A.2 is followed and the 

Completion Time of 8 hours is not met, Condition B is entered. 

If after entry into Condition B, Required Action A.1 or A.2 is met, 

Condition B is exited and operation may then continue in Condition A.
Completion Times 

1.3

Babcock & Wilcox STS 1.3-10 Rev. 4.0 

1.3 Completion Times 

EXAMPLES (continued) 

EXAMPLE 1.3-7 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One 

subsystem 

inoperable.

A.1 Verify affected 

subsystem isolated.

AND

A.2 Restore subsystem 

to OPERABLE 

status.

1 hour

AND

Once per 8 hours 

thereafter

72 hours

B. Required 

Action and 

associated 

Completion 

Time not met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 5.

6 hours

36 hours

Required Action A.1 has two Completion Times. The 1 hour Completion 

Time begins at the time the Condition is entered and each "Once per 

8 hours thereafter" interval begins upon performance of Required 

Action A.1. 

If after Condition A is entered, Required Action A.1 is not met within either 

the initial 1 hour or any subsequent 8 hour interval from the previous 

performance (plus the extension allowed by SR 3.0.2), Condition B is 

entered. The Completion Time clock for Condition A does not stop after 

Condition B is entered, but continues from the time Condition A was 

initially entered. If Required Action A.1 is met after Condition B is 

entered, Condition B is exited and operation may continue in accordance 

with Condition A, provided the Completion Time for Required Action A.2 

has not expired. 
Completion Times 

1.3

Babcock & Wilcox STS 1.3-11 Rev. 4.0 

1.3 Completion Times 

IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action 

COMPLETION TIME should be pursued without delay and in a controlled manner. 

Frequency

1.4

Babcock & Wilcox STS 1.4-1 Rev. 4.0 

1.0 USE AND APPLICATION 

1.4 Frequency

PURPOSE The purpose of this section is to define the proper use and application of 

Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which 

the Surveillance must be met in order to meet the associated LCO. An 

understanding of the correct application of the specified Frequency is 

necessary for compliance with the SR. 

The "specified Frequency" is referred to throughout this section and each 

of the Specifications of Section 3.0.2, Surveillance Requirement (SR) 

Applicability. The "specified Frequency" consists of the requirements of 

the Frequency column of each SR, as well as certain Notes in the 

Surveillance column that modify performance requirements. 

Sometimes special situations dictate when the requirements of a 

Surveillance are to be met. They are "otherwise stated" conditions 

allowed by SR 3.0.1. They may be stated as clarifying Notes in the 

Surveillance, as part of the Surveillance, or both. 

Situations where a Surveillance could be required (i.e., its Frequency 

could expire), but where it is not possible or not desired that it be 

preformed until sometime after the associated LCO is within its 

Applicability, represent potential SR 3.0.4 conflicts. To avoid these 

conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such 

that it is only "required" when it can be and should be performed. With an 

SR satisfied, SR 3.0.4 imposes no restriction. 

The use of "met" or "performed" in these instances conveys specific 

meanings. A Surveillance is "met" only when the acceptance criteria are 

satisfied. Known failure of the requirements of a Surveillance, even 

without a Surveillance specifically being "performed," constitutes a 

Surveillance not "met." "Performance" refers only to the requirement to 

specifically determine the ability to meet the acceptance criteria. 

Some Surveillances contain notes that modify the Frequency of 

performance or the conditions during which the acceptance criteria must 

be satisfied. For these Surveillances, the MODE-entry restrictions of 

SR 3.0.4 may not apply. Such a Surveillance is not required to be 

performed prior to entering a MODE or other specified condition in the 

Applicability of the associated LCO if any of the following three conditions 

are satisfied: 
Frequency

1.4

Babcock & Wilcox STS 1.4-2 Rev. 4.0 

1.4 Frequency

DESCRIPTION (continued) 

a. The Surveillance is not required to be met in the MODE or other 

specified condition to be entered; or 

b. The Surveillance is required to be met in the MODE or other 

specified condition to be entered, but has been performed within the 

specified Frequency (i.e., it is current) and is known not to be 

failed; or

c. The Surveillance is required to be met, but not performed, in the 

MODE or other specified condition to be entered, and is known not 

to be failed.

Examples 1.4-3, 1.4-4, 1.4-5, and 1.4-6 discuss these special situations. 

EXAMPLES The following examples illustrate the various ways that Frequencies are 

specified. In these examples, the Applicability of the LCO (LCO not 

shown) is MODES 1, 2, and 3.
Frequency

1.4

Babcock & Wilcox STS 1.4-3 Rev. 4.0 

1.4 Frequency

EXAMPLES (continued) 

EXAMPLE 1.4-1 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

Perform CHANNEL CHECK. 12 hours

Example 1.4-1 contains the type of SR most often encountered in the 

Technical Specifications (TS). The Frequency specifies an interval 

(12 hours) during which the associated Surveillance must be performed at 

least one time. Performance of the Surveillance initiates the subsequent 

interval. Although the Frequency is stated as 12 hours, an extension of 

the time interval to 1.25 times the stated Frequency is allowed by 

SR 3.0.2 for operational flexibility. The measurement of this interval 

continues at all times, even when the SR is not required to be met per 

SR 3.0.1 (such as when the equipment is inoperable, a variable is outside 

specified limits, or the unit is outside the Applicability of the LCO). If the 

interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or

other specified condition in the Applicability of the LCO, and the 

performance of the Surveillance is not otherwise modified (refer to 

Example 1.4-3), then SR 3.0.3 becomes applicable.

If the interval as specified by SR 3.0.2 is exceeded while the unit is not in 

a MODE or other specified condition in the Applicability of the LCO for 

which performance of the SR is required, then SR 3.0.4 becomes 

applicable. The Surveillance must be performed within the Frequency 

requirements of SR 3.0.2, as modified by SR 3.0.3, prior to entry into the 

MODE or other specified condition or the LCO is considered not met (in 

accordance with SR 3.0.1) and LCO 3.0.4 becomes applicable.
Frequency

1.4

Babcock & Wilcox STS 1.4-4 Rev. 4.0 

1.4 Frequency

EXAMPLES (continued) 

EXAMPLE 1.4-2 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

Verify flow is within limits. Once within 

12 hours after 

 25% RTP

AND

24 hours thereafter

Example 1.4-2 has two Frequencies. The first is a one time performance 

Frequency, and the second is of the type shown in Example 1.4-1. The 

logical connector "AND" indicates that both Frequency requirements must 

be met. Each time reactor power is increased from a power level 

< 25% RTP to  25% RTP, the Surveillance must be performed within 

12 hours.

The use of "once" indicates a single performance will satisfy the specified 

Frequency (assuming no other Frequencies are connected by "AND"). 

This type of Frequency does not qualify for the extension allowed by 

SR 3.0.2. "Thereafter" indicates future performances must be established 

per SR 3.0.2, but only after a specified condition is first met (i.e., the 

"once" performance in this example). If reactor power decreases to 

< 25% RTP, the measurement of both intervals stops. New intervals start 

upon reactor power reaching 25% RTP. 
Frequency

1.4

Babcock & Wilcox STS 1.4-5 Rev. 4.0 

1.4 Frequency

EXAMPLES (continued) 

EXAMPLE 1.4-3 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

----------------------------NOTE----------------------------

Not required to be performed until 12 hours after 

 25% RTP.

----------------------------------------------------------------

Perform channel adjustment. 7 days

The interval continues whether or not the unit operation is < 25% RTP 

between performances. 

As the Note modifies the required performance of the Surveillance, it is 

construed to be part of the "specified Frequency." Should the 7 day 

interval be exceeded while operation is < 25% RTP, this Note allows 

12 hours after power reaches  25% RTP to perform the Surveillance. 

The Surveillance is still considered to be performed within the "specified 

Frequency." Therefore, if the Surveillance were not performed within the 

7 day (plus the extension allowed by SR 3.0.2) interval, but operation was 

< 25% RTP, it would not constitute a failure of the SR or failure to meet 

the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, 

even with the 7 day Frequency not met, provided operation does not 

exceed 12 hours (plus the extension allowed by SR 3.0.2) with power 

 25% RTP. 

Once the unit reaches 25% RTP, 12 hours would be allowed for 

completing the Surveillance. If the Surveillance were not performed 

within this 12 hour interval (plus the extension allowed by SR 3.0.2), there 

would then be a failure to perform a Surveillance within the specified 

Frequency, and the provisions of SR 3.0.3 would apply. 
Frequency

1.4

Babcock & Wilcox STS 1.4-6 Rev. 4.0 

1.4 Frequency

EXAMPLES (continued) 

EXAMPLE 1.4-4 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

----------------------------NOTE----------------------------

Only required to be met in MODE 1.

----------------------------------------------------------------

Verify leakage rates are within limits. 24 hours

Example 1.4-4 specifies that the requirements of this Surveillance do not 

have to be met until the unit is in MODE 1. The interval measurement for 

the Frequency of this Surveillance continues at all times, as described in 

Example 1.4-1. However, the Note constitutes an "otherwise stated" 

exception to the Applicability of this Surveillance. Therefore, if the 

Surveillance were not performed within the 24 hour interval (plus the 

extension allowed by SR 3.0.2), but the unit was not in MODE 1, there 

would be no failure of the SR nor failure to meet the LCO. Therefore, no 

violation of SR 3.0.4 occurs when changing MODES, even with the 

24 hour Frequency exceeded, provided the MODE change was not made 

into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour 

Frequency were not met), SR 3.0.4 would require satisfying the SR.
Frequency

1.4

Babcock & Wilcox STS 1.4-7 Rev. 4.0 

1.4 Frequency

EXAMPLES (continued) 

EXAMPLE 1.4-5 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

----------------------------NOTE----------------------------

Only required to be met in MODE 1.

----------------------------------------------------------------

Perform complete cycle of the valve. 7 days

The interval continues, whether or not the unit operation is in MODE 1, 2 

or 3 (the assumed Applicability of the associated LCO) between 

performances. 

As the Note modifies the required performance of the Surveillance, the 

Note is construed to be part of the "specified Frequency." Should the 

7 day interval be exceeded while operation is not in MODE 1, this Note 

allows entry into and operation in MODES 2 and 3 to perform the 

Surveillance. The Surveillance is still considered to be performed within 

the "specified Frequency" if completed prior to entering MODE 1. 

Therefore, if the Surveillance were not performed within the 7 day (plus 

the extension allowed by SR 3.0.2) interval, but operation was not in 

MODE 1, it would not constitute a failure of the SR or failure to meet the 

LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even 

with the 7 day Frequency not met, provided operation does not result in 

entry into MODE 1. 

Once the unit reaches MODE 1, the requirement for the Surveillance to 

be performed within its specified Frequency applies and would require 

that the Surveillance had been performed. If the Surveillance were not 

performed prior to entering MODE 1, there would then be a failure to 

perform a Surveillance within the specified Frequency, and the provisions 

of SR 3.0.3 would apply. 
Frequency

1.4

Babcock & Wilcox STS 1.4-8 Rev. 4.0 

1.4 Frequency

EXAMPLES (continued) 

EXAMPLE 1.4-6 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

----------------------------NOTE----------------------------

Not required to be met in MODE 3.

----------------------------------------------------------------

Verify parameter is within limits. 24 hours

Example 1.4-[6] specifies that the requirements of this Surveillance do not 

have to be met while the unit is in MODE 3 (the assumed Applicability of 

the associated LCO is MODES 1, 2, and 3). The interval measurement 

for the Frequency of this Surveillance continues at all times, as described 

in Example 1.4-1. However, the Note constitutes an "otherwise stated" 

exception to the Applicability of this Surveillance. Therefore, if the 

Surveillance were not performed within the 24 hour interval (plus the 

extension allowed by SR 3.0.2), and the unit was in MODE 3, there would 

be no failure of the SR nor failure to meet the LCO. Therefore, no 

violation of SR 3.0.4 occurs when changing MODES to enter MODE 3, 

even with the 24 hour Frequency exceeded, provided the MODE change 

does not result in entry into MODE 2. Prior to entering MODE 2 

(assuming again that the 24 hour Frequency were not met), SR 3.0.4 

would require satisfying the SR. 
SLs 

2.0

Babcock & Wilcox STS 2.0-1 Rev. 4.0 

2.0 SAFETY LIMITS (SLs) 

2.1 SLs 

2.1.1 Reactor Core SLs 

 2.1.1.1 In MODES 1 and 2, the maximum local fuel pin centerline temperature 

shall be  [5080 - (6.5 x 10-3 MWD/MTU)F].

 2.1.1.2 In MODES 1 and 2, the departure from nucleate boiling ratio shall be 

maintained greater than the limits of [1.3 for the BAW-2 correlation and 

1.18 for the BWC correlation].

 2.1.1.3 In MODES 1 and 2, Reactor Coolant System (RCS) core outlet 

temperature and pressure shall be maintained above and to the left of 

the SL shown in Figure 2.1.1-1.

2.1.2 Reactor Coolant System Pressure SL 

 In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained  [2750] psig. 

2.2 SAFETY LIMIT VIOLATIONS 

With any SL violation, the following actions shall be completed:

2.2.1 In MODE 1 or 2, if SL 2.1.1.1 or SL 2.1.1.2 is violated, be in MODE 3 within 

1 hour. 

2.2.2 In MODE 1 or 2, if SL 2.1.1.3 is violated, restore RCS pressure and temperature 

within limits and be in MODE 3 within 1 hour. 

2.2.3 In MODE 1 or 2, if SL 2.1.2 is not met, restore compliance within limits and be in 

MODE 3 within 1 hour. 

2.2.4 In MODES 3, 4, and 5, if SL 2.1.2 is not met, restore RCS pressure to 

 [2750] psig within 5 minutes. 
SLs 

2.0

Babcock & Wilcox STS 2.0-2 Rev. 4.0 
LCO Applicability 

3.0

Babcock & Wilcox STS 3.0-1 Rev. 4.0 

3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 

LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the 

Applicability, except as provided in LCO 3.0.2, LCO 3.0.7, LCO 3.0.8, and 

LCO 3.0.9. 

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the 

associated Conditions shall be met, except as provided in LCO 3.0.5 and 

LCO 3.0.6.

If the LCO is met or is no longer applicable prior to expiration of the 

specified Completion Time(s), completion of the Required Action(s) is not 

required, unless otherwise stated. 

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an 

associated ACTION is not provided, or if directed by the associated 

ACTIONS, the unit shall be placed in a MODE or other specified condition 

in which the LCO is not applicable. Action shall be initiated within 1 hour 

to place the unit, as applicable, in: 

a. MODE 3 within 7 hours, 

b. MODE 4 within 13 hours, and 

c. MODE 5 within 37 hours. 

Exceptions to this Specification are stated in the individual Specifications. 

Where corrective measures are completed that permit operation in 

accordance with the LCO or ACTIONS, completion of the actions required 

by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4.

LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition 

in the Applicability shall only be made: 

a. When the associated ACTIONS to be entered permit continued 

operation in the MODE or other specified condition in the 

Applicability for an unlimited period of time; 

b. After performance of a risk assessment addressing inoperable 

systems and components, consideration of the results, 

determination of the acceptability of entering the MODE or other 

specified condition in the Applicability, and establishment of risk 

management actions, if appropriate; exceptions to this Specification 

are stated in the individual Specifications, or 
LCO Applicability 

3.0

Babcock & Wilcox STS 3.0-2 Rev. 4.0 

3.0 LCO Applicability 

LCO 3.0.4 (continued) 

c. When an allowance is stated in the individual value, parameter, or 

other Specification. 

This Specification shall not prevent changes in MODES or other specified 

conditions in the Applicability that are required to comply with ACTIONS 

or that are part of a shutdown of the unit. 

LCO 3.0.5 Equipment removed from service or declared inoperable to comply with 

ACTIONS may be returned to service under administrative control solely 

to perform testing required to demonstrate its OPERABILITY or the 

OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for 

the system returned to service under administrative control to perform the 

testing required to demonstrate OPERABILITY. 

LCO 3.0.6 When a supported system LCO is not met solely due to a support system 

LCO not being met, the Conditions and Required Actions associated with 

this supported system are not required to be entered. Only the support 

system LCO ACTIONS are required to be entered. This is an exception 

to LCO 3.0.2 for the supported system. In this event, an evaluation shall 

be performed in accordance with Specification 5.5.15, "Safety Function 

Determination Program (SFDP)." If a loss of safety function is determined 

to exist by this program, the appropriate Conditions and Required Actions 

of the LCO in which the loss of safety function exists are required to be 

entered. 

When a support system's Required Action directs a supported system to 

be declared inoperable or directs entry into Conditions and Required 

Actions for a supported system, the applicable Conditions and Required 

Actions shall be entered in accordance with LCO 3.0.2.

LCO 3.0.7 Test Exception LCOs [3.1.9, 3.1.10, 3.1.11, and 3.4.19] allow specified 

Technical Specification (TS) requirements to be changed to permit 

performance of special tests and operations. Unless otherwise specified, 

all other TS requirements remain unchanged. Compliance with Test 

Exception LCOs is optional. When a Test Exception LCO is desired to be 

met but is not met, the ACTIONS of the Test Exception LCO shall be met. 

When a Test Exception LCO is not desired to be met, entry into a MODE 

or other specified condition in the Applicability shall be made in 

accordance with the other applicable Specifications. 
LCO Applicability 

3.0

Babcock & Wilcox STS 3.0-3 Rev. 4.0 

3.0 LCO Applicability

LCO 3.0.8 When one or more required snubbers are unable to perform their 

associated support function(s), any affected supported LCO(s) are not 

required to be declared not met solely for this reason if risk is assessed 

and managed, and: 

 a. the snubbers not able to perform their associated support 

function(s) are associated with only one train or subsystem of a 

multiple train or subsystem supported system or are associated with 

a single train or subsystem supported system and are able to 

perform their associated support function within 72 hours; or 

 b. the snubbers not able to perform their associated support 

function(s) are associated with more than one train or subsystem of 

a multiple train or subsystem supported system and are able to 

perform their associated support function within 12 hours. 

 At the end of the specified period the required snubbers must be able to 

perform their associated support function(s), or the affected supported 

system LCO(s) shall be declared not met. 

LCO 3.0.9 When one or more required barriers are unable to perform their related 

support function(s), any supported system LCO(s) are not required to be 

declared not met solely for this reason for up to 30 days provided that at 

least one train or subsystem of the supported system is OPERABLE and 

supported by barriers capable of providing their related support 

function(s), and risk is assessed and managed. This specification may be 

concurrently applied to more than one train or subsystem of a multiple 

train or subsystem supported system provided at least one train or 

subsystem of the supported system is OPERABLE and the barriers 

supporting each of these trains or subsystems provide their related 

support function(s) for different categories of initiating events. 

If the required OPERABLE train or subsystem becomes inoperable while 

this specification is in use, it must be restored to OPERABLE status within 

24 hours or the provisions of this specification cannot be applied to the 

trains or subsystems supported by the barriers that cannot perform their 

related support function(s). 

At the end of the specified period, the required barriers must be able to 

perform their related support function(s) or the supported system LCO(s) 

shall be declared not met. 
SR Applicability 

3.0

Babcock & Wilcox STS 3.0-4 Rev. 4.0 

3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY 

SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the 

Applicability for individual LCOs, unless otherwise stated in the SR. 

Failure to meet a Surveillance, whether such failure is experienced during 

the performance of the Surveillance or between performances of the 

Surveillance, shall be failure to meet the LCO. Failure to perform a 

Surveillance within the specified Frequency shall be failure to meet the 

LCO except as provided in SR 3.0.3. Surveillances do not have to be 

performed on inoperable equipment or variables outside specified limits. 

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is 

performed within 1.25 times the interval specified in the Frequency, as 

measured from the previous performance or as measured from the time a 

specified condition of the Frequency is met. 

For Frequencies specified as "once," the above interval extension does 

not apply.

If a Completion Time requires periodic performance on a "once per . . ." 

basis, the above Frequency extension applies to each performance after 

the initial performance. 

Exceptions to this Specification are stated in the individual Specifications. 

SR 3.0.3 If it is discovered that a Surveillance was not performed within its 

specified Frequency, then compliance with the requirement to declare the 

LCO not met may be delayed, from the time of discovery, up to 24 hours 

or up to the limit of the specified Frequency, whichever is greater. This 

delay period is permitted to allow performance of the Surveillance. A risk 

evaluation shall be performed for any Surveillance delayed greater than 

24 hours and the risk impact shall be managed. 

If the Surveillance is not performed within the delay period, the LCO must 

immediately be declared not met, and the applicable Condition(s) must be 

entered. 

When the Surveillance is performed within the delay period and the 

Surveillance is not met, the LCO must immediately be declared not met, 

and the applicable Condition(s) must be entered. 

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an 

LCO shall only be made when the LCO's Surveillances have been met 

within their specified Frequency, except as provided by SR 3.0.3. When 

an LCO is not met due to Surveillances not having been met, entry into a 

MODE or other specified condition in the Applicability shall only be made 

in accordance with LCO 3.0.4. 
SR Applicability 

3.0

Babcock & Wilcox STS 3.0-5 Rev. 4.0 

3.0 SR Applicability 

SR 3.0.4 (continued) 

This provision shall not prevent entry into MODES or other specified 

conditions in the Applicability that are required to comply with ACTIONS 

or that are part of a shutdown of the unit.

SDM

3.1.1

Babcock & Wilcox STS 3.1.1-1 Rev. 4.0 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.1 SHUTDOWN MARGIN (SDM) 

LCO 3.1.1 The SDM shall be within the limits specified in the COLR. 

APPLICABILITY: MODES 3, 4, and 5.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. SDM not within limits. A.1 Initiate boration to restore 

SDM to within limits.

15 minutes

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.1.1 Verify SDM is within the limits specified in the 

COLR.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Reactivity Balance 

3.1.2

Babcock & Wilcox STS 3.1.2-1 Rev. 4.0 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.2 Reactivity Balance 

LCO 3.1.2 The measured core reactivity balance shall be within ± 1% k/k of 

predicted values. 

APPLICABILITY: MODES 1 and 2.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Measured core reactivity 

balance not within limit.

A.1 Re-evaluate core design 

and safety analysis and 

determine that the reactor 

core is acceptable for 

continued operation.

AND

A.2 Establish appropriate 

operating restrictions and 

SRs.

7 days

7 days

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3. 6 hours
Reactivity Balance 

3.1.2

Babcock & Wilcox STS 3.1.2-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.2.1 ------------------------------NOTES-----------------------------

1. The predicted reactivity values may be adjusted 

(normalized) to correspond to the measured 

core reactivity prior to exceeding a fuel burnup 

of 60 effective full power days (EFPD) after 

each fuel loading.

2. This Surveillance is not required to be 

performed prior to entry into MODE 2.

---------------------------------------------------------------------

Verify measured core reactivity balance is within 

± 1% k/k of predicted values.

Prior to entering 

MODE 1 after

each fuel loading

AND

--------NOTE--------

Only required 

after 60 EFPD

------------------------

[ 31 EFPD 

thereafter

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
MTC 

3.1.3

Babcock & Wilcox STS 3.1.3-1 Rev. 4.0 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.3 Moderator Temperature Coefficient (MTC) 

LCO 3.1.3 The MTC shall be maintained within the limits specified in the COLR. The 

maximum positive limit shall be [ [ ]  k/k/F at RTP]. 

APPLICABILITY: MODES 1 and 2.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. MTC not within limits. A.1 Be in MODE 3. 6 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.3.1 Verify MTC is within the upper limit specified in the 

COLR.

Prior to entering 

MODE 1 after 

each fuel loading

SR 3.1.3.2 -------------------------------NOTE------------------------------

If the MTC is more negative than the COLR limit 

when extrapolated to the end of cycle, SR 3.1.3.2 

may be repeated. Shutdown must occur prior to 

exceeding the minimum allowable boron 

concentration at which MTC is projected to exceed 

the lower limit.

---------------------------------------------------------------------

Verify extrapolated MTC is within the lower limit 

specified in the COLR.

Each fuel cycle 

within 7 EFPDs 

after reaching an 

equilibrium boron 

concentration 

equivalent to 

300 ppm

CONTROL ROD Group Alignment Limits 

3.1.4

Babcock & Wilcox STS 3.1.4-1 Rev. 4.0 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.4 CONTROL ROD Group Alignment Limits 

LCO 3.1.4 Each CONTROL ROD shall be OPERABLE. 

AND

 Each CONTROL ROD shall be aligned to within [6.5]% of its group 

average height.

APPLICABILITY: MODES 1 and 2.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One CONTROL ROD 

not aligned to within 

[6.5]% of its group 

average height.

A.1 Restore CONTROL ROD 

alignment.

OR

A.2.1.1 Verify SDM is within the 

limits specified in the 

COLR.

OR

A.2.1.2 Initiate boration to restore 

SDM to within limit.

AND

A.2.2 Reduce THERMAL 

POWER to  60% of the 

ALLOWABLE THERMAL 

POWER.

AND

1 hour

1 hour

AND

Once per 12 hours 

thereafter

1 hour

2 hours
CONTROL ROD Group Alignment Limits 

3.1.4

Babcock & Wilcox STS 3.1.4-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

A.2.3 Reduce the nuclear 

overpower trip setpoint to 

 70% of the ALLOWABLE 

THERMAL POWER.

AND

A.2.4 Verify the potential ejected 

rod worth is within the 

assumptions of the rod 

ejection analysis.

AND

A.2.5 --------------NOTE---------------

Only required when 

THERMAL POWER is 

> 20% RTP.

-------------------------------------

Perform SR 3.2.5.1.

10 hours

72 hours

72 hours

B. Required Action and 

associated Completion 

Time for Condition A not 

met.

B.1 Be in MODE 3. 6 hours

C. More than one 

CONTROL ROD not 

aligned within [6.5]% of 

its group average height.

C.1.1 Verify SDM is within the 

limits specified in the 

COLR.

OR

C.1.2 Initiate boration to restore 

SDM to within limit.

AND

C.2 Be in MODE 3.

1 hour

1 hour

6 hours
CONTROL ROD Group Alignment Limits 

3.1.4

Babcock & Wilcox STS 3.1.4-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

D. One or more rods 

inoperable.

D.1.1 Verify SDM is within the 

limits specified in the 

COLR.

OR

D.1.2 Initiate boration to restore 

SDM to within limit.

AND

D.2 Be in MODE 3.

1 hour

1 hour

6 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.4.1 Verify individual CONTROL ROD positions are 

within [6.5]% of their group average height.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.1.4.2 Verify CONTROL ROD freedom of movement 

(trippability) by moving each individual CONTROL

ROD that is not fully inserted  3% in any direction.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
CONTROL ROD Group Alignment Limits 

3.1.4

Babcock & Wilcox STS 3.1.4-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.1.4.3 -------------------------------NOTE------------------------------

With rod drop times determined with less than four 

reactor coolant pumps operating, operation may 

proceed provided operation is restricted to the pump 

combination operating during the rod drop time 

determination.

---------------------------------------------------------------------

Verify the rod drop time for each CONTROL ROD, 

from the fully withdrawn position, is  [1.66] seconds 

from power interruption at the CONTROL ROD drive 

breakers to 3/4 insertion (25% withdrawn position) 

with Tavg  525F.

Prior to reactor 

criticality after 

each removal of 

the reactor vessel 

head
Safety Rod Insertion Limits 

3.1.5

Babcock & Wilcox STS 3.1.5-1 Rev. 4.0 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.5 Safety Rod Insertion Limits 

LCO 3.1.5 Each safety rod shall be fully withdrawn. 

---------------------------------------------NOTE--------------------------------------------

 Not required for any safety rod inserted to perform SR 3.1.4.2. 

--------------------------------------------------------------------------------------------------

APPLICABILITY: MODES 1 and 2.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One safety rod not fully 

withdrawn.

A.1.1 Verify SDM is within the 

limits specified in the 

COLR.

 OR

A.1.2 Initiate boration to restore 

SDM to within limit.

AND

A.2 Declare the rod inoperable.

1 hour

1 hour

1 hour

B. More than one safety 

rod not fully withdrawn.

B.1.1 Verify SDM is within the 

limits specified in the 

COLR.

 OR

B.1.2 Initiate boration to restore 

SDM to within limit.

AND

1 hour

1 hour
Safety Rod Insertion Limits 

3.1.5

Babcock & Wilcox STS 3.1.5-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.2 Be in MODE 3. 6 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.5.1 Verify each safety rod is fully withdrawn. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
APSR Alignment Limits 

3.1.6

Babcock & Wilcox STS 3.1.6-1 Rev. 4.0 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.6 AXIAL POWER SHAPING ROD (APSR) Alignment Limits 

LCO 3.1.6 Each APSR shall be OPERABLE and aligned within [6.5]% of its group 

average height. 

APPLICABILITY: MODES 1 and 2.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One APSR inoperable, 

not aligned within its 

limits, or both.

A.1 Perform SR 3.2.3.1. 2 hours

AND

2 hours after each 

APSR movement

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3. 6 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.6.1 Verify position of each APSR is within [6.5]% of the 

group average height.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Position Indicator Channels 

3.1.7

Babcock & Wilcox STS 3.1.7-1 Rev. 4.0 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.7 Position Indicator Channels 

LCO 3.1.7 The absolute position indicator channel and the relative position indicator 

channel for each CONTROL ROD and APSR shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each inoperable position indicator channel. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. The relative position 

indicator channel 

inoperable for one or 

more rods.

A.1 Determine the absolute 

position indicator channel 

for the rod(s) is 

OPERABLE.

8 hours

AND

Once per 8 hours 

thereafter

B. The absolute position 

indicator channel 

inoperable for one or 

more rods.

B.1.1 Determine position of the 

rods with inoperable 

absolute position indicator 

by actuating the affected 

rod's zone position 

reference indicators.

 AND

8 hours
Position Indicator Channels 

3.1.7

Babcock & Wilcox STS 3.1.7-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.1.2 Determine rods with 

inoperable position 

indicators are maintained at 

the zone reference indicator

position and within the 

limits specified in 

LCO 3.1.5, "Safety Rod 

Insertion Limit," LCO 3.2.1, 

"Regulating Rod Insertion 

Limits," or LCO 3.2.2, 

"AXIAL POWER SHAPING 

ROD (APSR) Insertion 

Limits," as applicable.

OR

B.2.1 Place the control groups 

with nonindicating rods 

under manual control.

 AND

8 hours

AND

Once per 8 hours 

thereafter

8 hours
Position Indicator Channels 

3.1.7

Babcock & Wilcox STS 3.1.7-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.2.2 Determine the position of 

the nonindicating rods 

indirectly with fixed incore 

instrumentation.

8 hours

AND

Once per 8 hours 

thereafter

AND

-----------NOTE----------

Not applicable during 

first 8 hour period

-----------------------------

1 hour after motion of 

nonindicating rods, 

which exceeds 

[15 inches] in one 

direction since the 

last determination of 

the rod's position

C. The absolute position 

indicator channel and 

the relative position 

indicator channel 

inoperable for one or 

more rods.

OR

Required Action and 

associated Completion 

Time not met.

C.1 Declare the rod(s) 

inoperable.

Immediately
Position Indicator Channels 

3.1.7

Babcock & Wilcox STS 3.1.7-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.7.1 Verify the absolute position indicator channels and 

the relative position indicator channels agree within 

the limit specified in the COLR.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
PHYSICS TESTS Exceptions - MODE 1 

3.1.8

Babcock & Wilcox STS 3.1.8-1 Rev. 4.0 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.8 PHYSICS TESTS Exceptions - MODE 1 

LCO 3.1.8 During the performance of PHYSICS TESTS, the requirements of: 

 LCO 3.1.4, "CONTROL ROD Alignment Limits," 

 LCO 3.1.5, "Safety Rod Insertion Limits," 

 LCO 3.1.6, "AXIAL POWER SHAPING ROD Alignment Limits," 

 LCO 3.2.1, "Regulating Rod Insertion Limits," for the restricted 

operation region only, 

 LCO 3.2.3, "AXIAL POWER IMBALANCE Operating Limits," and

 LCO 3.2.4, "QUADRANT POWER TILT," 

 may be suspended, provided: 

 a. THERMAL POWER is maintained  85% RTP, 

 b. Nuclear overpower trip setpoint is  10% RTP higher than the 

THERMAL POWER at which the test is performed, with a maximum 

setting of 90% RTP, 

 -----------------------------------------NOTE-----------------------------------------

 c. Only required when THERMAL POWER is > 20% RTP. 

 ------------------------------------------------------------------------------------------

 FQ(Z) and 

N FH

 are maintained within the limits specified in the 

COLR and 

 d. SDM is within the limits specified in the COLR. 

APPLICABILITY: MODE 1 during PHYSICS TESTS. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. SDM not within limit. A.1 Initiate boration to restore 

SDM to within limit.

AND

A.2 Suspend PHYSICS TESTS 

exceptions.

15 minutes

1 hour
PHYSICS TESTS Exceptions - MODE 1 

3.1.8

Babcock & Wilcox STS 3.1.8-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B. THERMAL POWER 

> 85% RTP.

OR

Nuclear overpower trip 

setpoint > 10% higher 

than PHYSICS TESTS 

power level.

OR

Nuclear overpower trip 

setpoint > 90% RTP.

OR

------------NOTE------------

Only required when 

THERMAL POWER is 

> 20% RTP.

---------------------------------

FQ(Z) or 

N FH

not within 

limits.

B.1 Suspend PHYSICS TESTS 

exceptions.

1 hour

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.8.1 Verify THERMAL POWER is  85% RTP. [ 1 hour

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
PHYSICS TESTS Exceptions - MODE 1 

3.1.8

Babcock & Wilcox STS 3.1.8-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.1.8.2 -------------------------------NOTE------------------------------

Only required to be met when THERMAL POWER is 

> 20% RTP.

---------------------------------------------------------------------

Perform SR 3.2.5.1. [ 2 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.1.8.3 Verify nuclear overpower trip setpoint is  10% RTP 

higher than the THERMAL POWER at which the 

test is performed, with a maximum setting of 

90% RTP.

[ 8 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.1.8.4 Verify SDM is within the limits specified in the 

COLR.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

PHYSICS TESTS Exceptions - MODE 2 

3.1.9

Babcock & Wilcox STS 3.1.9-1 Rev. 4.0 

3.19 REACTIVITY CONTROL SYSTEMS 

3.1.9 PHYSICS TESTS Exceptions - MODE 2 

LCO 3.1.9 During performance of PHYSICS TESTS, the requirements of: 

LCO 3.1.3, "Moderator Temperature Coefficient,"

LCO 3.1.4, "CONTROL ROD Group Alignment Limits," 

LCO 3.1.5, "Safety Rod Insertion Limits," 

LCO 3.1.6, "AXIAL POWER SHAPING ROD Alignment Limits," 

LCO 3.2.1, "Regulating Rod Insertion Limits," for the restricted 

operation region only, and 

[ LCO 3.4.2, "RCS Minimum Temperature for Criticality" ] 

 may be suspended provided that: 

a. THERMAL POWER is  5% RTP, 

b. Reactor trip setpoints on the OPERABLE nuclear overpower 

channels are set to  25% RTP, 

c. Nuclear instrumentation high startup rate CONTROL ROD 

withdrawal inhibit is OPERABLE, and 

d. SDM is within the limits specified in the COLR. 

APPLICABILITY: During PHYSICS TESTS initiated in MODE 2. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. THERMAL POWER not 

within limit.

A.1 Open control rod drive trip 

breakers.

Immediately

B. SDM not within limit. B.1 Initiate boration to restore 

SDM to within limit.

AND

B.2 Suspend PHYSICS TESTS 

exceptions.

15 minutes

1 hour
PHYSICS TESTS Exceptions - MODE 2 

3.1.9

Babcock & Wilcox STS 3.1.9-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. Nuclear overpower trip 

setpoint is not within 

limit.

OR

Nuclear instrumentation 

high startup rate 

CONTROL ROD 

withdrawal inhibit 

inoperable.

C.1 Suspend PHYSICS TESTS 

exceptions.

1 hour

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.9.1 Verify THERMAL POWER is  5% RTP. [ 1 hour

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.1.9.2 Verify nuclear overpower trip setpoint is  25% RTP. [ 8 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
PHYSICS TESTS Exceptions - MODE 2 

3.1.9

Babcock & Wilcox STS 3.1.9-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.1.9.3 Verify SDM is within the limits specified in the 

COLR.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Regulating Rod Insertion Limits 

3.2.1

Babcock & Wilcox STS 3.2.1-1 Rev. 4.0 

3.2 POWER DISTRIBUTION LIMITS 

3.2.1 Regulating Rod Insertion Limits 

LCO 3.2.1 Regulating rod groups shall be within the physical insertion, sequence, 

and overlap limits specified in the COLR. 

---------------------------------------------NOTE--------------------------------------------

 Not required for any regulating rod repositioned to perform SR 3.1.4.2.

-------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODES 1 and 2.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Regulating rod groups 

inserted in restricted 

operational region, or 

sequence or overlap, or 

any combination, not 

met.

A.1 --------------NOTE--------------

Only required when 

THERMAL POWER is 

> 20% RTP.

-------------------------------------

Perform SR 3.2.5.1.

AND

A.2 Restore regulating rod 

groups to within limits.

Once per 2 hours

24 hours from 

discovery of failure to 

meet the LCO

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Reduce THERMAL 

POWER to less than or 

equal to THERMAL 

POWER allowed by 

regulating rod group 

insertion limits.

2 hours
Regulating Rod Insertion Limits 

3.2.1

Babcock & Wilcox STS 3.2.1-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. Regulating rod groups 

inserted in unacceptable 

operational region.

C.1 Initiate boration to restore 

SDM to within the limit 

specified in the COLR.

AND

C.2.1 Restore regulating rod 

groups to within restricted 

operating region.

 OR

C.2.2 Reduce THERMAL 

POWER to less than or 

equal to the THERMAL 

POWER allowed by the 

regulating rod group 

insertion limits.

15 minutes

2 hours

2 hours

D. Required Action and 

associated Completion 

Time of Condition C not 

met.

D.1 Be in MODE 3. 6 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.2.1.1 Verify regulating rod groups are within the sequence 

and overlap limits as specified in the COLR.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Regulating Rod Insertion Limits 

3.2.1

Babcock & Wilcox STS 3.2.1-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.2.1.2 Verify regulating rod groups meet the insertion limits 

as specified in the COLR.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.2.1.3 Verify SDM is within the limit specified in the COLR. Within 4 hours 

prior to achieving 

criticality

APSR Insertion Limits 

3.2.2

Babcock & Wilcox STS 3.2.2-1 Rev. 4.0 

3.2 POWER DISTRIBUTION LIMITS 

3.2.2 AXIAL POWER SHAPING ROD (APSR) Insertion Limits 

LCO 3.2.2 APSRs shall be positioned within the limits specified in the COLR. 

APPLICABILITY: MODES 1 and 2.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. APSRs not within limits. A.1 --------------NOTE--------------

Only required when 

THERMAL POWER is 

> 20% RTP.

-------------------------------------

Perform SR 3.2.5.1.

AND

A.2 Restore APSRs to within 

limits.

Once per 2 hours

24 hours

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3. 6 hours
APSR Insertion Limits 

3.2.2

Babcock & Wilcox STS 3.2.2-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.2.2.1 Verify APSRs are within acceptable limits specified 

in the COLR.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AXIAL POWER IMBALANCE Operating Limits 

3.2.3

Babcock & Wilcox STS 3.2.3-1 Rev. 4.0 

3.2 POWER DISTRIBUTION LIMITS 

3.2.3 AXIAL POWER IMBALANCE Operating Limits 

LCO 3.2.3 AXIAL POWER IMBALANCE shall be maintained within the limits 

specified in the COLR. 

APPLICABILITY: MODE 1 with THERMAL POWER > 40% RTP. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. AXIAL POWER 

IMBALANCE not within 

limits.

A.1 Perform SR 3.2.5.1.

AND

A.2 Reduce AXIAL POWER 

IMBALANCE within limits.

Once per 2 hours

24 hours

B. Required Action and 

associated Completion 

Time not met.

B.1 Reduce THERMAL 

POWER to  40% RTP.

2 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.2.3.1 Verify AXIAL POWER IMBALANCE is within limits 

as specified in the COLR.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

QPT 

3.2.4

Babcock & Wilcox STS 3.2.4-1 Rev. 4.0 

3.2 POWER DISTRIBUTION LIMITS 

3.2.4 QUADRANT POWER TILT (QPT) 

LCO 3.2.4 QPT shall be maintained less than or equal to the steady state limits 

specified in the COLR. 

APPLICABILITY: MODE 1 with THERMAL POWER > [20]% RTP. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. QPT greater than the 

steady state limit and 

less than or equal to the 

transient limit.

A.1.1 Perform SR 3.2.5.1.

OR

A.1.2.1 Reduce THERMAL 

POWER  2% RTP from 

the ALLOWABLE 

THERMAL POWER for 

each 1% of QPT greater 

than the steady state limit.

AND

A.1.2.2 Reduce nuclear overpower 

trip setpoint and nuclear 

overpower based on 

Reactor Coolant System 

flow and AXIAL POWER 

IMBALANCE trip setpoint 

 2% RTP from the 

ALLOWABLE THERMAL 

POWER for each 1% of 

QPT greater than the 

steady state limit.

AND

Once per 2 hours

2 hours

OR

2 hours after last 

performance of 

SR 3.5.2.1

10 hours
QPT 

3.2.4

Babcock & Wilcox STS 3.2.4-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

A.2 Restore QPT to less than or 

equal to the steady state

limit.

24 hours from 

discovery of failure to 

meet the LCO

B. QPT greater than the 

transient limit and less 

than or equal to the 

maximum limit due to 

misalignment of a 

CONTROL ROD or an 

APSR.

B.1 Reduce THERMAL 

POWER  2% RTP from 

ALLOWABLE THERMAL 

POWER for each 1% of 

QPT greater than the 

steady state limit.

AND

B.2 Restore QPT to less than or 

equal to the transient limit.

30 minutes

2 hours

C. Required Action and 

associated Completion 

Time of Condition A or B 

not met.

C.1 Reduce THERMAL 

POWER to < 60% of the 

ALLOWABLE THERMAL 

POWER.

AND

C.2 Reduce nuclear overpower 

trip setpoint to  65.5% of 

the ALLOWABLE 

THERMAL POWER.

2 hours

10 hours

D. QPT greater than the 

transient limit and less 

than or equal to the 

maximum limit due to 

causes other than the 

misalignment of either 

CONTROL ROD or 

APSR.

D.1 Reduce THERMAL 

POWER to < 60% of the 

ALLOWABLE THERMAL 

POWER.

AND

D.2 Reduce nuclear overpower 

trip setpoint to  65.5% of 

the ALLOWABLE 

THERMAL POWER.

2 hours

10 hours
QPT 

3.2.4

Babcock & Wilcox STS 3.2.4-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

E. Required Action and 

associated Completion 

Time for Condition C 

or D not met.

E.1 Reduce THERMAL 

POWER to  [20]% RTP.

2 hours

F. QPT greater than the 

maximum limit.

F.1 Reduce THERMAL 

POWER to  [20]% RTP.

2 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.2.4.1 Verify QPT is within limits as specified in the COLR. [ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

AND

When QPT has 

been restored to 

less than or equal 

to the steady state 

limit, 1 hour for 12 

consecutive 

hours, or until 

verified 

acceptable at 

 95% RTP

Power Peaking Factors 

3.2.5

Babcock & Wilcox STS 3.2.5-1 Rev. 4.0 

3.2 POWER DISTRIBUTION LIMITS 

3.2.5 Power Peaking Factors 

LCO 3.2.5 FQ(Z) and 

N FH

 shall be within the limits specified in the COLR. 

APPLICABILITY: MODE 1 with THERMAL POWER > 20% RTP. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. FQ(Z) not within limit. A.1 Reduce THERMAL 

POWER  1% RTP for 

each 1% that FQ(Z) 

exceeds limit.

AND

A.2 Reduce nuclear overpower 

trip setpoint and nuclear 

overpower based on 

Reactor Coolant System 

(RCS) flow and AXIAL 

POWER IMBALANCE trip 

setpoint  1% RTP for each 

1% that FQ(Z) exceeds limit.

AND

A.3 Restore FQ(Z) to within 

limit.

15 minutes

8 hours

24 hours

B.

N FH

not within limit. B.1 Reduce THERMAL 

POWER  RH(%) RTP 

(specified in the COLR) for 

each 1% that 

N FH

exceeds 

limit.

AND

15 minutes
Power Peaking Factors 

3.2.5

Babcock & Wilcox STS 3.2.5-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.2 Reduce nuclear overpower 

trip setpoint and nuclear 

overpower based on RCS 

flow and AXIAL POWER 

IMBALANCE trip setpoint 

 RH(%) RTP (specified in 

the COLR) for each 1% that 

N FH

exceeds limit.

AND

B.3 Restore 

N FH

to within limit.

8 hours

24 hours

C. Required Action and 

associated Completion 

Time not met.

C.1 Be in MODE 1 with 

THERMAL POWER  20% 

RTP.

2 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.2.5.1 -------------------------------NOTE------------------------------

Only required to be performed when specified in 

LCO 3.1.8, "PHYSICS TESTS Exceptions -

MODE 1," or when complying with Required Actions 

of LCO 3.1.4, "CONTROL ROD Group Alignment 

Limits," LCO 3.2.1, "Regulating Rod Insertion 

Limits," LCO 3.2.2, "AXIAL POWER SHAPING ROD 

(APSR) Insertion Limits," LCO 3.2.3, "AXIAL 

POWER IMBALANCE Operating Limits," LCO 3.2.4, 

"QUADRANT POWER TILT (QPT)."

---------------------------------------------------------------------

Verify FQ(Z) and 

N FH

are within limits by using the 

Incore Detector System to obtain a power 

distribution map.

As specified by 

the applicable 

LCO(s)
RPS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Babcock & Wilcox STS 3.3.1A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.1A Reactor Protection System (RPS) Instrumentation (Without Setpoint Control 

Program) 

LCO 3.3.1A Four channels of RPS instrumentation for each Function in Table 3.3.1-1 

shall be OPERABLE. 

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One channel inoperable. A.1 Place channel in bypass or 

trip.

1 hour

B. Two channels 

inoperable.

B.1 Place one channel in trip.

AND

B.2 Place second channel in 

bypass.

1 hour

1 hour

C. Three or more channels 

inoperable.

OR

Required Action and 

associated Completion 

Time of Condition A or B 

not met.

C.1 Enter the Condition 

referenced in Table 3.3.1-1 

for the Function.

Immediately

D. As required by Required 

Action C.1 and 

referenced in 

Table 3.3.1-1.

D.1 Be in MODE 3.

AND

D.2 Open all CONTROL ROD 

drive (CRD) trip breakers.

6 hours

6 hours
RPS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Babcock & Wilcox STS 3.3.1A-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

E. As required by Required 

Action C.1 and 

referenced in 

Table 3.3.1-1.

E.1 Open all CRD trip breakers. 6 hours

F. As required by Required 

Action C.1 and 

referenced in 

Table 3.3.1-1.

F.1 Reduce THERMAL 

POWER < [45]% RTP.

6 hours

G. As required by Required 

Action C.1 and 

referenced in 

Table 3.3.1-1.

G.1 Reduce THERMAL 

POWER < [15]% RTP.

6 hours

SURVEILLANCE REQUIREMENTS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Refer to Table 3.3.1-1 to determine which SRs apply to each RPS Function. 

-------------------------------------------------------------------------------------------------------------------------------

SURVEILLANCE FREQUENCY

SR 3.3.1.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the 

Surveillance 

Frequency 

Control Program ]
RPS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Babcock & Wilcox STS 3.3.1A-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.2 ------------------------------NOTES-----------------------------

1. Adjust power range channel output if the 

absolute difference is > [2]% RTP.

2. Not required to be performed until [24] hours 

after THERMAL POWER is  15% RTP.

---------------------------------------------------------------------

Compare result of calorimetric heat balance 

calculation to power range channel output.

[ 24 hours

OR

In accordance 

with the 

Surveillance 

Frequency 

Control Program ]

SR 3.3.1.3 ------------------------------NOTES-----------------------------

1. Adjust the power range channel imbalance 

output if the absolute value of the imbalance 

error is  [2]% RTP.

2. Not required to be performed until [24] hours 

after THERMAL POWER is  15% RTP.

---------------------------------------------------------------------

Compare results of out of core measured AXIAL 

POWER IMBALANCE (API0) to incore measured 

AXIAL POWER IMBALANCE (API1) as follows:

(RTP/TP)(API0 - API1) = imbalance error.

[ 31 days

OR

In accordance 

with the 

Surveillance 

Frequency 

Control Program ]
RPS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Babcock & Wilcox STS 3.3.1A-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.4 Perform CHANNEL FUNCTIONAL TEST. [ [45] days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the 

Surveillance 

Frequency 

Control Program ]

SR 3.3.1.5 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL 

CALIBRATION.

---------------------------------------------------------------------

Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the 

Surveillance 

Frequency 

Control Program ]

SR 3.3.1.6 -------------------------------NOTE------------------------------

Neutron detectors are excluded from RPS 

RESPONSE TIME testing.

---------------------------------------------------------------------

Verify that RPS RESPONSE TIME is within limits. [ [18] months on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the 

Surveillance 

Frequency 

Control Program ]
RPS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Babcock & Wilcox STS 3.3.1A-5 Rev. 4.0 

Table 3.3.1-1 (page 1 of 3) 

Reactor Protection System Instrumentation 

FUNCTION

APPLICABLE

MODES OR

OTHER

SPECIFIED

CONDITIONS

CONDITIONS

REFERENCED

FROM

REQUIRED

ACTION C.1

SURVEILLANCE

REQUIREMENTS

ALLOWABLE

VALUE

1. Nuclear Overpower -

a. High Setpoint 1,2(a),3(b) D SR 3.3.1.1 

SR 3.3.1.2 

SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

SR 3.3.1.6 

 [104.9]% RTP

b. Low Setpoint 2

(e)

,3(e)

4

(e)

,5(e)

E SR 3.3.1.1 

SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

SR 3.3.1.6 

 5% RTP

2. RCS High Outlet 

Temperature

1,2 D SR 3.3.1.1 

SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

 [618]F

3. RCS High Pressure 1,2(a),3(b) D SR 3.3.1.1 

SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

SR 3.3.1.6 

 [2355] psig

4. RCS Low Pressure 1,2(a) D SR 3.3.1.1 

SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

SR 3.3.1.6 

 [1800] psig

(a) When not in shutdown bypass operation. 

(b) With any CRD trip breaker in the closed position, the CRD System capable of rod withdrawal, and not in 

shutdown bypass operation. 

(c) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be 

evaluated to verify that it is functioning as required before returning the channel to service. 

(d) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting 

Trip Setpoint (LTSP) at the completion of the surveillance; otherwise, the channel shall be declared 

inoperable. Setpoints more conservative than the LTSP are acceptable provided that the as-found and as-left 

tolerances apply to the actual setpoint implemented in the Surveillance procedures [Nominal Trip Setpoint] to 

confirm channel performance. The LTSP and the methodologies used to determine the as-found and as-left 

tolerances are specified in [insert the facility FSAR reference or the name of any document incorporated into 

the facility FSAR by reference]. 

(e) During shutdown bypass operation with any CRD trip breaker in the closed position and the CRD System 

capable of rod withdrawal. 
RPS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Babcock & Wilcox STS 3.3.1A-6 Rev. 4.0 

Table 3.3.1-1 (page 2 of 3) 

Reactor Protection System Instrumentation 

FUNCTION

APPLICABLE

MODES OR

OTHER

SPECIFIED

CONDITIONS

CONDITIONS

REFERENCED

FROM

REQUIRED

ACTION C.1

SURVEILLANCE

REQUIREMENTS

ALLOWABLE

VALUE

5. RCS Variable Low Pressure 1,2(a) D SR 3.3.1.1 

SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

 ([11.59] * Tout -

[5037.8]) psig

6. Reactor Building High 

Pressure

1,2,3(f) D SR 3.3.1.1 

SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

 [4] psig

7. Reactor Coolant Pump to 

Power

1,2(a) D SR 3.3.1.1 

SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

SR 3.3.1.6 

[5]% RTP with  2 pumps 

operating

8. Nuclear Overpower RCS 

Flow and Measured AXIAL 

POWER IMBALANCE

1,2(a) D SR 3.3.1.1 

SR 3.3.1.3 

SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

SR 3.3.1.6 

Nuclear Overpower RCS 

Flow and AXIAL POWER 

IMBALANCE setpoint 

envelope in COLR

9. Main Turbine Trip (Control 

Oil Pressure)

 [45]% RTP F SR 3.3.1.1 

SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

 [45] psig

(a) When not in shutdown bypass operation. 

(c) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be 

evaluated to verify that it is functioning as required before returning the channel to service. 

(d) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting 

Trip Setpoint (LTSP) at the completion of the surveillance; otherwise, the channel shall be declared 

inoperable. Setpoints more conservative than the LTSP are acceptable provided that the as-found and as-left 

tolerances apply to the actual setpoint implemented in the Surveillance procedures [Nominal Trip Setpoint] to 

confirm channel performance. The LTSP and the methodologies used to determine the as-found and as-left 

tolerances are specified in [insert the facility FSAR reference or the name of any document incorporated into 

the facility FSAR by reference]. 

(f) With any CRD trip breaker in the closed position and the CRD System capable of rod withdrawal. 
RPS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Babcock & Wilcox STS 3.3.1A-7 Rev. 4.0 

Table 3.3.1-1 (page 3 of 3)

Reactor Protection System Instrumentation 

FUNCTION

APPLICABLE

MODES OR

OTHER

SPECIFIED

CONDITIONS

CONDITIONS

REFERENCED

FROM

REQUIRED

ACTION C.1

SURVEILLANCE

REQUIREMENTS

ALLOWABLE

VALUE

10. Loss of Main Feedwater 

Pumps (Control Oil 

Pressure)

 [15]% RTP G SR 3.3.1.1 

SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

 [55] psig

11. Shutdown Bypass RCS High 

Pressure

2

(e),3(e),4(e)

5

(e)

E SR 3.3.1.1 

SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

 [1720] psig

(c) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be 

evaluated to verify that it is functioning as required before returning the channel to service. 

(d) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting 

Trip Setpoint (LTSP) at the completion of the surveillance; otherwise, the channel shall be declared 

inoperable. Setpoints more conservative than the LTSP are acceptable provided that the as-found and as-left 

tolerances apply to the actual setpoint implemented in the Surveillance procedures [Nominal Trip Setpoint] to 

confirm channel performance. The LTSP and the methodologies used to determine the as-found and as-left 

tolerances are specified in [insert the facility FSAR reference or the name of any document incorporated into 

the facility FSAR by reference]. 

(e) During shutdown bypass operation with any CRD trip breaker in the closed position and the CRD System 

capable of rod withdrawal. 

RPS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Babcock & Wilcox STS 3.3.1B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.1B Reactor Protection System (RPS) Instrumentation (With Setpoint Control Program) 

LCO 3.3.1B Four channels of RPS instrumentation for each Function in Table 3.3.1-1 

shall be OPERABLE. 

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One channel inoperable. A.1 Place channel in bypass or 

trip.

1 hour

B. Two channels 

inoperable.

B.1 Place one channel in trip.

AND

B.2 Place second channel in 

bypass.

1 hour

1 hour

C. Three or more channels 

inoperable.

OR

Required Action and 

associated Completion 

Time of Condition A or B 

not met.

C.1 Enter the Condition 

referenced in Table 3.3.1-1 

for the Function.

Immediately

D. As required by Required 

Action C.1 and 

referenced in 

Table 3.3.1-1.

D.1 Be in MODE 3.

AND

D.2 Open all CONTROL ROD 

drive (CRD) trip breakers.

6 hours

6 hours
RPS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Babcock & Wilcox STS 3.3.1B-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

E. As required by Required 

Action C.1 and 

referenced in 

Table 3.3.1-1.

E.1 Open all CRD trip breakers. 6 hours

F. As required by Required 

Action C.1 and 

referenced in 

Table 3.3.1-1.

F.1 Reduce THERMAL 

POWER < [45]% RTP.

6 hours

G. As required by Required 

Action C.1 and 

referenced in 

Table 3.3.1-1.

G.1 Reduce THERMAL 

POWER < [15]% RTP.

6 hours

SURVEILLANCE REQUIREMENTS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Refer to Table 3.3.1-1 to determine which SRs apply to each RPS Function. 

-------------------------------------------------------------------------------------------------------------------------------

SURVEILLANCE FREQUENCY

SR 3.3.1.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RPS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Babcock & Wilcox STS 3.3.1B-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.2 ------------------------------NOTES-----------------------------

1. Adjust power range channel output if the 

absolute difference is > [2]% RTP.

2. Not required to be performed until [24] hours 

after THERMAL POWER is  15% RTP.

---------------------------------------------------------------------

Compare result of calorimetric heat balance 

calculation to power range channel output.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.3 ------------------------------NOTES-----------------------------

1. Adjust the power range channel imbalance 

output if the absolute value of the imbalance 

error is  [2]% RTP.

2. Not required to be performed until [24] hours 

after THERMAL POWER is  15% RTP.

---------------------------------------------------------------------

Compare results of out of core measured AXIAL 

POWER IMBALANCE (API0) to incore measured 

AXIAL POWER IMBALANCE (API1) as follows:

(RTP/TP)(API0 - API1) = imbalance error.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RPS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Babcock & Wilcox STS 3.3.1B-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.4 Perform CHANNEL FUNCTIONAL TEST in 

accordance with the Setpoint Control Program.

[ [45] days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.5 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL 

CALIBRATION.

---------------------------------------------------------------------

Perform CHANNEL CALIBRATION in accordance 

with the Setpoint Control Program.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RPS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Babcock & Wilcox STS 3.3.1B-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.6 -------------------------------NOTE------------------------------

Neutron detectors are excluded from RPS 

RESPONSE TIME testing.

---------------------------------------------------------------------

Verify that RPS RESPONSE TIME is within limits. [ [18] months on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RPS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Babcock & Wilcox STS 3.3.1B-6 Rev. 4.0 

Table 3.3.1-1 (page 1 of 2)

Reactor Protection System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER SPECIFIED 

CONDITIONS

CONDITIONS 

REFERENCED

FROM REQUIRED 

ACTION C.1

SURVEILLANCE

REQUIREMENTS

1. Nuclear Overpower -

a. High Setpoint 1,2(a),3(b) D SR 3.3.1.1

SR 3.3.1.2

SR 3.3.1.4

SR 3.3.1.5

SR 3.3.1.6

b. Low Setpoint 2

(c),3(c)

4

(c),5(c)

E SR 3.3.1.1

SR 3.3.1.4

SR 3.3.1.5

SR 3.3.1.6

2. RCS High Outlet Temperature 1,2 D SR 3.3.1.1

SR 3.3.1.4

SR 3.3.1.5

3. RCS High Pressure 1,2(a),3(b) D SR 3.3.1.1

SR 3.3.1.4

SR 3.3.1.5

SR 3.3.1.6

4. RCS Low Pressure 1,2(a) D SR 3.3.1.1

SR 3.3.1.4

SR 3.3.1.5

SR 3.3.1.6

5. RCS Variable Low Pressure 1,2(a) D SR 3.3.1.1

SR 3.3.1.4

SR 3.3.1.5

6. Reactor Building High Pressure 1,2,3(d) D SR 3.3.1.1

SR 3.3.1.4

SR 3.3.1.5

(a) When not in shutdown bypass operation. 

(b) With any CRD trip breaker in the closed position, the CRD System capable of rod withdrawal, and not in 

shutdown bypass operation. 

(c) During shutdown bypass operation with any CRD trip breaker in the closed position and the CRD System 

capable of rod withdrawal. 

(d) With any CRD trip breaker in the closed position and the CRD System capable of rod withdrawal. 
RPS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Babcock & Wilcox STS 3.3.1B-7 Rev. 4.0 

Table 3.3.1-1 (page 2 of 2)

Reactor Protection System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER SPECIFIED 

CONDITIONS

CONDITIONS 

REFERENCED 

FROM REQUIRED 

ACTION C.1

SURVEILLANCE

REQUIREMENTS

7. Reactor Coolant Pump to Power 1,2(a) D SR 3.3.1.1

SR 3.3.1.4

SR 3.3.1.5

SR 3.3.1.6

8. Nuclear Overpower RCS Flow and 

Measured AXIAL POWER IMBALANCE

1,2(a) D SR 3.3.1.1

SR 3.3.1.3

SR 3.3.1.4

SR 3.3.1.5

SR 3.3.1.6

9. Main Turbine Trip (Control Oil Pressure)  [45]% RTP F SR 3.3.1.1

SR 3.3.1.4

SR 3.3.1.5

10. Loss of Main Feedwater Pumps (Control Oil 

Pressure)

 [15]% RTP G SR 3.3.1.1

SR 3.3.1.4

SR 3.3.1.5

11. Shutdown Bypass RCS High Pressure 2

(c)

,3(c),4(c)

5

(c)

E SR 3.3.1.1

SR 3.3.1.4

SR 3.3.1.5

(a) When not in shutdown bypass operation. 

(c) During shutdown bypass operation with any CRD trip breakers in the closed position and the CRD System 

capable of rod withdrawal. 

RPS Manual Reactor Trip 

3.3.2

Babcock & Wilcox STS 3.3.2-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.2 Reactor Protection System (RPS) Manual Reactor Trip 

LCO 3.3.2 The RPS Manual Reactor Trip Function shall be OPERABLE. 

APPLICABILITY: MODES 1 and 2,

MODES 3, 4, and 5 with any CONTROL ROD drive (CRD) trip breaker in 

the closed position and the CRD System capable of rod withdrawal. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Manual Reactor Trip 

Function inoperable.

A.1 Restore Function to 

OPERABLE status.

1 hour

B. Required Action and 

associated Completion 

Time not met in 

MODE 1, 2, or 3.

B.1 Be in MODE 3.

AND

B.2 Open all CRD trip breakers.

6 hours

6 hours

C. Required Action and 

associated Completion 

Time not met in MODE 4 

or 5.

C.1 Open all CRD trip breakers. 6 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.2.1 Perform CHANNEL FUNCTIONAL TEST. Once prior to 

each reactor 

startup if not 

performed within 

the previous 

7 days

RPS - RTM (Without Setpoint Control Program) 

3.3.3A 

Babcock & Wilcox STS 3.3.3A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.3A Reactor Protection System (RPS) - Reactor Trip Module (RTM) (Without Setpoint 

Control Program) 

LCO 3.3.3A Four RTMs shall be OPERABLE. 

APPLICABILITY: MODES 1 and 2,

MODES 3, 4, and 5 with any CONTROL ROD drive (CRD) trip breaker in 

the closed position and the CRD System capable of rod withdrawal. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One RTM inoperable. A.1.1 Trip the associated CRD 

trip breaker.

 OR

A.1.2 Remove power from the 

associated CRD trip 

breaker.

AND

A.2 Physically remove the 

inoperable RTM.

1 hour

1 hour

1 hour

B. Two or more RTMs 

inoperable in MODE 1, 

2, or 3.

OR

Required Action and 

associated Completion 

Time not met in 

MODE 1, 2, or 3.

B.1 Be in MODE 3.

AND

B.2.1 Open all CRD trip breakers.

 OR

B.2.2 Remove power from all

CRD trip breakers.

6 hours

6 hours

6 hours
RPS - RTM (Without Setpoint Control Program) 

3.3.3A 

Babcock & Wilcox STS 3.3.3A-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. Two or more RTMs 

inoperable in MODE 4 

or 5.

OR

Required Action and 

associated Completion 

Time not met in MODE 4 

or 5.

C.1 Open all CRD trip breakers.

OR

C.2 Remove power from all 

CRD trip breakers.

6 hours

6 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.3.1 Perform CHANNEL FUNCTIONAL TEST. [ [23] days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RPS - RTM (With Setpoint Control Program) 

3.3.3B 

Babcock & Wilcox STS 3.3.3B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.3B Reactor Protection System (RPS) - Reactor Trip Module (RTM) (With Setpoint 

Control Program) 

LCO 3.3.3B Four RTMs shall be OPERABLE. 

APPLICABILITY: MODES 1 and 2,

MODES 3, 4, and 5 with any CONTROL ROD drive (CRD) trip breaker in 

the closed position and the CRD System capable of rod withdrawal. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One RTM inoperable. A.1.1 Trip the associated CRD 

trip breaker.

 OR

A.1.2 Remove power from the 

associated CRD trip 

breaker.

AND

A.2 Physically remove the 

inoperable RTM.

1 hour

1 hour

1 hour

B. Two or more RTMs 

inoperable in MODE 1, 

2, or 3.

OR

Required Action and 

associated Completion 

Time not met in 

MODE 1, 2, or 3.

B.1 Be in MODE 3.

AND

B.2.1 Open all CRD trip breakers.

 OR

B.2.2 Remove power from all 

CRD trip breakers.

6 hours

6 hours

6 hours
RPS - RTM (With Setpoint Control Program) 

3.3.3B 

Babcock & Wilcox STS 3.3.3B-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. Two or more RTMs 

inoperable in MODE 4 

or 5.

OR

Required Action and 

associated Completion 

Time not met in MODE 4 

or 5.

C.1 Open all CRD trip breakers.

OR

C.2 Remove power from all 

CRD trip breakers.

6 hours

6 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.3.1 Perform CHANNEL FUNCTIONAL TEST in 

accordance with the Setpoint Control Program.

[ [23] days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
CRD Trip Devices (Without Setpoint Control Program) 

3.3.4A 

Babcock & Wilcox STS 3.3.4A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.4A CONTROL ROD Drive (CRD) Trip Devices (Without Setpoint Control Program) 

LCO 3.3.4A The following CRD trip devices shall be OPERABLE: 

a. Two AC CRD trip breakers, 

b. Two DC CRD trip breaker pairs, and 

c. Eight electronic trip assembly (ETA) relays. 

APPLICABILITY: MODES 1 and 2,

MODES 3, 4, and 5 when any CRD trip breaker is in the closed position 

and the CRD System is capable of rod withdrawal.

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each CRD trip device. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more CRD trip 

breaker(s) [or breaker 

pair] undervoltage or 

shunt trip Functions 

inoperable.

A.1 Trip the CRD trip 

breaker(s)

OR

A.2 Remove power from the 

CRD trip breaker(s).

48 hours

48 hours

B. One or more CRD trip 

breaker(s) [or breaker 

pair] inoperable for 

reasons other than those 

in Condition A.

B.1 Trip the CRD trip 

breaker(s).

OR

B.2 Remove power from the 

CRD trip breaker(s).

1 hour

1 hour
CRD Trip Devices (Without Setpoint Control Program) 

3.3.4A 

Babcock & Wilcox STS 3.3.4A-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. One or more ETA relays 

inoperable.

C.1 Transfer affected 

CONTROL ROD group to 

power supply with 

OPERABLE ETA relays.

OR

C.2 Trip corresponding AC 

CRD trip breaker.

1 hour

1 hour

D. Required Action and 

associated Completion 

Time not met in 

MODE 1, 2, or 3.

D.1 Be in MODE 3.

AND

D.2.1 Open all CRD trip breakers.

 OR

D.2.2 Remove power from all 

CRD trip breakers.

6 hours

6 hours

6 hours

E. Required Action and 

associated Completion 

Time not met in MODE 4 

or 5.

E.1 Open all CRD trip breakers.

OR

E.2 Remove power from all 

CRD trip breakers.

6 hours

6 hours
CRD Trip Devices (Without Setpoint Control Program) 

3.3.4A 

Babcock & Wilcox STS 3.3.4A-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.4.1 Perform CHANNEL FUNCTIONAL TEST. [ [23] days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

CRD Trip Devices (With Setpoint Control Program) 

3.3.4B 

Babcock & Wilcox STS 3.3.4B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.4B CONTROL ROD Drive (CRD) Trip Devices (With Setpoint Control Program) 

LCO 3.3.4B The following CRD trip devices shall be OPERABLE: 

a. Two AC CRD trip breakers, 

b. Two DC CRD trip breaker pairs, and 

c. Eight electronic trip assembly (ETA) relays. 

APPLICABILITY: MODES 1 and 2,

MODES 3, 4, and 5 when any CRD trip breaker is in the closed position 

and the CRD System is capable of rod withdrawal.

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each CRD trip device. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more CRD trip 

breaker(s) [or breaker 

pair] undervoltage or 

shunt trip Functions 

inoperable.

A.1 Trip the CRD trip 

breaker(s)

OR

A.2 Remove power from the 

CRD trip breaker(s).

48 hours

48 hours

B. One or more CRD trip 

breaker(s) [or breaker 

pair] inoperable for 

reasons other than those 

in Condition A.

B.1 Trip the CRD trip 

breaker(s).

OR

B.2 Remove power from the 

CRD trip breaker(s).

1 hour

1 hour
CRD Trip Devices (With Setpoint Control Program) 

3.3.4B 

Babcock & Wilcox STS 3.3.4B-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. One or more ETA relays 

inoperable.

C.1 Transfer affected 

CONTROL ROD group to 

power supply with 

OPERABLE ETA relays.

OR

C.2 Trip corresponding AC 

CRD trip breaker.

1 hour

1 hour

D. Required Action and 

associated Completion 

Time not met in 

MODE 1, 2, or 3.

D.1 Be in MODE 3.

AND

D.2.1 Open all CRD trip breakers.

 OR

D.2.2 Remove power from all 

CRD trip breakers.

6 hours

6 hours

6 hours

E. Required Action and 

associated Completion 

Time not met in MODE 4 

or 5.

E.1 Open all CRD trip breakers.

OR

E.2 Remove power from all 

CRD trip breakers.

6 hours

6 hours
CRD Trip Devices (With Setpoint Control Program) 

3.3.4B 

Babcock & Wilcox STS 3.3.4B-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.4.1 Perform CHANNEL FUNCTIONAL TEST in 

accordance with the Setpoint Control Program.

[ [23] days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.5A 

Babcock & Wilcox STS 3.3.5A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.5A Engineered Safety Feature Actuation System (ESFAS) Instrumentation (Without 

Setpoint Control Program) 

LCO 3.3.5A Three channels of ESFAS instrumentation for each Parameter in 

Table 3.3.5-1 shall be OPERABLE in each ESFAS train. 

APPLICABILITY: According to Table 3.3.5-1.

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each Parameter. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Parameters 

with one channel 

inoperable.

A.1 Place channel in trip. 1 hour

B. One or more Parameters 

with two or more 

channels inoperable.

OR

Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3.

AND

6 hours
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.5A 

Babcock & Wilcox STS 3.3.5A-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.2.1 --------------NOTE--------------

Only required for RCS 

Pressure - Low setpoint.

-------------------------------------

Reduce RCS pressure 

< [1800] psig.

 AND

B.2.2 --------------NOTE--------------

Only required for RCS 

Pressure - Low Low 

setpoint.

-------------------------------------

Reduce RCS pressure 

< [900] psig.

 AND

B.2.3 --------------NOTES-------------

1. Only required for 

Reactor Building 

Pressure High setpoint 

and High High 

setpoint.

2. LCO 3.0.4.a is not 

applicable when 

entering MODE 4.

-------------------------------------

Be in MODE 4.

36 hours

36 hours

12 hours
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.5A 

Babcock & Wilcox STS 3.3.5A-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.5.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the 

Surveillance 

Frequency 

Control Program ]
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.5A 

Babcock & Wilcox STS 3.3.5A-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.5.2 -------------------------------NOTES----------------------------

1. When an ESFAS channel is placed in an 

inoperable status solely for performance of this 

Surveillance, entry into associated Conditions 

and Required Actions may be delayed for up to 

8 hours, provided the remaining two channels of 

ESFAS instrumentation are OPERABLE or 

tripped.

2. If the as-found channel setpoint is outside its 

predefined as-found tolerance, then the channel 

shall be evaluated to verify that it is functioning 

as required before returning the channel to 

service.

3. The instrument channel setpoint shall be reset

to a value that is within the as-left tolerance 

around the Limiting Trip Setpoint (LTSP) at the 

completion of the surveillance; otherwise, the 

channel shall be declared inoperable. Setpoints 

more conservative than the LTSP are 

acceptable provided that the as-found and asleft tolerances apply to the actual setpoint 

implemented in the Surveillance procedures 

(Nominal Trip Setpoint) to confirm channel 

performance. The LTSP and the 

methodologies used to determine the as-found 

and the as-left tolerances are specified in [insert 

the facility FSAR reference or the name of any 

document incorporated into the facility FSAR by 

reference].

---------------------------------------------------------------------

Perform CHANNEL FUNCTIONAL TEST.

[ 31 days

OR

In accordance 

with the 

Surveillance 

Frequency 

Control Program ]
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.5A 

Babcock & Wilcox STS 3.3.5A-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.5.3 -------------------------------NOTES----------------------------

1. If the as-found channel setpoint is outside its 

predefined as-found tolerance, then the channel 

shall be evaluated to verify that it is functioning 

as required before returning the channel to 

service.

2. The instrument channel setpoint shall be reset 

to a value that is within the as-left tolerance 

around the LTSP at the completion of the 

surveillance; otherwise, the channel shall be 

declared inoperable. Setpoints more 

conservative than the LTSP are acceptable 

provided that the as-found and as-left 

tolerances apply to the actual setpoint 

implemented in the Surveillance procedures 

(Nominal Trip Setpoint) to confirm channel 

performance. The LTSP and the 

methodologies used to determine the as-found 

and the as-left tolerances are specified in [insert 

the facility FSAR reference or the name of any 

document incorporated into the facility FSAR by 

reference].

---------------------------------------------------------------------

Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the 

Surveillance 

Frequency 

Control Program ]
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.5A 

Babcock & Wilcox STS 3.3.5A-6 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.5.4 Verify ESFAS RESPONSE TIME within limits. [ [18] months on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the 

Surveillance 

Frequency 

Control Program ]
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.5A 

Babcock & Wilcox STS 3.3.5A-7 Rev. 4.0 

Table 3.3.5-1 (page 1 of 1)

Engineered Safety Feature Actuation System Instrumentation 

PARAMETER

APPLICABLE

MODES OR OTHER SPECIFIED 

CONDITIONS

ALLOWABLE

VALUE

1. Reactor Coolant System Pressure - Low 

Setpoint (HPI Actuation, RB Isolation, RB 

Cooling, EDG Start)

 [1800] psig  [1600] psig

2. Reactor Coolant System Pressure - Low Low 

Setpoint (HPI Actuation, LPI Actuation, RB 

Isolation, RB Cooling)

 [900] psig  [400] psig

3. Reactor Building (RB) Pressure - High 

Setpoint (HPI Actuation, LPI Actuation, RB 

Isolation, RB Cooling)

1,2,3,4  [5] psig

4. Reactor Building Pressure - High High 

Setpoint (RB Spray Actuation)

1,2,3,4  [30] psig

ESFAS Instrumentation (With Setpoint Control Program) 

3.3.5B 

Babcock & Wilcox STS 3.3.5B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.5B Engineered Safety Feature Actuation System (ESFAS) Instrumentation (With 

Setpoint Control Program) 

LCO 3.3.5B Three channels of ESFAS instrumentation for each Parameter in 

Table 3.3.5-1 shall be OPERABLE in each ESFAS train. 

APPLICABILITY: According to Table 3.3.5-1.

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each Parameter. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Parameters 

with one channel 

inoperable.

A.1 Place channel in trip. 1 hour

B. One or more Parameters 

with two or more 

channels inoperable.

OR

Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3.

AND

6 hours
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.5B 

Babcock & Wilcox STS 3.3.5B-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.2.1 --------------NOTE--------------

Only required for RCS 

Pressure - Low setpoint.

-------------------------------------

Reduce RCS pressure 

< [1800] psig.

 AND

B.2.2 --------------NOTE--------------

Only required for RCS 

Pressure - Low Low 

setpoint.

-------------------------------------

Reduce RCS pressure 

< [900] psig.

 AND

B.2.3 --------------NOTES-------------

1. Only required for 

Reactor Building 

Pressure High setpoint 

and High High 

setpoint.

2. LCO 3.0.4.a is not 

applicable when 

entering MODE 4.

-------------------------------------

Be in MODE 4.

36 hours

36 hours

12 hours
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.5B 

Babcock & Wilcox STS 3.3.5B-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.5.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.5.2 -------------------------------NOTE------------------------------

When an ESFAS channel is placed in an inoperable 

status solely for performance of this Surveillance, 

entry into associated Conditions and Required 

Actions may be delayed for up to 8 hours, provided 

the remaining two channels of ESFAS 

instrumentation are OPERABLE or tripped.

---------------------------------------------------------------------

Perform CHANNEL FUNCTIONAL TEST in 

accordance with the Setpoint Control Program.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.5.3 Perform CHANNEL CALIBRATION in accordance 

with the Setpoint Control Program.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.5B 

Babcock & Wilcox STS 3.3.5B-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.5.4 Verify ESFAS RESPONSE TIME within limits. [ [18] months on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.5B 

Babcock & Wilcox STS 3.3.5B-5 Rev. 4.0 

Table 3.3.5-1 (page 1 of 1)

Engineered Safety Feature Actuation System Instrumentation 

PARAMETER

APPLICABLE

MODES OR OTHER SPECIFIED 

CONDITIONS

1. Reactor Coolant System Pressure - Low Setpoint (HPI Actuation, RB 

Isolation, RB Cooling, EDG Start)

 [1800] psig

2. Reactor Coolant System Pressure - Low Low Setpoint (HPI Actuation, 

LPI Actuation, RB Isolation, RB Cooling)

 [900] psig

3. Reactor Building (RB) Pressure - High Setpoint (HPI Actuation, LPI 

Actuation, RB Isolation, RB Cooling)

1,2,3,4

4. Reactor Building Pressure - High High Setpoint (RB Spray Actuation) 1,2,3,4

ESFAS Manual Initiation 

3.3.6

Babcock & Wilcox STS 3.3.6-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.6 Engineered Safety Feature Actuation System (ESFAS) Manual Initiation 

LCO 3.3.6 Two manual initiation channels of each one of the ESFAS Functions 

below shall be OPERABLE: 

a. High Pressure Injection, 

b. Low Pressure Injection, 

 [ c. Reactor Building (RB) Cooling, ] 

 [ d. RB Spray, ]

e. RB Isolation, and 

 [ f. Control Room Isolation. ] 

APPLICABILITY: MODES 1, 2, and 3,

MODE 4 when associated engineered safeguard equipment is required to 

be OPERABLE. 

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each Function. 

------------------------------------------------------------------------------------------------------------------------------- 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more ESFAS 

Functions with one 

channel inoperable.

A.1 Restore channel to 

OPERABLE status.

72 hours

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3.

AND

6 hours
ESFAS Manual Initiation 

3.3.6

Babcock & Wilcox STS 3.3.6-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.2 --------------NOTE--------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4. 12 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.6.1 Perform CHANNEL FUNCTIONAL TEST. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
ESFAS Automatic Actuation Logic 

3.3.7

Babcock & Wilcox STS 3.3.7-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.7 Engineered Safety Feature Actuation System (ESFAS) Automatic Actuation Logic 

LCO 3.3.7 All the ESFAS automatic actuation logic matrices shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3, 

MODE 4 when associated engineered safeguard equipment is required to 

be OPERABLE. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each automatic actuation logic matrix. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more automatic 

actuation logic matrices 

inoperable.

A.1 Place associated 

component(s) in 

engineered safeguard 

configuration.

OR

A.2 Declare the associated 

component(s) inoperable.

1 hour

1 hour
ESFAS Automatic Actuation Logic 

3.3.7

Babcock & Wilcox STS 3.3.7-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.7.1 Perform automatic actuation logic CHANNEL 

FUNCTIONAL TEST.

[ 31 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
EDG LOPS (Without Setpoint Control Program) 

3.3.8A 

Babcock & Wilcox STS 3.3.8A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.8A Emergency Diesel Generator (EDG) Loss of Power Start (LOPS) (Without Setpoint 

Control Program) 

LCO 3.3.8A Three channels of loss of voltage Function and three channels of 

degraded voltage Function EDG LOPS instrumentation per EDG shall be 

OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4,

When associated EDG is required to be OPERABLE by LCO 3.8.2 "AC 

Sources - Shutdown." 

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each Function. 

------------------------------------------------------------------------------------------------------------------------------- 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Functions 

with one channel per 

EDG inoperable.

A.1 Place channel in trip. 1 hour

B. One or more Functions 

with two or more 

channels per EDG 

inoperable.

B.1 Restore all but one channel 

to OPERABLE status.

1 hour

C. Required Action and 

associated Completion 

Time not met.

C.1 Enter applicable 

Condition(s) and Required 

Action for EDG made 

inoperable by EDG LOPS.

Immediately
EDG LOPS (Without Setpoint Control Program) 

3.3.8A 

Babcock & Wilcox STS 3.3.8A-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.8.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.8.2 -------------------------------NOTE------------------------------

When EDG LOPS instrumentation is placed in an 

inoperable status solely for performance of this 

Surveillance, entry into associated Conditions and 

Required Actions may be delayed as follows: (a) up 

to 4 hours for the degraded voltage Function, and 

(b) up to 4 hours for the loss of voltage Function, 

provided the two channels monitoring the Function 

for the bus are OPERABLE or tripped.

---------------------------------------------------------------------

Perform CHANNEL FUNCTIONAL TEST. [ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.8.3 Perform CHANNEL CALIBRATION with setpoint 

Allowable Value as follows:

a. Degraded voltage  [ ] and  [ ] V with a time 

delay of [ ] seconds ± [ ] seconds at [ ] V and

b. Loss of voltage  [ ] and  [ ] V with a time 

delay of [ ] seconds ± [ ] seconds at [ ] V.

[ 18 months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
EDG LOPS (With Setpoint Control Program) 

3.3.8B 

Babcock & Wilcox STS 3.3.8B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.8B Emergency Diesel Generator (EDG) Loss of Power Start (LOPS) (With Setpoint 

Control Program) 

LCO 3.3.8B Three channels of loss of voltage Function and three channels of 

degraded voltage Function EDG LOPS instrumentation per EDG shall be 

OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4,

When associated EDG is required to be OPERABLE by LCO 3.8.2 "AC 

Sources - Shutdown." 

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each Function. 

------------------------------------------------------------------------------------------------------------------------------- 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Functions 

with one channel per 

EDG inoperable.

A.1 Place channel in trip. 1 hour

B. One or more Functions 

with two or more 

channels per EDG 

inoperable.

B.1 Restore all but one channel 

to OPERABLE status.

1 hour

C. Required Action and 

associated Completion 

Time not met.

C.1 Enter applicable 

Condition(s) and Required 

Action for EDG made 

inoperable by EDG LOPS.

Immediately
EDG LOPS (With Setpoint Control Program) 

3.3.8B 

Babcock & Wilcox STS 3.3.8B-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.8.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.8.2 -------------------------------NOTE------------------------------

When EDG LOPS instrumentation is placed in an 

inoperable status solely for performance of this 

Surveillance, entry into associated Conditions and 

Required Actions may be delayed as follows: (a) up 

to 4 hours for the degraded voltage Function, and 

(b) up to 4 hours for the loss of voltage Function, 

provided the two channels monitoring the Function 

for the bus are OPERABLE or tripped.

---------------------------------------------------------------------

Perform CHANNEL FUNCTIONAL TEST in 

accordance with the Setpoint Control Program.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.8.3 Perform CHANNEL CALIBRATION in accordance 

with the Setpoint Control Program.

[ 18 months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Source Range Neutron Flux (Without Setpoint Control Program) 

3.3.9A 

Babcock & Wilcox STS 3.3.9A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.9A Source Range Neutron Flux (Without Setpoint Control Program) 

LCO 3.3.9A Two source range neutron flux channels shall be OPERABLE. 

---------------------------------------------NOTE--------------------------------------------

 High voltage to detector may be de-energized with neutron flux 

> 1E-10 amp on intermediate range channels. 

-------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODES 2, 3, 4, and 5.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One source range 

neutron flux channel 

inoperable with neutron 

flux  1E-10 amp on the 

intermediate range 

neutron flux channels.

A.1 Restore channel to 

OPERABLE status.

Prior to increasing 

neutron flux

B. Two source range 

neutron flux channels 

inoperable with neutron 

flux  1E-10 amp on the 

intermediate range 

neutron flux channels.

B.1 --------------NOTE--------------

Plant temperature changes 

are allowed provided the 

temperature change is 

accounted for in the 

calculated SDM.

-------------------------------------

Suspend operations 

involving positive reactivity 

changes.

AND

B.2 Initiate action to insert all 

CONTROL RODS.

AND

Immediately

Immediately
Source Range Neutron Flux (Without Setpoint Control Program) 

3.3.9A 

Babcock & Wilcox STS 3.3.9A-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.3 Open CONTROL ROD 

drive trip breakers.

AND

B.4 Verify SDM is within the 

limits specified in the 

COLR.

1 hour

1 hour

AND

Once per 12 hours 

thereafter

C. One or more source 

range neutron flux 

channel(s) inoperable 

with neutron flux 

> 1E-10 amp on the 

intermediate range 

neutron flux channels.

C.1 Initiate action to restore 

affected channel(s) to 

OPERABLE status.

1 hour

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.9.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Source Range Neutron Flux (Without Setpoint Control Program) 

3.3.9A 

Babcock & Wilcox STS 3.3.9A-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.9.2 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL 

CALIBRATION.

---------------------------------------------------------------------

Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Source Range Neutron Flux (With Setpoint Control Program) 

3.3.9B 

Babcock & Wilcox STS 3.3.9B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.9B Source Range Neutron Flux (With Setpoint Control Program) 

LCO 3.3.9B Two source range neutron flux channels shall be OPERABLE. 

---------------------------------------------NOTE--------------------------------------------

 High voltage to detector may be de-energized with neutron flux 

> 1E-10 amp on intermediate range channels. 

-------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODES 2, 3, 4, and 5.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One source range 

neutron flux channel 

inoperable with neutron 

flux  1E-10 amp on the 

intermediate range 

neutron flux channels.

A.1 Restore channel to 

OPERABLE status.

Prior to increasing 

neutron flux

B. Two source range 

neutron flux channels 

inoperable with neutron 

flux  1E-10 amp on the 

intermediate range 

neutron flux channels.

B.1 --------------NOTE--------------

Plant temperature changes 

are allowed provided the 

temperature change is 

accounted for in the 

calculated SDM.

-------------------------------------

Suspend operations 

involving positive reactivity 

changes.

AND

B.2 Initiate action to insert all 

CONTROL RODS.

AND

Immediately

Immediately
Source Range Neutron Flux (With Setpoint Control Program) 

3.3.9B 

Babcock & Wilcox STS 3.3.9B-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.3 Open CONTROL ROD 

drive trip breakers.

AND

B.4 Verify SDM is within the 

limits specified in the 

COLR.

1 hour

1 hour

AND

Once per 12 hours 

thereafter

C. One or more source 

range neutron flux 

channel(s) inoperable 

with neutron flux 

> 1E-10 amp on the 

intermediate range 

neutron flux channels.

C.1 Initiate action to restore 

affected channel(s) to 

OPERABLE status.

1 hour

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.9.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Source Range Neutron Flux (With Setpoint Control Program) 

3.3.9B 

Babcock & Wilcox STS 3.3.9B-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.9.2 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL 

CALIBRATION.

---------------------------------------------------------------------

Perform CHANNEL CALIBRATION in accordance 

with the Setpoint Control Program.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Intermediate Range Neutron Flux (Without Setpoint Control Program) 

3.3.10A 

Babcock & Wilcox STS 3.3.10A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.10A Intermediate Range Neutron Flux (Without Setpoint Control Program) 

LCO 3.3.10A Two intermediate range neutron flux channels shall be OPERABLE. 

APPLICABILITY: MODE 2,

MODES 3, 4, and 5 with any CONTROL ROD drive (CRD) trip breaker in 

the closed position and the CRD System capable of rod withdrawal. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One channel inoperable. A.1 Reduce neutron flux to 

 1E-10 amp.

2 hours

B. Two channels 

inoperable.

B.1 --------------NOTE--------------

Plant temperature changes 

are allowed provided the 

temperature change is 

accounted for in the 

calculated SDM.

-------------------------------------

Suspend operations 

involving positive reactivity 

changes.

AND

B.2 Open CRD trip breakers.

Immediately

1 hour
Intermediate Range Neutron Flux (Without Setpoint Control Program) 

3.3.10A 

Babcock & Wilcox STS 3.3.10A-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.10.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.10.2 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL 

CALIBRATION.

---------------------------------------------------------------------

Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Intermediate Range Neutron Flux (With Setpoint Control Program) 

3.3.10B 

Babcock & Wilcox STS 3.3.10B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.10B Intermediate Range Neutron Flux (With Setpoint Control Program) 

LCO 3.3.10B Two intermediate range neutron flux channels shall be OPERABLE. 

APPLICABILITY: MODE 2,

MODES 3, 4, and 5 with any CONTROL ROD drive (CRD) trip breaker in 

the closed position and the CRD System capable of rod withdrawal. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One channel inoperable. A.1 Reduce neutron flux to 

 1E-10 amp.

2 hours

B. Two channels 

inoperable.

B.1 --------------NOTE--------------

Plant temperature changes 

are allowed provided the 

temperature change is 

accounted for in the 

calculated SDM.

-------------------------------------

Suspend operations 

involving positive reactivity 

changes.

AND

B.2 Open CRD trip breakers.

Immediately

1 hour
Intermediate Range Neutron Flux (With Setpoint Control Program) 

3.3.10B 

Babcock & Wilcox STS 3.3.10B-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.10.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.10.2 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL 

CALIBRATION.

---------------------------------------------------------------------

Perform CHANNEL CALIBRATION in accordance 

with the Setpoint Control Program.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
EFIC System Instrumentation (Without Setpoint Control Program) 

3.3.11A 

Babcock & Wilcox STS 3.3.11A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.11A Emergency Feedwater Initiation and Control (EFIC) System Instrumentation 

(Without Setpoint Control Program) 

LCO 3.3.11A The EFIC System instrumentation channels for each Function in 

Table 3.3.11-1 shall be OPERABLE. 

APPLICABILITY: According to Table 3.3.11-1.

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Emergency 

Feedwater (EFW) 

Initiation, Main Steam 

Line Isolation, or Main 

Feedwater (MFW) 

Isolation Functions listed 

in Table 3.3.11-1 with 

one channel inoperable.

A.1 Place channel(s) in bypass 

or trip.

AND

A.2 Place channel(s) in trip.

1 hour

72 hours

B. One or more EFW 

Initiation, Main Steam 

Line Isolation, or MFW 

Isolation Functions listed 

in Table 3.3.11-1 with 

two channels inoperable.

B.1 Place one channel in 

bypass.

AND

B.2 Place second channel in 

trip.

AND

B.3 Restore one channel to 

OPERABLE status.

1 hour

1 hour

72 hours
EFIC System Instrumentation (Without Setpoint Control Program) 

3.3.11A 

Babcock & Wilcox STS 3.3.11A-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. One EFW Vector Valve 

Control channel 

inoperable.

C.1 Restore channel to 

OPERABLE status.

72 hours

D. Three or more channels 

inoperable for 

Functions 1.a or 1.b.

OR

Required Action and 

associated Completion 

Time not met for 

Functions 1.a or 1.b.

D.1 Be in MODE 3.

AND

D.2.1 --------------NOTE--------------

Only required for 

Function 1a.

-------------------------------------

Open CONTROL ROD 

drive trip breakers.

 AND

D.2.2 --------------NOTE--------------

Only required for 

Function 1b.

-------------------------------------

Be in MODE 4.

6 hours

6 hours

12 hours

E. Three or more channels 

inoperable for 

Functions 1.d.

OR

Required Action and 

associated Completion 

Time not met for 

Function 1.d.

E.1 Reduce THERMAL 

POWER to  10% RTP.

6 hours
EFIC System Instrumentation (Without Setpoint Control Program) 

3.3.11A 

Babcock & Wilcox STS 3.3.11A-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

F. Three or more channels 

inoperable for 

Functions 1.c, 2, 3, or 4.

OR

Required Action and 

associated Completion 

Time not met for 

Functions 1.c, 2, 3, or 4.

F.1 Reduce once through 

steam generator pressure 

to < 750 psig.

12 hours

SURVEILLANCE REQUIREMENTS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Refer to Table 3.3.11-1 to determine which SRs shall be performed for each EFIC Function. 

SURVEILLANCE FREQUENCY

SR 3.3.11.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.11.2 Perform CHANNEL FUNCTIONAL TEST. [ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
EFIC System Instrumentation (Without Setpoint Control Program) 

3.3.11A 

Babcock & Wilcox STS 3.3.11A-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.11.3 Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.11.4 Verify EFIC RESPONSE TIME is within limits. [ [18] months on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
EFIC System Instrumentation (Without Setpoint Control Program) 

3.3.11A 

Babcock & Wilcox STS 3.3.11A-5 Rev. 4.0 

Table 3.3.11-1 (page 1 of 2)

Emergency Feedwater Initiation and Control System Instrumentation 

FUNCTION

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE

VALUE

1. EFW Initiation

a. Loss of MFW Pumps 

(Control Oil Pressure)

1,2(a),3(a) 4 SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

> [55] psig

b. SG Level - Low 1,2,3 4 per SG SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

SR 3.3.11.4

 [9] inches

c. SG Pressure - Low 1,2,3(b) 4 per SG SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

 [600] psig

d. RCP Status  10% RTP 4 SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

NA

2. EFW Vector Valve Control

a. SG Pressure - Low 1,2,3(b) 4 per SG SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

 [600] psig

b. SG Differential 

Pressure - High

1,2,3(b) 4 SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

 [125] psid

c. [ SG Level - High 1,2,3(b) 4 SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

 [ ] inches ]

3. Main Steam Line Isolation

a. SG Pressure - Low 1,2,3(b)(c) 4 per SG SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

SR 3.3.11.4

 [600] psig

(a) When not in shutdown bypass. 

(b) When SG pressure  750 psig. 

(c) Except when all associated valves are closed and [deactivated]. 
EFIC System Instrumentation (Without Setpoint Control Program) 

3.3.11A 

Babcock & Wilcox STS 3.3.11A-6 Rev. 4.0 

Table 3.3.11-1 (page 2 of 2)

Emergency Feedwater Initiation and Control System Instrumentation 

FUNCTION

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS

SURVEILLANCE

REQUIREMENTS

ALLOWABLE

VALUE

4. MFW Isolation

a. SG Pressure - Low 1,2,3(b)(d) 4 per SG SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

SR 3.3.11.4

 [600] psig

(b) When SG pressure  750 psig. 

(d) Except when all [MFSVs], [MFCVs], [or associated SFCVs] are closed and [deactivated] [or isolated by a closed 

manual valve]. 
EFIC System Instrumentation (With Setpoint Control Program) 

3.3.11B 

Babcock & Wilcox STS 3.3.11B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.11B Emergency Feedwater Initiation and Control (EFIC) System Instrumentation (With 

Setpoint Control Program) 

LCO 3.3.11B The EFIC System instrumentation channels for each Function in 

Table 3.3.11-1 shall be OPERABLE. 

APPLICABILITY: According to Table 3.3.11-1.

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Emergency 

Feedwater (EFW) 

Initiation, Main Steam 

Line Isolation, or Main 

Feedwater (MFW) 

Isolation Functions listed 

in Table 3.3.11-1 with 

one channel inoperable.

A.1 Place channel(s) in bypass 

or trip.

AND

A.2 Place channel(s) in trip.

1 hour

72 hours

B. One or more EFW 

Initiation, Main Steam 

Line Isolation, or MFW 

Isolation Functions listed 

in Table 3.3.11-1 with 

two channels inoperable.

B.1 Place one channel in 

bypass.

AND

B.2 Place second channel in 

trip.

AND

B.3 Restore one channel to 

OPERABLE status.

1 hour

1 hour

72 hours
EFIC System Instrumentation (With Setpoint Control Program) 

3.3.11B 

Babcock & Wilcox STS 3.3.11B-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. One EFW Vector Valve 

Control channel 

inoperable.

C.1 Restore channel to 

OPERABLE status.

72 hours

D. Three or more channels 

inoperable for 

Functions 1.a or 1.b.

OR

Required Action and 

associated Completion 

Time not met for 

Functions 1.a or 1.b.

D.1 Be in MODE 3.

AND

D.2.1 --------------NOTE--------------

Only required for 

Function 1a.

-------------------------------------

Open CONTROL ROD 

drive trip breakers.

 AND

D.2.2 --------------NOTE--------------

Only required for 

Function 1b.

-------------------------------------

Be in MODE 4.

6 hours

6 hours

12 hours

E. Three or more channels 

inoperable for 

Functions 1.d.

OR

Required Action and 

associated Completion 

Time not met for 

Function 1.d.

E.1 Reduce THERMAL 

POWER to  10% RTP.

6 hours
EFIC System Instrumentation (With Setpoint Control Program) 

3.3.11B 

Babcock & Wilcox STS 3.3.11B-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

F. Three or more channels 

inoperable for 

Functions 1.c, 2, 3, or 4.

OR

Required Action and 

associated Completion 

Time not met for 

Functions 1.c, 2, 3, or 4.

F.1 Reduce once through 

steam generator pressure 

to < 750 psig.

12 hours

SURVEILLANCE REQUIREMENTS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Refer to Table 3.3.11-1 to determine which SRs shall be performed for each EFIC Function. 

SURVEILLANCE FREQUENCY

SR 3.3.11.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.11.2 Perform CHANNEL FUNCTIONAL TEST in 

accordance with the Setpoint Control Program.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
EFIC System Instrumentation (With Setpoint Control Program) 

3.3.11B 

Babcock & Wilcox STS 3.3.11B-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.11.3 Perform CHANNEL CALIBRATION in accordance 

with the Setpoint Control Program.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.11.4 Verify EFIC RESPONSE TIME is within limits. [ [18] months on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
EFIC System Instrumentation (With Setpoint Control Program) 

3.3.11B 

Babcock & Wilcox STS 3.3.11B-5 Rev. 4.0 

Table 3.3.11-1 (page 1 of 2)

Emergency Feedwater Initiation and Control System Instrumentation 

FUNCTION

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS

SURVEILLANCE 

REQUIREMENTS

1. EFW Initiation

a. Loss of MFW Pumps (Control Oil 

Pressure)

1,2(a),3(a) 4 SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

b. SG Level - Low 1,2,3 4 per SG SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

SR 3.3.11.4

c. SG Pressure - Low 1,2,3(b) 4 per SG SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

d. RCP Status  10% RTP 4 SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

2. EFW Vector Valve Control

a. SG Pressure - Low 1,2,3(b) 4 per SG SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

b. SG Differential Pressure - High 1,2,3(b) 4 SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

c. [ SG Level - High 1,2,3(b) 4 SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3 ]

3. Main Steam Line Isolation

a. SG Pressure - Low 1,2,3(b)(c) 4 per SG SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

SR 3.3.11.4

(a) When not in shutdown bypass. 

(b) When SG pressure  750 psig. 

(c) Except when all associated valves are closed and [deactivated]. 
EFIC System Instrumentation (With Setpoint Control Program) 

3.3.11B 

Babcock & Wilcox STS 3.3.11B-6 Rev. 4.0 

Table 3.3.11-1 (page 2 of 2)

Emergency Feedwater Initiation and Control System Instrumentation 

FUNCTION

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS

SURVEILLANCE

REQUIREMENTS

4. MFW Isolation

a. SG Pressure - Low 1,2,3(b)(d) 4 per SG SR 3.3.11.1

SR 3.3.11.2

SR 3.3.11.3

SR 3.3.11.4

(b) When SG pressure  750 psig. 

(d) Except when all [MFSVs], [MFCVs], [or associated SFCVs] are closed and [deactivated] [or isolated by a closed 

manual valve]. 
EFIC Manual Initiation 

3.3.12

Babcock & Wilcox STS 3.3.12-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.12 Emergency Feedwater Initiation and Control (EFIC) Manual Initiation 

LCO 3.3.12 Two manual initiation switches per actuation channel for each of the 

following EFIC Functions shall be OPERABLE: 

a. Steam generator (SG) A Main Feedwater (MFW) Isolation, 

b. SG B MFW Isolation, 

c. SG A Main Steam Line Isolation, 

d. SG B Main Steam Line Isolation, and

e. Emergency Feedwater Actuation. 

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more EFIC 

Function(s) with one or 

both manual initiation 

switches inoperable in 

one actuation channel.

A.1 Place actuation channel for 

the associated EFIC 

Function(s) in trip.

72 hours

B. One or more EFIC 

Function(s) with one or 

both manual initiation 

switches inoperable in 

both actuation channels.

B.1 Restore one actuation 

channel for the associated 

EFIC Function(s) to 

OPERABLE status.

1 hour
EFIC Manual Initiation 

3.3.12

Babcock & Wilcox STS 3.3.12-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. Required Action and 

associated Completion 

Time not met.

C.1 Be in MODE 3.

AND

C.2 Be in MODE 4.

6 hours

12 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.12.1 Perform CHANNEL FUNCTIONAL TEST. [ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
EFIC Logic 

3.3.13

Babcock & Wilcox STS 3.3.13-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.13 Emergency Feedwater Initiation and Control (EFIC) Logic 

LCO 3.3.13 Channels A and B of each Logic Function shown below shall be 

OPERABLE: 

a. Main Feedwater Isolation, 

b. Main Steam Line Isolation, 

c. Emergency Feedwater Actuation, and 

d. Vector Valve Enable Logic. 

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more channel A 

Functions inoperable 

with all channel B 

Functions OPERABLE.

OR

One or more channel B 

Functions inoperable 

with all channel A 

Functions OPERABLE.

A.1 Restore affected channel to 

OPERABLE status.

72 hours

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 4.

6 hours

12 hours
EFIC Logic 

3.3.13

Babcock & Wilcox STS 3.3.13-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.13.1 Perform CHANNEL FUNCTIONAL TEST. [ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
EFIC-EFW - Vector Valve Logic 

3.3.14

Babcock & Wilcox STS 3.3.14-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.14 Emergency Feedwater Initiation and Control (EFIC) - Emergency Feedwater (EFW) 

- Vector Valve Logic 

LCO 3.3.14 Four channels of the vector valve logic shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One vector valve logic 

channel inoperable.

A.1 Restore channel to 

OPERABLE status.

72 hours

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 4.

6 hours

12 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.14.1 Perform a CHANNEL FUNCTIONAL TEST. [ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

RB Purge Isolation - High Radiation (Without Setpoint Control Program) 

3.3.15A 

Babcock & Wilcox STS 3.3.15A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.15A Reactor Building (RB) Purge Isolation - High Radiation (Without Setpoint Control 

Program) 

LCO 3.3.15A [One] channel of Reactor Building Purge Isolation - High Radiation shall 

be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4,

During movement of [recently] irradiated fuel assemblies within the RB. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One channel inoperable 

in MODE 1, 2, 3, or 4.

A.1 Place and maintain RB 

purge valves in closed 

positions.

1 hour

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 5.

6 hours

36 hours

C. One channel inoperable 

during movement of 

[recently] irradiated fuel 

assemblies within the 

RB.

C.1 Place and maintain RB 

purge valves in closed 

positions.

OR

C.2 Suspend movement of 

[recently] irradiated fuel 

assemblies within the RB.

Immediately

Immediately
RB Purge Isolation - High Radiation (Without Setpoint Control Program) 

3.3.15A 

Babcock & Wilcox STS 3.3.15A-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.15.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.15.2 Perform CHANNEL FUNCTIONAL TEST. [ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.15.3 Perform CHANNEL CALIBRATION with setpoint 

Allowable Value  [25] mR/hr.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RB Purge Isolation - High Radiation (With Setpoint Control Program) 

3.3.15B 

Babcock & Wilcox STS 3.3.15B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.15B Reactor Building (RB) Purge Isolation - High Radiation (With Setpoint Control 

Program) 

LCO 3.3.15B [One] channel of Reactor Building Purge Isolation - High Radiation shall 

be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4,

During movement of [recently] irradiated fuel assemblies within the RB. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One channel inoperable 

in MODE 1, 2, 3, or 4.

A.1 Place and maintain RB 

purge valves in closed 

positions.

1 hour

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 5.

6 hours

36 hours

C. One channel inoperable 

during movement of 

[recently] irradiated fuel 

assemblies within the 

RB.

C.1 Place and maintain RB 

purge valves in closed 

positions.

OR

C.2 Suspend movement of 

[recently] irradiated fuel 

assemblies within the RB.

Immediately

Immediately
RB Purge Isolation - High Radiation (With Setpoint Control Program) 

3.3.15B 

Babcock & Wilcox STS 3.3.15B-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.15.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.15.2 Perform CHANNEL FUNCTIONAL TEST in 

accordance with the Setpoint Control Program.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.15.3 Perform CHANNEL CALIBRATION in accordance 

with the Setpoint Control Program.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Control Room Isolation - High Radiation (Without Setpoint Control Program) 

3.3.16A 

Babcock & Wilcox STS 3.3.16A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.16A Control Room Isolation - High Radiation (Without Setpoint Control Program) 

LCO 3.3.16A [One] channel of Control Room Isolation - High Radiation shall be 

OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, 4, [5, and 6,]

During movement of [recently] irradiated fuel assemblies. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One channel inoperable 

in MODE 1, 2, 3, or 4.

A.1 --------------NOTE--------------

Place in toxic gas 

protection mode if 

automatic transfer to toxic 

gas protection mode is 

inoperable.

-------------------------------------

Place one OPERABLE 

Control Room Emergency 

Ventilation System 

(CREVS) train in the 

emergency recirculation 

mode.

1 hour

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 5.

6 hours

36 hours

C. One channel inoperable 

during movement of 

[recently] irradiated fuel.

C.1 Place one OPERABLE 

CREVS train in emergency 

recirculation mode.

OR

Immediately
Control Room Isolation - High Radiation (Without Setpoint Control Program) 

3.3.16A 

Babcock & Wilcox STS 3.3.16A-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C.2 Suspend movement of 

[recently] irradiated fuel 

assemblies.

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.16.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.16.2 -------------------------------NOTE------------------------------

When the Control Room Isolation - High Radiation 

instrumentation is placed in an inoperable status 

solely for performance of this Surveillance, entry into 

associated Conditions and Required Actions may be 

delayed for up to 3 hours.

---------------------------------------------------------------------

Perform CHANNEL FUNCTIONAL TEST. [ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Control Room Isolation - High Radiation (Without Setpoint Control Program) 

3.3.16A 

Babcock & Wilcox STS 3.3.16A-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.16.3 Perform CHANNEL CALIBRATION with setpoint 

Allowable Value  [25] mR/hr.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Control Room Isolation - High Radiation (With Setpoint Control Program) 

3.3.16B 

Babcock & Wilcox STS 3.3.16B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.16B Control Room Isolation - High Radiation (With Setpoint Control Program) 

LCO 3.3.16B [One] channel of Control Room Isolation - High Radiation shall be 

OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, 4, [5, and 6,]

During movement of [recently] irradiated fuel assemblies. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One channel inoperable 

in MODE 1, 2, 3, or 4.

A.1 --------------NOTE--------------

Place in toxic gas 

protection mode if 

automatic transfer to toxic 

gas protection mode is 

inoperable.

-------------------------------------

Place one OPERABLE 

Control Room Emergency 

Ventilation System 

(CREVS) train in the 

emergency recirculation 

mode.

1 hour

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 5.

6 hours

36 hours

C. One channel inoperable 

during movement of 

[recently] irradiated fuel.

C.1 Place one OPERABLE 

CREVS train in emergency 

recirculation mode.

OR

Immediately
Control Room Isolation - High Radiation (With Setpoint Control Program) 

3.3.16B 

Babcock & Wilcox STS 3.3.16B-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C.2 Suspend movement of 

[recently] irradiated fuel 

assemblies.

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.16.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.16.2 -------------------------------NOTE------------------------------

When the Control Room Isolation - High Radiation 

instrumentation is placed in an inoperable status 

solely for performance of this Surveillance, entry into 

associated Conditions and Required Actions may be 

delayed for up to 3 hours.

---------------------------------------------------------------------

Perform CHANNEL FUNCTIONAL TEST in 

accordance with the Setpoint Control Program.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Control Room Isolation - High Radiation (With Setpoint Control Program) 

3.3.16B 

Babcock & Wilcox STS 3.3.16B-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.16.3 Perform CHANNEL CALIBRATION in accordance 

with the Setpoint Control Program.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

PAM Instrumentation 

3.3.17

Babcock & Wilcox STS 3.3.17-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.17 Post Accident Monitoring (PAM) Instrumentation 

LCO 3.3.17 The PAM instrumentation for each Function in Table 3.3.17-1 shall be 

OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS 

-----------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Functions 

with one required 

channel inoperable.

A.1 Restore required channel to 

OPERABLE status.

30 days

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Initiate action in accordance 

with Specification 5.6.5.

Immediately

C. One or more Functions 

with two required 

channels inoperable.

C.1 Restore one channel to 

OPERABLE status.

7 days

D. Required Action and 

associated Completion 

Time of Condition C not 

met.

D.1 Enter the Condition 

referenced in 

Table 3.3.17-1 for the 

channel.

Immediately
PAM Instrumentation 

3.3.17

Babcock & Wilcox STS 3.3.17-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

E. As required by Required 

Action D.1 and 

referenced in 

Table 3.3.17-1.

E.1 Be in MODE 3.

AND

E.2 Be in MODE 4.

6 hours

12 hours

F. As required by Required 

Action D.1 and 

referenced in 

Table 3.3.17-1.

F.1 Initiate action in accordance 

with Specification 5.6.5.

Immediately

SURVEILLANCE REQUIREMENTS 

------------------------------------------------------------NOTE-----------------------------------------------------------

These SRs apply to each PAM instrumentation Function in Table 3.3.17-1.

-------------------------------------------------------------------------------------------------------------------------------

SURVEILLANCE FREQUENCY

SR 3.3.17.1 Perform CHANNEL CHECK for each required 

instrumentation channel that is normally energized.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
PAM Instrumentation 

3.3.17

Babcock & Wilcox STS 3.3.17-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.17.2 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL 

CALIBRATION.

---------------------------------------------------------------------

Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
PAM Instrumentation 

3.3.17

Babcock & Wilcox STS 3.3.17-4 Rev. 4.0 

Table 3.3.17-1 (page 1 of 1)

Post Accident Monitoring Instrumentation 

FUNCTION REQUIRED CHANNELS

CONDITIONS

REFERENCED FROM 

REQUIRED ACTION D.1

1. Wide Range Neutron Flux 2 E

2. RCS Hot Leg Temperature 2 per loop E

3. RCS Cold Leg Temperature 2 per loop E

4. RCS Pressure (Wide Range) 2 E

5. Reactor Vessel Water Level 2 F

6. Containment Sump Water Level (Wide Range) 2 E

7. Containment Pressure (Wide Range) 2 E

8. Penetration Flow Path Containment Isolation 

Valve Position

2 per penetration flow path(a)(b) E

9. Containment Area Radiation (High Range) 2 F

10. Pressurizer Level 2 E

11. Steam Generator Water Level 2 per SG E

12. Condensate Storage Tank Level 2 E

13. Core Exit Temperature 2 independent sets of 5(c) E

14. Emergency Feedwater Flow 2 E

-----------------------------------------------------------------REVIEWER'S NOTE---------------------------------------------------------------

Table 3.3.17-1 shall be amended for each unit as necessary to list all U.S. NRC Regulatory Guide 1.97, Type A 

instruments and all U.S. NRC Regulatory Guide 1.97, Category I, non-Type A instruments in accordance with the 

unit's U.S. NRC Regulatory Guide 1.97, Safety Evaluation Report. 

------------------------------------------------------------------------------------------------------------------------------------------------------------

(a) Not required for isolation valves whose associated penetration is isolated by at least one closed and 

deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve 

secured. 

(b) Only one position indication channel is required for penetration flow paths with only one installed control room 

indication channel. 

(c) The subcooling margin monitor takes the average of the five highest CETs for each of the inadequate core 

cooling monitor (ICCM) trains. 
Remote Shutdown System 

3.3.18

Babcock & Wilcox STS 3.3.18-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.18 Remote Shutdown System 

LCO 3.3.18 The Remote Shutdown System Functions shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS 

-----------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more required 

Functions inoperable.

A.1 Restore required Function 

to OPERABLE status.

30 days

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 4.

6 hours

12 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.18.1 [ Perform CHANNEL CHECK for each required 

instrumentation channel that is normally energized.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
Remote Shutdown System 

3.3.18

Babcock & Wilcox STS 3.3.18-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.18.2 Verify each required control circuit and transfer 

switch is capable of performing the intended 

function.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.18.3 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL 

CALIBRATION.

---------------------------------------------------------------------

Perform CHANNEL CALIBRATION for each 

required instrumentation channel.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Pressure, Temperature, and Flow DNB Limits 

3.4.1

Babcock & Wilcox STS 3.4.1-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) 

Limits 

LCO 3.4.1 RCS DNB parameters for loop pressure, hot leg temperature, and RCS 

total flow rate shall be within the limits specified below: 

a. With four reactor coolant pumps (RCPs) operating:

 RCS loop pressure shall be  [2061.6] psig, RCS hot leg 

temperature shall be  [604.6]F, and RCS total flow rate shall be 

 [139.7 E6] lb/hr, and

b. With three RCPs operating: 

 RCS loop pressure shall be  [2057.2] psig, RCS hot leg 

temperature shall be  [604.6]  F, and RCS total flow rate shall be 

 [104.4 E6] lb/hr.

APPLICABILITY: MODE 1.

--------------------------------------------NOTES-------------------------------------------

RCS loop pressure limit does not apply during: 

a. THERMAL POWER ramp > 5% RTP per minute or 

b. THERMAL POWER step > 10% RTP. 

--------------------------------------------------------------------------------------------------

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more RCS DNB 

parameters not within 

limits.

A.1 Restore RCS DNB 

parameter(s) to within limit.

2 hours

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 2. 6 hours
RCS Pressure, Temperature, and Flow DNB Limits 

3.4.1

Babcock & Wilcox STS 3.4.1-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.1.1 -------------------------------NOTE------------------------------

With three RCPs operating, the limits are applied to 

the loop with two RCPs in operation.

---------------------------------------------------------------------

Verify RCS loop pressure  [2061.6] psig with 

four RCPs operating or  [2057.2] psig with 

three RCPs operating.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.1.2 -------------------------------NOTE------------------------------

With three RCPs operating, the limits are applied to 

the loop with two RCPs in operation.

---------------------------------------------------------------------

Verify RCS hot leg temperature  [604.6]F. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.1.3 Verify RCS total flow  [139.7 E6] lb/hr with four 

RCPs operating or  [104.4 E6] lb/hr with three 

RCPS operating.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Pressure, Temperature, and Flow DNB Limits 

3.4.1

Babcock & Wilcox STS 3.4.1-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.1.4 -------------------------------NOTE------------------------------

Only required to be performed when stable thermal 

conditions are established in the higher power range 

of MODE 1.

---------------------------------------------------------------------

Verify RCS total flow rate is within limit by 

measurement.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

RCS Minimum Temperature for Criticality 

3.4.2

Babcock & Wilcox STS 3.4.2-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.2 RCS Minimum Temperature for Criticality 

LCO 3.4.2 Each RCS loop average temperature (Tavg) shall be  525F.

APPLICABILITY: MODE 1,

MODE 2 with keff  1.0.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Tavg in one or more RCS 

loops not within limit.

A.1 Be in MODE 2 with Keff

< 1.0.

30 minutes

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.2.1 Verify RCS Tavg in each loop  525F. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

RCS P/T Limits 

3.4.3

Babcock & Wilcox STS 3.4.3-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.3 RCS Pressure and Temperature (P/T) Limits 

LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cooldown rates 

shall be maintained within the limits specified in the PTLR. 

APPLICABILITY: At all times. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. ------------NOTE------------

Required Action A.2 

shall be completed 

whenever this Condition 

is entered.

---------------------------------

Requirements of 

LCO not met in 

MODE 1, 2, 3, or 4.

A.1 Restore parameter(s) to 

within limits.

AND

A.2 Determine RCS is 

acceptable for continued 

operation.

30 minutes

72 hours

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 5.

6 hours

36 hours

C. ------------NOTE------------

Required Action C.2 

shall be completed 

whenever this Condition 

is entered.

---------------------------------

Requirements of 

LCO not met in other 

than MODE 1, 2, 3, or 4.

C.1 Initiate action to restore 

parameter(s) to within limit.

AND

C.2 Determine RCS is 

acceptable for continued 

operation.

Immediately

Prior to entering 

MODE 4
RCS P/T Limits 

3.4.3

Babcock & Wilcox STS 3.4.3-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.3.1 -------------------------------NOTE------------------------------

Only required to be performed during RCS heatup 

and cooldown operations and RCS inservice leak 

and hydrostatic testing.

---------------------------------------------------------------------

Verify RCS pressure, RCS temperature, and RCS 

heatup and cooldown rates are within the limits 

specified in the PTLR.

[ 30 minutes

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Loops - MODES 1 and 2 

3.4.4

Babcock & Wilcox STS 3.4.4-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.4 RCS Loops - MODES 1 and 2 

LCO 3.4.4 Two RCS Loops shall be in operation, with: 

a. Four reactor coolant pumps (RCPs) operating or

b. Three RCPs operating and THERMAL POWER restricted to 

[79.9]% RTP. 

APPLICABILITY: MODES 1 and 2.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Requirements of 

LCO not met.

A.1 Be in MODE 3. 6 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.4.1 Verify required RCS loops are in operation. [ 12 hours

OR

In accordance

with the

Surveillance 

Frequency

Control Program ]

RCS Loops - MODE 3 

3.4.5

Babcock & Wilcox STS 3.4.5-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.5 RCS Loops - MODE 3 

LCO 3.4.5 Two RCS loops shall be OPERABLE and one RCS loop shall be in 

operation.

---------------------------------------------NOTE--------------------------------------------

 All reactor coolant pumps (RCPs) may be removed from operation for 

 8 hours per 24 hour period for the transition to or from the Decay Heat 

Removal System, and all RCPs may be de-energized for  1 hour per 

8 hour period for any other reason, provided: 

 a. No operations are permitted that would cause introduction of coolant 

into the RCS with boron concentration less than required to meet 

the SDM of LCO 3.1.1 and 

b. Core outlet temperature is maintained at least [10]F below 

saturation temperature. 

--------------------------------------------------------------------------------------------------

APPLICABILITY: MODE 3.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One RCS loop 

inoperable.

A.1 Restore RCS loop to 

OPERABLE status.

72 hours

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 4. 12 hours
RCS Loops - MODE 3 

3.4.5

Babcock & Wilcox STS 3.4.5-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. Two RCS loops 

inoperable.

OR

Required RCS loop not 

in operation.

C.1 Suspend operations that 

would cause introduction of 

coolant into the RCS with 

boron concentration less 

than required to meet SDM 

of LCO 3.1.1.

AND

C.2 Initiate action to restore 

one RCS loop to 

OPERABLE status and 

operation.

Immediately

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.5.1 Verify one RCS loop is in operation. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Loops - MODE 3 

3.4.5

Babcock & Wilcox STS 3.4.5-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.5.2 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours after a 

required pump is not in operation.

---------------------------------------------------------------------

Verify correct breaker alignment and indicated 

power available to each required pump.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

RCS Loops - MODE 4 

3.4.6

Babcock & Wilcox STS 3.4.6-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.6 RCS Loops - MODE 4 

LCO 3.4.6 Two loops consisting of any combination of RCS loops and decay heat 

removal (DHR) loops shall be OPERABLE and one loop shall be in 

operation.

---------------------------------------------NOTE--------------------------------------------

 All reactor coolant pumps (RCPs) may be removed from operation for 

 8 hours per 24 hour period for the transition to or from the DHR System, 

and all RCPs and DHR pumps may be de-energized for  1 hour per 

8 hour period for any other reason, provided: 

a. No operations are permitted that would cause introduction of coolant 

into the RCS with boron concentration less than required to meet 

the SDM of LCO 3.1.1 and 

b. Core outlet temperature is maintained at least 10F below saturation 

temperature. 

-------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODE 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One required loop 

inoperable.

A.1 --------------NOTE--------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Initiate action to restore a 

second loop to OPERABLE 

status.

Immediately
RCS Loops - MODE 4 

3.4.6

Babcock & Wilcox STS 3.4.6-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B. Two required loops 

inoperable.

OR

Required loop not in 

operation.

B.1 Suspend operations that 

would cause introduction of 

coolant into the RCS with 

boron concentration less 

than required to meet SDM 

of LCO 3.1.1.

AND

B.2 Initiate action to restore one 

loop to OPERABLE status 

and operation.

Immediately

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.6.1 Verify required DHR or RCS loop is in operation. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Loops - MODE 4 

3.4.6

Babcock & Wilcox STS 3.4.6-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.6.2 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours after a 

required pump is not in operation.

---------------------------------------------------------------------

Verify correct breaker alignment and indicated 

power available to each required pump.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

RCS Loops - MODE 5, Loops Filled 

3.4.7

Babcock & Wilcox STS 3.4.7-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.7 RCS Loops - MODE 5, Loops Filled 

LCO 3.4.7 One decay heat removal (DHR) loop shall be OPERABLE and in 

operation, and either: 

a. One additional DHR loop shall be OPERABLE or 

b. The secondary side water level of each steam generator (SG) shall 

be  [50]%. 

--------------------------------------------NOTES-------------------------------------------

1. The DHR pump of the loop in operation may be removed from 

operation for  1 hour per 8 hour period provided: 

 a. No operations are permitted that would cause introduction of 

coolant into the RCS with boron concentration less than 

required to meet the SDM of LCO 3.1.1 and 

 b. Core outlet temperature is maintained at least 10F below 

saturation temperature. 

2. One required DHR loop may be inoperable for up to 2 hours for 

surveillance testing provided that the other DHR loop is OPERABLE 

and in operation.

3. All DHR loops may be not in operation during planned heatup to 

MODE 4 when at least one RCS loop is in operation. 

--------------------------------------------------------------------------------------------------

APPLICABILITY: MODE 5 with RCS loops filled. 
RCS Loops - MODE 5, Loops Filled 

3.4.7

Babcock & Wilcox STS 3.4.7-2 Rev. 4.0 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One required DHR loop 

inoperable.

AND

One DHR loop 

OPERABLE.

A.1 Initiate action to restore a 

second DHR loop to 

OPERABLE status.

OR

A.2 Initiate action to restore 

required SGs secondary 

side water levels to within 

limits.

Immediately

Immediately

B. One or more required 

SGs with secondary side 

water level not within 

limit.

AND

One DHR loop 

OPERABLE.

B.1 Initiate action to restore a 

second DHR loop to 

OPERABLE status.

OR

B.2 Initiate action to restore 

required SGs secondary 

side water level to within 

limit.

Immediately

Immediately

C. No required DHR loop 

OPERABLE.

OR

Required DHR loop not 

in operation.

C.1 Suspend operations that 

would cause introduction of 

coolant into the RCS with 

boron concentration less 

than required to meet SDM 

of LCO 3.1.1.

AND

C.2 Initiate action to restore one 

DHR loop to OPERABLE 

status and operation.

Immediately

Immediately
RCS Loops - MODE 5, Loops Filled 

3.4.7

Babcock & Wilcox STS 3.4.7-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.7.1 Verify required DHR loop is in operation. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.7.2 Verify required SG secondary side water levels are 

 [50]%.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.7.3 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours after a 

required pump is not in operation.

---------------------------------------------------------------------

Verify correct breaker alignment and indicated 

power available to each required DHR pump.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

RCS Loops - MODE 5, Loops Not Filled 

3.4.8

Babcock & Wilcox STS 3.4.8-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.8 RCS Loops - MODE 5, Loops Not Filled 

LCO 3.4.8 Two decay heat removal (DHR) loops shall be OPERABLE and one DHR 

loop shall be in operation.

--------------------------------------------NOTES-------------------------------------------

1. All DHR pumps may be removed from operation for  15 minutes 

when switching from one loop to another provided: 

 [ a. The maximum RCS temperature is  [160]F, ]

 b. No operations are permitted that would cause introduction of 

coolant into the RCS with boron concentration less than 

required to meet the SDM of LCO 3.1.1 and 

 c. No draining operations to further reduce the RCS water 

volume are permitted. 

2. One DHR loop may be inoperable for  2 hours for surveillance 

testing provided that the other DHR loop is OPERABLE and in 

operation. 

-------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODE 5 with RCS loops not filled. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One required DHR loop 

inoperable.

A.1 Initiate action to restore 

DHR loop to OPERABLE 

status.

Immediately
RCS Loops - MODE 5, Loops Not Filled 

3.4.8

Babcock & Wilcox STS 3.4.8-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B. No required DHR loop 

OPERABLE.

OR

Required DHR loop not 

in operation.

B.1 Suspend operations that 

would cause introduction of 

coolant into the RCS with 

boron concentration less 

than required to meet SDM 

of LCO 3.1.1.

AND

B.2 Initiate action to restore one 

DHR loop to OPERABLE 

status and operation.

Immediately

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.8.1 Verify required DHR loop is in operation. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Loops - MODE 5, Loops Not Filled 

3.4.8

Babcock & Wilcox STS 3.4.8-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.8.2 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours after a 

required pump is not in operation.

---------------------------------------------------------------------

Verify correct breaker alignment and indicated 

power available to each required DHR pump.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Pressurizer 

3.4.9

Babcock & Wilcox STS 3.4.9-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.9 Pressurizer 

LCO 3.4.9 The pressurizer shall be OPERABLE with:

a. Pressurizer water level  [290] inches and 

b. A minimum of [126] kW of pressurizer heaters OPERABLE [and 

capable of being powered from an emergency power supply]. 

---------------------------------------------NOTE--------------------------------------------

 OPERABILITY requirements on pressurizer heaters do not apply in 

MODE 4.

--------------------------------------------------------------------------------------------------

APPLICABILITY: MODES 1, 2, and 3,

MODE 4 with RCS temperature  [275]F.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Pressurizer water level 

not within limit.

A.1 Restore level to within limit. 1 hour

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 4 with RCS 

temperature  [275]F.

6 hours

[24] hours

C. Capacity of pressurizer 

heaters [capable of 

being powered by 

emergency power 

supply] less than limit.

C.1 Restore pressurizer heater 

capability.

72 hours
Pressurizer 

3.4.9

Babcock & Wilcox STS 3.4.9-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

D. Required Action and 

associated Completion 

Time of Condition C not 

met.

D.1 Be in MODE 3.

AND

D.2 Be in MODE 4.

6 hours

12 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.9.1 Verify pressurizer water level  [290] inches. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.9.2 [ Verify  [126] kW of pressurizer heaters are 

capable of being powered from an emergency 

power supply.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
Pressurizer 

3.4.9

Babcock & Wilcox STS 3.4.9-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.9.3 [ Verify emergency power supply for pressurizer 

heaters is OPERABLE.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

Pressurizer Safety Valves 

3.4.10

Babcock & Wilcox STS 3.4.10-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.10 Pressurizer Safety Valves 

LCO 3.4.10 Two pressurizer safety valves shall be OPERABLE with lift settings 

 [2475] psig and  [2525] psig. 

APPLICABILITY: MODES 1, 2, and 3,

MODE 4 with all RCS cold leg temperatures > [283]F.

---------------------------------------------NOTE--------------------------------------------

The lift settings are not required to be within the LCO limits for entry into 

MODES 3 and 4 for the purpose of setting the pressurizer safety valves 

under ambient (hot) conditions. This exception is allowed for [36] hours 

following entry into MODE 3 provided a preliminary cold setting was made 

prior to heatup. 

--------------------------------------------------------------------------------------------------

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One pressurizer safety 

valve inoperable.

A.1 Restore valve to 

OPERABLE status.

15 minutes

B. Required Action and 

associated Completion 

Time not met.

OR

Two pressurizer safety 

valves inoperable.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 4 with any 

RCS cold leg temperature 

 [283]F.

6 hours

[24] hours
Pressurizer Safety Valves 

3.4.10

Babcock & Wilcox STS 3.4.10-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.10.1 Verify each pressurizer safety valve is OPERABLE 

in accordance with the Inservice Testing Program. 

Following testing, lift settings shall be within ± 1%.

In accordance 

with the Inservice 

Testing Program
Pressurizer PORV 

3.4.11

Babcock & Wilcox STS 3.4.11-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.11 Pressurizer Power Operated Relief Valve (PORV) 

LCO 3.4.11 The PORV and associated block valve shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. PORV inoperable. A.1 Close block valve.

AND

A.2 Remove power from block 

valve.

1 hour

1 hour

B. Block valve inoperable. B.1 Close block valve.

AND

B.2 Remove power from block 

valve.

1 hour

1 hour

C. Required Action and 

associated Completion 

Time not met.

C.1 Be in MODE 3.

AND

C.2 Be in MODE 4.

6 hours

12 hours
Pressurizer PORV 

3.4.11

Babcock & Wilcox STS 3.4.11-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.11.1 -------------------------------NOTE------------------------------

Not required to be performed with block valve 

closed in accordance with the Required Actions of 

this LCO.

---------------------------------------------------------------------

Perform one complete cycle of the block valve. [ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.11.2 Perform one complete cycle of the PORV. [ 18 months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.11.3 [ Verify PORV and block valve are capable of being 

powered from an emergency power source.

[ 18 months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
LTOP System 

3.4.12

Babcock & Wilcox STS 3.4.12-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.12 Low Temperature Overpressure Protection (LTOP) System 

LCO 3.4.12 An LTOP System shall be OPERABLE with a maximum of [one] makeup 

pump capable of injecting into the RCS, high pressure injection (HPI) 

deactivated, and the core flood tanks (CFTs) isolated and: 

--------------------------------------------NOTES-------------------------------------------

1. [Two makeup pumps] may be capable of injecting for  1 hour for 

pump swap operations. 

2. CFT may be unisolated when CFT pressure is less than the 

maximum RCS pressure for the existing RCS temperature allowed 

by the pressure and temperature limit curves provided in the PTLR. 

--------------------------------------------------------------------------------------------------

a. Pressurizer level  [220] inches and an OPERABLE power operated 

relief valve (PORV) with a lift setpoint of  [555] psig or 

b. The RCS depressurized and an RCS vent of  [0.75] square inch. 

APPLICABILITY: MODE 4 when any RCS cold leg temperature is  [283]F,

MODE 5,

MODE 6 when the reactor vessel head is on. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. More than [one] makeup 

pump capable of 

injecting into the RCS.

A.1 Initiate action to verify only 

[one] makeup pump is 

capable of injecting into the 

RCS.

Immediately

B. HPI activated. B.1 Initiate action to verify HPI 

deactivated.

Immediately
LTOP System 

3.4.12

Babcock & Wilcox STS 3.4.12-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. A CFT not isolated when 

CFT pressure is greater 

than or equal to the 

maximum RCS pressure 

for existing temperature 

allowed in the PTLR.

C.1 Isolate affected CFT. 1 hour

D. Required Action C.1 not 

met within the required 

Completion Time.

D.1 Increase RCS temperature 

to > 175F.

OR

D.2 Depressurize affected CFT 

to < [555] psig.

12 hours

12 hours

E. Pressurizer level 

> [220] inches.

E.1 Restore pressurizer level to 

 [220] inches.

1 hour

F. Required Action E.1 not 

met within the required 

Completion Time.

F.1 Close and maintain closed 

the makeup control valve 

and its associated isolation 

valve.

AND

F.2 Stop RCS heatup.

12 hours

12 hours

G. PORV inoperable. G.1 Restore PORV to 

OPERABLE status.

1 hour

H. Required Action G.1 not 

met within the required 

Completion Time.

H.1 Reduce makeup tank level 

to  [70] inches.

AND

H.2 Deactivate low low makeup 

tank level interlock to the 

borated water storage tank 

suction valves.

12 hours

12 hours
LTOP System 

3.4.12

Babcock & Wilcox STS 3.4.12-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

I. Pressurizer level 

> [220] inches.

AND

PORV inoperable.

OR

LTOP System 

inoperable for any 

reason other than 

Condition A through 

Condition H.

I.1 Depressurize RCS and 

establish RCS vent of 

 [0.75] square inch.

12 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.12.1 Verify a maximum of [one] makeup pump is capable 

of injecting into the RCS.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.12.2 Verify HPI is deactivated. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
LTOP System 

3.4.12

Babcock & Wilcox STS 3.4.12-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.12.3 Verify each CFT is isolated. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.12.4 Verify pressurizer level is  [220] inches. 30 minutes during 

RCS heatup and 

cooldown

AND

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.12.5 Verify PORV block valve is open. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
LTOP System 

3.4.12

Babcock & Wilcox STS 3.4.12-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.12.6 Verify required RCS vent  [0.75] square inch is 

open.

[ 12 hours for 

unlocked open 

vent valve(s)

AND

31 days for other 

vent path(s)

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.12.7 Perform CHANNEL FUNCTIONAL TEST for PORV. Within [12] hours 

after decreasing 

RCS temperature 

to  [283]F

AND

[ 31 days 

thereafter

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
LTOP System 

3.4.12

Babcock & Wilcox STS 3.4.12-6 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.12.8 Perform CHANNEL CALIBRATION for PORV. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Operational LEAKAGE 

3.4.13

Babcock & Wilcox STS 3.4.13-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.13 RCS Operational LEAKAGE 

LCO 3.4.13 RCS operational LEAKAGE shall be limited to: 

a. No pressure boundary LEAKAGE, 

b. 1 gpm unidentified LEAKAGE, 

c. 10 gpm identified LEAKAGE, and

d. 150 gallons per day primary to secondary LEAKAGE through any 

one steam generator (SG). 

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. RCS operational 

LEAKAGE not within 

limits for reasons other 

than pressure boundary 

LEAKAGE or primary to 

secondary LEAKAGE.

A.1 Reduce LEAKAGE to within 

limits.

4 hours

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

OR

Pressure boundary 

LEAKAGE exists.

OR

Primary to secondary 

LEAKAGE not within 

limit.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 5.

6 hours

36 hours
RCS Operational LEAKAGE 

3.4.13

Babcock & Wilcox STS 3.4.13-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.13.1 ------------------------------NOTES-----------------------------

1. Not required to be performed until 12 hours 

after establishment of steady state operation.

2. Not applicable to primary to secondary 

LEAKAGE.

---------------------------------------------------------------------

Verify RCS operational LEAKAGE is within limits by 

performance of RCS water inventory balance.

[ 72 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.13.2 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours after 

establishment of steady state operation.

---------------------------------------------------------------------

Verify primary to secondary LEAKAGE is 

 150 gallons per day through any one SG.

[ 72 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS PIV Leakage 

3.4.14

Babcock & Wilcox STS 3.4.14-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.14 RCS Pressure Isolation Valve (PIV) Leakage 

LCO 3.4.14 Leakage from each RCS PIV shall be within limits. 

APPLICABILITY: MODES 1, 2, and 3,

MODE 4, except valves in the decay heat removal (DHR) flow path when 

in, or during the transition to or from, the DHR mode of operation. 

ACTIONS 

-----------------------------------------------------------NOTES---------------------------------------------------------- 

1. Separate Condition entry is allowed for each flow path. 

2. Enter applicable Conditions and Required Actions for systems made inoperable by an 

inoperable PIV. 

------------------------------------------------------------------------------------------------------------------------------- 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more flow paths 

with leakage from one or 

more RCS PIVs not 

within limit.

--------------------NOTE-------------------

Each valve used to satisfy Required 

Action A.1 and Required Action A.2 

must have been verified to meet 

SR 3.4.14.1 and be on the RCS 

pressure boundary [or the high 

pressure portion of the system].

------------------------------------------------

A.1 Isolate the high pressure 

portion of the affected 

system from the low 

pressure portion by use of 

one closed manual, 

deactivated automatic, or 

check valve.

AND

4 hours
RCS PIV Leakage 

3.4.14

Babcock & Wilcox STS 3.4.14-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

A.2 [ Isolate the high pressure 

portion of the affected 

system from the low 

pressure portion by use of a 

second closed manual, 

deactivated automatic, or 

check valve.

[or]

Restore RCS PIV to within 

limits.

72 hours

72 hours ]

B. Required Action and

associated Completion 

Time for Condition A not 

met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 5.

6 hours

36 hours

C. [ Decay Heat Removal 

(DHR) System 

autoclosure interlock 

function inoperable.

C.1 Isolate the affected 

penetration by use of one 

closed manual or 

deactivated automatic 

valve.

4 hours ]
RCS PIV Leakage 

3.4.14

Babcock & Wilcox STS 3.4.14-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.14.1 ------------------------------NOTES-----------------------------

1. Not required to be performed in MODES 3 

and 4.

2. Not required to be performed on the RCS PIVs 

located in the DHR flow path when in the DHR 

mode of operation.

3. RCS PIVs actuated during the performance of 

this Surveillance are not required to be tested 

more than once if a repetitive testing loop 

cannot be avoided.

---------------------------------------------------------------------

Verify leakage from each RCS PIV is equivalent to 

 0.5 gpm per nominal inch of valve size up to a 

maximum of 5 gpm at an RCS pressure 

 [2215] psia and  [2255] psia.

[ In accordance 

with the Inservice 

Testing Program 

OR

[ [18] months]

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

AND

Prior to entering 

MODE 2 

whenever the unit 

has been in 

MODE 5 for 

7 days or more, if 

leakage testing 

has not been 

performed in the 

previous 9 months

AND
RCS PIV Leakage 

3.4.14

Babcock & Wilcox STS 3.4.14-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

[ Within 24 hours 

following valve 

actuation due to 

automatic or 

manual action or

flow through the 

valve ]

SR 3.4.14.2 -------------------------------NOTE------------------------------

[ Not required to be met when the DHR System 

autoclosure interlock is disabled in accordance with 

LCO 3.4.12.

---------------------------------------------------------------------

Verify DHR System autoclosure interlock prevents 

the valves from being opened with a simulated or 

actual RCS pressure signal  [425] psig.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.4.14.3 -------------------------------NOTE------------------------------

[ Not required to be met when the DHR System 

autoclosure interlock is disabled in accordance with 

LCO 3.4.12.

---------------------------------------------------------------------

Verify DHR System autoclosure interlock causes the 

valves to close automatically with a simulated or 

actual RCS pressure signal  [600] psig.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
RCS Leakage Detection Instrumentation 

3.4.15

Babcock & Wilcox STS 3.4.15-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.15 RCS Leakage Detection Instrumentation 

LCO 3.4.15 The following RCS leakage detection instrumentation shall be 

OPERABLE: 

a. One containment sump monitor and 

b. One containment atmosphere radioactivity monitor (gaseous or 

particulate). 

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Containment sump 

monitor inoperable.

A.1 --------------NOTE--------------

Not required until 12 hours 

after establishment of 

steady state operation.

-------------------------------------

Perform SR 3.4.13.1.

AND

A.2 Restore containment sump 

monitor to OPERABLE 

status.

Once per 24 hours

30 days

B. Required containment 

atmosphere radioactivity 

monitor inoperable.

B.1.1 Analyze grab samples of 

the containment 

atmosphere.

 OR

Once per 24 hours
RCS Leakage Detection Instrumentation 

3.4.15

Babcock & Wilcox STS 3.4.15-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.1.2 --------------NOTE--------------

Not required until 12 hours 

after establishment of 

steady state operation.

-------------------------------------

Perform SR 3.4.13.1.

AND

B.2 Restore required 

containment atmosphere 

radioactivity monitor to 

OPERABLE status.

Once per 24 hours

30 days

------------- NOTE --------------

Only applicable when the 

containment atmosphere 

gaseous radiation monitor is 

the only OPERABLE 

monitor.

-------------------------------------

C. Containment sump 

monitor inoperable.

C.1 Analyze grab samples of 

the containment 

atmosphere.

AND

C.2 Restore containment sump 

monitor to OPERABLE 

status.

Once per 12 hours

7 days

D. Required Action and 

associated Completion 

Time not met.

D.1 Be in MODE 3.

AND

D.2 ------------- NOTE ------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-----------------------------------

Be in MODE 4.

6 hours

12 hours

E. Both required monitors 

inoperable.

E.1 Enter LCO 3.0.3. Immediately
RCS Leakage Detection Instrumentation 

3.4.15

Babcock & Wilcox STS 3.4.15-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.15.1 Perform CHANNEL CHECK of required containment 

atmosphere radioactivity monitor.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.15.2 Perform CHANNEL FUNCTIONAL TEST of required 

containment atmosphere radioactivity monitor.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Leakage Detection Instrumentation 

3.4.15

Babcock & Wilcox STS 3.4.15-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

SR 3.4.15.3 Perform CHANNEL CALIBRATION of required 

containment sump monitor.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.15.4 Perform CHANNEL CALIBRATION of required 

containment atmosphere radioactivity monitor.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Specific Activity 

3.4.16

Babcock & Wilcox STS 3.4.16-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.16 RCS Specific Activity 

LCO 3.4.16 The specific activity of the reactor coolant shall be within limits. 

APPLICABILITY: MODES 1 and 2,

MODE 3 with RCS average temperature (Tavg)  500F.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. DOSE EQUIVALENT 

I-131 > 1.0 Ci/gm.

--------------------NOTE-------------------

LCO 3.0.4.c is applicable.

------------------------------------------------

A.1 Verify DOSE EQUIVALENT 

I-131 within the acceptable 

region of Figure 3.4.16-1.

AND

A.2 Restore DOSE 

EQUIVALENT I-131 to 

within limit.

Once per 4 hours

48 hours

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

OR

DOSE EQUIVALENT 

I-131 in unacceptable 

region of 

Figure 3.4.16-1.

B.1 Be in MODE 3 with 

Tavg < 500F.

6 hours
RCS Specific Activity 

3.4.16

Babcock & Wilcox STS 3.4.16-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. Gross specific activity of 

the coolant not within 

limit.

C.1 Be in MODE 3 with 

Tavg < 500F.

6 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.16.1 Verify reactor coolant gross specific activity 

 100/Ē Ci/gm.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Specific Activity 

3.4.16

Babcock & Wilcox STS 3.4.16-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.16.2 -------------------------------NOTE------------------------------

Only required to be performed in MODE 1.

---------------------------------------------------------------------

Verify reactor coolant DOSE EQUIVALENT I-131 

specific activity  1.0 Ci/gm.

[ 14 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

AND

Between 2 and 

6 hours after 

THERMAL 

POWER change 

of  15% RTP 

within a 1 hour 

period

SR 3.4.16.3 -------------------------------NOTE------------------------------

Not required to be performed until 31 days after a 

minimum of 2 EFPD and 20 days of MODE 1 

operation have elapsed since the reactor was last 

subcritical for  48 hours.

---------------------------------------------------------------------

Determine Ē. [ 184 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Specific Activity 

3.4.16

Babcock & Wilcox STS 3.4.16-4 Rev. 4.0 
SG Tube Integrity 

3.4.17

Babcock & Wilcox STS 3.4.17-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.17 Steam Generator (SG) Tube Integrity 

LCO 3.4.17 SG tube integrity shall be maintained.

AND

All SG tubes satisfying the tube repair criteria shall be plugged [or 

repaired] in accordance with the Steam Generator Program. 

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each SG tube. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more SG tubes 

satisfying the tube repair 

criteria and not plugged 

[or repaired] in 

accordance with the 

Steam Generator 

Program.

A.1 Verify tube integrity of the 

affected tube(s) is 

maintained until the next 

refueling outage or SG tube 

inspection.

AND

A.2 Plug [or repair] the affected 

tube(s) in accordance with 

the Steam Generator 

Program.

7 days

Prior to entering 

MODE 4 following the 

next refueling outage

or SG tube inspection

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

OR

SG tube integrity not 

maintained.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 5.

6 hours

36 hours
SG Tube Integrity 

3.4.17

Babcock & Wilcox STS 3.4.17-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.17.1 Verify SG tube integrity in accordance with the 

Steam Generator Program.

In accordance 

with the Steam 

Generator 

Program

SR 3.4.17.2 Verify that each inspected SG tube that satisfies the 

tube repair criteria is plugged [or repaired] in 

accordance with the Steam Generator Program.

Prior to entering 

MODE 4 following 

a SG tube 

inspection
CFTs 

3.5.1

Babcock & Wilcox STS 3.5.1-1 Rev. 4.0 

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.1 Core Flood Tanks (CFTs) 

LCO 3.5.1 Two CFTs shall be OPERABLE. 

APPLICABILITY: MODES 1 and 2,

MODE 3 with Reactor Coolant System (RCS) pressure > [750] psig. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One CFT inoperable due 

to boron concentration 

not within limits.

A.1 Restore boron 

concentration to within 

limits.

72 hours

B. One CFT inoperable for 

reasons other than 

Condition A.

B.1 Restore CFT to 

OPERABLE status.

1 hour

C. Required Action and 

associated Completion 

Time of Condition A or B 

not met.

C.1 Be in MODE 3.

AND

C.2 Reduce RCS pressure to 

 [750] psig.

6 hours

[12] hours

D. Two CFTs inoperable. D.1 Enter LCO 3.0.3. Immediately
CFTs 

3.5.1

Babcock & Wilcox STS 3.5.1-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.5.1.1 Verify each CFT isolation valve is fully open. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.5.1.2 Verify borated water volume in each CFT is 

 [7555 gallons, [ ] ft and  8005 gallons, [ ] ft].

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.5.1.3 Verify nitrogen cover pressure in each CFT is 

 [575] psig and  [625] psig.

[ 12 hours

OR

In accordance

with the

Surveillance 

Frequency

Control Program ]
CFTs 

3.5.1

Babcock & Wilcox STS 3.5.1-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.5.1.4 Verify boron concentration in each CFT is 

 [2270] ppm and  [3500] ppm.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

AND

--------NOTE--------

Only required to 

be performed for 

affected CFT

Once within 

6 hours after each 

solution volume 

increase of 

 [80 gallons] that 

is not the result of 

addition from the 

borated water 

storage tank

SR 3.5.1.5 Verify power is removed from each CFT isolation 

valve operator when RCS pressure is  [2000] psig.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

ECCS - Operating 

3.5.2

Babcock & Wilcox STS 3.5.2-1 Rev. 4.0 

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.2 ECCS - Operating 

LCO 3.5.2 Two ECCS trains shall be OPERABLE. 

---------------------------------------------NOTE-------------------------------------------- 

 [ Operation in MODE 3 with high pressure injection (HPI) de-activated in 

accordance with LCO 3.4.12, "Low Temperature Overpressure Protection 

(LTOP) System," is allowed for up to [4] hours. ]

--------------------------------------------------------------------------------------------------

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One low pressure 

injection (LPI) 

subsystem inoperable.

A.1 Restore LPI subsystem to 

OPERABLE status.

[7] days

B. One or more trains 

inoperable for reasons 

other than Condition A.

B.1 Restore train(s) to 

OPERABLE status.

72 hours

C. Required Action and 

associated Completion 

Time not met.

C.1 Be in MODE 3.

AND

C.2 Be in MODE 4.

6 hours

12 hours

D. Less than 100% of the 

ECCS flow equivalent to 

a single OPERABLE 

train available.

D.1 Enter LCO 3.0.3. Immediately
ECCS - Operating 

3.5.2

Babcock & Wilcox STS 3.5.2-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.5.2.1 [ Verify the following valves are in the listed position 

with power to the valve operator removed.

Valve Number Position Function

 [ ] [ ] [ ]

 [ ] [ ] [ ]

 [ ] [ ] [ ]

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.5.2.2 Verify each ECCS manual, power operated, and 

automatic valve in the flow path, that is not locked, 

sealed, or otherwise secured in position, is in the 

correct position.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.5.2.3 [ Verify ECCS piping is full of water. [ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.5.2.4 Verify each ECCS pump's developed head at the 

test flow point is greater than or equal to the 

required developed head.

In accordance 

with the Inservice 

Testing Program
ECCS - Operating 

3.5.2

Babcock & Wilcox STS 3.5.2-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.5.2.5 Verify each ECCS automatic valve in the flow path 

that is not locked, sealed, or otherwise secured in 

position, actuates to the correct position on an 

actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.5.2.6 Verify each ECCS pump starts automatically on an 

actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.5.2.7 [ Verify the correct settings of stops for the following 

HPI stop check valves:

a. [MUV-2],

b. [MUV-6], and

c. [MUV-10].

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
ECCS - Operating 

3.5.2

Babcock & Wilcox STS 3.5.2-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.5.2.8 [ Verify the flow controllers for the following LPI 

throttle valves operate properly:

a. [DHV-110] and

b. [DHV-111].

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.5.2.9 Verify, by visual inspection, each ECCS train 

containment sump suction inlet is not restricted by 

debris and suction inlet trash racks and screens 

show no evidence of structural distress or abnormal 

corrosion.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
ECCS - Shutdown 

3.5.3

Babcock & Wilcox STS 3.5.3-1 Rev. 4.0 

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.3 ECCS - Shutdown 

LCO 3.5.3 One ECCS train shall be OPERABLE. 

--------------------------------------------NOTES-------------------------------------------

1. A DHR train may be considered OPERABLE during alignment and 

operation for DHR, if capable of being manually realigned to the 

ECCS mode of operation. 

2. High pressure injection (HPI) may be de-activated in accordance 

with LCO 3.4.12, "Low Temperature Overpressure Protection 

(LTOP) System." 

--------------------------------------------------------------------------------------------------

APPLICABILITY: MODE 4.

ACTIONS 

-----------------------------------------------------------NOTE-----------------------------------------------------------

LCO 3.0.4.b is not applicable to ECCS DHR loops. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. Required ECCS decay 

heat removal (DHR) loop 

inoperable.

A.1 Initiate action to restore 

required ECCS DHR loop 

to OPERABLE status.

Immediately

B. Required ECCS HPI 

subsystem inoperable.

B.1 Restore required ECCS 

HPI subsystem to 

OPERABLE status.

1 hour

C. Required Action and 

associated Completion 

Time of Condition B not 

met.

C.1 Be in MODE 5. 24 hours
ECCS - Shutdown 

3.5.3

Babcock & Wilcox STS 3.5.3-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.5.3.1 For all equipment required to be OPERABLE, the 

following SRs are applicable:

[SR 3.5.2.1] SR 3.5.2.6

SR 3.5.2.2 [SR 3.5.2.7]

[SR 3.5.2.3] [SR 3.5.2.8]

SR 3.5.2.4 SR 3.5.2.9

SR 3.5.2.5

In accordance 

with applicable 

SRs
BWST 

3.5.4

Babcock & Wilcox STS 3.5.4-1 Rev. 4.0 

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.4 Borated Water Storage Tank (BWST) 

LCO 3.5.4 The BWST shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. BWST boron 

concentration not within 

limits.

A.1 Restore BWST to 

OPERABLE status.

8 hours

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 3.

AND

B.2 --------------NOTE--------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

6 hours

12 hours

C. BWST water 

temperature not within

limits.

C.1 Restore BWST to 

OPERABLE status.

8 hours

D. BWST inoperable for 

reasons other than 

Condition A or C.

D.1 Restore BWST to 

OPERABLE status.

1 hour

E. Required Action and 

associated Completion 

Time of Condition C or D 

not met.

E.1 Be in MODE 3.

AND

E.2 Be in MODE 5.

6 hours

36 hours
BWST 

3.5.4

Babcock & Wilcox STS 3.5.4-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.5.4.1 -------------------------------NOTE------------------------------

Only required to be performed when ambient air 

temperature is < [40]F or > [100]F.

---------------------------------------------------------------------

Verify BWST borated water temperature is  [40]F 

and  [100]F.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.5.4.2 Verify BWST borated water volume is 

 [415,200 gallons] [ ] ft. and  [449,000 gallons] 

[ ] ft.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.5.4.3 Verify BWST boron concentration is  [2270] ppm 

and  [2450] ppm.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment 

3.6.1

Babcock & Wilcox STS 3.6.1-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.1 Containment 

LCO 3.6.1 Containment shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Containment inoperable. A.1 Restore containment to 

OPERABLE status.

1 hour

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 5.

6 hours

36 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.1.1 Perform required visual examinations and leakage 

rate testing except for containment air lock testing, 

in accordance with the Containment Leakage Rate 

Testing Program.

In accordance 

with the 

Containment 

Leakage Rate 

Testing Program

SR 3.6.1.2 [ Verify containment structural integrity in 

accordance with the Containment Tendon 

Surveillance Program.

In accordance 

with the 

Containment 

Tendon 

Surveillance 

Program ]

Containment Air Locks 

3.6.2

Babcock & Wilcox STS 3.6.2-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.2 Containment Air Locks

LCO 3.6.2 [Two] containment air lock[s] shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

-----------------------------------------------------------NOTES----------------------------------------------------------

1. Entry and exit is permissible to perform repairs on the affected air lock components. 

2. Separate Condition entry is allowed for each air lock. 

3. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when air 

lock leakage results in exceeding the overall containment leakage rate acceptance criteria. 

------------------------------------------------------------------------------------------------------------------------------- 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more 

containment air locks 

with one containment air 

lock door inoperable.

-------------------NOTES------------------

1. Required Actions A.1, A.2, 

and A.3 are not applicable if both 

doors in the same air lock are 

inoperable and Condition C is 

entered.

2. Entry and exit is permissible for 

7 days under administrative 

controls [if both air locks are 

inoperable].

------------------------------------------------

A.1 Verify the OPERABLE door 

is closed in the affected air 

lock.

AND

1 hour
Containment Air Locks 

3.6.2

Babcock & Wilcox STS 3.6.2-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

A.2 Lock the OPERABLE door 

closed in the affected air 

lock.

AND

A.3 --------------NOTE--------------

Air lock doors in high 

radiation areas may be 

verified locked closed by 

administrative means.

-------------------------------------

Verify the OPERABLE door 

is locked closed in the 

affected air lock.

24 hours

Once per 31 days

B. One or more 

containment air locks 

with containment air lock 

interlock mechanism 

inoperable.

-------------------NOTES------------------

1. Required Actions B.1, B.2, 

and B.3 are not applicable if both 

doors in the same air lock are 

inoperable and Condition C is 

entered.

2. Entry and exit of containment is 

permissible under the control of a 

dedicated individual.

------------------------------------------------

B.1 Verify an OPERABLE door 

is closed in the affected air 

lock.

AND

1 hour
Containment Air Locks 

3.6.2

Babcock & Wilcox STS 3.6.2-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.2 Lock an OPERABLE door 

closed in the affected air 

lock.

AND

B.3 --------------NOTE--------------

Air lock doors in high 

radiation areas may be 

verified locked closed by 

administrative means.

-------------------------------------

Verify an OPERABLE door 

is locked closed in the 

affected air lock.

24 hours

Once per 31 days

C. One or more 

containment air locks 

inoperable for reasons 

other than Condition A 

or B.

C.1 Initiate action to evaluate 

overall containment 

leakage rate per LCO 3.6.1.

AND

C.2 Verify a door is closed in 

the affected air lock.

AND

C.3 Restore air lock to 

OPERABLE status.

Immediately

1 hour

24 hours

D. Required Action and 

associated Completion 

Time not met.

D.1 Be in MODE 3.

AND

D.2 --------------NOTE--------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

6 hours

12 hours
Containment Air Locks 

3.6.2

Babcock & Wilcox STS 3.6.2-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.2.1 ------------------------------NOTES-----------------------------

1. An inoperable air lock door does not invalidate 

the previous successful performance of the 

overall air lock leakage test.

2. Results shall be evaluated against acceptance 

criteria applicable to SR 3.6.1.1.

---------------------------------------------------------------------

Perform required air lock leakage rate testing in 

accordance with the Containment Leakage Rate 

Testing Program.

In accordance 

with the 

Containment 

Leakage Rate 

Testing Program

SR 3.6.2.2 Verify only one door in the air lock can be opened at 

a time.

[ 24 months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Isolation Valves 

3.6.3

Babcock & Wilcox STS 3.6.3-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.3 Containment Isolation Valves 

LCO 3.6.3 Each containment isolation valve shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

-----------------------------------------------------------NOTES----------------------------------------------------------

1. Penetration flow paths [except for 48 inch purge valve penetration flow paths] may be 

unisolated intermittently under administrative controls. 

2. Separate Condition entry is allowed for each penetration flow path. 

3. Enter applicable Conditions and Required Actions for system(s) made inoperable by 

containment isolation valves. 

4. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when 

isolation valve leakage results in exceeding the overall containment leakage rate 

acceptance criteria. 

------------------------------------------------------------------------------------------------------------------------------- 
Containment Isolation Valves 

3.6.3

Babcock & Wilcox STS 3.6.3-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

-----REVIEWER'S NOTE-----

The Condition A Note 

should list the specific 

penetrations (if any) 

identified by the plantspecific risk analysis as 

having high risk significance 

for an interfacing systems 

loss of coolant accident 

(ISLOCA).

--------------------------------------

A. ------------NOTE------------

Only applicable to 

penetration flow paths 

with two [or more] 

containment isolation 

valves except 

containment isolation 

valves in the main steam 

lines and [ ].

---------------------------------

One or more penetration 

flow paths with one 

containment isolation

valve inoperable [for 

reasons other than 

purge valve leakage not 

within limit].

A.1 Determine the OPERABLE 

containment isolation valve 

in the affected penetration 

is not inoperable due to 

common cause failure.

AND

A.2 Isolate the affected 

penetration flow path by 

use of at least one closed 

and de-activated automatic 

valve, closed manual valve, 

blind flange, or check valve 

with flow through the valve 

secured.

AND

A.3 -------------NOTES--------------

1. Isolation devices in high 

radiation areas may be 

verified by use of 

administrative means.

2. Isolation devices that 

are locked, sealed, or 

otherwise secured may 

be verified by use of 

administrative means.

-------------------------------------

Verify the affected 

penetration flow path is 

isolated.

4 hours

7 days

Once per 31 days for 

isolation devices 

outside containment

AND

Prior to entering 

MODE 4 from 

MODE 5 if not 

performed within the 

previous 92 days for 

isolation devices 

inside containment
Containment Isolation Valves 

3.6.3

Babcock & Wilcox STS 3.6.3-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

-----REVIEWER'S NOTE-----

The Condition B Note 

should list the specific 

penetrations (if any) 

identified by the plantspecific risk analysis as 

having high risk significance 

for an interfacing systems 

loss of coolant accident 

(ISLOCA).

--------------------------------------

B. ------------NOTE------------

Only applicable to 

penetration flow paths 

with two [or more] 

containment isolation 

valves in the main steam 

lines and [ ].

---------------------------------

One or more penetration 

flow paths with one 

containment isolation 

valve inoperable [for 

reasons other than 

purge valve leakage not 

within limit].

B.1 Isolate the affected 

penetration flow path by 

use of at least one closed 

and de-activated automatic 

valve, closed manual valve, 

blind flange, or check valve 

with flow through the valve 

secured.

AND

B.2 -------------NOTES--------------

1. Isolation devises in high 

radiation areas may be 

verified by use of 

administrative means.

2. Isolation devices that 

are locked, sealed, or 

otherwise secured may 

be verified by use of 

administrative means.

-------------------------------------

Verify the affected

penetration flow path is 

isolated.

4 hours

Once per 31 days for 

isolation devices 

outside containment

AND

Prior to entering 

MODE 4 from 

MODE 5 if not 

performed within the

previous 92 days for 

isolation devices 

inside containment
Containment Isolation Valves 

3.6.3

Babcock & Wilcox STS 3.6.3-4 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. ------------NOTE------------

Only applicable to 

penetration flow paths 

with two [or more] 

containment isolation 

valves.

---------------------------------

Two or more penetration 

flow paths with one 

containment isolation 

valve inoperable [for 

reasons other than 

Condition[s] E [and F] ].

C.1 Isolate all but one of the 

affected penetration flow 

paths by use of at least one 

closed and de-activated 

automatic valve, closed 

manual valve, or blind 

flange.

4 hours

D. ------------NOTE------------

Only applicable to 

penetration flow paths 

with two [or more] 

containment isolation 

valves.

---------------------------------

One or more penetration 

flow paths with two [or 

more] containment 

isolation valves 

inoperable [for reasons 

other than purge valve 

leakage not within limit].

D.1 Isolate the affected 

penetration flow path by 

use of at least one closed 

and de-activated automatic 

valve, closed manual valve, 

or blind flange.

1 hour
Containment Isolation Valves 

3.6.3

Babcock & Wilcox STS 3.6.3-5 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

E. ------------NOTE------------

Only applicable to 

penetration flow paths 

with only one 

containment isolation 

valve and a closed 

system.

---------------------------------

One or more penetration 

flow paths with one 

containment isolation 

valve inoperable.

E.1 Isolate the affected 

penetration flow path by 

use of at least one closed 

and de-activated automatic 

valve, closed manual valve, 

or blind flange.

AND

E.2 -------------NOTES--------------

1. Isolation devices in high 

radiation areas may be 

verified by use of 

administrative means.

2. Isolation devices that 

are locked, sealed, or 

otherwise secured may 

be verified by use of 

administrative means.

-------------------------------------

Verify the affected 

penetration flow path is 

isolated.

72 hours

Once per 31 days

F. [ One or more 

penetration flow paths 

with one or more 

containment purge 

valves not within purge 

valve leakage limits.

F.1 Isolate the affected 

penetration flow path by 

use of at least one [closed 

and de-activated automatic 

valve, closed manual valve, 

or blind flange].

AND

24 hours
Containment Isolation Valves 

3.6.3

Babcock & Wilcox STS 3.6.3-6 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

F.2 -------------NOTES--------------

1. Isolation devices in high 

radiation areas may be 

verified by use of 

administrative means.

2. Isolation devices that 

are locked, sealed, or 

otherwise secured may 

be verified by use of 

administrative means.

-------------------------------------

Verify the affected 

penetration flow path is 

isolated.

AND

F.3 Perform SR 3.6.3.6 for the 

resilient seal purge valves 

closed to comply with 

Required Action E.1.

Once per 31 days for 

isolation devices 

outside containment

AND

Prior to entering 

MODE 4 from 

MODE 5 if not 

performed within the 

previous 92 days for 

isolation devices 

inside containment

Once per [ ] days ]
Containment Isolation Valves 

3.6.3

Babcock & Wilcox STS 3.6.3-7 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

G. Required Action and 

associated Completion 

Time not met.

G.1 Be in MODE 3.

AND

G.2 --------------NOTE---------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

6 hours

12 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.3.1 [ Verify each [48] inch purge valve is sealed closed 

except for one purge valve in a penetration flow 

path while in Condition D of the LCO.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.6.3.2 Verify each [8] inch purge valve is closed except 

when the [8] inch purge valves are open for 

pressure control, ALARA or air quality 

considerations for personnel entry, or for 

Surveillances that require the valves to be open.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Isolation Valves 

3.6.3

Babcock & Wilcox STS 3.6.3-8 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.3.3 -------------------------------NOTE------------------------------

Valves and blind flanges in high radiation areas may 

be verified by use of administrative means.

---------------------------------------------------------------------

Verify each containment isolation manual valve and 

blind flange that is located outside containment and 

not locked, sealed, or otherwise secured and is 

required to be closed during accident conditions is 

closed, except for containment isolation valves that 

are open under administrative controls.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.3.4 -------------------------------NOTE------------------------------

Valves and blind flanges in high radiation areas may 

be verified by use of administrative means.

---------------------------------------------------------------------

Verify each containment isolation manual valve and 

blind flange that is located inside containment and 

not locked, sealed, or otherwise secured and 

required to be closed during accident conditions is 

closed, except for containment isolation valves that 

are open under administrative controls.

Prior to entering 

MODE 4 from 

MODE 5 if not 

performed within 

the previous 

92 days

SR 3.6.3.5 Verify the isolation time of each automatic power 

operated containment isolation valve is within limits.

[In accordance 

with the Inservice 

Testing Program

OR

[92 days]

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Isolation Valves 

3.6.3

Babcock & Wilcox STS 3.6.3-9 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.3.6 Perform leakage rate testing for containment purge 

valves with resilient seals.

[ 184 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

AND

Within 92 days 

after opening the 

valve

SR 3.6.3.7 Verify each automatic containment isolation valve 

that is not locked, sealed, or otherwise secured in 

position, actuates to the isolation position on an 

actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.3.8 [ Verify each [ ] inch containment purge valve is 

blocked to restrict the valve from opening > [50]%.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

Containment Pressure 

3.6.4

Babcock & Wilcox STS 3.6.4-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.4 Containment Pressure 

LCO 3.6.4 Containment pressure shall be  [-2.0] psig and  [+3.0] psig. 

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Containment pressure 

not within limits.

A.1 Restore containment 

pressure to within limits.

1 hour

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3.

AND

B.2 --------------NOTE---------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

6 hours

12 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.4.1 Verify containment pressure is within limits. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Containment Air Temperature 

3.6.5

Babcock & Wilcox STS 3.6.5-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.5 Containment Air Temperature 

LCO 3.6.5 Containment average air temperature shall be  [130]F.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Containment average air 

temperature not within 

limit.

A.1 Restore containment 

average air temperature to 

within limit.

8 hours

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3.

AND

B.2 --------------NOTE---------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

6 hours

12 hours
Containment Air Temperature 

3.6.5

Babcock & Wilcox STS 3.6.5-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.5.1 Verify containment average air temperature is within 

limit.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Spray and Cooling Systems 

3.6.6

Babcock & Wilcox STS 3.6.6-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.6 Containment Spray and Cooling Systems 

LCO 3.6.6 Two containment spray trains and two containment cooling trains shall be 

OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One containment spray 

train inoperable.

A.1 Restore containment spray 

train to OPERABLE status.

[7] days

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 3.

AND

B.2 --------------NOTE---------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

6 hours

60 hours

C. One [required] 

containment cooling 

train inoperable.

C.1 Restore [required] 

containment cooling train to 

OPERABLE status.

7 days

D. One containment spray 

train and one [required] 

containment cooling 

train inoperable.

D.1 Restore containment spray 

train to OPERABLE status.

OR

D.2 Restore [required] 

containment cooling train to 

OPERABLE status.

72 hours
Containment Spray and Cooling Systems 

3.6.6

Babcock & Wilcox STS 3.6.6-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

E. Two [required] 

containment cooling 

trains inoperable.

E.1 Restore one [required] 

containment cooling train to 

OPERABLE status.

72 hours

F. Required Action and 

associated Completion 

Time of Condition C or D 

not met.

F.1 Be in MODE 3.

AND

F.2 --------------NOTE---------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

6 hours

12 hours

G. Two containment spray 

trains inoperable.

OR

Any combination of three 

or more trains 

inoperable.

G.1 Enter LCO 3.0.3. Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.6.1 Verify each containment spray manual, power 

operated, and automatic valve in the flow path that 

is not locked, sealed, or otherwise secured in 

position is in the correct position.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Spray and Cooling Systems 

3.6.6

Babcock & Wilcox STS 3.6.6-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.6.2 Operate each [required] containment cooling train 

fan unit for  15 minutes.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.6.3 Verify each [required] containment cooling train 

cooling water flow rate is  [1780] gpm.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.6.4 Verify each containment spray pump's developed 

head at the flow test point is greater than or equal to 

the required developed head.

In accordance 

with the Inservice 

Testing Program

SR 3.6.6.5 Verify each automatic containment spray valve in 

the flow path that is not locked, sealed, or otherwise 

secured in position, actuates to the correct position 

on an actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Spray and Cooling Systems 

3.6.6

Babcock & Wilcox STS 3.6.6-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.6.6 Verify each containment spray pump starts 

automatically on an actual or simulated actuation 

signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.6.7 Verify each [required] containment cooling train 

starts automatically on an actual or simulated 

actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.6.8 Verify each spray nozzle is unobstructed. [ At first refueling ]

AND

[ 10 years

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Spray Additive System 

3.6.7

Babcock & Wilcox STS 3.6.7-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.7 Spray Additive System 

LCO 3.6.7 The Spray Additive System shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Spray Additive System 

inoperable.

A.1 Restore Spray Additive 

System to OPERABLE 

status.

72 hours

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 5.

6 hours

84 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.7.1 Verify each spray additive manual, power operated, 

and automatic valve in the flow path that is not 

locked, sealed, or otherwise secured in position is in 

the correct position.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Spray Additive System 

3.6.7

Babcock & Wilcox STS 3.6.7-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.7.2 Verify spray additive tank solution volume is 

 [12,970] gal and  [13,920] gal.

[ 184 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.7.3 Verify spray additive tank [NaOH] solution 

concentration is  [60,000 ppm] and  [65,000 ppm].

[ 184 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.7.4 Verify each spray additive automatic valve in the 

flow path actuates to the correct position on an 

actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.7.5 Verify Spray Additive System flow [rate] from each 

solution's flow path.

[ 5 years

OR

In accordance 

with the

Surveillance

Frequency

Control Program ]
MSSVs 

3.7.1

Babcock & Wilcox STS 3.7.1-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.1 Main Steam Safety Valves (MSSVs) 

LCO 3.7.1 The MSSVs shall be OPERABLE as specified in Table 3.7.1-1 and 

Figure 3.7.1-1.

APPLICABILITY: MODES 1, 2, and 3. 

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each MSSV. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more required 

MSSVs inoperable.

A.1 Reduce power to less than 

the reduced power 

requirement of 

Figure 3.7.1-1.

AND

A.2 Reduce the nuclear 

overpower trip setpoint in 

accordance with 

Figure 3.7.1-1.

4 hours

36 hours

B. Required Action and 

associated Completion 

Time not met.

OR

One or more steam 

generators with less 

than [two] MSSVs 

OPERABLE.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 4.

6 hours

12 hours
MSSVs 

3.7.1

Babcock & Wilcox STS 3.7.1-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.1.1 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

---------------------------------------------------------------------

Verify each required MSSV lift setpoint per 

Table 3.7.1-1 in accordance with the Inservice 

Testing Program. Following testing, lift settings 

shall be within ± 1%.

In accordance 

with the Inservice 

Testing Program
MSSVs 

3.7.1

Babcock & Wilcox STS 3.7.1-3 Rev. 4.0 

Table 3.7.1-1 (page 1 of 1) 

Main Steam Safety Valve Lift Settings 

VALVE NUMBER

LIFT SETTING

(psig ± [3]%)

[2] MSSVs/steam generator [1050]

[7] MSSVs/steam generator [ 1100]
MSSVs 

3.7.1

Babcock & Wilcox STS 3.7.1-4 Rev. 4.0 
MSIVs 

3.7.2

Babcock & Wilcox STS 3.7.2-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.2 Main Steam Isolation Valves (MSIVs) 

LCO 3.7.2 Two MSIVs shall be OPERABLE. 

APPLICABILITY: MODE 1, 

MODES 2 and 3 except when all MSIVs are closed [and deactivated]. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One MSIV inoperable in 

MODE 1.

A.1 Restore MSIV to 

OPERABLE status.

[8] hours

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 2. 6 hours

C. ------------NOTE------------

Separate Condition entry 

is allowed for each 

MSIV.

---------------------------------

One or more MSIVs 

inoperable in MODE 2 

or 3.

C.1 Close MSIV.

AND

C.2 Verify MSIV is closed.

[8] hours

Once per 7 days

D. Required Action and 

associated Completion 

Time of Condition C not 

met.

D.1 Be in MODE 3.

AND

D.2 Be in MODE 4.

6 hours

12 hours
MSIVs 

3.7.2

Babcock & Wilcox STS 3.7.2-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.2.1 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

---------------------------------------------------------------------

Verify isolation time of each MSIV is within limits. In accordance 

with the Inservice 

Testing Program

SR 3.7.2.2 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

---------------------------------------------------------------------

Verify each MSIV actuates to the isolation position 

on an actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
 [MFSVs, MFCVs, and Associated SFCVs] 

3.7.3

Babcock & Wilcox STS 3.7.3-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.3 [Main Feedwater Stop Valves (MFSVs), Main Feedwater Control Valves (MFCVs), 

and Associated Startup Feedwater Control Valves (SFCVs)] 

LCO 3.7.3 [Two] [MFSVs], [MFCVs], [or associated SFCVs] shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3 except when all [MFSVs], [MFCVs], [or associated 

SFCVs] are closed [and deactivated] [or isolated by a closed manual 

valve]. 

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each valve. 

------------------------------------------------------------------------------------------------------------------------------- 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One [MFSV] in one or 

more flow paths 

inoperable.

A.1 Close or isolate [MFSV].

AND

A.2 Verify [MFSV] is closed or 

isolated.

[8 or 72] hours

Once per 7 days

B. One [MFCV] in one or 

more flow paths 

inoperable.

B.1 Close or isolate [MFCV].

AND

B.2 Verify [MFCV] is closed or 

isolated.

[8 or 72] hours

Once per 7 days

C. One [SFCV] in one or 

more flow paths 

inoperable.

C.1 Close or isolate [SFCV].

AND

C.2 Verify [SFCV] is closed or 

isolated.

[8 or 72] hours

Once per 7 days
 [MFSVs, MFCVs, and Associated SFCVs] 

3.7.3

Babcock & Wilcox STS 3.7.3-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

D. Two valves in the same 

flow path inoperable for 

one or more flow paths.

D.1 Isolate affected flow path. 8 hours

E. Required Action and 

associated Completion 

Time not met.

E.1 Be in MODE 3.

[ AND

E.2 Be in MODE 4.

6 hours

12 hours ]

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.3.1 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

---------------------------------------------------------------------

Verify the isolation time of each [MFSV], [MFCV], 

and [SFCV] is within limits.

In accordance 

with the Inservice 

Testing Program

SR 3.7.3.2 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

---------------------------------------------------------------------

Verify each [MFSV], [MFCV], and [SFCV] actuates 

to the isolation position on an actual or simulated 

actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AVVs

3.7.4

Babcock & Wilcox STS 3.7.4-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.4 Atmospheric Vent Valves (AVVs) 

LCO 3.7.4 [Two] AVVs [lines per steam generator] shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3, 

MODE 4 when steam generator is relied upon for heat removal. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One required AVV [line] 

inoperable.

A.1 Restore required AVV [line] 

to OPERABLE status.

[7 days]

B. [ Two or more required 

AVV [lines] inoperable.

B.1 Restore all but one AVV 

[line] to OPERABLE status.

24 hours ]

C. Required Action and 

associated Completion 

Time not met.

C.1 Be in MODE 3.

AND

C.2 Be in MODE 4 without 

reliance upon steam 

generator for heat removal.

6 hours

[24] hours
AVVs

3.7.4

Babcock & Wilcox STS 3.7.4-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.4.1 Verify one complete cycle of each AVV. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.7.4.2 [ Verify one complete cycle of each AVV block 

valve.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
EFW System 

3.7.5

Babcock & Wilcox STS 3.7.5-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.5 Emergency Feedwater (EFW) System 

LCO 3.7.5 [Three] EFW trains shall be OPERABLE. 

---------------------------------------------NOTE--------------------------------------------

 Only one EFW train, which includes a motor driven pump, is required to 

be OPERABLE in MODE 4.

--------------------------------------------------------------------------------------------------

APPLICABILITY: MODES 1, 2, and 3,

MODE 4 when steam generator is relied upon for heat removal. 

ACTIONS 

-----------------------------------------------------------NOTE-----------------------------------------------------------

LCO 3.0.4.b is not applicable when entering MODE 1.

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. [ Turbine driven EFW 

train inoperable due to 

one inoperable steam 

supply.

OR

------------NOTE------------

Only applicable if 

MODE 2 has not been 

entered following 

refueling.

---------------------------------

One turbine driven EFW 

pump inoperable in 

MODE 3 following 

refueling.

A.1 Restore affected equipment 

to OPERABLE status.

7 days ]
EFW System 

3.7.5

Babcock & Wilcox STS 3.7.5-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B. One EFW train 

inoperable in MODE 1, 

2, or 3 [for reasons other 

than Condition A].

B.1 Restore EFW train to 

OPERABLE status.

72 hours

C. One turbine driven EFW 

train inoperable due to 

one inoperable steam 

supply.

AND

Motor driven EFW train 

inoperable.

C.1 Restore the steam supply 

to the turbine driven train to 

OPERABLE status.

OR

C.2 Restore the motor driven 

EFW train to OPERABLE 

status.

[24 or 48] hours

[24 or 48] hours

D. Required Action and 

associated Completion 

Time of Condition A [B, 

or C] not met.

[ OR

Two EFW trains 

inoperable in MODE 1, 

2, or 3 for reasons other 

than Condition C. ]

D.1 Be in MODE 3.

AND

D.2 Be in MODE 4.

6 hours

[18] hours

E. [Three] EFW trains 

inoperable in MODE 1, 

2, or 3.

E.1 --------------NOTE---------------

LCO 3.0.3 and all other 

LCO Required Actions 

requiring MODE changes 

are suspended until one 

EFW train is restored to 

OPERABLE status.

-------------------------------------

Initiate action to restore 

one EFW train to 

OPERABLE status.

Immediately
EFW System 

3.7.5

Babcock & Wilcox STS 3.7.5-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

F. Required EFW train 

inoperable in MODE 4.

F.1 Initiate action to restore 

EFW train to OPERABLE 

status.

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.5.1 Verify each EFW manual, power operated, and 

automatic valve in each water flow path and in both 

steam supply flow paths to the steam turbine driven 

pumps, that is not locked, sealed, or otherwise 

secured in position, is in the correct position.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.7.5.2 -------------------------------NOTE------------------------------

Not required to be performed for the turbine driven 

EFW pumps, until [24] hours after reaching 

[800] psig in the steam generators.

---------------------------------------------------------------------

Verify the developed head of each EFW pump at the 

flow test point is greater than or equal to the 

required developed head.

In accordance 

with the Inservice 

Testing Program
EFW System 

3.7.5

Babcock & Wilcox STS 3.7.5-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

SR 3.7.5.3 ------------------------------NOTES-----------------------------

1. Not required to be performed until [24] hours 

after reaching [800] psig in the steam 

generators.

2. Not required to be met in MODE 4.

---------------------------------------------------------------------

Verify each EFW automatic valve that is not locked, 

sealed, or otherwise secured in position, actuates to 

the correct position on an actual or simulated 

actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.7.5.4 ------------------------------NOTES-----------------------------

1. Not required to be performed until [24] hours 

after reaching [800] psig in the steam 

generators.

2. Not required to be met in MODE 4.

---------------------------------------------------------------------

Verify each EFW pump starts automatically on an 

actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
EFW System 

3.7.5

Babcock & Wilcox STS 3.7.5-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.7.5.5 Verify proper alignment of the required EFW flow 

paths by verifying [valve alignment/flow] from the 

condensate storage tank to each steam generator.

Prior to entering 

MODE 2 

whenever plant 

has been in 

MODE 5, 

MODE 6, or 

defueled for a 

cumulative period 

of > 30 days

SR 3.7.5.6 [ Perform a CHANNEL FUNCTIONAL TEST for the 

EFW pump suction pressure interlocks.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.7.5.7 [ Perform a CHANNEL CALIBRATION for the EFW 

pump suction pressure interlocks.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

CST

3.7.6

Babcock & Wilcox STS 3.7.6-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.6 Condensate Storage Tank (CST) 

LCO 3.7.6 The [two] CST(s) shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3,

MODE 4 when steam generator is relied upon for heat removal. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. The [two] CST(s) 

inoperable.

A.1 Verify by administrative 

means OPERABILITY of 

backup water supply.

AND

A.2 Restore CST(s) to 

OPERABLE status.

4 hours

AND

Once per 12 hours 

thereafter

7 days

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 4 without 

reliance on steam 

generator for heat removal.

6 hours

[24] hours
CST

3.7.6

Babcock & Wilcox STS 3.7.6-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.6.1 Verify CST level is  [250,000] gal. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
CCW System 

3.7.7

Babcock & Wilcox STS 3.7.7-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.7 Component Cooling Water (CCW) System 

LCO 3.7.7 Two CCW trains shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One CCW train 

inoperable.

A.1 -------------NOTES--------------

1. Enter applicable 

Conditions and 

Required Actions of 

LCO 3.8.1, 

"AC Sources - 

Operating," for 

emergency diesel 

generator made 

inoperable by CCW.

2. Enter applicable 

Conditions and 

Required Actions of 

LCO 3.4.6, "RCS Loops 

- MODE 4," for decay 

heat removal made 

inoperable by CCW.

-------------------------------------

Restore CCW train to 

OPERABLE status.

72 hours
CCW System 

3.7.7

Babcock & Wilcox STS 3.7.7-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 3.

AND

B.2 --------------NOTE---------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

6 hours

12 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.7.1 -------------------------------NOTE------------------------------

Isolation of CCW flow to individual components 

does not render CCW System inoperable.

---------------------------------------------------------------------

Verify each CCW manual, power operated, and 

automatic valve in the flow path servicing safety 

related equipment, that is not locked, sealed, or 

otherwise secured in position, is in the correct 

position.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.7.7.2 Verify each CCW automatic valve in the flow path 

that is not locked, sealed, or otherwise secured in 

position, actuates to the correct position on an 

actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
CCW System 

3.7.7

Babcock & Wilcox STS 3.7.7-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.7.7.3 Verify each CCW pump starts automatically on an 

actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SWS 

3.7.8

Babcock & Wilcox STS 3.7.8-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.8 Service Water System (SWS) 

LCO 3.7.8 Two SWS trains shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One SWS train 

inoperable.

A.1 -------------NOTES--------------

1. [ Enter applicable 

Conditions and 

Required Actions of 

LCO 3.8.1, "AC 

Sources - Operating," 

for emergency diesel 

generator made 

inoperable by SWS. ]

2. [ Enter Applicable 

Conditions and 

Required Actions of 

LCO 3.4.6, "RCS Loops 

- MODE 4," for decay 

heat removal made 

inoperable by SWS. ]

-------------------------------------

Restore SWS train to 

OPERABLE status.

72 hours
SWS 

3.7.8

Babcock & Wilcox STS 3.7.8-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 3.

AND

B.2 --------------NOTE---------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

6 hours

12 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.8.1 -------------------------------NOTE------------------------------

Isolation of SWS flow to individual components does 

not render the SWS inoperable.

---------------------------------------------------------------------

Verify each SWS manual, power operated, and 

automatic valve in the flow path servicing safety 

related equipment, that is not locked, sealed, or 

otherwise secured in position, is in the correct 

position.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.7.8.2 Verify each SWS automatic valve in the flow path 

that is not locked, sealed, or otherwise secured in 

position, actuates to the correct position on an 

actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
SWS 

3.7.8

Babcock & Wilcox STS 3.7.8-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.7.8.3 Verify each SWS pump starts automatically on an 

actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance

Frequency

Control Program ]

UHS

3.7.9

Babcock & Wilcox STS 3.7.9-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.9 Ultimate Heat Sink (UHS) 

LCO 3.7.9 The UHS shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. [ One or more cooling 

towers with one cooling 

tower fan inoperable.

A.1 Restore cooling tower 

fan(s) to OPERABLE 

status.

7 days ]

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 3.

AND

B.2 --------------NOTE---------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

6 hours

12 hours

-----REVIEWER'S NOTE-----

The [ ]F is the maximum 

allowed UHS temperature 

value and is based on 

temperature limitations of 

the equipment that is relied 

upon for accident mitigation 

and safe shutdown of the 

unit.

--------------------------------------

C. [ Water temperature of 

the UHS > [90]F and 

 [ ]F.

C.1 Verify water temperature of 

the UHS is  [90]F 

averaged over the previous 

24 hour period.

Once per hour]
UHS

3.7.9

Babcock & Wilcox STS 3.7.9-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

D. [ Required Action and 

associated Completion 

Time of Condition C not 

met.

OR ]

UHS inoperable [for 

reasons other than 

Condition A or C].

D.1 Be in MODE 3.

AND

D.2 Be in MODE 5.

6 hours

36 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.9.1 [ Verify water level of UHS is  [562] ft [mean sea 

level].

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.7.9.2 [ Verify average water temperature of UHS is 

 [90]F.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
UHS

3.7.9

Babcock & Wilcox STS 3.7.9-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.7.9.3 [ Operate each cooling tower fan for > [15] minutes. [ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

CREVS 

3.7.10

Babcock & Wilcox STS 3.7.10-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.10 Control Room Emergency Ventilation System (CREVS) 

LCO 3.7.10 Two CREVS trains shall be OPERABLE. 

---------------------------------------------NOTE--------------------------------------------

 The control room envelope (CRE) boundary may be opened intermittently 

under administrative control. 

--------------------------------------------------------------------------------------------------

APPLICABILITY: MODES 1, 2, 3, 4, [5, and 6], 

[During movement of [recently] irradiated fuel assemblies]. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One CREVS train 

inoperable for reasons 

other than Condition B.

A.1 Restore CREVS train to 

OPERABLE status.

7 days

B. One or more CREVS 

trains inoperable due to 

inoperable CRE

boundary in MODE 1, 2, 

3, or 4.

B.1 Initiate action to implement 

mitigating actions.

AND

B.2 Verify mitigating actions 

ensure CRE occupant 

exposures to radiological, 

chemical, and smoke 

hazards will not exceed 

limits.

AND

B.3 Restore CRE boundary to 

OPERABLE status.

Immediately

24 hours

90 days
CREVS 

3.7.10

Babcock & Wilcox STS 3.7.10-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. Required Action and 

associated Completion 

Time of Condition A or B 

not met in MODE 1, 2, 3, 

or 4.

C.1 Be in MODE 3.

AND

C.2 --------------NOTE---------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

6 hours

12 hours

D. [ Required Action and 

associated Completion 

Time of Condition A not 

met [in MODE 5 or 6, or] 

during movement of 

[recently] irradiated fuel 

assemblies.

D.1 --------------NOTE---------------

Place in emergency mode if 

automatic transfer to 

emergency mode is 

inoperable.

-------------------------------------

Place OPERABLE CREVS 

train in emergency mode.

OR

D.2 Suspend movement of 

[recently] irradiated fuel 

assemblies.

Immediately

Immediately ]
CREVS 

3.7.10

Babcock & Wilcox STS 3.7.10-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

E. [ Two CREVS trains 

inoperable [in MODE 5 

or 6, or] during 

movement of [recently] 

irradiated fuel 

assemblies.

OR

One or more CREVS 

trains inoperable due to 

an inoperable CRE 

boundary [in MODE 5 or 

6, or] during movement 

of [recently] irradiated 

fuel assemblies.

E.1 Suspend movement of 

[recently] irradiated fuel 

assemblies.

Immediately ]

F. Two CREVS trains 

inoperable in MODE 1, 

2, 3, or 4 for reasons 

other than Condition B.

F.1 Enter LCO 3.0.3. Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.10.1 Operate each CREVS train for [ 10 continuous 

hours with the heaters operating or (for systems

without heaters)  15 minutes].

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
CREVS 

3.7.10

Babcock & Wilcox STS 3.7.10-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.7.10.2 Perform required CREVS filter testing in accordance 

with the [Ventilation Filter Testing Program (VFTP)].

In accordance 

with the [VFTP]

SR 3.7.10.3 Verify [each CREVS train actuates] [or the control 

room isolates] on an actual or simulated actuation 

signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.7.10.4 Perform required CRE unfiltered air inleakage 

testing in accordance with the Control Room 

Envelope Habitability Program.

In accordance 

with the Control 

Room Envelope 

Habitability 

Program

SR 3.7.10.5 [ Verify the system makeup flow rate is  [270] and 

 [330] cfm when supplying the the control room 

with outside air.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
CREATCS 

3.7.11

Babcock & Wilcox STS 3.7.11-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.11 Control Room Emergency Air Temperature Control System (CREATCS) 

LCO 3.7.11 Two CREATCS trains shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4, [5, and 6],

[During movement of [recently] irradiated fuel assemblies]. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One CREATCS train 

inoperable.

A.1 Restore CREATCS train to 

OPERABLE status.

30 days

B. Required Action and 

associated Completion 

Time of Condition A not 

met in MODE 1, 2, 3, 

or 4.

B.1 Be in MODE 3.

AND

B.2 --------------NOTE---------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

6 hours

12 hours

C. [ Required Action and 

associated Completion 

Time of Condition A not 

met during movement of 

[recently] irradiated fuel 

assemblies.

C.1 Place OPERABLE 

CREATCS train in 

operation.

OR

C.2 Suspend movement of 

[recently] irradiated fuel 

assemblies.

Immediately

Immediately ]
CREATCS 

3.7.11

Babcock & Wilcox STS 3.7.11-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

D. [ Two CREATCS trains 

inoperable during 

movement of [recently] 

irradiated fuel 

assemblies.

D.1 Suspend movement of 

[recently] irradiated fuel 

assemblies.

Immediately ]

E. Two CREATCS trains 

inoperable during 

MODE 1, 2, 3, or 4.

E.1 Enter LCO 3.0.3. Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.11.1 Verify each CREATCS train has the capability to 

remove the assumed heat load.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
EVS

3.7.12

Babcock & Wilcox STS 3.7.12-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.12 Emergency Ventilation System (EVS) 

LCO 3.7.12 Two EVS trains shall be OPERABLE. 

---------------------------------------------NOTE--------------------------------------------

 The auxiliary building negative pressure area boundary may be opened 

intermittently under administrative control. 

--------------------------------------------------------------------------------------------------

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One EVS train 

inoperable.

A.1 Restore EVS train to 

OPERABLE status.

7 days

B. Two EVS trains 

inoperable due to 

inoperable auxiliary 

building negative 

pressure area boundary.

B.1 Restore auxiliary building 

negative pressure area 

boundary to OPERABLE 

status.

24 hours

C. Required Action and 

associated Completion 

Time not met.

C.1 Be in MODE 3.

AND

C.2 Be in MODE 5.

6 hours

36 hours
EVS

3.7.12

Babcock & Wilcox STS 3.7.12-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.12.1 Operate each EVS train for [ 10 continuous hours 

with the heaters operating or (for systems without 

heaters)  15 minutes].

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.7.12.2 Perform required EVS filter testing in accordance 

with the [Ventilation Filter Testing Program (VFTP)].

In accordance 

with the [VFTP]

SR 3.7.12.3 Verify each EVS train actuates on an actual or 

simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.7.12.4 Verify one EVS train can maintain a pressure  [ ] 

inches water gauge relative to atmospheric pressure 

during the [post accident] mode of operation at a 

flow rate of  [3000] cfm.

[ [18] months on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
EVS

3.7.12

Babcock & Wilcox STS 3.7.12-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.7.12.5 [ Verify each EVS filter cooling bypass damper can 

be opened.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

FSPVS 

3.7.13

Babcock & Wilcox STS 3.7.13-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.13 Fuel Storage Pool Ventilation System (FSPVS) 

LCO 3.7.13 [Two] FSPVS trains shall be OPERABLE. 

---------------------------------------------NOTE--------------------------------------------

The fuel building boundary may be opened intermittently under 

administrative control. 

--------------------------------------------------------------------------------------------------

APPLICABILITY: [MODES 1, 2, 3, and 4,]

During movement of [recently] irradiated fuel assemblies in the fuel 

building.

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

LCO 3.0.3 is not applicable. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One FSPVS train 

inoperable.

A.1 Restore FSPVS train to 

OPERABLE status.

7 days

B. Two FSPVS trains 

inoperable due to 

inoperable fuel building 

boundary in MODE 1, 2, 

3, or 4.

B.1 Restore fuel building 

boundary to OPERABLE 

status.

24 hours
FSPVS 

3.7.13

Babcock & Wilcox STS 3.7.13-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. [ Required Action and 

associated Completion 

Time of Condition A or B 

not met in MODE 1, 2, 3, 

or 4.

OR

Two FSPVs trains 

inoperable in MODE 1, 

2, 3, or 4 for reasons 

other than Condition B.

C.1 Be in MODE 3.

AND

C.2 Be in MODE 5.

6 hours

36 hours ]

D. Required Action and 

associated Completion 

Time of Condition A not 

met during movement of 

[recently] irradiated fuel 

assemblies in the fuel 

building.

D.1 Place OPERABLE FSPVS 

train in operation.

OR

D.2 Suspend movement of 

[recently] irradiated fuel 

assemblies in the fuel 

building.

Immediately

Immediately

E. Two FSPVS trains

inoperable during 

movement of [recently] 

irradiated fuel 

assemblies in the fuel 

building.

E.1 Suspend movement of 

[recently] irradiated fuel 

assemblies in the fuel 

building.

Immediately
FSPVS 

3.7.13

Babcock & Wilcox STS 3.7.13-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.13.1 [ Operate each FSPVS train for [ 10 continuous 

hours with the heaters operating or (for systems 

without heaters)  15 minutes].

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.7.13.2 [ Perform required FSPVS filter testing in 

accordance with the [Ventilation Filter Testing 

Program (VFTP)].

In accordance 

with the [VFTP] ]

SR 3.7.13.3 [ Verify each FSPVS train actuates on an actual or 

simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.7.13.4 Verify one FSPVS train can maintain a pressure 

 [ ] inches water gauge with respect to 

atmospheric pressure during the [post accident] 

mode of operation at a flow rate  [3000] cfm.

[ [18] months on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
FSPVS 

3.7.13

Babcock & Wilcox STS 3.7.13-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.7.13.5 [ Verify each FSPVS filter bypass damper can be 

opened.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
Fuel Storage Pool Water Level 

3.7.14

Babcock & Wilcox STS 3.7.14-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.14 Fuel Storage Pool Water Level 

LCO 3.7.14 The fuel storage pool water level shall be  23 ft over the top of irradiated 

fuel assemblies seated in the storage racks. 

APPLICABILITY: During movement of irradiated fuel assemblies in fuel storage pool. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Fuel storage pool water 

level not within limit.

A.1 --------------NOTE---------------

LCO 3.0.3 is not applicable.

-------------------------------------

Suspend movement of 

irradiated fuel assemblies in 

fuel storage pool.

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.14.1 Verify the fuel storage pool water level is  23 ft 

above the top of irradiated fuel assemblies seated in 

the storage racks.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

 [Spent Fuel Pool Boron Concentration] 

3.7.15

Babcock & Wilcox STS 3.7.15-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.15 [ Spent Fuel Pool Boron Concentration ] 

LCO 3.7.15 The spent fuel pool boron concentration shall be  [500] ppm. 

APPLICABILITY: When fuel assemblies are stored in the spent fuel pool and a spent fuel 

pool verification has not been performed since the last movement of 

fuel assemblies in the spent fuel pool. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Spent fuel pool boron 

concentration not within 

limit.

-------------------NOTE--------------------

LCO 3.0.3 is not applicable.

------------------------------------------------

A.1 Suspend movement of fuel 

assemblies in the spent fuel 

pool.

AND

A.2.1 Initiate action to restore 

spent fuel pool boron 

concentration to within limit.

 OR

A.2.2 Initiate action to perform a 

fuel storage pool 

verification.

Immediately

Immediately

Immediately
 [Spent Fuel Pool Boron Concentration] 

3.7.15

Babcock & Wilcox STS 3.7.15-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.15.1 Verify the spent fuel pool boron concentration is 

within limit.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
 [Spent Fuel Pool Storage] 

3.7.16

Babcock & Wilcox STS 3.7.16-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.16 [ Spent Fuel Pool Storage ] 

LCO 3.7.16 The combination of initial enrichment and burnup of each fuel assembly 

stored in [Region 2] shall be within the acceptable [burnup domain] of 

Figure 3.7.16-1 or in accordance with Specification 4.3.1.1.

APPLICABILITY: Whenever any fuel assembly is stored in [Region 2] of the spent fuel pool.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Requirements of the 

LCO not met.

A.1 --------------NOTE---------------

LCO 3.0.3 is not applicable.

-------------------------------------

Initiate action to move the 

noncomplying fuel 

assembly from [Region 2].

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.16.1 Verify by administrative means the initial enrichment 

and burnup of the fuel assembly is in accordance 

with Figure 3.7.16-1 or Specification 4.3.1.1.

Prior to storing the 

fuel assembly in 

[Region 2]
 [Spent Fuel Pool Storage] 

3.7.16

Babcock & Wilcox STS 3.7.16-2 Rev. 4.0 
Secondary Specific Activity 

3.7.17

Babcock & Wilcox STS 3.7.17-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.17 Secondary Specific Activity 

LCO 3.7.17 The specific activity of the secondary coolant shall be  [0.10] Ci/gm 

DOSE EQUIVALENT I-131. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Specific activity not 

within limit.

A.1 Be in MODE 3.

AND

A.2 Be in MODE 5.

6 hours

36 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.17.1 Verify the specific activity of the secondary coolant 

is  [0.10] Ci/gm DOSE EQUIVALENT I-131.

[ [31] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Steam Generator Level 

3.7.18

Babcock & Wilcox STS 3.7.18-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.18 Steam Generator Level 

LCO 3.7.18 Water level of each steam generator shall be less than or equal to the 

maximum water level shown in Figure 3.7.18-1.

APPLICABILITY: MODES 1 and 2.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Water level in one or 

more steam generators 

greater than maximum 

water level in 

Figure 3.7.18-1.

A.1 Restore steam generator

level to within limit.

15 minutes

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 3. 6 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.18.1 Verify steam generator water level to be within 

limits.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Steam Generator Level 

3.7.18

Babcock & Wilcox STS 3.7.18-2 Rev. 4.0 
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-1 Rev. 4.0 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.1 AC Sources - Operating 

LCO 3.8.1 The following AC electrical power sources shall be OPERABLE: 

a. Two qualified circuits between the offsite transmission network and 

the onsite Class 1E AC Electrical Power Distribution System, 

b. Two diesel generators (DGs) each capable of supplying one train of 

the onsite Class 1E AC Electrical Power Distribution System, and 

 [ c. Automatic load sequencers for Train A and Train B. ] 

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

-----------------------------------------------------------NOTE-----------------------------------------------------------

LCO 3.0.4.b is not applicable to DGs. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One [required] offsite 

circuit inoperable.

A.1 Perform SR 3.8.1.1 for 

OPERABLE [required] 

offsite circuit.

AND

A.2 Declare required feature(s) 

with no offsite power 

available inoperable when 

its redundant required 

feature(s) is inoperable.

AND

1 hour

AND

Once per 8 hours 

thereafter

24 hours from 

discovery of no offsite 

power to one train 

concurrent with 

inoperability of 

redundant required 

feature(s)
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

A.3 Restore [required] offsite 

circuit to OPERABLE 

status.

72 hours

B. One [required] DG 

inoperable.

B.1 Perform SR 3.8.1.1 for 

OPERABLE [required] 

offsite circuit(s).

AND

B.2 Declare required feature(s) 

supported by the inoperable 

DG inoperable when its 

redundant required 

feature(s) is inoperable.

AND

B.3.1 Determine OPERABLE 

DG(s) is not inoperable due 

to common cause failure.

 OR

B.3.2 Perform SR 3.8.1.2 for 

OPERABLE DG(s).

AND

B.4 Restore [required] DG to 

OPERABLE status.

1 hour

AND

Once per 8 hours 

thereafter

4 hours from 

discovery of 

Condition B 

concurrent with 

inoperability of 

redundant required 

feature(s)

[24] hours

[24] hours

72 hours
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. Two [required] offsite 

circuits inoperable.

C.1 Declare required feature(s) 

inoperable when its 

redundant required 

feature(s) is inoperable.

AND

C.2 Restore one [required] 

offsite circuit to OPERABLE 

status.

12 hours from 

discovery of 

Condition C 

concurrent with 

inoperability of 

redundant required 

feature(s)

24 hours

D. One [required] offsite 

circuit inoperable.

AND

One [required] DG 

inoperable.

-------------------NOTE--------------------

Enter applicable Conditions and 

Required Actions of LCO 3.8.9, 

"Distribution Systems - Operating," 

when Condition D is entered with no 

AC power source to any train.

------------------------------------------------

D.1 Restore [required] offsite 

circuit to OPERABLE 

status.

OR

D.2 Restore [required] DG to 

OPERABLE status.

12 hours

12 hours

E. Two [required] DGs 

inoperable.

E.1 Restore one [required] DG 

to OPERABLE status.

2 hours
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-4 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

-----REVIEWER'S NOTE-----

[ This Condition may be 

deleted if the unit design is 

such that any sequencer 

failure mode will only affect 

the ability of the associated 

DG to power its respective 

safety loads following a loss 

of offsite power independent 

of, or coincident with, a 

Design Basis Event.

--------------------------------------

F. One [required] 

[automatic load 

sequencer] inoperable.

F.1 Restore [required] 

[automatic load sequencer] 

to OPERABLE status.

[12] hours ]

G. Required Action and 

Associated Completion 

Time of Condition A, B, 

C, D, E, or [F] not met.

G.1 Be in MODE 3.

AND

G.2 --------------NOTE---------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

12 hours

12 hours

H. Three or more [required] 

AC sources inoperable.

H.1 Enter LCO 3.0.3. Immediately
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.8.1.1 Verify correct breaker alignment and indicated 

power availability for each [required] offsite circuit.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.8.1.2 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine 

prelube period and followed by a warmup 

period prior to loading.

[ 2. A modified DG start involving idling and gradual 

acceleration to synchronous speed may be 

used for this SR as recommended by the 

manufacturer. When modified start procedures 

are not used, the time, voltage, and frequency 

tolerances of SR 3.8.1.7 must be met. ]

---------------------------------------------------------------------

Verify each DG starts from standby conditions and 

achieves steady state voltage  [3740] V and 

 [4580] V, and frequency  [58.8] Hz and 

 [61.2] Hz.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-6 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.1.3 ------------------------------NOTES-----------------------------

1. DG loadings may include gradual loading as 

recommended by the manufacturer.

2. Momentary transients outside the load range do 

not invalidate this test.

3. This Surveillance shall be conducted on only 

one DG at a time.

4. This SR shall be preceded by and immediately 

follow, without shutdown, a successful 

performance of SR 3.8.1.2 or SR 3.8.1.7.

---------------------------------------------------------------------

Verify each DG is synchronized and loaded and 

operates for  60 minutes at a load  [4500] kW and 

 [5000] kW.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.8.1.4 Verify each day tank [and engine mounted tank] 

contains  [220] gal of fuel oil.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-7 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.1.5 Check for and remove accumulated water from each 

day tank [and engine mounted tank].

[ [31] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.8.1.6 Verify the fuel oil transfer system operates to 

[automatically] transfer fuel oil from storage tank[s] 

to the day tank [and engine mounted tank].

[ [92] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.8.1.7 -------------------------------NOTE------------------------------

All DG starts may be preceded by an engine prelube 

period.

---------------------------------------------------------------------

Verify each DG starts from standby condition and 

achieves:

a. In  [10] seconds, voltage  [3740] V and 

frequency  [58.8] Hz and

b. Steady state voltage  [3740] V and  [4580] V, 

and frequency  [58.8] Hz and  [61.2] Hz.

[ 184 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-8 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.1.8 -------------------------------NOTE------------------------------

[ This Surveillance shall not normally be performed 

in MODE 1 or 2. However, this Surveillance may be 

performed to reestablish OPERABILITY provided an 

assessment determines the safety of the plant is 

maintained or enhanced. Credit may be taken for 

unplanned events that satisfy this SR.

---------------------------------------------------------------------

Verify [automatic [and] manual] transfer of AC power 

sources from the normal offsite circuit to each 

alternate [required] offsite circuit.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-9 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.1.9 ------------------------------NOTES-----------------------------

[ 1. This Surveillance shall not normally be 

performed in MODE 1 or 2. However, this 

Surveillance may be performed to reestablish 

OPERABILITY provided an assessment 

determines the safety of the plant is maintained 

or enhanced. Credit may be taken for 

unplanned events that satisfy this SR.

2. If performed with the DG synchronized with 

offsite power, it shall be performed at a power 

factor  [0.9]. However, if grid conditions do not 

permit, the power factor limit is not required to 

be met. Under this condition the power factor 

shall be maintained as close to the limit as 

practicable. ]

---------------------------------------------------------------------

Verify each DG rejects a load greater than or equal 

to its associated single largest post-accident load, 

and:

a. Following load rejection, the frequency is 

 [63] Hz,

b. Within [3] seconds following load rejection, the 

voltage is  [3740] V and  [4580] V, and

c. Within [3] seconds following load rejection, the 

frequency is  [58.8] Hz and  [61.2] Hz.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-10 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.1.10 ------------------------------NOTES-----------------------------

[1. This Surveillance shall not normally be 

performed in MODE 1 or 2. However, this 

Surveillance may be performed to reestablish 

OPERABILITY provided an assessment 

determines the safety of the plant is maintained 

or enhanced. Credit may be taken for 

unplanned events that satisfy this SR.

2. If performed with the DG synchronized with 

offsite power, it shall be performed at a power 

factor  [0.9]. However, if grid conditions do not 

permit, the power factor limit is not required to 

be met. Under this condition the power factor 

shall be maintained as close to the limit as 

practicable. ]

---------------------------------------------------------------------

Verify each DG does not trip, and voltage is 

maintained  [5000] V during and following a load 

rejection of  [4500] kW and  [5000] kW.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-11 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.1.11 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine 

prelube period.

2. This Surveillance shall not normally be 

performed in MODE 1, 2, 3, or 4. However, 

portions of the Surveillance may be performed 

to reestablish OPERABILITY provided an 

assessment determines the safety of the plant 

is maintained or enhanced. Credit may be 

taken for unplanned events that satisfy this SR.

---------------------------------------------------------------------

Verify on an actual or simulated loss of offsite power 

signal:

a. De-energization of emergency buses,

b. Load shedding from emergency buses, and

c. DG auto-starts from standby condition and:

1. Energizes permanently connected loads 

in  [10] seconds,

2. Energizes auto-connected shutdown load 

through [automatic load sequencer],

3. Maintains steady-state voltage  [3740] V 

and  [4580] V,

4. Maintains steady-state frequency 

 [58.8] Hz and  [61.2] Hz, and

5. Supplies permanently connected and 

auto-connected shutdown loads for 

 5 minutes.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-12 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.1.12 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine 

prelube period.

2. This Surveillance shall not normally be 

performed in MODE 1 or 2. However, portions 

of the Surveillance may be performed to 

reestablish OPERABILITY provided an 

assessment determines the safety of the plant 

is maintained or enhanced. Credit may be 

taken for unplanned events that satisfy this SR.

---------------------------------------------------------------------

Verify on an actual or simulated [Engineered Safety 

Feature (ESF)] actuation signal each DG auto-starts 

from standby condition and:

a. In  [12] seconds after auto-start and during 

tests, achieves voltage  [3740] V and 

frequency  [58.8] Hz,

b. Achieves steady state voltage  [3740] V 

and [4580] V and frequency  [58.8] Hz and 

 [61.2] Hz,

c. Operates for  5 minutes,

d. Permanently connected loads remain energized 

from the offsite power system, and

e. Emergency loads are energized [or autoconnected through the automatic load 

sequencer] from the offsite power system.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-13 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.1.13 -------------------------------NOTE------------------------------

[ This Surveillance shall not normally be performed 

in MODE 1 or 2. However, this Surveillance may be 

performed to reestablish OPERABILITY provided an 

assessment determines the safety of the plant is 

maintained or enhanced. Credit may be taken for 

unplanned events that satisfy this SR. ]

---------------------------------------------------------------------

Verify each DG's noncritical automatic trips are

bypassed on [actual or simulated loss of voltage 

signal on the emergency bus concurrent with an 

actual or simulated ESF actuation signal].

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-14 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.1.14 ------------------------------NOTES-----------------------------

1. Momentary transients outside the load and 

power factor ranges do not invalidate this test.

2. This Surveillance shall not normally be 

performed in MODE 1 or 2. However, this 

Surveillance may be performed to reestablish 

OPERABILITY provided an assessment 

determines the safety of the plant is maintained 

or enhanced. Credit may be taken for 

unplanned events that satisfy this SR.

3. If performed with DC synchronized with offsite 

power, it shall be performed at a power factor 

 [0.9]. However, if grid conditions do not 

permit, the power factor limit is not required to 

be met. Under this condition the power factor 

shall be maintained as close to the limit as 

practicable.

---------------------------------------------------------------------

Verify each DG operates for  24 hours:

a. For  [2] hours loaded  [5250] kW and 

 [6000] kW and

b. For the remaining hours of the test loaded 

 [4500] kW and  [5000] kW.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-15 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.1.15 ------------------------------NOTES-----------------------------

1. This Surveillance shall be performed within 

5 minutes of shutting down the DG after the DG 

has operated  [2] hours loaded  [4500] kW 

and  [5000] kW.

Momentary transients outside of load range do 

not invalidate this test.

2. All DG starts may be preceded by an engine 

prelube period.

---------------------------------------------------------------------

Verify each DG starts and achieves:

a. In  [10] seconds, voltage  [3740] V and 

frequency  [58.8] Hz and

b. Steady state voltage  [3740] V and  [4580] V, 

and frequency  [58.8] Hz and  [61.2] Hz.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.8.1.16 -------------------------------NOTE------------------------------

This Surveillance shall not normally be performed in 

MODE 1, 2, 3, or 4. However, this Surveillance may 

be performed to reestablish OPERABILITY provided 

an assessment determines the safety of the plant is 

maintained or enhanced. Credit may be taken for 

unplanned events that satisfy this SR.

---------------------------------------------------------------------

Verify each DG:

a. Synchronizes with offsite power source while 

loaded with emergency loads upon a simulated 

restoration of offsite power,

b. Transfers loads to offsite power source, and

c. Returns to ready-to-load operation.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-16 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.1.17 -------------------------------NOTE------------------------------

[ This Surveillance shall not normally be performed 

in MODE 1, 2, or 3. However, portions of the 

Surveillance may be performed to reestablish 

OPERABILITY provided an assessment determines 

the safety of the plant is maintained or enhanced. 

Credit may be taken for unplanned events that 

satisfy this SR.

---------------------------------------------------------------------

Verify, with a DG operating in test mode and 

connected to its bus, an actual or simulated ESF 

actuation signal overrides the test mode by:

a. Returning DG to ready-to-load operation and

[ b. Automatically energizing the emergency load 

from offsite power. ]

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.8.1.18 -------------------------------NOTE------------------------------

[ This Surveillance shall not normally be performed 

in MODE 1, 2, 3, or 4. However, this Surveillance 

may be performed to reestablish OPERABILITY 

provided an assessment determines the safety of 

the plant is maintained or enhanced. Credit may be 

taken for unplanned events that satisfy this SR. ]

---------------------------------------------------------------------

Verify interval between each sequenced load block 

is within ± [10% of design interval] for each 

emergency [and shutdown] load sequencer.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-17 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.1.19 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine 

prelube period.

2. This Surveillance shall not normally be 

performed in MODE 1, 2, 3, or 4. However, 

portions of the Surveillance may be performed 

to reestablish OPERABILITY provided an 

assessment determines the safety of the plant 

is maintained or enhanced. Credit may be 

taken for unplanned events that satisfy this SR.

---------------------------------------------------------------------

Verify on an actual or simulated loss of offsite power 

signal in conjunction with an actual or simulated 

ESF actuation signal:

a. De-energization of emergency buses,

b. Load shedding from emergency buses,

c. DG auto-starts from standby condition and:

1. Energizes permanently connected loads 

in  [10] seconds,

2. Energizes auto-connected emergency 

loads through [load sequencer],

3. Achieves steady-state voltage  [3740] V 

and  [4580] V,

4. Achieves steady-state frequency 

 [58.8] Hz and  [61.2] Hz, and

5. Supplies permanently connected and 

auto-connected emergency loads for 

 [5] minutes.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AC Sources - Operating 

3.8.1

Babcock & Wilcox STS 3.8.1-18 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.1.20 -------------------------------NOTE------------------------------

All DG starts may be preceded by an engine prelube 

period.

---------------------------------------------------------------------

Verify, when started simultaneously from standby 

condition, each DG achieves, in  [10] seconds, 

voltage  [3740] V and  [4580] V, and frequency 

 [58.8] Hz and  [61.2] Hz.

[ 10 years

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AC Sources - Shutdown 

3.8.2

Babcock & Wilcox STS 3.8.2-1 Rev. 4.0 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.2 AC Sources - Shutdown 

LCO 3.8.2 The following AC electrical power sources shall be OPERABLE: 

a. One qualified circuit between the offsite transmission network and 

the onsite Class 1E AC electrical power distribution subsystem(s) 

required by LCO 3.8.10, "Distribution Systems - Shutdown," and 

b. One diesel generator (DG) capable of supplying one train of the 

onsite Class 1E AC electrical power distribution subsystem(s) 

required by LCO 3.8.10.

APPLICABILITY: MODES 5 and 6,

During movement of [recently] irradiated fuel assemblies. 

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

LCO 3.0.3 is not applicable. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One required offsite 

circuit inoperable.

-------------------NOTE--------------------

Enter applicable Conditions and 

Required Actions of LCO 3.8.10, 

with one required train de-energized 

as a result of Condition A.

------------------------------------------------

A.1 Declare affected required 

feature(s) with no offsite 

power available inoperable.

OR

Immediately
AC Sources - Shutdown 

3.8.2

Babcock & Wilcox STS 3.8.2-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

A.2.1 Suspend movement of 

[recently] irradiated fuel 

assemblies.

 AND

A.2.2 Suspend operations 

involving positive reactivity 

additions that could result in 

loss of required SDM or 

boron concentration.

 AND

A.2.3 Initiate action to restore 

required offsite power 

circuit to OPERABLE 

status.

Immediately

Immediately

Immediately

B. One required DG 

inoperable.

B.1 Suspend movement of 

[recently] irradiated fuel 

assemblies.

AND

B.2 Suspend operations 

involving positive reactivity 

additions that could result in 

loss of required SDM or 

boron concentration.

AND

B.3 Initiate action to restore 

required DG to OPERABLE 

status.

Immediately

Immediately

Immediately
AC Sources - Shutdown 

3.8.2

Babcock & Wilcox STS 3.8.2-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.8.2.1 ------------------------------NOTE------------------------------

The following SRs are not required to be performed: 

SR 3.8.1.3, SR 3.8.1.9 through SR 3.8.1.11, 

SR 3.8.1.13 through SR 3.8.1.16, and 

[SR 3.8.1.18].

---------------------------------------------------------------------

For AC sources required to be OPERABLE, the SRs 

of Specification 3.8.1, "AC Sources - Operating," 

except SR 3.8.1.8, SR 3.8.1.12, SR 3.8.1.17, 

SR 3.8.1.19, and SR 3.8.1.20, are applicable.

In accordance 

with applicable 

SRs

Diesel Fuel Oil, Lube Oil, and Starting Air 

3.8.3

Babcock & Wilcox STS 3.8.3-1 Rev. 4.0 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air 

LCO 3.8.3 The stored diesel fuel oil, lube oil, and starting air subsystem shall be 

within limits for each required diesel generator (DG). 

APPLICABILITY: When associated DG is required to be OPERABLE. 

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each DG. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more DGs with 

fuel level less than a 

[7] day supply and 

greater than a [6] day 

supply in storage tank.

A.1 Restore fuel oil level to 

within limits.

48 hours

B. One or more DGs with 

lube oil inventory less 

than a [7] day supply 

and greater than a 

[6] day supply.

B.1 Restore lube oil inventory to 

within limits.

48 hours

C. One or more DGs with 

stored fuel oil total 

particulates not within 

limit.

C.1 Restore fuel oil total 

particulates to within limits.

7 days

D. One or more DGs with 

new fuel oil properties 

not within limits.

D.1 Restore stored fuel oil 

properties to within limits.

30 days
Diesel Fuel Oil, Lube Oil, and Starting Air 

3.8.3

Babcock & Wilcox STS 3.8.3-2 Rev. 4.0 

ACTIONS (continued) 

E. One or more DGs with 

starting air receiver 

pressure < [225] psig 

and  [125] psig.

E.1 Restore starting air receiver 

pressure to  [225] psig.

48 hours

F. Required Action and 

associated Completion 

Time not met.

OR

One or more DGs with 

diesel fuel oil, lube oil, or 

starting air subsystem 

not within limits for 

reasons other than 

Condition A, B, C, D, 

or E.

F.1 Declare associated DG 

inoperable.

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.8.3.1 Verify each fuel oil storage tank contains  a [7] day 

supply of fuel.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.8.3.2 Verify lube oil inventory is  a [7] day supply. [ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Diesel Fuel Oil, Lube Oil, and Starting Air 

3.8.3

Babcock & Wilcox STS 3.8.3-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.3.3 Verify fuel oil properties of new and stored fuel oil 

are tested in accordance with, and maintained within 

the limits of, the Diesel Fuel Oil Testing Program.

In accordance 

with the Diesel 

Fuel Oil Testing 

Program

SR 3.8.3.4 Verify each DG air start receiver pressure is 

 [225] psig.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.8.3.5 Check for and remove accumulated water from each 

fuel oil storage tank.

[ [31] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

DC Sources - Operating 

3.8.4

Babcock & Wilcox STS 3.8.4-1 Rev. 4.0 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.4 DC Sources - Operating 

LCO 3.8.4 The Train A and Train B DC electrical power subsystems shall be 

OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One [or two] battery 

charger[s] on one 

subsystem inoperable.

A.1 Restore battery terminal 

voltage to greater than or 

equal to the minimum 

established float voltage.

AND

A.2 Verify battery float current 

 [2] amps.

AND

A.3 Restore battery charger[s] 

to OPERABLE status.

2 hours

Once per [12] hours

[72] hours

[ B. One [or two] batter[y][ies 

on one subsystem] 

inoperable.

B.1 Restore batter[y][ies] to 

OPERABLE status.

[2] hours ]

C. One DC electrical power 

subsystem inoperable 

for reasons other than 

Condition A [or B].

C.1 Restore DC electrical 

power subsystem to 

OPERABLE status.

[2] hours
DC Sources - Operating 

3.8.4

Babcock & Wilcox STS 3.8.4-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

D. Required Action and 

Associated Completion 

Time not met.

D.1 Be in MODE 3.

AND

D.2 --------------NOTE---------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

6 hours

12 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.8.4.1 Verify battery terminal voltage is greater than or 

equal to the minimum established float voltage.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.8.4.2 Verify each battery charger supplies  [400] amps at

greater than or equal to the minimum established 

float voltage for  [8] hours.

OR

Verify each battery charger can recharge the battery 

to the fully charged state within [24] hours while 

supplying the largest combined demands of the 

various continuous steady state loads, after a 

battery discharge to the bounding design basis 

event discharge state.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
DC Sources - Operating 

3.8.4

Babcock & Wilcox STS 3.8.4-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.4.3 ------------------------------NOTES-----------------------------

1. The modified performance discharge test in 

SR 3.8.6.6 may be performed in lieu of 

SR 3.8.4.3.

2. This Surveillance shall not normally be 

performed in MODE 1, 2, 3, or 4. However, 

portions of the Surveillance may be performed 

to reestablish OPERABILITY provided an 

assessment determines the safety of the plant 

is maintained or enhanced. Credit may be 

taken for unplanned events that satisfy this SR.

---------------------------------------------------------------------

Verify battery capacity is adequate to supply, and 

maintain in OPERABLE status, the required 

emergency loads for the design duty cycle when 

subjected to a battery service test.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

DC Sources - Shutdown 

3.8.5

Babcock & Wilcox STS 3.8.5-1 Rev. 4.0 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.5 DC Sources - Shutdown 

LCO 3.8.5 [DC electrical power subsystem shall be OPERABLE to support the DC 

electrical power distribution subsystem(s) required by LCO 3.8.10, 

"Distribution Systems - Shutdown."] 

 [One DC electrical power subsystem shall be OPERABLE.] 

-----------------------------------REVIEWER'S NOTE-----------------------------------

 The second option above applies for plants having a pre-ITS licensing 

basis (CTS) for electrical power requirements during shutdown conditions 

that required only one DC electrical power subsystem to be OPERABLE. 

Action A and the bracketed optional wording in Condition B are also 

eliminated for this case. The first option above is adopted for plants that 

have a CTS requiring the same level of DC electrical power subsystem 

support as is required for power operating conditions. 

-------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODES 5 and 6,

During movement of [recently] irradiated fuel assemblies. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

LCO 3.0.3 is not applicable. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

[A. One [or two] battery 

charger[s on one 

subsystem] inoperable.

AND

The redundant 

subsystem battery and 

charger[s] OPERABLE.

A.1 Restore battery terminal 

voltage to greater than or 

equal to the minimum 

established float voltage.

AND

A.2 Verify battery float current 

 [2] amps.

AND

2 hours

Once per [12] hours
DC Sources - Shutdown 

3.8.5

Babcock & Wilcox STS 3.8.5-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

A.3 Restore battery charger[s] 

to OPERABLE status.

[72] hours ]

B. One [or more] required 

DC electrical power 

subsystem[s] inoperable 

[for reasons other than 

Condition A.

OR

Required Action and 

associated Completion 

Time of Condition A not 

met].

B.1 Declare affected required 

feature(s) inoperable.

OR

B.2.1 Suspend movement of 

[recently] irradiated fuel 

assemblies.

 AND

B.2.2 Suspend operations 

involving positive reactivity 

additions that could result in 

loss of required SDM or 

boron concentration.

 AND

B.2.3 Initiate action to restore 

required DC electrical 

power subsystems to 

OPERABLE status.

Immediately

Immediately

Immediately

Immediately
DC Sources - Shutdown 

3.8.5

Babcock & Wilcox STS 3.8.5-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.8.5.1 -------------------------------NOTE------------------------------

The following SRs are not required to be performed: 

SR 3.8.4.2 and SR 3.8.4.3.

---------------------------------------------------------------------

For DC sources required to be OPERABLE, the 

following SRs are applicable:

SR 3.8.4.1

SR 3.8.4.2

SR 3.8.4.3

In accordance 

with applicable 

SRs

Battery Parameters 

3.8.6

Babcock & Wilcox STS 3.8.6-1 Rev. 4.0 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.6 Battery Parameters 

LCO 3.8.6 Battery parameters for the Train A and Train B electrical power 

subsystem batteries shall be within limits. 

APPLICABILITY: When associated DC electrical power subsystems are required to be 

OPERABLE. 

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each battery. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One [or two] batter[y][ies 

on one subsystem] with 

one or more battery cells 

float voltage < [2.07] V.

A.1 Perform SR 3.8.4.1

AND

A.2 Perform SR 3.8.6.1.

AND

A.3 Restore affected cell 

voltage  [2.07] V.

2 hours

2 hours

24 hours

B. One [or two] batter[y][ies 

on one subsystem] with 

float current > [2] amps.

B.1 Perform SR 3.8.4.1.

AND

B.2 Restore battery float current 

to  [2] amps.

2 hours

[12] hours
Battery Parameters 

3.8.6

Babcock & Wilcox STS 3.8.6-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. ------------NOTE------------

Required Action C.2 

shall be completed if 

electrolyte level was 

below the top of plates.

---------------------------------

One [or two] batter[y][ies 

on one subsystem] with 

one or more cells 

electrolyte level less 

than minimum 

established design 

limits.

-------------------NOTE--------------------

Required Actions C.1 and C.2 are 

only applicable if electrolyte level 

was below the top of plates.

------------------------------------------------

C.1 Restore electrolyte level to 

above top of plates.

AND

C.2 Verify no evidence of 

leakage.

AND

C.3 Restore electrolyte level to 

greater than or equal to 

minimum established 

design limits.

8 hours

12 hours

31 days

D. One [or two] batter[y][ies 

on one subsystem] with 

pilot cell electrolyte 

temperature less than 

minimum established 

design limits.

D.1 Restore battery pilot cell 

temperature to greater than 

or equal to minimum 

established design limits.

12 hours

E. One or more batteries in 

redundant subsystem

with battery parameters 

not within limits.

E.1 Restore battery parameters 

for batteries in one 

subsystem to within limits.

2 hours
Battery Parameters 

3.8.6

Babcock & Wilcox STS 3.8.6-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

F. Required Action and 

associated Completion 

Time of Condition A, B, 

C, D, or E not met.

OR

One [or two] batter[y][ies 

on one subsystem] with 

one or more battery cells 

float voltage < [2.07] V 

and float current > [2] 

amps.

F.1 Declare associated battery 

inoperable.

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.8.6.1 -------------------------------NOTE------------------------------

Not required to be met when battery terminal 

voltage is less than the minimum established float 

voltage of SR 3.8.4.1.

---------------------------------------------------------------------

Verify each battery float current is  [2] amps. [ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Battery Parameters 

3.8.6

Babcock & Wilcox STS 3.8.6-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.6.2 Verify each battery pilot cell float voltage is 

 [2.07] V.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.8.6.3 Verify each battery connected cell electrolyte level is 

greater than or equal to minimum established 

design limits.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.8.6.4 Verify each battery pilot cell temperature is greater 

than or equal to minimum established design limits.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Battery Parameters 

3.8.6

Babcock & Wilcox STS 3.8.6-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.6.5 Verify each battery connected cell float voltage is 

 [2.07] V.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Battery Parameters 

3.8.6

Babcock & Wilcox STS 3.8.6-6 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.6.6 -------------------------------NOTE------------------------------

This Surveillance shall not be performed in 

MODE 1, 2, 3, or 4. However, portions of the 

Surveillance may be performed to reestablish 

OPERABILITY provided an assessment determines 

the safety of the plant is maintained or enhanced. 

Credit may be taken for unplanned events that 

satisfy this SR.

---------------------------------------------------------------------

Verify battery capacity is  [80%] of the 

manufacturer's rating when subjected to a 

performance discharge test or a modified 

performance discharge test.

[ 60 months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

AND

12 months when 

battery shows 

degradation, or 

has reached 

[85]% of the 

expected life with 

capacity < 100% 

of manufacturer's 

rating

AND

24 months when 

battery has 

reached [85]% of 

the expected life 

with capacity 

 100% of 

manufacturer's 

rating
Inverters - Operating 

3.8.7

Babcock & Wilcox STS 3.8.7-1 Rev. 4.0 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.7 Inverters - Operating 

LCO 3.8.7 The required Train A and Train B inverters shall be OPERABLE. 

---------------------------------------------NOTE-------------------------------------------- 

 [ [One/two] inverter[s] may be disconnected from [its/their] associated DC 

bus for  24 hours to perform an equalizing charge on [its/their] 

associated [common] battery provided: 

a. The associated AC vital bus(es) [is/are] energized from [its/their] 

[Class 1E constant voltage source transformers] [inverter using 

internal AC source] and 

b. All other AC vital buses are energized from their associated 

OPERABLE inverters. ] 

--------------------------------------------------------------------------------------------------

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One [required] inverter 

inoperable.

A.1 --------------NOTE---------------

Enter applicable Conditions 

and Required Actions of 

LCO 3.8.9, "Distribution 

Systems - Operating" with 

any vital bus de-energized.

-------------------------------------

Restore inverter to 

OPERABLE status.

24 hour
Inverters - Operating 

3.8.7

Babcock & Wilcox STS 3.8.7-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3.

AND

B.2 --------------NOTE---------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

6 hours

12 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.8.7.1 Verify correct inverter voltage, [frequency,] and 

alignment to required AC vital buses.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Inverters - Shutdown 

3.8.8

Babcock & Wilcox STS 3.8.8-1 Rev. 4.0 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.8 Inverters - Shutdown 

LCO 3.8.8 [Inverters shall be OPERABLE to support the onsite Class 1E AC vital 

bus electrical power distribution subsystem(s) required by LCO 3.8.10,

"Distribution Systems - Shutdown."] 

 [One] inverter[s] shall be OPERABLE.] 

-----------------------------------REVIEWER'S NOTE-----------------------------------

 This second option above applies for plants having a pre-ITS licensing 

basis (CTS) for electrical power requirements during shutdown conditions 

that required only [one] inverter to be OPERABLE. The "[or more]" 

optional wording in Condition A is also eliminated for this case. The first 

option above is adopted for plants that have a CTS requiring the same 

level of DC electrical power subsystem/inverter support as is required for 

power operating conditions. 

-------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODES 5 and 6,

During movement of [recently] irradiated fuel assemblies. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

LCO 3.0.3 is not applicable. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One [or more] [required] 

inverters inoperable.

A.1 Declare affected required 

feature(s) inoperable.

OR

A.2.1 Suspend movement of 

[recently] irradiated fuel 

assemblies.

 AND

Immediately

Immediately
Inverters - Shutdown 

3.8.8

Babcock & Wilcox STS 3.8.8-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

A.2.2 Suspend operations 

involving positive reactivity 

additions that could result in 

loss of required SDM or 

boron concentration.

 AND

A.2.3 Initiate action to restore 

required inverters to 

OPERABLE status.

Immediately

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.8.8.1 Verify correct inverter voltage, [frequency,] and 

alignments to required AC vital buses.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Distribution Systems - Operating 

3.8.9

Babcock & Wilcox STS 3.8.9-1 Rev. 4.0 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.9 Distribution Systems - Operating 

LCO 3.8.9 Train A and Train B AC, DC, and AC vital bus electrical power distribution 

subsystems shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more AC 

electrical power 

distribution subsystems 

inoperable.

A.1 --------------NOTE---------------

Enter applicable Conditions 

and Required Actions of 

LCO 3.0.4, "DC Sources -

Operating," for DC trains 

made inoperable by 

inoperable power 

distribution subsystems.

-------------------------------------

Restore AC electrical power 

distribution subsystem(s) to 

OPERABLE status.

8 hours

B. One or more AC vital 

buses inoperable.

B.1 Restore AC vital bus 

subsystem(s) to 

OPERABLE status.

2 hours

C. One or more DC 

electrical power 

distribution subsystems 

inoperable.

C.1 Restore DC electrical 

power distribution 

subsystem(s) to 

OPERABLE status.

2 hours
Distribution Systems - Operating 

3.8.9

Babcock & Wilcox STS 3.8.9-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

D. Required Action and 

associated Completion 

Time not met.

D.1 Be in MODE 3.

AND

D.2 --------------NOTE---------------

LCO 3.0.4.a is not 

applicable when entering 

MODE 4.

-------------------------------------

Be in MODE 4.

6 hours

12 hours

E. Two or more electrical 

power distribution 

subsystems inoperable 

that result in a loss of 

function.

E.1 Enter LCO 3.0.3. Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.8.9.1 Verify correct breaker alignments and voltage to 

[required] AC, DC, and AC vital bus electrical power 

distribution subsystems.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Distribution Systems - Shutdown 

3.8.10

Babcock & Wilcox STS 3.8.10-1 Rev. 4.0 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.10 Distribution Systems - Shutdown 

LCO 3.8.10 The necessary portion of AC, DC, and AC vital bus electrical power 

distribution subsystems shall be OPERABLE to support equipment 

required to be OPERABLE. 

APPLICABILITY: MODES 5 and 6,

During movement of [recently] irradiated fuel assemblies. 

ACTIONS 

------------------------------------------------------------NOTE-----------------------------------------------------------

LCO 3.0.3 is not applicable. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more required 

AC, DC, or AC vital bus 

electrical power 

distribution subsystems 

inoperable.

A.1 Declare associated 

supported required 

feature(s) inoperable.

OR

A.2.1 Suspend movement of 

[recently] irradiated fuel 

assemblies.

 AND

A.2.2 Suspend operations 

involving positive reactivity 

additions that could result in 

loss of required SDM or 

boron concentration.

 AND

Immediately

Immediately

Immediately
Distribution Systems - Shutdown 

3.8.10

Babcock & Wilcox STS 3.8.10-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

A.2.3 Initiate actions to restore 

required AC, DC, and AC 

vital bus electrical power 

distribution subsystems to 

OPERABLE status.

 AND

A.2.4 Declare associated 

required decay heat 

removal subsystem(s) 

inoperable and not in 

operation.

Immediately

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.8.10.1 Verify correct breaker alignments and voltage to 

required AC, DC, and AC vital bus electrical power 

distribution subsystems.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Boron Concentration

3.9.1

Babcock & Wilcox STS 3.9.1-1 Rev. 4.0 

3.9 REFUELING OPERATIONS 

3.9.1 Boron Concentration 

LCO 3.9.1 Boron concentrations of the Reactor Coolant System, the refueling canal, 

and the refueling cavity shall be maintained within the limit specified in the 

COLR. 

APPLICABILITY: MODE 6.

---------------------------------------------NOTE--------------------------------------------

Only applicable to the refueling canal and refueling cavity when 

connected to the RCS. 

--------------------------------------------------------------------------------------------------

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Boron concentration not 

within limit.

A.1 Suspend positive reactivity 

additions.

AND

A.2 Initiate action to restore 

boron concentration to 

within limit.

Immediately

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.9.1.1 Verify boron concentration is within the limit 

specified in the COLR.

[ 72 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Nuclear Instrumentation 

3.9.2

Babcock & Wilcox STS 3.9.2-1 Rev. 4.0 

3.9 REFUELING OPERATIONS 

3.9.2 Nuclear Instrumentation 

LCO 3.9.2 Two source range neutron flux monitors shall be OPERABLE. 

APPLICABILITY: MODE 6. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One [required] source 

range neutron flux 

monitor inoperable.

A.1 Suspend positive reactivity 

additions.

AND

A.2 Suspend operations that 

would cause introduction of 

coolant into the RCS with 

boron concentration less 

than required to meet the 

boron concentration of 

LCO 3.9.1.

Immediately

Immediately

B. Two [required] source 

range neutron flux 

monitors inoperable.

B.1 Initiate action to restore one 

source range neutron flux 

monitor to OPERABLE 

status.

AND

B.2 Perform SR 3.9.1.1.

Immediately

Once per 12 hours
Nuclear Instrumentation 

3.9.2

Babcock & Wilcox STS 3.9.2-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.9.2.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.9.2.2 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL 

CALIBRATION.

---------------------------------------------------------------------

Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Penetrations 

3.9.3

Babcock & Wilcox STS 3.9.3-1 Rev. 4.0 

3.9 REFUELING OPERATIONS 

3.9.3 Containment Penetrations 

LCO 3.9.3 The containment penetrations shall be in the following status: 

a. The equipment hatch closed and held in place by four bolts,

b. One door in each air lock is [capable of being] closed, and 

c. Each penetration providing direct access from the containment 

atmosphere to the outside atmosphere either: 

 1. Closed by a manual or automatic isolation valve, blind flange, 

or equivalent or 

 2. Capable of being closed by an OPERABLE Containment 

Purge and Exhaust Isolation System. 

---------------------------------------------NOTE--------------------------------------------

 Penetration flow path(s) providing direct access from the containment 

atmosphere to the outside atmosphere may be unisolated under 

administrative controls. 

-------------------------------------------------------------------------------------------------- 

APPLICABILITY: During movement of [recently] irradiated fuel assemblies within 

containment. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more 

containment 

penetrations not in 

required status.

A.1 Suspend movement of 

[recently] irradiated fuel 

assemblies within 

containment.

Immediately
Containment Penetrations 

3.9.3

Babcock & Wilcox STS 3.9.3-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.9.3.1 Verify each required containment penetration is in 

the required status.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.9.3.2 -------------------------------NOTE------------------------------

Not required to be met for containment purge and 

exhaust valve(s) in penetrations closed to comply 

with LCO 3.9.3.c.1.

---------------------------------------------------------------------

Verify each required containment purge and 

exhaust valve actuates to the isolation position on 

an actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
DHR and Coolant Circulation - High Water Level 

3.9.4

Babcock & Wilcox STS 3.9.4-1 Rev. 4.0 

3.9 REFUELING OPERATIONS 

3.9.4 Decay Heat Removal (DHR) and Coolant Circulation - High Water Level 

LCO 3.9.4 One DHR loop shall be OPERABLE and in operation. 

---------------------------------------------NOTE--------------------------------------------

The required DHR loop may be removed from operation for  1 hour per 

8 hour period, provided no operations are permitted that would cause 

introduction of coolant into the Reactor Coolant System with boron 

concentration less than that required to meet the minimum required boron 

concentration of LCO 3.9.1. 

--------------------------------------------------------------------------------------------------

APPLICABILITY: MODE 6 with the water level  23 ft above the top of reactor vessel 

flange. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. DHR loop requirements 

not met.

A.1 Suspend operations that 

would cause introduction of 

coolant into the RCS with 

boron concentration less 

than required to meet the 

boron concentration of 

LCO 3.9.1.

AND

A.2 Suspend loading irradiated 

fuel assemblies in the core.

AND

A.3 Initiate action to satisfy 

DHR loop requirements.

AND

Immediately

Immediately

Immediately
DHR and Coolant Circulation - High Water Level 

3.9.4

Babcock & Wilcox STS 3.9.4-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

A.4 Close equipment hatch and 

secure with [four] bolts.

AND

A.5 Close one door in each air 

lock.

AND

A.6.1 Close each penetration 

providing direct access 

from the containment 

atmosphere to the outside 

atmosphere with a manual 

or automatic isolation valve, 

blind flange, or equivalent.

 OR

A.6.2 Verify each penetration is 

capable of being closed by 

an OPERABLE 

Containment Purge and 

Exhaust Isolation System.

4 hours

4 hours

4 hours

4 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.9.4.1 Verify one DHR loop is in operation and circulating 

reactor coolant at a flow rate of  [2800] gpm.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
DHR and Coolant Circulation - Low Water Level 

3.9.5

Babcock & Wilcox STS 3.9.5-1 Rev. 4.0 

3.9 REFUELING OPERATIONS 

3.9.5 Decay Heat Removal (DHR) and Coolant Circulation - Low Water Level 

LCO 3.9.5 Two DHR loops shall be OPERABLE, and one DHR loop shall be in 

operation. 

--------------------------------------------NOTES-------------------------------------------

1. All DHR pumps may be removed from operation for  15 minutes 

when switching from one train to another provided: 

 a. The core outlet temperature is maintained > 10 degrees F 

below saturation temperature, 

 b. No operations are permitted that would cause introduction of 

coolant into the Reactor Coolant System with boron 

concentration less than that required to meet the minimum 

required boron concentration of LCO 3.9.1, and

 c. No draining operations to further reduce RCS water volume 

are permitted. 

2. One required DHR loop may be inoperable for up to 2 hours for 

surveillance testing, provided that the other DHR loop is 

OPERABLE and in operation. 

--------------------------------------------------------------------------------------------------

APPLICABILITY: MODE 6 with the water level < 23 ft above the top of reactor vessel 

flange. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Less than required 

number of DHR loops 

OPERABLE.

A.1 Initiate action to restore 

DHR loop to OPERABLE 

status.

OR

A.2 Initiate action to establish 

 23 ft of water above the 

top of reactor vessel flange.

Immediately

Immediately
DHR and Coolant Circulation - Low Water Level 

3.9.5

Babcock & Wilcox STS 3.9.5-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B. No DHR loop 

OPERABLE or in 

operation.

B.1 Suspend operations that 

would cause introduction of 

coolant into the RCS with 

boron concentration less 

than required to meet the 

boron concentration of 

LCO 3.9.1.

AND

B.2 Initiate action to restore one 

DHR loop to OPERABLE 

status and to operation.

AND

B.3 Close equipment hatch and 

secure with [four] bolts.

AND

B.4 Close one door in each air 

lock.

AND

B.5.1 Close each penetration 

providing direct access 

from the containment 

atmosphere to the outside 

atmosphere with a manual 

or automatic isolation valve, 

blind flange, or equivalent.

 OR

Immediately

Immediately

4 hours

4 hours

4 hours
DHR and Coolant Circulation - Low Water Level 

3.9.5

Babcock & Wilcox STS 3.9.5-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.5.2 Verify each penetration is 

capable of being closed by 

an OPERABLE 

Containment Purge and 

Exhaust Isolation System.

4 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.9.5.1 Verify one DHR loop is in operation. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.9.5.2 Verify correct breaker alignment and indicated 

power available to the required DHR pump that is 

not in operation.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Refueling Canal Water Level 

3.9.6

Babcock & Wilcox STS 3.9.6-1 Rev. 4.0 

3.9 REFUELING OPERATIONS 

3.9.6 Refueling Canal Water Level 

LCO 3.9.6 Refueling canal water level shall be maintained  23 ft above the top of 

the reactor vessel flange.

APPLICABILITY: During movement of irradiated fuel assemblies within containment. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Refueling cavity water 

level not within limit.

A.1 Suspend movement of 

irradiated fuel assemblies 

within containment.

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.9.6.1 Verify refueling canal water level is  23 ft above the 

top of reactor vessel flange.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Design Features 

4.0

Babcock & Wilcox STS 4.0-1 Rev. 4.0 

4.0 DESIGN FEATURES 

4.1 Site Location 

 [ Text description of site location. ] 

4.2 Reactor Core 

4.2.1 Fuel Assemblies 

 The reactor shall contain [177] fuel assemblies. Each assembly shall consist of a 

matrix of [Zircalloy or ZIRLO] fuel rods with an initial composition of natural or 

slightly enriched uranium dioxide (UO2) as fuel material. Limited substitutions of 

zirconium alloy or stainless steel filler rods for fuel rods, in accordance with 

approved applications of fuel rod configurations, may be used. Fuel assemblies 

shall be limited to those fuel designs that have been analyzed with applicable 

NRC staff approved codes and methods and shown by tests or analyses to 

comply with all fuel safety design bases. A limited number of lead test 

assemblies that have not completed representative testing may be placed in 

nonlimiting core regions. 

4.2.2 Control Rods 

 The reactor core shall contain [60] safety and regulating CONTROL ROD 

assemblies and [8] APSR assemblies. The material shall be [silver indium 

cadmium, boron carbide, or hafnium metal] as approved by the NRC. 

4.3 Fuel Storage 

4.3.1 Criticality 

 4.3.1.1 The spent fuel storage racks are designed and shall be maintained 

with: 

 a. Fuel assemblies having a maximum U-235 enrichment of 

[4.5] weight percent, 

 b. keff  0.95 if fully flooded with unborated water, which includes an 

allowance for uncertainties as described in [Section 9.1 of the 

FSAR], 

 [ c. A nominal [ ] inch center to center distance between fuel 

assemblies placed in [the high density fuel storage racks], ] 

 [ d. A nominal [ ] inch center to center distance between fuel 

assemblies placed in [the low density fuel storage racks], ] 
Design Features 

4.0

Babcock & Wilcox STS 4.0-2 Rev. 4.0 

4.0 DESIGN FEATURES 

4.3 Fuel Storage (continued) 

 [ e. New or partially spent fuel assemblies with a discharge burnup in 

the "acceptable range" of Figure [3.7.17-1] may be allowed 

unrestricted storage in [either] fuel storage rack(s), and ] 

 [ f. New or partially spent fuel assemblies with a discharge burnup in 

the "unacceptable range" of Figure [3.7.17-1] will be stored in 

compliance with the NRC approved [specific document containing 

the analytical methods, title, date, or specific configuration or 

figure]. ] 

 4.3.1.2 The new fuel storage racks are designed and shall be maintained with: 

 a. Fuel assemblies having a maximum U-235 enrichment of 

[4.5] weight percent, 

 b. keff  0.95 if fully flooded with unborated water, which includes an 

allowance for uncertainties as described in [Section 9.1 of the 

FSAR], 

 c. keff  0.98 if moderated by aqueous foam, which includes an 

allowance for uncertainties as described in [Section 9.1 of the 

FSAR], and 

 d. A nominal [21.125] inch center to center distance between fuel 

assemblies placed in the storage racks. 

4.3.2 Drainage 

 The spent fuel storage pool is designed and shall be maintained to prevent 

inadvertent draining of the pool below elevation [138 ft 4 inches]. 

4.3.3 Capacity 

 The spent fuel storage pool is designed and shall be maintained with a storage 

capacity limited to no more than [1357] fuel assemblies [and six failed fuel 

containers]. 
Responsibility 

5.1

Babcock & Wilcox STS 5.1-1 Rev. 4.0 

5.0 ADMINISTRATIVE CONTROLS 

5.1 Responsibility 

 ----------------------------------------REVIEWER'S NOTE----------------------------------------

 Titles for members of the unit staff shall be specified by use of an overall 

statement referencing an ANSI Standard acceptable to the NRC staff from which 

the titles were obtained, or an alternative title may be designated for this position. 

Generally, the first method is preferable; however, the second method is 

adaptable to those unit staffs requiring special titles because of unique 

organizational structures. 

 The ANSI Standard shall be the same ANSI Standard referenced in Section 5.3, 

Unit Staff Qualifications. If alternative titles are used, all requirements of these 

Technical Specifications apply to the position with the alternative title as apply 

with the specified title. Unit staff titles shall be specified in the Final Safety 

Analysis Report or Quality Assurance Plan. Unit staff titles shall be maintained 

and revised using those procedures approved for modifying/revising the Final 

Safety Analysis Report or Quality Assurance Plan. 

 ------------------------------------------------------------------------------------------------------------

5.1.1 The plant manager shall be responsible for overall unit operation and shall 

delegate in writing the succession to this responsibility during his absence.

 The plant manager or his designee shall approve, prior to implementation, each 

proposed test, experiment or modification to systems or equipment that affect 

nuclear safety. 

5.1.2 The [Shift Supervisor (SS)] shall be responsible for the control room command 

function. During any absence of the [SS] from the control room while the unit is 

in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor Operator 

(SRO) license shall be designated to assume the control room command 

function. During any absence of the [SS] from the control room while the unit is 

in MODE 5 or 6, an individual with an active SRO license or Reactor Operator 

license shall be designated to assume the control room command function.

Organization 

5.2

Babcock & Wilcox STS 5.2-1 Rev. 4.0 

5.2 ADMINISTRATIVE CONTROLS 

5.2 Organization 

5.2.1 Onsite and Offsite Organizations 

 Onsite and offsite organizations shall be established for unit operation and 

corporate management, respectively. The onsite and offsite organizations shall 

include the positions for activities affecting safety of the nuclear power plant.

 a. Lines of authority, responsibility, and communication shall be defined and 

established throughout highest management levels, intermediate levels, 

and all operating organization positions. These relationships shall be 

documented and updated, as appropriate, in organization charts, functional 

descriptions of departmental responsibilities and relationships, and job 

descriptions for key personnel positions, or in equivalent forms of 

documentation. These requirements including the plant-specific titles of 

those personnel fulfilling the responsibilities of the positions delineated in 

these Technical Specifications shall be documented in the [FSAR/QA Plan], 

 b. The plant manager shall be responsible for overall safe operation of the 

plant and shall have control over those onsite activities necessary for safe 

operation and maintenance of the plant, 

 c. A specified corporate officer shall have corporate responsibility for overall 

plant nuclear safety and shall take any measures needed to ensure 

acceptable performance of the staff in operating, maintaining, and providing 

technical support to the plant to ensure nuclear safety, and 

 d. The individuals who train the operating staff, carry out health physics, or 

perform quality assurance functions may report to the appropriate onsite 

manager; however, these individuals shall have sufficient organizational 

freedom to ensure their independence from operating pressures. 

5.2.2 Unit Staff 

 The unit staff organization shall include the following: 

 a. A non-licensed operator shall be assigned to each reactor containing fuel 

and an additional non-licensed operator shall be assigned for each control 

room from which a reactor is operating in MODES 1, 2, 3, or 4. 

 ----------------------------------------REVIEWER'S NOTE---------------------------------------- 

 Two unit sites with both units shutdown or defueled require a total of three nonlicensed operators for the two units.

 ------------------------------------------------------------------------------------------------------------ 
Organization 

5.2

Babcock & Wilcox STS 5.2-2 Rev. 4.0 

5.2 Organization 

5.2.2 Unit Staff (continued) 

 b. Shift crew composition may be less than the minimum requirement of 

10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.e for a period of time not to 

exceed 2 hours in order to accommodate unexpected absence of on-duty 

shift crew members provided immediate action is taken to restore the shift 

crew composition to within the minimum requirements. 

 c. A radiation protection technician shall be on site when fuel is in the reactor. 

The position may be vacant for not more than 2 hours, in order to provide 

for unexpected absence, provided immediate action is taken to fill the 

required position. 

 d. The operations manager or assistant operations manager shall hold an 

SRO license. 

 e. An individual shall provide advisory technical support to the unit operations 

shift crew in the areas of thermal hydraulics, reactor engineering, and plant 

analysis with regard to the safe operation of the unit. This individual shall 

meet the qualifications specified by the Commission Policy Statement on 

Engineering Expertise on Shift. 
Unit Staff Qualifications 

5.3

Babcock & Wilcox STS 5.3-1 Rev. 4.0 

5.0 ADMINISTRATIVE CONTROLS 

5.3 Unit Staff Qualifications 

--------------------------------------------------REVIEWER'S NOTE------------------------------------------------- 

Minimum qualifications for members of the unit staff shall be specified by use of an overall 

qualification statement referencing an ANSI Standard acceptable to the NRC staff or by 

specifying individual position qualifications. Generally, the first method is preferable; however, 

the second method is adaptable to those unit staffs requiring special qualification statements 

because of unique organizational structures. 

-------------------------------------------------------------------------------------------------------------------------------

5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of 

[Regulatory Guide 1.8, Revision 2, 1987, or more recent revisions, or ANSI 

Standard acceptable to the NRC staff]. [The staff not covered by Regulatory 

Guide 1.8 shall meet or exceed the minimum qualifications of Regulations, 

Regulatory Guides, or ANSI Standards acceptable to NRC staff]. 

5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and 

a licensed Reactor Operator (RO) are those individuals who, in addition to 

meeting the requirements of TS 5.3.1, perform the functions described in 

10 CFR 50.54(m). 

Procedures 

5.4

Babcock & Wilcox STS 5.4-1 Rev. 4.0 

5.0 ADMINISTRATIVE CONTROLS 

5.4 Procedures 

5.4.1 Written procedures shall be established, implemented, and maintained covering 

the following activities: 

 a. The applicable procedures recommended in Regulatory Guide 1.33, 

Revision 2, Appendix A, February 1978,

 b. The emergency operating procedures required to implement the 

requirements of NUREG-0737 and to NUREG-0737, Supplement 1, as 

stated in [Generic Letter 82-33],

 c. Quality assurance for effluent and environmental monitoring, 

 d. Fire Protection Program implementation, and 

 e. All programs specified in Specification 5.5.

Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-1 Rev. 4.0 

5.0 ADMINISTRATIVE CONTROLS 

5.5 Programs and Manuals 

The following programs shall be established, implemented, and maintained. 

5.5.1 Offsite Dose Calculation Manual (ODCM) 

 a. The ODCM shall contain the methodology and parameters used in the 

calculation of offsite doses resulting from radioactive gaseous and liquid 

effluents, in the calculation of gaseous and liquid effluent monitoring alarm 

and trip setpoints, and in the conduct of the radiological environmental 

monitoring program, and 

 b. The ODCM shall also contain the radioactive effluent controls and 

radiological environmental monitoring activities, and descriptions of the 

information that should be included in the Annual Radiological 

Environmental Operating, and Radioactive Effluent Release Reports 

required by Specification [5.6.1] and Specification [5.6.2].

 Licensee initiated changes to the ODCM: 

 a. Shall be documented and records of reviews performed shall be retained. 

This documentation shall contain: 

 1. Sufficient information to support the change(s) together with the 

appropriate analyses or evaluations justifying the change(s) and 

 2. A determination that the change(s) maintain the levels of radioactive 

effluent control required by 10 CFR 20.1302, 40 CFR 190, 

10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely 

impact the accuracy or reliability of effluent, dose, or setpoint 

calculations, 

 b. Shall become effective after the approval of the plant manager, and 

 c. Shall be submitted to the NRC in the form of a complete, legible copy of the 

entire ODCM as a part of or concurrent with the Radioactive Effluent 

Release Report for the period of the report in which any change in the 

ODCM was made. Each change shall be identified by markings in the 

margin of the affected pages, clearly indicating the area of the page that 

was changed, and shall indicate the date (i.e., month and year) the change 

was implemented. 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-2 Rev. 4.0 

5.5 Programs and Manuals 

5.5.2 Primary Coolant Sources Outside Containment 

 This program provides controls to minimize leakage from those portions of 

systems outside containment that could contain highly radioactive fluids during a 

serious transient or accident to levels as low as practicable. The systems include 

[Low Pressure Injection, Reactor Building Spray, Makeup and Purification, and 

Hydrogen Recombiner]. The program shall include the following: 

 a. Preventive maintenance and periodic visual inspection requirements and 

 b. Integrated leak test requirements for each system at least once per [18] 

months. 

 The provisions of SR 3.0.2 are applicable.

[ 5.5.3 Post Accident Sampling 

 ------------------------------------REVIEWER’S NOTE-------------------------------------------- 

 This program may be eliminated based on the implementation of BAW-2387, 

"Justification for the Elimination of the Post Accident Sampling System From the 

Licensing Bases of Babcock and Wilcox-Designed Plants," the associated NRC 

Safety Evaluation, and implementation of the following commitments: 

1. [Licensee] [verified it has or is making a regulatory commitment to develop] 

contingency plans for obtaining and analyzing highly radioactive samples 

from the RCS, containment sump, and containment atmosphere. The 

contingency plans will be contained in [specified document or program] and 

implementation [is complete, will be completed with the implementation of 

the License amendment, or will be completed within x days (< 6 months) 

after the implementation of the License amendment]. Establishment and 

maintenance of contingency plans is considered a regulatory commitment. 

2. The capability for classifying fuel damage events at the Alert level threshold 

[has been or will be] established for [PLANT] at radioactivity levels of 

[300 mCi/cc dose equivalent iodine]. This capability will be described in 

[specified document or program] and implementation [is complete, will be 

completed with the implementation of the License amendment, or will be 

completed within x days (< 6 months) after the implementation of the 

License amendment]. The capability for classifying fuel damage events is 

considered a regulatory commitment. 

3. [Licensee] [verified that it has or is making a regulatory commitment to 

develop] an ability to assess radioactive iodines released to offsite 

environs. The capability for monitoring iodines will be maintained within the 

[specified document or program]. Implementation of this commitment [is 

complete, will be completed with the implementation of the License 

amendment, or will be completed within x days (< 6 months) after the 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-3 Rev. 4.0 

5.5 Programs and Manuals 

5.5.3 Post Accident Sampling (continued) 

 implementation of the License amendment]. The capability to monitor 

radioactive iodines is considered a regulatory commitment. 

 ------------------------------------------------------------------------------------------------------------

 This program provides controls that ensure the capability to obtain and analyze 

reactor coolant, radioactive gases, and particulates in plant gaseous effluents 

and containment atmosphere samples under accident conditions. The program 

shall include the following: 

 a. Training of personnel, 

 b. Procedures for sampling and analysis, and 

 c. Provisions for maintenance of sampling and analysis equipment. ] 

5.5.4 Radioactive Effluent Controls Program 

 This program conforms to 10 CFR 50.36a for the control of radioactive effluents 

and for maintaining the doses to members of the public from radioactive effluents 

as low as reasonably achievable. The program shall be contained in the ODCM, 

shall be implemented by procedures, and shall include remedial actions to be 

taken whenever the program limits are exceeded. The program shall include the 

following elements: 

 a. Limitations on the functional capability of radioactive liquid and gaseous 

monitoring instrumentation including surveillance tests and setpoint 

determination in accordance with the methodology in the ODCM, 

 b. Limitations on the concentrations of radioactive material released in liquid 

effluents to unrestricted areas, conforming to ten times the concentration 

values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402,

 c. Monitoring, sampling, and analysis of radioactive liquid and gaseous 

effluents in accordance with 10 CFR 20.1302 and with the methodology 

and parameters in the ODCM, 

 d. Limitations on the annual and quarterly doses or dose commitment to a 

member of the public from radioactive materials in liquid effluents released 

from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I,

 e. Determination of cumulative dose contributions from radioactive effluents 

for the current calendar quarter and current calendar year in accordance 

with the methodology and parameters in the ODCM at least every 31 days. 

Determination of projected dose contributions from radioactive effluents in 

accordance with the methodology in the ODCM at least every 31 days, 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-4 Rev. 4.0 

5.5 Programs and Manuals 

5.5.4 Radioactive Effluent Controls Program (continued) 

 f. Limitations on the functional capability and use of the liquid and gaseous 

effluent treatment systems to ensure that appropriate portions of these 

systems are used to reduce releases of radioactivity when the projected 

doses in a period of 31 days would exceed 2% of the guidelines for the 

annual dose or dose commitment, conforming to 10 CFR 50, Appendix I,

 g. Limitations on the dose rate resulting from radioactive material released in 

gaseous effluents from the site to areas at or beyond the site boundary 

shall be in accordance with the following: 

 1. For noble gases: a dose rate  500 mrem/yr to the whole body and a 

dose rate  3000 mrem/yr to the skin and 

 2. For iodine-131, iodine-133, tritium, and all radionuclides in particulate 

form with half-lives greater than 8 days: a dose rate  1500 mrem/yr 

to any organ, 

 h. Limitations on the annual and quarterly air doses resulting from noble 

gases released in gaseous effluents from each unit to areas beyond the 

site boundary, conforming to 10 CFR 50, Appendix I,

 i. Limitations on the annual and quarterly doses to a member of the public 

from iodine-131, iodine-133, tritium, and all radionuclides in particulate form 

with half lives > 8 days in gaseous effluents released from each unit to 

areas beyond the site boundary, conforming to 10 CFR 50, Appendix I, and

 j. Limitations on the annual dose or dose commitment to any member of the 

public, beyond the site boundary, due to releases of radioactivity and to 

radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

 The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive 

Effluent Controls Program surveillance frequency. 

5.5.5 Component Cyclic or Transient Limit 

 This program provides controls to track the FSAR, Section [ ], cyclic and 

transient occurrences to ensure that components are maintained within the 

design limits.

5.5.6 [ Pre-Stressed Concrete Containment Tendon Surveillance Program 

 This program provides controls for monitoring any tendon degradation in prestressed concrete containments, including effectiveness of its corrosion 

protection medium, to ensure containment structural integrity. The program shall 

include baseline measurements prior to initial operations. The Tendon 

Surveillance Program, inspection frequencies, and acceptance criteria shall be in
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-5 Rev. 4.0 

5.5 Programs and Manuals 

5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program (continued) 

 accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure 

Vessel Code and applicable addenda as required by 10 CFR50.55a, except 

where an alternative, exemption, or relief has been authorized by the NRC. 

 The provisions of SR 3.0.3 are applicable to the Tendon Surveillance Program 

inspection frequencies. ] 

5.5.7 Reactor Coolant Pump Flywheel Inspection Program 

 This program shall provide for the inspection of each reactor coolant pump 

flywheel per the recommendation of Regulatory position c.4.b of Regulatory 

Guide 1.14, Revision 1, August 1975.

5.5.8 Inservice Testing Program 

 This program provides controls for inservice testing of ASME Code Class 1, 2, 

and 3 components. The program shall include the following:

 a. Testing frequencies applicable to the ASME Code for Operations and 

Maintenance of Nuclear Power Plants (ASME OM Codes) and applicable 

Addenda as follows: 

ASME OM Code and applicable 

Addenda terminology for inservice 

testing activities

Required Frequencies for 

performing inservice testing 

activities

Weekly At least once per 7 days

Monthly At least once per 31 days

Quarterly or every 3 months At least once per 92 days

Semiannually or every 6 months At least once per 184 days

Every 9 months At least once per 276 days

Yearly or annually At least once per 366 days

Biennially or every 2 years At least once per 731 days

 b. The provisions of SR 3.0.2 are applicable to the above required 

Frequencies and to other normal and accelerated Frequencies specified as 

2 years or less in the Inservice Testing Program for performing inservice 

testing activities,

 c. The provisions of SR 3.0.3 are applicable to inservice testing activities, and

 d. Nothing in the ASME OM Code shall be construed to supersede the 

requirements of any TS. 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-6 Rev. 4.0 

5.5 Programs and Manuals 

5.5.9 Steam Generator (SG) Program 

A Steam Generator Program shall be established and implemented to ensure 

that SG tube integrity is maintained. In addition, the Steam Generator Program 

shall include the following provisions: 

 a. Provisions for condition monitoring assessments. Condition monitoring 

assessment means an evaluation of the "as found" condition of the tubing 

with respect to the performance criteria for structural integrity and accident 

induced leakage. The "as found" condition refers to the condition of the 

tubing during an SG inspection outage, as determined from the inservice 

inspection results or by other means, prior to the plugging [or repair] of 

tubes. Condition monitoring assessments shall be conducted during each 

outage during which the SG tubes are inspected, plugged, [or repaired] to 

confirm that the performance criteria are being met. 

 b. Performance criteria for SG tube integrity. SG tube integrity shall be 

maintained by meeting the performance criteria for tube structural integrity, 

accident induced leakage, and operational LEAKAGE. 

 1. Structural integrity performance criterion: All in-service steam 

generator tubes shall retain structural integrity over the full range of 

normal operating conditions (including startup, operation in the power 

range, hot standby, and cool down and all anticipated transients 

included in the design specification) and design basis accidents. This 

includes retaining a safety factor of 3.0 against burst under normal 

steady state full power operation primary-to-secondary pressure 

differential and a safety factor of 1.4 against burst applied to the 

design basis accident primary-to-secondary pressure differentials. 

Apart from the above requirements, additional loading conditions 

associated with the design basis accidents, or combination of 

accidents in accordance with the design and licensing basis, shall 

also be evaluated to determine if the associated loads contribute 

significantly to burst or collapse. In the assessment of tube integrity, 

those loads that do significantly affect burst or collapse shall be 

determined and assessed in combination with the loads due to 

pressure with a safety factor of 1.2 on the combined primary loads 

and 1.0 on axial secondary loads.

 2. Accident induced leakage performance criterion: The primary to 

secondary accident induced leakage rate for any design basis 

accident, other than a SG tube rupture, shall not exceed the leakage 

rate assumed in the accident analysis in terms of total leakage rate for 

all SGs and leakage rate for an individual SG. Leakage is not to 

exceed [1 gpm] per SG [, except for specific types of degradation at 

specific locations as described in paragraph c of the Steam Generator 

Program]. 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-7 Rev. 4.0 

5.5 Programs and Manuals 

5.5.9 Steam Generator (SG) Program (continued)

 3. The operational LEAKAGE performance criterion is specified in 

LCO 3.4.13, "RCS Operational LEAKAGE." 

 c. Provisions for SG tube repair criteria. Tubes found by inservice inspection 

to contain flaws with a depth equal to or exceeding [40%] of the nominal 

tube wall thickness shall be plugged [or repaired]. 

----------------------------------------REVIEWER'S NOTE----------------------------------------

Alternate tube repair criteria currently permitted by plant technical specifications 

are listed here. The description of these alternate tube repair criteria should be 

equivalent to the descriptions in current technical specifications and should also 

include any allowed accident induced leakage rates for specific types of 

degradation at specific locations associated with tube repair criteria. 

------------------------------------------------------------------------------------------------------------

[The following alternate tube repair criteria may be applied as an alternative to 

the 40% depth based criteria: 

 1. . . .]

 d. Provisions for SG tube inspections. Periodic SG tube inspections shall be 

performed. The number and portions of the tubes inspected and methods 

of inspection shall be performed with the objective of detecting flaws of any 

type (e.g., volumetric flaws, axial and circumferential cracks) that may be 

present along the length of the tube, from the tube-to-tubesheet weld at the 

tube inlet to the tube-to-tubesheet weld at the tube outlet, and that may 

satisfy the applicable tube repair criteria. The tube-to-tubesheet weld is not 

part of the tube. In addition to meeting the requirements of d.1, d.2, and 

d.3 below, the inspection scope, inspection methods, and inspection 

intervals shall be such as to ensure that SG tube integrity is maintained 

until the next SG inspection. An assessment of degradation shall be 

performed to determine the type and location of flaws to which the tubes 

may be susceptible and, based on this assessment, to determine which 

inspection methods need to be employed and at what locations. 

 -----------------------------------REVIEWER'S NOTE-------------------------------------

Plants are to include the appropriate Frequency (e.g., select the 

appropriate Item 2.) for their SG design. The first Item 2 is applicable to 

SGs with Alloy 600 mill annealed tubing. The second Item 2 is applicable 

to SGs with Alloy 600 thermally treated tubing. The third Item 2 is 

applicable to SGs with Alloy 690 thermally treated tubing.

 ----------------------------------------------------------------------------------------------------

 1. Inspect 100% of the tubes in each SG during the first refueling outage 

following SG replacement. 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-8 Rev. 4.0 

5.5 Programs and Manuals 

5.5.9 Steam Generator (SG) Program (continued)

 [2. Inspect 100% of the tubes at sequential periods of 60 effective full 

power months. The first sequential period shall be considered to 

begin after the first inservice inspection of the SGs. No SG shall 

operate for more than 24 effective full power months or one refueling 

outage (whichever is less) without being inspected.]

 [2. Inspect 100% of the tubes at sequential periods of 120, 90, and, 

thereafter, 60 effective full power months. The first sequential period 

shall be considered to begin after the first inservice inspection of the 

SGs. In addition, inspect 50% of the tubes by the refueling outage 

nearest the midpoint of the period and the remaining 50% by the 

refueling outage nearest the end of the period. No SG shall operate 

for more than 48 effective full power months or two refueling outages 

(whichever is less) without being inspected.]

 [2. Inspect 100% of the tubes at sequential periods of 144, 108, 72, and, 

thereafter, 60 effective full power months. The first sequential period 

shall be considered to begin after the first inservice inspection of the 

SGs. In addition, inspect 50% of the tubes by the refueling outage 

nearest the midpoint of the period and the remaining 50% by the 

refueling outage nearest the end of the period. No SG shall operate 

for more than 72 effective full power months or three refueling 

outages (whichever is less) without being inspected.] 

 3. If crack indications are found in any SG tube, then the next inspection 

for each SG for the degradation mechanism that caused the crack 

indication shall not exceed 24 effective full power months or one 

refueling outage (whichever is less). If definitive information, such as 

from examination of a pulled tube, diagnostic non-destructive testing, 

or engineering evaluation indicates that a crack-like indication is not 

associated with a crack(s), then the indication need not be treated as 

a crack. 

 e. Provisions for monitoring operational primary to secondary LEAKAGE. 

 [f. Provisions for SG tube repair methods. Steam generator tube repair 

methods shall provide the means to reestablish the RCS pressure 

boundary integrity of SG tubes without removing the tube from service. For 

the purposes of these Specifications, tube plugging is not a repair. All 

acceptable tube repair methods are listed below. 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-9 Rev. 4.0 

5.5 Programs and Manuals 

5.5.9 Steam Generator (SG) Program (continued)

 ----------------------------------------REVIEWER'S NOTE----------------------------------------

Tube repair methods currently permitted by plant technical specifications are to 

be listed here. The description of these tube repair methods should be 

equivalent to the descriptions in current technical specifications. If there are no 

approved tube repair methods, this section should not be used. 

 ------------------------------------------------------------------------------------------------------------

 1. . . .]

5.5.10 Secondary Water Chemistry Program 

 This program provides controls for monitoring secondary water chemistry to 

inhibit SG tube degradation and low pressure turbine disc stress corrosion 

cracking. The program shall include:

 a. Identification of a sampling schedule for the critical variables and control 

points for these variables,

 b. Identification of the procedures used to measure the values of the critical 

variables, 

 c. Identification of process sampling points, which shall include monitoring the 

discharge of the condensate pumps for evidence of condenser in leakage, 

 d. Procedures for the recording and management of data, 

 e. Procedures defining corrective actions for all off control point chemistry 

conditions, and 

 f. A procedure identifying the authority responsible for the interpretation of the 

data and the sequence and timing of administrative events, which is 

required to initiate corrective action. 

5.5.11 Ventilation Filter Testing Program (VFTP) 

 A program shall be established to implement the following required testing of 

Engineered Safety Feature (ESF) filter ventilation systems at the frequencies 

specified in [Regulatory Guide], and in accordance with [Regulatory Guide 1.52, 

Revision 2, ASME N510-1989, and AG-1].

 a. Demonstrate for each of the ESF systems that an inplace test of the high 

efficiency particulate air (HEPA) filters shows a penetration and system 

bypass < [0.05]% when tested in accordance with [Regulatory Guide 1.52, 

Revision 2, and ASME N510-1989] at the system flowrate specified below 

[± 10%].
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-10 Rev. 4.0 

5.5 Programs and Manuals 

5.5.11 Ventilation Filter Testing Program (continued) 

ESF Ventilation System Flowrate 

[ ] [ ]

 b. Demonstrate for each of the ESF systems that an inplace test of the 

charcoal adsorber shows a penetration and system bypass < [0.05]% when 

tested in accordance with [Regulatory Guide 1.52, Revision 2, and 

ASME N510-1989] at the system flowrate specified below [± 10%].

ESF Ventilation System Flowrate 

[ ] [ ]

 c. Demonstrate for each of the ESF systems that a laboratory test of a sample 

of the charcoal adsorber, when obtained as described in [Regulatory 

Guide 1.52, Revision 2], shows the methyl iodide penetration less than the 

value specified below when tested in accordance with ASTM D3803-1989 

at a temperature of 30C (86F) and the relative humidity specified below.

ESF Ventilation System Penetration RH Face Velocity

[ ] [See Reviewer's [See [See Reviewer's 

Note] Reviewer's Note] 

Note]

 ----------------------------------------REVIEWER'S NOTE----------------------------------------

 The use of any standard other than ASTM D3803-1989 to test the charcoal 

sample may result in an overestimation of the capability of the charcoal to adsorb 

radioiodine. As a result, the ability of the charcoal filters to perform in a manner 

consistent with the licensing basis for the facility is indeterminate. 

 ASTM D 3803-1989 is a more stringent testing standard because it does not 

differentiate between used and new charcoal, it has a longer equilibration period 

performed at a temperature of 30C (86F) and a relative humidity (RH) of 95% 

(or 70% RH with humidity control), and it has more stringent tolerances that 

improve repeatability of the test. 

 Allowable Penetration = [(100% - Methyl Iodide Efficiently * for Charcoal Credited 

in Licensee's Accident Analysis) / Safety Factor] 

 When ASTM D3803-1989 is used with 30C (86F) and 95% RH (or 70% RH 

with humidity control) is used, the staff will accept the following: 

 Safety factor  2 for systems with or without humidity control. 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-11 Rev. 4.0 

5.5 Programs and Manuals 

5.5.11 Ventilation Filter Testing Program (continued) 

 Humidity control can be provided by heaters or an NRC-approved analysis that 

demonstrates that the air entering the charcoal will be maintained less than or 

equal to 70 percent RH under worst-case design-basis conditions. 

 If the system has a face velocity greater than 110 percent of 0.203 m/s 

(40 ft/min), the face velocity should be specified. 

 *This value should be the efficiency that was incorporated in the licensee's 

accident analysis which was reviewed and approved by the staff in a safety 

evaluation. 

 ------------------------------------------------------------------------------------------------------------

 d. Demonstrate for each of the ESF systems that the pressure drop across 

the combined HEPA filters, the prefilters, and the charcoal adsorbers is less 

than the value specified below when tested in accordance with [Regulatory 

Guide 1.52, Revision 2, and ASME N510-1989] at the system flowrate 

specified below [± 10%].

ESF Ventilation System Delta P Flowrate 

[ ] [ ] [ ]

 [ e. Demonstrate that the heaters for each of the ESF systems dissipate the 

value specified below [± 10%] when tested in accordance with 

[ASME N510-1989].

ESF Ventilation System Wattage ] 

[ ] [ ] 

 The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test 

frequencies.

5.5.12 [ Explosive Gas and Storage Tank Radioactivity Monitoring Program 

 This program provides controls for potentially explosive gas mixtures contained 

in the [Waste Gas Holdup System], [the quantity of radioactivity contained in gas 

storage tanks or fed into the offgas treatment system, and the quantity of 

radioactivity contained in unprotected outdoor liquid storage tanks]. The gaseous 

radioactivity quantities shall be determined following the methodology in [Branch 

Technical Position (BTP) ETSB 11-5, "Postulated Radioactive Release due to 

Waste Gas System Leak or Failure"]. The liquid radwaste quantities shall be 

determined in accordance with [Standard Review Plan, Section 15.7.3, 

"Postulated Radioactive Release due to Tank Failures"].
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-12 Rev. 4.0 

5.5 Programs and Manuals 

5.5.12 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued)

 The program shall include:

 a. The limits for concentrations of hydrogen and oxygen in the [Waste Gas 

Holdup System] and a surveillance program to ensure the limits are 

maintained. Such limits shall be appropriate to the system's design criteria 

(i.e., whether or not the system is designed to withstand a hydrogen 

explosion), 

 b. A surveillance program to ensure that the quantity of radioactivity contained 

in [each gas storage tank and fed into the offgas treatment system] is less 

than the amount that would result in a whole body exposure of  0.5 rem to 

any individual in an unrestricted area, in the event of [an uncontrolled 

release of the tanks' contents], and 

 c. A surveillance program to ensure that the quantity of radioactivity contained 

in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, 

or walls, capable of holding the tanks' contents and that do not have tank 

overflows and surrounding area drains connected to the [Liquid Radwaste 

Treatment System] is less than the amount that would result in 

concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, 

Column 2, at the nearest potable water supply and the nearest surface 

water supply in an unrestricted area, in the event of an uncontrolled release 

of the tanks' contents.

 The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and 

Storage Tank Radioactivity Monitoring Program surveillance frequencies. ] 

5.5.13 Diesel Fuel Oil Testing Program 

 A diesel fuel oil testing program to implement required testing of both new fuel oil 

and stored fuel oil shall be established. The program shall include sampling and 

testing requirements, and acceptance criteria, all in accordance with applicable 

ASTM Standards. The purpose of the program is to establish the following: 

 a. Acceptability of new fuel oil for use prior to addition to storage tanks by 

determining that the fuel oil has: 

 1. An API gravity or an absolute specific gravity within limits, 

 2. A flash point and kinematic viscosity within limits for ASTM 2D fuel oil, 

and

 3. A clear and bright appearance with proper color or a water and 

sediment content within limits, 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-13 Rev. 4.0 

5.5 Programs and Manuals 

5.5.13 Diesel Fuel Oil Testing Program (continued) 

 b. Within 31 days following addition of the new fuel oil to storage tanks, verify 

that the properties of the new fuel oil, other than those addressed in a., 

above, are within limits for ASTM 2D fuel oil, and 

 c. Total particulate concentration of the fuel oil is  10 mg/l when tested every 

31 days. 

 The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil 

Testing Program testing frequencies. 

5.5.14 Technical Specifications (TS) Bases Control Program 

 This program provides a means for processing changes to the Bases of these 

Technical Specifications. 

 a. Changes to the Bases of the TS shall be made under appropriate 

administrative controls and reviews. 

 b. Licensees may make changes to Bases without prior NRC approval 

provided the changes do not require either of the following: 

 1. A change in the TS incorporated in the license or 

 2. A change to the updated FSAR or Bases that requires NRC approval 

pursuant to 10 CFR 50.59.

 c. The Bases Control Program shall contain provisions to ensure that the 

Bases are maintained consistent with the FSAR. 

 d. Proposed changes that meet the criteria of 5.5.14b above shall be reviewed 

and approved by the NRC prior to implementation. Changes to the Bases 

implemented without prior NRC approval shall be provided to the NRC on a 

frequency consistent with 10 CFR 50.71(e). 

5.5.15 Safety Function Determination Program (SFDP) 

 This program ensures loss of safety function is detected and appropriate actions 

taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if 

loss of safety function exists. Additionally, other appropriate limitations and 

remedial or compensatory actions may be identified to be taken as a result of the 

support system inoperability and corresponding exception to entering supported 

system Condition and Required Actions. This program implements the 

requirements of LCO 3.0.6. The SFDP shall contain the following:
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-14 Rev. 4.0 

5.5 Programs and Manuals 

5.5.15 Safety Function Determination Program (continued)

 a. Provisions for cross train checks to ensure a loss of the capability to 

perform the safety function assumed in the accident analysis does not go 

undetected, 

 b. Provisions for ensuring the plant is maintained in a safe condition if a loss 

of function condition exists, 

 c. Provisions to ensure that an inoperable supported system's Completion 

Time is not inappropriately extended as a result of multiple support system 

inoperabilities, and 

 d. Other appropriate limitations and remedial or compensatory actions. 

 A loss of safety function exists when, assuming no concurrent single failure, no 

concurrent loss of offsite power, or no concurrent loss of onsite diesel 

generator(s), a safety function assumed in the accident analysis cannot be 

performed. For the purpose of this program, a loss of safety function may exist 

when a support system is inoperable, and

 a. A required system redundant to the system(s) supported by the inoperable 

support system is also inoperable, or 

 b. A required system redundant to the system(s) in turn supported by the 

inoperable supported system is also inoperable, or 

 c. A required system redundant to the support system(s) for the supported 

systems (a) and (b) above is also inoperable. 

 The SFDP identifies where a loss of safety function exists. If a loss of safety 

function is determined to exist by this program, the appropriate Conditions and 

Required Actions of the LCO in which the loss of safety function exists are 

required to be entered. When a loss of safety function is caused by the 

inoperability of a single Technical Specification support system, the appropriate 

Conditions and Required Actions to enter are those of the support system. 

5.5.16 Containment Leakage Rate Testing Program 

 [OPTION A] 

 a. A program shall establish the leakage rate testing of the containment as 

required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option A, as 

modified by approved exemptions.

 b. The maximum allowable containment leakage rate, La, at Pa, shall be [ ]% 

of containment air weight per day. 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-15 Rev. 4.0 

5.5 Programs and Manuals 

5.5.16 Containment Leakage Rate Testing Program (continued)

 c. Leakage rate acceptance criteria are: 

 1. Containment leakage rate acceptance criterion is  1.0 La. During the 

first unit startup following testing in accordance with this program, the 

leakage rate acceptance criteria are < 0.60 La for the Type B and C 

tests and < 0.75 La for Type A tests. 

 2. Air lock testing acceptance criteria are: 

 a) Overall air lock leakage rate is  [0.05 La] when tested at  Pa. 

 b) For each door, leakage rate is  [0.01 La] when pressurized to 

[ 10 psig]. 

 d. The provisions of SR 3.0.3 are applicable to the Containment Leakage 

Rate Testing Program. 

 e. Nothing in these Technical Specifications shall be construed to modify the 

testing Frequencies required by 10 CFR 50, Appendix J.

 [OPTION B] 

 a. A program shall establish the leakage rate testing of the containment as 

required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as 

modified by approved exemptions. This program shall be in accordance 

with the guidelines contained in Regulatory Guide 1.163, "PerformanceBased Containment Leak-Test Program," dated September, 1995, as 

modified by the following exceptions: 

 1. The visual examination of containment concrete surfaces intended to 

fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, 

will be performed in accordance with the requirements of and 

frequency specified by the ASME Section XI Code, Subsection IWL, 

except where relief has been authorized by the NRC. 

 2. The visual examination of the steel liner plate inside containment 

intended to fulfill the requirements of 10 CFR50, Appendix J, 

Option B, will be performed in accordance with the requirements of 

and frequency specified by the ASME Section XI Code, 

Subsection IWE, except where relief has been authorized by the 

NRC.

 [ 3. . . . ]
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-16 Rev. 4.0 

5.5 Programs and Manuals 

5.5.16 Containment Leakage Rate Testing Program (continued)

 b. The calculated peak containment internal pressure for the design basis loss 

of coolant accident, Pa, is [45 psig]. The containment design pressure is 

[50 psig]. 

 c. The maximum allowable containment leakage rate, La, at Pa, shall be [ ]% 

of containment air weight per day. 

 d. Leakage rate acceptance criteria are: 

 1. Containment leakage rate acceptance criterion is  1.0 La. During the 

first unit startup following testing in accordance with this program, the 

leakage rate acceptance criteria are < 0.60 La for the Type B and C 

tests and  0.75 La for Type A tests. 

 2. Air lock testing acceptance criteria are: 

 a) Overall air lock leakage rate is  [0.05 La] when tested at  Pa. 

 b) For each door, leakage rate is  [0.01 La] when pressurized to 

[ 10 psig]. 

 e. The provisions of SR 3.0.3 are applicable to the Containment Leakage 

Rate Testing Program. 

 f. Nothing in these Technical Specifications shall be construed to modify the 

testing Frequencies required by 10 CFR 50, Appendix J.

 [OPTION A/B Combined] 

 a. A program shall establish the leakage rate testing of the containment as 

required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J. [Type A][Type B 

and C] test requirements are in accordance with 10 CFR 50, Appendix J, 

Option A, as modified by approved exemptions. [Type B and C][Type A] 

test requirements are in accordance with 10 CFR 50, Appendix J, Option B, 

as modified by approved exemptions. The 10 CFR 50, Appendix J, 

Option B test requirements shall be in accordance with the guidelines 

contained in Regulatory Guide 1.163, "Performance-Based Containment 

Leak-Test Program," dated September, 1995, as modified by the following 

exceptions: 

 1. The visual examination of containment concrete surfaces intended to 

fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, 

will be performed in accordance with the requirements of and 

frequency specified by the ASME Section XI Code, Subsection IWL, 

except where relief has been authorized by the NRC. 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-17 Rev. 4.0 

5.5 Programs and Manuals 

5.5.16 Containment Leakage Rate Testing Program (continued)

 2. The visual examination of the steel liner plate inside containment 

intended to fulfill the requirements of 10 CFR50, Appendix J, 

Option B, will be performed in accordance with the requirements of 

and frequency specified by the ASME Section XI Code, 

Subsection IWE, except where relief has been authorized by the 

NRC.

 [ 3. . . . ]

 b. The calculated peak containment internal pressure for the design basis loss 

of coolant accident, Pa, is [45 psig]. The containment design pressure is 

[50 psig]. 

 c. The maximum allowable containment leakage rate, La, at Pa, shall be [ ]% 

of containment air weight per day. 

 d. Leakage rate acceptance criteria are: 

 1. Containment leakage rate acceptance criterion is  1.0 La. During the 

first unit startup following testing in accordance with this program, the 

leakage rate acceptance criteria are < 0.60 La for the Type B and C 

tests and [< 0.75 La for Option A Type A tests] [ 0.75 La for Option B 

Type A tests]. 

 2. Air lock testing acceptance criteria are: 

 a) Overall air lock leakage rate is  [0.05 La] when tested at  Pa. 

 b) For each door, leakage rate is  [0.01 La] when pressurized to 

[ 10 psig]. 

 e. The provisions of SR 3.0.3 are applicable to the Containment Leakage 

Rate Testing Program. 

 f. Nothing in these Technical Specifications shall be construed to modify the 

testing Frequencies required by 10 CFR 50, Appendix J 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-18 Rev. 4.0 

5.5 Programs and Manuals 

5.5.17 Battery Monitoring and Maintenance Program 

 --------------------------------------REVIEWER’S NOTE------------------------------------------

 This program and the corresponding requirements in LCO 3.8.4, LCO 3.8.5, and 

LCO 3.8.6 require providing the information and verifications requested in the 

Notice of Availability for TSTF-500, Revision 2, "DC Electrical Rewrite - Update to 

TSTF-360," (76FR54510). 

 ------------------------------------------------------------------------------------------------------------

This Program provides controls for battery restoration and maintenance. The 

program shall be in accordance with IEEE Standard (Std) 450-2002, "IEEE 

Recommended Practice for Maintenance, Testing, and Replacement of Vented 

Lead-Acid Batteries for Stationary Applications," as endorsed by Regulatory 

Guide 1.129, Revision 2 (RG), with RG exceptions and program provisions as 

identified below: 

 a. The program allows the following RG 1.129, Revision 2 exceptions: 

 1. Battery temperature correction may be performed before or after 

conducting discharge tests. 

 2. RG 1.129, Regulatory Position 1, Subsection 2, "References," is not 

applicable to this program. 

 3. In lieu of RG 1.129, Regulatory Position 2, Subsection 5.2, 

"Inspections," the following shall be used: "Where reference is made 

to the pilot cell, pilot cell selection shall be based on the lowest 

voltage cell in the battery." 

 4 In Regulatory Guide 1.129, Regulatory Position 3, Subsection 5.4.1, 

"State of Charge Indicator," the following statements in paragraph (d) 

may be omitted: "When it has been recorded that the charging 

current has stabilized at the charging voltage for three consecutive 

hourly measurements, the battery is near full charge. These 

measurements shall be made after the initially high charging current 

decreases sharply and the battery voltage rises to approach the 

charger output voltage." 

 5. In lieu of RG 1.129, Regulatory Position 7, Subsection 7.6,

"Restoration", the following may be used: "Following the test, record 

the float voltage of each cell of the string." 

 b. The program shall include the following provisions: 

 1. Actions to restore battery cells with float voltage < [2.13] V; 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-19 Rev. 4.0 

5.5 Programs and Manuals 

5.5.17 Battery Monitoring and Maintenance Program (continued) 

 2. Actions to determine whether the float voltage of the remaining 

battery cells is ≥ [2.13] V when the float voltage of a battery cell has 

been found to be < [2.13] V;

 3. Actions to equalize and test battery cells that had been discovered 

with electrolyte level below the top of the plates; 

 4. Limits on average electrolyte temperature, battery connection 

resistance, and battery terminal voltage; and 

 5. A requirement to obtain specific gravity readings of all cells at each 

discharge test, consistent with manufacturer recommendations. 

5.5.18 Control Room Envelope (CRE) Habitability Program 

A Control Room Envelope (CRE) Habitability Program shall be established and 

implemented to ensure that CRE habitability is maintained such that, with an 

OPERABLE Control Room Emergency Air Cleanup System (CREACS), CRE 

occupants can control the reactor safely under normal conditions and maintain it 

in a safe condition following a radiological event, hazardous chemical release, or 

a smoke challenge. The program shall ensure that adequate radiation protection 

is provided to permit access and occupancy of the CRE under design basis 

accident (DBA) conditions without personnel receiving radiation exposures in 

excess of [5 rem whole body or its equivalent to any part of the body] [5 rem total 

effective dose equivalent (TEDE)] for the duration of the accident. The program 

shall include the following elements: 

 a. The definition of the CRE and the CRE boundary.

 b. Requirements for maintaining the CRE boundary in its design condition 

including configuration control and preventive maintenance. 

 c. Requirements for (i) determining the unfiltered air inleakage past the CRE 

boundary into the CRE in accordance with the testing methods and at the 

Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, 

"Demonstrating Control Room Envelope Integrity at Nuclear Power 

Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the 

Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, 

Revision 0. 

 [The following are exceptions to Sections C.1 and C.2 of Regulatory 

Guide 1.197, Revision 0:

 1. ;and]
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-20 Rev. 4.0 

5.5 Programs and Manuals 

5.5.18 Control Room Envelope (CRE) Habitability Program (continued) 

 d. Measurement, at designated locations, of the CRE pressure relative to all 

external areas adjacent to the CRE boundary during the pressurization 

mode of operation by one train of the CREACS, operating at the flow rate 

required by the VFTP, at a Frequency of [18] months on a STAGGERED 

TEST BASIS. The results shall be trended and used as part of the 

[18] month assessment of the CRE boundary. 

 e. The quantitative limits on unfiltered air inleakage into the CRE. These 

limits shall be stated in a manner to allow direct comparison to the 

unfiltered air inleakage measured by the testing described in paragraph c. 

The unfiltered air inleakage limit for radiological challenges is the inleakage 

flow rate assumed in the licensing basis analyses of DBA consequences. 

Unfiltered air inleakage limits for hazardous chemicals must ensure that 

exposure of CRE occupants to these hazards will be within the 

assumptions in the licensing basis. 

 f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing 

CRE habitability, determining CRE unfiltered inleakage, and measuring 

CRE pressure and assessing the CRE boundary as required by 

paragraphs c and d, respectively. 

5.5.19 [ Setpoint Control Program 

 This program shall establish the requirements for ensuring that setpoints for 

automatic protective devices are initially within and remain within the 

assumptions of the applicable safety analyses, provides a means for processing 

changes to instrumentation setpoints, and identifies setpoint methodologies to 

ensure instrumentation will function as required. The program shall ensure that 

testing of automatic protective devices related to variables having significant 

safety functions as delineated by 10 CFR 50.36(c)(1)(ii)(A) verifies that 

instrumentation will function as required. 

 a. The program shall list the Functions in the following specifications to which 

it applies: 

 1. LCO 3.3.1, “Reactor Protection System (RPS) Instrumentation;” 

 2. LCO 3.3.3, “Reactor Protection System (RPS) - Reactor Trip Module 

(RTM);” 

 3. LCO 3.3.4, “CONTROL ROD Drive (CRD) Trip Devices;” 

 4. LCO 3.3.5, “Engineered Safety Feature Actuation System (ESFAS) 

Instrumentation;” 

 5. LCO 3.3.8, “Emergency Diesel Generator (EDG) Loss of Power Start 

(LOPS);” 

 6. LCO 3.3.9, “Source Range Neutron Flux;” 

 7. LCO 3.3.10, “Intermediate Range Neutron Flux;” 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-21 Rev. 4.0 

5.5 Programs and Manuals 

5.5.19 Setpoint Control Program (continued) 

 8. LCO 3.3.11, “Emergency Feedwater Initiation and Control (EFIC) 

System Instrumentation;” 

 9. LCO 3.3.15, “Reactor Building (RB) Purge Isolation - High Radiation;” 

 10. LCO 3.3.16, “Control Room Isolation - High Radiation.” 

 b. The program shall require the [Limiting Trip Setpoint (LTSP)], [Nominal Trip 

Setpoint (NTSP)], Allowable Value (AV), As-Found Tolerance (AFT), and 

As-Left Tolerance (ALT) (as applicable) of the Functions described in 

paragraph a. are calculated using the NRC approved setpoint methodology, 

as listed below. In addition, the program shall contain the value of the 

[LTSP], [NTSP], AV, AFT, and ALT (as applicable) for each Function 

described in paragraph a. and shall identify the setpoint methodology used 

to calculate these values. 

 -------------------------------------- Reviewer's Note ---------------------------------------

 List the NRC safety evaluation report by letter, date, and ADAMS accession 

number (if available) that approved the setpoint methodologies. 

 ----------------------------------------------------------------------------------------------------

 1. [Insert reference to NRC safety evaluation that approved the setpoint 

methodology.] 

 c. The program shall establish methods to ensure that Functions described in 

paragraph a. will function as required by verifying the as-left and as-found 

settings are consistent with those established by the setpoint methodology. 

 d. -----------------------------------REVIEWER’S NOTE-------------------------------------

 A license amendment request to implement a Setpoint Control Program 

must list the instrument functions to which the program requirements of 

paragraph d. will be applied. Paragraph d. shall apply to all Functions in 

the Reactor Protection System and Engineered Safety Feature Actuation 

System specifications unless one or more of the following exclusions apply: 

 1. Manual actuation circuits, automatic actuation logic circuits or to 

instrument functions that derive input from contacts which have no 

associated sensor or adjustable device, e.g., limit switches, breaker 

position switches, manual actuation switches, float switches, proximity 

detectors, etc. are excluded. In addition, those permissives and 

interlocks that derive input from a sensor or adjustable device that is 

tested as part of another TS function are excluded. 

 2. Settings associated with safety relief valves are excluded. The 

performance of these components is already controlled (i.e., trended 

with as-left and as-found limits) under the ASME Code for Operation 

and Maintenance of Nuclear Power Plants testing program. 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-22 Rev. 4.0 

5.5 Programs and Manuals 

5.5.19 Setpoint Control Program (continued) 

 3. Functions and Surveillance Requirements which test only digital 

components are normally excluded. There is no expected change in 

result between SR performances for these components. Where 

separate as-left and as-found tolerance is established for digital 

component SRs, the requirements would apply. 

 ----------------------------------------------------------------------------------------------------

 The program shall identify the Functions described in paragraph a. that are 

automatic protective devices related to variables having significant safety 

functions as delineated by 10 CFR 50.36(c)(1)(ii)(A). The [LTSP] of these 

Functions are Limiting Safety System Settings. These Functions shall be 

demonstrated to be functioning as required by applying the following 

requirements during CHANNEL CALIBRATIONS and CHANNEL 

FUNCTIONAL TESTS that verify the [LTSP or NTSP]. 

 1 The as-found value of the instrument channel trip setting shall be 

compared with the previous as-left value or the specified [LTSP or 

NTSP]. 

 2. If the as-found value of the instrument channel trip setting differs from 

the previous as-left value or the specified [LTSP or NTSP] by more 

than the pre-defined test acceptance criteria band (i.e., the specified 

AFT), then the instrument channel shall be evaluated before declaring 

the SR met and returning the instrument channel to service. This 

condition shall be entered in the plant corrective action program. 

 3. If the as-found value of the instrument channel trip setting is less 

conservative than the specified AV, then the SR is not met and the 

instrument channel shall be immediately declared inoperable. 

 4. The instrument channel setpoint shall be reset to a value that is within 

the as-left tolerance around the [LTSP or NTSP] at the completion of 

the surveillance test; otherwise, the channel is inoperable (setpoints 

may be more conservative than the [LTSP or NTSP] provided that the 

as-found and as-left tolerances apply to the actual setpoint used to 

confirm channel performance). 

 e. The program shall be specified in [insert the facility FSAR reference or the 

name of any document incorporated into the facility FSAR by reference]. ] 
Programs and Manuals 

5.5

Babcock & Wilcox STS 5.5-23 Rev. 4.0 

5.5 Programs and Manuals 

5.5.20 [ Surveillance Frequency Control Program 

 This program provides controls for Surveillance Frequencies. The program shall 

ensure that Surveillance Requirements specified in the Technical Specifications 

are performed at intervals sufficient to assure the associated Limiting Conditions 

for Operation are met.

 a. The Surveillance Frequency Control Program shall contain a list of 

Frequencies of those Surveillance Requirements for which the Frequency 

is controlled by the program. 

 b. Changes to the Frequencies listed in the Surveillance Frequency Control 

Program shall be made in accordance with NEI 04-10, "Risk-Informed 

Method for Control of Surveillance Frequencies," Revision 1. 

 c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable 

to the Frequencies established in the Surveillance Frequency Control 

Program. ] 

Reporting Requirements 

5.6

Babcock & Wilcox STS 5.6-1 Rev. 4.0 

5.0 ADMINISTRATIVE CONTROLS 

5.6 Reporting Requirements 

The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Annual Radiological Environmental Operating Report 

 --------------------------------------------------NOTE------------------------------------------------- 

 [ A single submittal may be made for a multiple unit station. The submittal should 

combine sections common to all units at the station. ] 

 ------------------------------------------------------------------------------------------------------------

 The Annual Radiological Environmental Operating Report covering the operation 

of the unit during the previous calendar year shall be submitted by May 15 of 

each year. The report shall include summaries, interpretations, and analyses of 

trends of the results of the Radiological Environmental Monitoring Program for 

the reporting period. The material provided shall be consistent with the 

objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 

10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. 

 The Annual Radiological Environmental Operating Report shall include the 

results of analyses of all radiological environmental samples and of all 

environmental radiation measurements taken during the period pursuant to the 

locations specified in the table and figures in the ODCM, as well as summarized 

and tabulated results of these analyses and measurements [in the format of the 

table in the Radiological Assessment Branch Technical Position, Revision 1, 

November 1979]. In the event that some individual results are not available for 

inclusion with the report, the report shall be submitted noting and explaining the 

reasons for the missing results. The missing data shall be submitted in a 

supplementary report as soon as possible. 

5.6.2 Radiological Effluent Release Report 

 --------------------------------------------------NOTE------------------------------------------------- 

 [ A single submittal may be made for a multiple unit station. The submittal shall 

combine sections common to all units at the station; however, for units with 

separate radwaste systems, the submittal shall specify the releases of 

radioactive material from each unit. ] 

 ------------------------------------------------------------------------------------------------------------

 The Radioactive Effluent Release Report covering the operation of the unit in the 

previous year shall be submitted prior to May 1 of each year in accordance with 

10 CFR 50.36a. The report shall include a summary of the quantities of 

radioactive liquid and gaseous effluents and solid waste released from the unit. 

The material provided shall be consistent with the objectives outlined in the 

ODCM and Process Control Program and in conformance with 10 CFR 50.36a 

and 10 CFR Part 50, Appendix I, Section IV.B.1. 
Reporting Requirements 

5.6

Babcock & Wilcox STS 5.6-2 Rev. 4.0 

5.6 Reporting Requirements 

5.6.3 CORE OPERATING LIMITS REPORT (COLR) 

 a. Core operating limits shall be established prior to each reload cycle, or prior 

to any remaining portion of a reload cycle, and shall be documented in the 

COLR for the following: 

[ The individual specifications that address core operating limits must be 

referenced here. ] 

 b. The analytical methods used to determine the core operating limits shall be 

those previously reviewed and approved by the NRC, specifically those 

described in the following documents: 

--------------------------------REVIEWER’S NOTE---------------------------------------- 

Licensees that have received prior NRC approval to relocate Topical Report 

revision numbers and dates to licensee control need only list the number 

and title of the Topical Report, and the COLR will contain the complete 

identification for each of the Technical Specification referenced Topical 

Reports used to prepare the COLR (i.e., report number, title, revision, date, 

and any supplements). See NRC ADAMS Accession No: ML110660285 

for details. 

----------------------------------------------------------------------------------------------------

 [ Identify the Topical Report(s) by number, title, date, and NRC staff 

approval document or identify the staff Safety Evaluation Report for a plant 

specific methodology by NRC letter and date. ]

 c. The core operating limits shall be determined such that all applicable limits 

(e.g., fuel thermal mechanical limits, core thermal hydraulic limits, 

Emergency Core Cooling System (ECCS) limits, nuclear limits such as 

SDM, transient analysis limits, and accident analysis limits) of the safety 

analysis are met. 

 d. The COLR, including any midcycle revisions or supplements, shall be 

provided upon issuance for each reload cycle to the NRC. 

5.6.4 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS 

REPORT 

 a. RCS pressure and temperature limits for heat up, cooldown, low 

temperature operation, criticality, and hydrostatic testing as well as heatup 

and cooldown rates shall be established and documented in the PTLR for 

the following: 

 [ The individual specifications that address RCS pressure and temperature 

limits must be referenced here. ] 
Reporting Requirements 

5.6

Babcock & Wilcox STS 5.6-3 Rev. 4.0 

5.6 Reporting Requirements 

5.6.4 RCS PRESSURE AND TEMPERATURE LIMITS REPORT (continued) 

 b. The analytical methods used to determine the RCS pressure and 

temperature limits shall be those previously reviewed and approved by the 

NRC, specifically those described in the following documents: 

--------------------------------REVIEWER’S NOTE---------------------------------------- 

Licensees that have received prior NRC approval to relocate Topical Report 

revision numbers and dates to licensee control need only list the number 

and title of the Topical Report, and the PTLR will contain the complete 

identification for each of the Technical Specification referenced Topical 

Reports used to prepare the PTLR (i.e., report number, title, revision, date, 

and any supplements). See NRC ADAMS Accession No: ML110660285 

for details. 

----------------------------------------------------------------------------------------------------

 [ Identify the NRC staff approval document by date. ]

 c. The PTLR shall be provided to the NRC upon issuance for each reactor 

vessel fluence period and for any revision or supplement thereto. 

 ----------------------------------------REVIEWER'S NOTE----------------------------------------

 The methodology for the calculation of the P-T limits for NRC approval should 

include the following provisions:

 1. The methodology shall describe how the neutron fluence is calculated 

(reference new Regulatory Guide when issued). 

 2. The Reactor Vessel Material Surveillance Program shall comply with 

Appendix H to 10 CFR 50. The reactor vessel material irradiation 

surveillance specimen removal schedule shall be provided, along with how 

the specimen examinations shall be used to update the PTLR curves. 

 3. Low Temperature Overpressure Protection (LTOP) System lift setting limits 

for the Power Operated Relief Valves (PORVs), developed using NRCapproved methodologies may be included in the PTLR. 

 4. The adjusted reference temperature (ART) for each reactor beltline material 

shall be calculated, accounting for radiation embrittlement, in accordance 

with Regulatory Guide 1.99, Revision 2. 

 5. The limiting ART shall be incorporated into the calculation of the pressure 

and temperature limit curves in accordance with NUREG-0800 Standard 

Review Plan 5.3.2, Pressure-Temperature Limits. 

 6. The minimum temperature requirements of Appendix G to 10 CFR Part 50 

shall be incorporated into the pressure and temperature limit curves. 
Reporting Requirements 

5.6

Babcock & Wilcox STS 5.6-4 Rev. 4.0 

5.6 Reporting Requirements 

5.6.4 RCS PRESSURE AND TEMPERATURE LIMITS REPORT (continued) 

 7. Licensees who have removed two or more capsules should compare for 

each surveillance material the measured increase in reference temperature 

(RTNDT) to the predicted increase in RTNDT; where the predicted increase in 

RTNDT is based on the mean shift in RTNDT plus the two standard deviation 

value (2) specified in Regulatory Guide 1.99, Revision 2. If the measured 

value exceeds the predicted value (increase in RTNDT + 2), the licensee 

should provide a supplement to the PTLR to demonstrate how the results 

affect the approved methodology. 

 ------------------------------------------------------------------------------------------------------------

5.6.5 Post Accident Monitoring Report 

 When a report is required by Condition B or F of LCO 3.3.[17], "Post Accident 

Monitoring (PAM) Instrumentation," a report shall be submitted within the 

following 14 days. The report shall outline the preplanned alternate method of 

monitoring, the cause of the inoperability, and the plans and schedule for 

restoring the instrumentation channels of the Function to OPERABLE status. 

5.6.6 [ Tendon Surveillance Report

 Any abnormal degradation of the containment structure detected during the tests 

required by the Pre-stressed Concrete Containment Tendon Surveillance 

Program shall be reported to the NRC within 30 days. The report shall include a 

description of the tendon condition, the condition of the concrete (especially at 

tendon anchorages), the inspection procedures, the tolerances on cracking, and 

the corrective action taken. ] 

5.6.7 Steam Generator Tube Inspection Report 

A report shall be submitted within 180 days after the initial entry into MODE 4 

following completion of an inspection performed in accordance with the 

Specification 5.5.9, "Steam Generator (SG) Program." The report shall include:

 a. The scope of inspections performed on each SG, 

b. Active degradation mechanisms found, 

 c. Nondestructive examination techniques utilized for each degradation 

mechanism, 

 d. Location, orientation (if linear), and measured sizes (if available) of service 

induced indications,
Reporting Requirements 

5.6

Babcock & Wilcox STS 5.6-5 Rev. 4.0 

5.6 Reporting Requirements 

5.6.7 Steam Generator Tube Inspection Report (continued) 

 e. Number of tubes plugged [or repaired] during the inspection outage for 

each active degradation mechanism, 

 f. Total number and percentage of tubes plugged [or repaired] to date, 

 g. The results of condition monitoring, including the results of tube pulls and 

in-situ testing, 

 [h. The effective plugging percentage for all plugging [and tube repairs] in each 

SG, and] 

 [i. Repair method utilized and the number of tubes repaired by each repair 

method.] 

 [High Radiation Area] 

5.7

Babcock & Wilcox STS 5.7-1 Rev. 4.0 

5.0 ADMINISTRATIVE CONTROLS 

5.7 High Radiation Area 

As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied 

to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 

10 CFR Part 20: 

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 

Centimeters from the Radiation Source or from any Surface Penetrated by the 

Radiation 

 a. Each entryway to such an area shall be barricaded and conspicuously 

posted as a high radiation area. Such barricades may be opened as 

necessary to permit entry or exit of personnel or equipment. 

 b. Access to, and activities in, each such area shall be controlled by means of 

Radiation Work Permit (RWP) or equivalent that includes specification of 

radiation dose rates in the immediate work area(s) and other appropriate 

radiation protection equipment and measures. 

 c. Individuals qualified in radiation protection procedures and personnel 

continuously escorted by such individuals may be exempted from the 

requirement for an RWP or equivalent while performing their assigned 

duties provided that they are otherwise following plant radiation protection 

procedures for entry to, exit from, and work in such areas. 

 d. Each individual or group entering such an area shall possess: 

 1. A radiation monitoring device that continuously displays radiation 

dose rates in the area; or 

 2. A radiation monitoring device that continuously integrates the 

radiation dose rates in the area and alarms when the device's dose 

alarm setpoint is reached, with an appropriate alarm setpoint, or

 3. A radiation monitoring device that continuously transmits dose rate 

and cumulative dose information to a remote receiver monitored by 

radiation protection personnel responsible for controlling personnel 

radiation exposure within the area, or 

 4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic 

dosimeter) and, 

 (i) Be under the surveillance, as specified in the RWP or 

equivalent, while in the area, or an individual qualified in 

radiation protection procedures, equipped with a radiation 

monitoring device that continuously displays radiation dose 

rates in the area; who is responsible for controlling personnel 

exposure within the area, or 
 [High Radiation Area] 

5.7

Babcock & Wilcox STS 5.7-2 Rev. 4.0 

5.7 High Radiation Area 

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters 

from the Radiation Source or from any Surface Penetrated by the Radiation

 (continued) 

 (ii) Be under the surveillance, as specified in the RWP or 

equivalent, while in the area, by means of closed circuit 

television, of personnel qualified in radiation protection 

procedures, responsible for controlling personnel radiation 

exposure in the area, and with the means to communicate with 

individuals in the area who are covered by such surveillance. 

 e. Except for individuals qualified in radiation protection procedures, or 

personnel continuously escorted by such individuals, entry into such areas 

shall be made only after dose rates in the area have been determined and 

entry personnel are knowledgeable of them. These continuously escorted 

personnel will receive a pre-job briefing prior to entry into such areas. This 

dose rate determination, knowledge, and pre-job briefing does not require 

documentation prior to initial entry. 

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 

Centimeters from the Radiation Source or from any Surface Penetrated by the 

Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or 

from any Surface Penetrated by the Radiation 

 a. Each entryway to such an area shall be conspicuously posted as a high 

radiation area and shall be provided with a locked or continuously guarded 

door or gate that prevents unauthorized entry, and, in addition: 

 1. All such door and gate keys shall be maintained under the 

administrative control of the shift supervisor, radiation protection 

manager, or his or her designee, 

 2. Doors and gates shall remain locked except during periods of 

personnel or equipment entry or exit. 

 b. Access to, and activities in, each such area shall be controlled by means of 

an RWP or equivalent that includes specification of radiation dose rates in 

the immediate work area(s) and other appropriate radiation protection 

equipment and measures. 

 c. Individuals qualified in radiation protection procedures may be exempted 

from the requirement for an RWP or equivalent while performing radiation 

surveys in such areas provided that they are otherwise following plant 

radiation protection procedures for entry to, exit from, and work in such 

areas. 
 [High Radiation Area] 

5.7

Babcock & Wilcox STS 5.7-3 Rev. 4.0 

5.7 High Radiation Area 

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters 

from the Radiation Source or from any Surface Penetrated by the Radiation, but less 

than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface 

Penetrated by the Radiation (continued) 

 d. Each individual or group entering such an area shall possess (one of the 

following:) 

 1. A radiation monitoring device that continuously integrates the 

radiation rates in the area and alarms when the device's dose alarm 

setpoint is reached, with an appropriate alarm setpoint, or 

 2. A radiation monitoring device that continuously transmits dose rate 

and cumulative dose information to a remote receiver monitored by 

radiation protection personnel responsible for controlling personnel 

radiation exposure within the area with the means to communicate 

with and control every individual in the area, or 

 3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic 

dosimeter) and 

 (i) Be under the surveillance, as specified in the RWP or 

equivalent, while in the area, of an individual qualified in 

radiation protection procedures, equipped with a radiation 

monitoring device that continuously displays radiation dose 

rates in the area; who is responsible for controlling personnel 

exposure within the area, 

 (ii) Be under the surveillance, as specified in the RWP or 

equivalent, while in the area, by means of closed circuit 

television, of personnel qualified in radiation protection 

procedures, responsible for controlling personnel radiation 

exposure in the area, and with the means to communicate with 

and control every individual in the area. 

 4. In those cases where options (2) and (3), above, are impractical or 

determined to be inconsistent with the "As Low As is Reasonably 

Achievable" principle, a radiation monitoring device that continuously 

displays radiation dose rates in the area. 

 e. Except for individuals qualified in radiation protection procedures, or 

personnel continuously escorted by such individuals, entry into such areas 

shall be made only after dose rates in the area have been determined and 

entry personnel are knowledgeable of them. These continuously escorted 

personnel will receive a pre-job briefing prior to entry into such areas. This 

dose rate determination, knowledge, and pre-job briefing does not require 

documentation prior to initial entry. 
 [High Radiation Area] 

5.7

Babcock & Wilcox STS 5.7-4 Rev. 4.0 

5.7 High Radiation Area 

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters 

from the Radiation Source or from any Surface Penetrated by the Radiation, but less 

than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface 

Penetrated by the Radiation (continued) 

 f. Such individual areas that are within a larger area where no enclosure 

exists for the purpose of locking and where no enclosure can reasonably be 

constructed around the individual area need not be controlled by a locked 

door or gate, nor continuously guarded, but shall be barricaded, 

conspicuously posted, and a clearly visible flashing light shall be activated 

at the area as a warning device.