Standard Technical 

Specifications

Westinghouse Plants

Revision 4.0

Volume 1, Specifications

Office of Nuclear Reactor Regulation

NUREG-1431

Volume 1

Revision 4.0

Standard Technical 

Specifications

Westinghouse Plants

Revision 4.0

Volume 1, Specifications

Manuscript Completed: October 2011

Date Published: April 2012

Office of Nuclear Reactor Regulation

NUREG-1431

Volume 1

Revision 4.0
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Westinghouse STS iii Rev. 4.0

ABSTRACT 

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

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. 

Westinghouse 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 APPLICABILITY.............................3.0-1 4.0

3.0 SURVEILLANCE REQUIREMENT 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 Core Reactivity ..........................................................................................3.1.2-1 4.0

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

3.1.4 Rod Group Alignment Limits .....................................................................3.1.4-1 4.0

3.1.5 Shutdown Bank Insertion Limits ................................................................3.1.5-1 4.0

3.1.6 Control Bank Insertion Limits ....................................................................3.1.6-1 4.0

3.1.7 Rod Position Indication..............................................................................3.1.7-1 4.0

3.1.8 PHYSICS TESTS Exceptions - MODE 2 ..................................................3.1.8-1 4.0

3.2 POWER DISTRIBUTION LIMITS

3.2.1A Heat Flux Hot Channel Factor (FQ(Z)) (CAOC-FXY Methodology)...........3.2.1A-1 4.0

3.2.1B Heat Flux Hot Channel Factor (FQ(Z)) (RAOC-W(Z) Methodology) ........3.2.1B-1 4.0

3.2.1C Heat Flux Hot Channel Factor (FQ(Z)) (CAOC-W(Z) Methodology) ....... 3.2.1C-1 4.0

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (

N FH

).....................................3.2.2-1 4.0

3.2.3A AXIAL FLUX DIFFERENCE (Constant Axial Offset Control 

Methodology).....................................................................................3.2.3A-1 4.0

3.2.3B AXIAL FLUX DIFFERENCE (Relaxed Axial Offset Control 

Methodology).....................................................................................3.2.3B-1 4.0

3.2.4 QUADRANT POWER TILT RATIO ...........................................................3.2.4-1 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 Trip System (RTS) Instrumentation ...........................................3.3.1A-1 4.0

3.3.1B Reactor Trip System (RTS) Instrumentation ...........................................3.3.1B-1 4.0

3.3.2A Engineered Safety Feature Actuation System (ESFAS) 

Instrumentation..................................................................................3.3.2A-1 4.0

3.3.2B Engineered Safety Feature Actuation System (ESFAS) 

Instrumentation..................................................................................3.3.2B-1 4.0

3.3.3 Post Accident Monitoring (PAM) Instrumentation......................................3.3.3-1 4.0

3.3.4 Remote Shutdown System........................................................................3.3.4-1 4.0
Westinghouse STS vi Rev. 4.0

TABLE OF CONTENTS / REVISION SUMMARY Page Rev.

3.3 INSTRUMENTATION (continued) 

3.3.5A Loss of Power (LOP) Diesel Generator (DG) Start 

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

3.3.5B Loss of Power (LOP) Diesel Generator (DG) Start 

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

3.3.6A Containment Purge and Exhaust Isolation Instrumentation ....................3.3.6A-1 4.0

3.3.6B Containment Purge and Exhaust Isolation Instrumentation ....................3.3.6B-1 4.0

3.3.7A Control Room Emergency Filtration System (CREFS) Actuation

 Instrumentation ..................................................................................3.3.7A-1 4.0

3.3.7B Control Room Emergency Filtration System (CREFS) Actuation 

 Instrumentation ..................................................................................3.3.7B-1 4.0

3.3.8A Fuel Building Air Cleanup System (FBACS) Actuation 

 Instrumentation ..................................................................................3.3.8A-1 4.0

3.3.8B Fuel Building Air Cleanup System (FBACS) Actuation 

 Instrumentation ..................................................................................3.3.8B-1 4.0

3.3.9A Boron Dilution Protection System (BDPS) ..............................................3.3.9A-1 4.0

3.3.9B Boron Dilution Protection System (BDPS) ..............................................3.3.9B-1 4.0

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate 

 Boiling 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 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 Valves .............................................3.4.11-1 4.0

3.4.12 Low Temperature Overpressure Protection 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 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 RCS Loop Isolation Valves ......................................................................3.4.17-1 4.0

3.4.18 RCS Isolated Loop Startup ......................................................................3.4.18-1 4.0

3.4.19 RCS Loops - Test Exceptions ................................................................. 3.4.19-1 4.0

3.4.20 Steam Generator (SG) Tube Integrity .....................................................3.4.20-1 4.0

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.1 Accumulators .............................................................................................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 Refueling Water Storage Tank (RWST) ....................................................3.5.4-1 4.0

3.5.5 Seal Injection Flow ....................................................................................3.5.5-1 4.0

3.5.6 Boron Injection Tank (BIT) ........................................................................3.5.6-1 4.0
Westinghouse STS vii Rev. 4.0

TABLE OF CONTENTS / REVISION SUMMARY Page Rev.

3.6 CONTAINMENT SYSTEMS 

3.6.1 Containment (Atmospheric, Subatmospheric, Ice Condenser, and 

 Dual) ....................................................................................................3.6.1-1 4.0

3.6.2 Containment Air Locks (Atmospheric, Subatmospheric, Ice 

 Condenser, and Dual) .........................................................................3.6.2-1 4.0

3.6.3 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice 

 Condenser, and Dual) .........................................................................3.6.3-1 4.0

3.6.4A Containment Pressure (Atmospheric, Dual, and Ice Condenser) ...........3.6.4A-1 4.0

3.6.4B Containment Pressure (Subatmospheric) ...............................................3.6.4B-1 4.0

3.6.5A Containment Air Temperature (Atmospheric and Dual) ..........................3.6.5A-1 4.0

3.6.5B Containment Air Temperature (Ice Condenser) ......................................3.6.5B-1 4.0

3.6.5C Containment Air Temperature (Subatmospheric) ................................... 3.6.5C-1 4.0

3.6.6A Containment Spray and Cooling Systems (Atmospheric and Dual) 

 (Credit taken for iodine removal by the Containment Spray 

 System) .............................................................................................3.6.6A-1 4.0

3.6.6B Containment Spray and Cooling Systems (Atmospheric and Dual) 

 (Credit not taken for iodine removal by the Containment Spray 

 System) ...........................................................................................3.6.6B1-1 4.0

3.6.6C Containment Spray System (Ice Condenser) ......................................... 3.6.6C-1 4.0

3.6.6D Quench Spray (QS) System (Subatmospheric) ..................................... 3.6.6D-1 4.0

3.6.6E Recirculation Spray (RS) System (Subatmospheric) ..............................3.6.6E-1 4.0

3.6.7 Spray Additive System (Atmospheric, Subatmospheric, Ice 

 Condenser, and Dual) .........................................................................3.6.7-1 4.0

3.6.8 Shield Building (Dual and Ice Condenser) ................................................3.6.8-1 4.0

3.6.9 Hydrogen Mixing System (HMS) (Atmospheric, Ice Condenser, 

 and Dual) .............................................................................................3.6.9-1 4.0

3.6.10 Hydrogen Ignition System (HIS) (Ice Condenser) ...................................3.6.10-1 4.0

3.6.11 Iodine Cleanup System (ICS) (Atmospheric and 

 Subatmospheric) ...............................................................................3.6.11-1 4.0

3.6.12 Vacuum Relief Valves (Atmospheric and Ice Condenser) ......................3.6.12-1 4.0

3.6.13 Shield Building Air Cleanup System (SBACS) (Dual and Ice 

 Condenser) ........................................................................................3.6.13-1 4.0

3.6.14 Air Return System (ARS) (Ice Condenser) ..............................................3.6.14-1 4.0

3.6.15 Ice Bed (Ice Condenser) .........................................................................3.6.15-1 4.0

3.6.16 Ice Condenser Doors (Ice Condenser)....................................................3.6.16-1 4.0

3.6.17 Divider Barrier Integrity (Ice Condenser) .................................................3.6.17-1 4.0

3.6.18 Containment Recirculation Drains (Ice Condenser) ................................3.6.18-1 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 Isolation Valves (MFIVs) and Main Feedwater 

 Regulation Valves (MFRVs) [ and Associated Bypass Valves ] ..........3.7.3-1 4.0

3.7.4 Atmospheric Dump Valves (ADVs) ...........................................................3.7.4-1 4.0

3.7.5 Auxiliary Feedwater (AFW) 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
Westinghouse STS viii Rev. 4.0

TABLE OF CONTENTS / REVISION SUMMARY Page Rev.

3.7 PLANT SYSTEMS (continued) 

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

3.7.10 Control Room Emergency Filtration System (CREFS) ............................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 Core Cooling System (ECCS) Pump Room Exhaust Air 

 Cleanup System (PREACS) ..............................................................3.7.12-1 4.0

3.7.13 Fuel Building Air Cleanup System (FBACS) ...........................................3.7.13-1 4.0

3.7.14 Penetration Room Exhaust Air Cleanup System (PREACS) ..................3.7.14-1 4.0

3.7.15 Fuel Storage Pool Water Level ...............................................................3.7.15-1 4.0

[ 3.7.16 Fuel Storage Pool Boron Concentration ..................................................3.7.16-1 4.0 ] 

[ 3.7.17 Spent Fuel Pool Storage .........................................................................3.7.10-1 4.0 ] 

3.7.18 Secondary Specific Activity .....................................................................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 Unborated Water Source Isolation Valves ................................................3.9.2-1 4.0 ] 

3.9.3 Nuclear Instrumentation ............................................................................3.9.3-1 4.0

3.9.4 Containment Penetrations .........................................................................3.9.4-1 4.0

3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - High 

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

3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low 

 Water Level .........................................................................................3.9.6-1 4.0

3.9.7 Refueling Cavity Water Level ....................................................................3.9.7-1 4.0

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

4.1 Site Location 

4.2 Reactor Core 

4.3 Fuel Storage 
Westinghouse STS ix Rev. 4.0

TABLE OF CONTENTS / REVISION SUMMARY Page Rev.

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

Westinghouse 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. 

ACTUATION LOGIC TEST An ACTUATION LOGIC TEST shall be the application of 

various simulated or actual input combinations in conjunction 

with each possible interlock logic state required for 

OPERABILITY of a logic circuit and the verification of the 

required logic output. The ACTUATION LOGIC TEST, as a 

minimum, shall include a continuity check of output devices. 

AXIAL FLUX DIFFERENCE AFD shall be the difference in normalized flux signals 

(AFD) between the [top and bottom halves of a two section excore 

neutron detector]. 

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. 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

Westinghouse STS 1.1-2 Rev. 4.0 

1.1 Definitions 

CHANNEL OPERATIONAL A COT shall be the injection of a simulated or actual signal 

TEST (COT) into the channel as close to the sensor as practicable to

verify OPERABILITY of all devices in the channel required for 

channel OPERABILITY. The COT shall include adjustments, 

as necessary, of the required alarm, interlock, and trip 

setpoints required for channel OPERABILITY such that the 

setpoints are within the necessary range and accuracy. The 

COT may be performed by means of any series of 

sequential, overlapping, or total channel steps. 

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

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

These cycle specific parameter 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, I132, 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

Westinghouse STS 1.1-3 Rev. 4.0 

1.1 Definitions 

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

FEATURE (ESF) RESPONSE when the monitored parameter exceeds its 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. In lieu of 

measurement, response time may be verified for selected 

components provided that the components and methodology 

for verification have been previously reviewed and approved 

by the NRC. 

LEAKAGE LEAKAGE shall be: 

 a. Identified LEAKAGE 

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

packing (except reactor coolant pump (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 

 c. Pressure Boundary LEAKAGE 

 LEAKAGE (except primary to secondary LEAKAGE) 

through a nonisolable fault in an RCS component body, 

pipe wall, or vessel wall.
Definitions 

1.1

Westinghouse STS 1.1-4 Rev. 4.0 

1.1 Definitions 

MASTER RELAY TEST A MASTER RELAY TEST shall consist of energizing all 

master relays in the channel required for channel 

OPERABILITY and verifying the OPERABILITY of each 

required master relay. The MASTER RELAY TEST shall 

include a continuity check of each associated required slave 

relay. The MASTER RELAY TEST may be performed by 

means of any series of sequential, overlapping, or total steps. 

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. 

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. 

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 and the low temperature 

overpressure protection arming temperature, 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. 
Definitions 

1.1

Westinghouse STS 1.1-5 Rev. 4.0 

1.1 Definitions 

QUADRANT POWER TILT QPTR shall be the ratio of the maximum upper excore 

RATIO (QPTR) detector calibrated output to the average of the upper excore 

detector calibrated outputs, or the ratio of the maximum lower 

excore detector calibrated output to the average of the lower 

excore detector calibrated outputs, whichever is greater. 

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

(RTP) reactor coolant of [2893] MWt. 

REACTOR TRIP SYSTEM The RTS RESPONSE TIME shall be that time interval from 

(RTS) RESPONSE TIME when the monitored parameter exceeds its RTS trip setpoint 

at the channel sensor until loss of stationary gripper coil 

voltage. 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. In lieu of 

measurement, response time may be verified for selected 

components provided that the components and methodology 

for verification have been previously reviewed and approved 

by the NRC. 

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 rod cluster control assemblies (RCCAs) are fully 

inserted except for the single RCCA of highest reactivity 

worth, which is assumed to be fully withdrawn. 

However, with all RCCAs verified fully inserted by two 

independent means, it is not necessary to account for a 

stuck RCCA in the SDM calculation. With any RCCA 

not capable of being fully inserted, the reactivity worth 

of the RCCA must be accounted for in the 

determination of SDM, and 

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

temperatures are changed to the [nominal zero power 

design level]. 

SLAVE RELAY TEST A SLAVE RELAY TEST shall consist of energizing all slave 

relays in the channel required for channel OPERABILITY and 

verifying the OPERABILITY of each required slave relay. 

The SLAVE RELAY TEST shall include a continuity check of 

associated required testable actuation devices. The SLAVE 

RELAY TEST may be performed by means of any series of 

sequential, overlapping, or total steps. 
Definitions 

1.1

Westinghouse 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. 

TRIP ACTUATING DEVICE A TADOT shall consist of operating the trip actuating 

OPERATIONAL TEST device and verifying the OPERABILITY of all devices in the 

(TADOT) channel required for trip actuating device OPERABILITY. 

The TADOT shall include adjustment, as necessary, of the 

trip actuating device so that it actuates at the required 

setpoint within the necessary accuracy. The TADOT may be 

performed by means of any series of sequential, overlapping, 

or total channel steps. 
Definitions 

1.1

Westinghouse 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 ≥ [350]

4 Hot Shutdown(b) < 0.99 NA [350] > 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

Westinghouse 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

Westinghouse 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

Westinghouse 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

Westinghouse 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 
Completion Times 

1.3

Westinghouse STS 1.3-2 Rev. 4.0 

1.3 Completion Times 

DESCRIPTION (continued) 

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

inoperability is resolved. 

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 

re-entry 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
Completion Times 

1.3

Westinghouse STS 1.3-3 Rev. 4.0 

1.3 Completion Times 

EXAMPLES (continued) 

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. 

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. 
Completion Times 

1.3

Westinghouse STS 1.3-4 Rev. 4.0 

1.3 Completion Times 

EXAMPLES (continued) 

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. 

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

Westinghouse 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

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). 
Completion Times 

1.3

Westinghouse STS 1.3-6 Rev. 4.0 

1.3 Completion Times 

EXAMPLES (continued) 

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. 

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. 
Completion Times 

1.3

Westinghouse STS 1.3-7 Rev. 4.0 

1.3 Completion Times 

EXAMPLES (continued) 

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 (including the extension) expires while 

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

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. 
Completion Times 

1.3

Westinghouse STS 1.3-8 Rev. 4.0 

1.3 Completion Times 

EXAMPLES (continued) 

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. 

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
Completion Times 

1.3

Westinghouse STS 1.3-9 Rev. 4.0 

1.3 Completion Times 

EXAMPLES (continued) 

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.

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
Completion Times 

1.3

Westinghouse STS 1.3-10 Rev. 4.0 

1.3 Completion Times 

EXAMPLES (continued) 

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. 

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

Westinghouse 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 

performed 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

Westinghouse 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

Westinghouse 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

Westinghouse 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 25% 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

Westinghouse 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

Westinghouse 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

Westinghouse 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 performed 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

Westinghouse 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

Westinghouse STS 2.0-1 Rev. 4.0 

2.0 SAFETY LIMITS (SLs) 

2.1 SLs 

 2.1.1 Reactor Core SLs 

 In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant 

System (RCS) highest loop average temperature, and pressurizer pressure shall 

not exceed the limits specified in the COLR; and the following SLs shall not be 

exceeded: 

 2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained 

≥ [1.17 for the WRB-1/WRB-2 DNB correlations]. 

 2.1.1.2 The peak fuel centerline temperature shall be maintained < [5080°F, 

decreasing by 58°F per 10,000 MWD/MTU of burnup]. 

2.1.2 Reactor Coolant System Pressure SL 

 In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained ≤ [2735] psig. 

2.2 SAFETY LIMIT VIOLATIONS 

2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour. 

2.2.2 If SL 2.1.2 is violated:

 2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour. 

 2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes. 

LCO Applicability 

3.0

Westinghouse 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

Westinghouse 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 [3.1.8 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

Westinghouse 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

Westinghouse 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

Westinghouse 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

Westinghouse STS 3.1.1-1 Rev. 4.0 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.1 SHUTDOWN MARGIN (SDM) 

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

APPLICABILITY: MODE 2 with keff < 1.0,

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 to be within the limits specified in the 

COLR.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Core Reactivity 

3.1.2

Westinghouse STS 3.1.2-1 Rev. 4.0 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.2 Core Reactivity 

LCO 3.1.2 The measured core reactivity shall be within ± 1% ∆k/k of predicted 

values. 

APPLICABILITY: MODES 1 and 2.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Measured core reactivity 

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
Core Reactivity 

3.1.2

Westinghouse STS 3.1.2-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.2.1 ---------------------------NOTE----------------------------------

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.

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

Verify measured core reactivity is within ± 1% ∆k/k 

of predicted values.

Once prior to 

entering MODE 1 

after each 

refueling

AND

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

Only required 

after 60 EFPD

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

[ 31 EFPD 

thereafter

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
MTC 

3.1.3

Westinghouse 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 upper limit shall be [≤ [ ] ∆k/k°F at hot zero power] [that 

specified in Figure 3.1.3-1].

APPLICABILITY: MODE 1 and MODE 2 with keff ≥ 1.0 for the upper MTC limit, 

MODES 1, 2, and 3 for the lower MTC limit. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. MTC not within upper 

limit.

A.1 Establish administrative 

withdrawal limits for control 

banks to maintain MTC 

within limit.

24 hours

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 2 with 

keff < 1.0.

6 hours

C. MTC not within lower 

limit.

C.1 Be in MODE 4. 12 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.3.1 Verify MTC is within upper limit. Prior to entering 

MODE 1 after 

each refueling
MTC 

3.1.3

Westinghouse STS 3.1.3-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.1.3.2 ---------------------------NOTES--------------------------------

1. Not required to be performed until 7 effective full 

power days (EFPD) after reaching the 

equivalent of an equilibrium RTP all rods out 

(ARO) boron concentration of 300 ppm.

2. If the MTC is more negative than the 300 ppm 

Surveillance limit (not LCO limit) specified in the 

COLR, SR 3.1.3.2 shall be repeated once per 

14 EFPD during the remainder of the fuel cycle.

3. SR 3.1.3.2 need not be repeated if the MTC 

measured at the equivalent of equilibrium RTPARO boron concentration of ≤ 60 ppm is less 

negative than the 60 ppm Surveillance limit 

specified in the COLR.

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

Verify MTC is within lower limit. Once each cycle
MTC 

3.1.3

Westinghouse STS 3.1.3-3 Rev. 4.0 

Figure 3.1.3 - 1 (page 1 of 1) 

Moderator Temperature Coefficient Vs. Rated Thermal Power 

Rod Group Alignment Limits 

3.1.4

Westinghouse STS 3.1.4-1 Rev. 4.0 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.4 Rod Group Alignment Limits 

LCO 3.1.4 All shutdown and control rods shall be OPERABLE. 

 AND

Individual indicated rod positions shall be within 12 steps of their group 

step counter demand position. 

APPLICABILITY: MODES 1 and 2.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more rod(s) 

inoperable.

A.1.1 Verify SDM to be within the 

limits specified in the 

COLR.

OR

A.1.2 Initiate boration to restore 

SDM to within limit.

AND

A.2 Be in MODE 3.

1 hour

1 hour

6 hours

B. One rod not within 

alignment limits.

B.1 Restore rod to within 

alignment limits.

OR

B.2.1.1 Verify SDM to be within the 

limits specified in the 

COLR.

OR

1 hour

1 hour
Rod Group Alignment Limits 

3.1.4

Westinghouse STS 3.1.4-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.2.1.2 Initiate boration to restore 

SDM to within limit.

AND

B.2.2 Reduce THERMAL 

POWER to ≤ 75% RTP.

AND

B.2.3 Verify SDM is within the 

limits specified in the 

COLR.

AND

B.2.4 Perform SR 3.2.1.1 and 

SR 3.2.1.2.

AND

B.2.5 Perform SR 3.2.2.1.

AND

B.2.6 Re-evaluate safety 

analyses and confirm 

results remain valid for 

duration of operation under 

these conditions.

1 hour

2 hours

Once per

12 hours

72 hours

72 hours

5 days

C. Required Action and 

associated Completion 

Time of Condition B not 

met.

C.1 Be in MODE 3. 6 hours

D. More than one rod not 

within alignment limit.

D.1.1 Verify SDM is within the 

limits specified in the 

COLR.

OR

1 hour
Rod Group Alignment Limits 

3.1.4

Westinghouse STS 3.1.4-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

D.1.2 Initiate boration to restore 

required SDM to within 

limit.

AND

D.2 Be in MODE 3.

1 hour

6 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.4.1 Verify individual rod positions within alignment limit. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.1.4.2 Verify rod freedom of movement (trippability) by 

moving each rod not fully inserted in the core 

≥ 10 steps in either direction.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Rod Group Alignment Limits 

3.1.4

Westinghouse STS 3.1.4-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.1.4.3 Verify rod drop time of each rod, from the fully 

withdrawn position, is ≤ [2.2] seconds from the 

beginning of decay of stationary gripper coil voltage 

to dashpot entry, with:

a. Tavg ≥ 500°F and

b. All reactor coolant pumps operating.

Prior to criticality 

after each 

removal of the 

reactor head
Shutdown Bank Insertion Limits 

3.1.5

Westinghouse STS 3.1.5-1 Rev. 4.0 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.5 Shutdown Bank Insertion Limits 

LCO 3.1.5 Each shutdown bank shall be within insertion limits specified in the 

COLR. 

APPLICABILITY: MODES 1 and 2. 

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

 This LCO is not applicable while performing SR 3.1.4.2. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more shutdown 

banks not within limits.

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 Restore shutdown banks to 

within limits.

1 hour

1 hour

2 hours

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3. 6 hours
Shutdown Bank Insertion Limits 

3.1.5

Westinghouse STS 3.1.5-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.5.1 Verify each shutdown bank is within the insertion 

limits specified in the COLR.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Control Bank Insertion Limits 

3.1.6

Westinghouse STS 3.1.6-1 Rev. 4.0 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.6 Control Bank Insertion Limits 

LCO 3.1.6 Control banks shall be within the insertion, sequence, and overlap limits 

specified in the COLR. 

APPLICABILITY: MODE 1, 

 MODE 2 with keff ≥1.0. 

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

 This LCO is not applicable while performing SR 3.1.4.2. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Control bank insertion 

limits not met.

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 Restore control bank(s) to 

within limits.

1 hour

1 hour

2 hours

B. Control bank sequence 

or overlap limits not met.

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
Control Bank Insertion Limits 

3.1.6

Westinghouse STS 3.1.6-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.2 Restore control bank 

sequence and overlap to 

within limits.

2 hours

C. Required Action and 

associated Completion 

Time not met.

C.1 Be in MODE 2 with keff

< 1.0.

6 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.6.1 Verify estimated critical control bank position is 

within the limits specified in the COLR.

Within 4 hours 

prior to achieving 

criticality

SR 3.1.6.2 Verify each control bank insertion is within the 

insertion limits specified in the COLR.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.1.6.3 Verify sequence and overlap limits specified in the 

COLR are met for control banks not fully withdrawn 

from the core.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Rod Position Indication 

3.1.7

Westinghouse STS 3.1.7-1 Rev. 4.0 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.7 Rod Position Indication 

LCO 3.1.7 The [Digital] Rod Position Indication ([D]RPI) System and the Demand 

Position Indication System shall be OPERABLE. 

APPLICABILITY: MODES 1 and 2.

ACTIONS 

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

Separate Condition entry is allowed for each inoperable rod position indicator and each demand 

position indicator. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. One [D]RPI per group 

inoperable for one or 

more groups.

A.1 Verify the position of the 

rods with inoperable 

position indicators indirectly 

by using movable incore 

detectors.

OR

A.2 Reduce THERMAL 

POWER to ≤ 50% RTP.

Once per 8 hours

8 hours

B. More than one [D]RPI 

per group inoperable.

B.1 Place the control rods 

under manual control.

AND

B.2 Monitor and record Reactor 

Coolant System Tavg.

AND

Immediately

Once per 1 hour
Rod Position Indication 

3.1.7

Westinghouse STS 3.1.7-2 Rev. 4.0 

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

B.3 Verify the position of the 

rods with inoperable 

position indicators indirectly 

by using the movable 

incore detectors.

AND

B.4 Restore inoperable position 

indicators to OPERABLE 

status such that a 

maximum of one [D]RPI per 

group is inoperable.

Once per 8 hours

24 hours

C. One or more rods with 

inoperable position 

indicators have been 

moved in excess of 

24 steps in one direction 

since the last 

determination of the 

rod's position.

C.1 Verify the position of the 

rods with inoperable 

position indicators indirectly 

by using movable incore 

detectors.

OR

C.2 Reduce THERMAL 

POWER to ≤ 50% RTP.

[4] hours

8 hours

D. One demand position 

indicator per bank

inoperable for one or 

more banks.

D.1.1 Verify by administrative 

means all [D]RPIs for the 

affected banks are 

OPERABLE.

 AND

D.1.2 Verify the most withdrawn 

rod and the least withdrawn 

rod of the affected banks 

are ≤ 12 steps apart.

OR

Once per 8 hours

Once per 8 hours
Rod Position Indication 

3.1.7

Westinghouse STS 3.1.7-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

D.2 Reduce THERMAL 

POWER to ≤ 50% RTP.

8 hours

E. Required Action and 

associated Completion 

Time not met.

E.1 Be in MODE 3. 6 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.7.1 Verify each [D]RPI agrees within [12] steps of the 

group demand position for the [full indicated range] 

of rod travel.

Once prior to 

criticality after 

each removal of 

the reactor head

PHYSICS TESTS Exceptions – MODE 2 

3.1.8

Westinghouse STS 3.1.8-1 Rev. 4.0 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.8 PHYSICS TESTS Exceptions – MODE 2 

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

 LCO 3.1.3, "Moderator Temperature Coefficient,"

 LCO 3.1.4, "Rod Group Alignment Limits,"

 LCO 3.1.5, "Shutdown Bank Insertion Limits," 

 LCO 3.1.6, "Control Bank Insertion Limits," and

 LCO 3.4.2, "RCS Minimum Temperature for Criticality"

may be suspended and the number of required channels for LCO 3.3.1, 

"RTS Instrumentation," Functions 2, 3, 6 and 18.e, may be reduced to 3 

required channels, provided: 

a. RCS lowest loop average temperature is  [531]°F, 

b. SDM is within the limits specified in the COLR, and 

c. THERMAL POWER is < 5% RTP. 

APPLICABILITY: During PHYSICS TESTS initiated in MODE 2.

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

B. THERMAL POWER not 

within limit.

B.1 Open reactor trip breakers. Immediately

C. RCS lowest loop 

average temperature not 

within limit.

C.1 Restore RCS lowest loop 

average temperature to 

within limit.

15 minutes
PHYSICS TESTS Exceptions – MODE 2 

3.1.8

Westinghouse STS 3.1.8-2 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. 15 minutes

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.1.8.1 Perform a CHANNEL OPERATIONAL TEST on 

power range and intermediate range channels per

[SR 3.3.1.7, SR 3.3.1.8, and Table 3.3.1-1].

Prior to initiation 

of PHYSICS 

TESTS

SR 3.1.8.2 Verify the RCS lowest loop average temperature is 

≥ [531]°F.

[ 30 minutes

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.1.8.3 Verify THERMAL POWER is  5% RTP. [ 30 minutes

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
PHYSICS TESTS Exceptions – MODE 2 

3.1.8

Westinghouse STS 3.1.8-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

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 ]

FQ(Z) (CAOC-Fxy Methodology) 

3.2.1A

Westinghouse STS 3.2.1A-1 Rev. 4.0 

3.2 POWER DISTRIBUTION LIMITS 

3.2.1A Heat Flux Hot Channel Factor (FQ(Z)) ( CAOC-Fxy Methodology) 

LCO 3.2.1A FQ(Z) shall be within the limits specified in the COLR. 

APPLICABILITY: MODE 1.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

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

Required Action A.4 

shall be completed 

whenever this Condition 

is entered.

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

FQ(Z) not within limit.

A.1 Reduce THERMAL 

POWER ≥ 1% RTP for 

each 1% FQ(Z) exceeds 

limit.

AND

A.2 Reduce Power Range 

Neutron Flux - High trip 

setpoints ≥ 1% for each 

1% FQ(Z) exceeds limit.

AND

A.3 Reduce Overpower ∆T trip 

setpoints ≥ 1% for each 

1% FQ(Z) exceeds limit.

AND

A.4 Perform SR 3.2.1.1 and 

SR 3.2.1.2.

15 minutes after each 

FQ(Z) determination

72 hours after each 

FQ(Z) determination

72 hours after each 

FQ(Z) determination

Prior to increasing 

THERMAL POWER 

above the limit of 

Required Action A.1

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 2. 6 hours
FQ(Z) (CAOC-Fxy Methodology) 

3.2.1A

Westinghouse STS 3.2.1A-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.2.1.1 Verify measured values of FQ(Z) are within limits 

specified in the COLR.

Once after each 

refueling prior to 

THERMAL 

POWER 

exceeding 

75% RTP

AND

[ 31 EFPD 

thereafter

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
FQ(Z) (CAOC-Fxy Methodology) 

3.2.1A

Westinghouse STS 3.2.1A-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.2.1.2 ------------------------------NOTES-----------------------------

1. If 

C FXY

>

L FXY

, evaluate the effect of Fxy on the 

predicted 

PR FQ

to determine if FQ(Z) is within its 

limits.

2. If 

RTP FXY

<

C FXY

≤

L FXY

, SR 3.2.1.2 shall be 

repeated within 24 hours after an increase in 

THERMAL POWER at which 

C FXY

was last 

determined, of at least 20% RTP.

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

Verify 

C FXY

<

L FXY

. Once after each 

refueling prior to 

THERMAL 

POWER 

exceeding 

75% RTP

AND

[ 31 EFPD 

thereafter

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

FQ(Z) (RAOC-W(Z) Methodology) 

3.2.1B

Westinghouse STS 3.2.1B-1 Rev. 4.0 

3.2 POWER DISTRIBUTION LIMITS 

3.2.1B Heat Flux Hot Channel Factor (FQ(Z) (RAOC-W(Z) Methodology) 

LCO 3.2.1B FQ(Z), as approximated by 

)Z(F

C

Q

and 

)Z(F

W

Q

, shall be within the limits 

specified in the COLR. 

APPLICABILITY: MODE 1.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

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

Required Action A.4 

shall be completed 

whenever this Condition 

is entered.

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

)Z(F

C

Q

not within limit.

A.1 Reduce THERMAL 

POWER ≥ 1% RTP for 

each 1%

)Z(F

C

Q

exceeds 

limit.

AND

A.2 Reduce Power Range 

Neutron Flux - High trip 

setpoints ≥ 1% for each 

1%

)Z(F

C

Q

exceeds limit.

AND

A.3 Reduce Overpower ∆T trip 

setpoints ≥ 1% for each 

1%

)Z(F

C

Q

exceeds limit.

AND

A.4 Perform SR 3.2.1.1 and 

SR 3.2.1.2.

15 minutes after each 

)Z(F

C

Q

determination

72 hours after each 

)Z(F

C

Q

determination

72 hours after each 

)Z(F

C

Q

determination

Prior to increasing 

THERMAL POWER 

above the limit of 

Required Action A.1
FQ(Z) (RAOC-W(Z) Methodology) 

3.2.1B

Westinghouse STS 3.2.1B-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

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

Required Action B.4 

shall be completed 

whenever this Condition 

is entered.

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

)Z(F

W

Q

not within limits.

B.1 Reduce AFD limits ≥ 1% for 

each 1%

)Z(F

W

Q

exceeds 

limit.

AND

B.2 Reduce Power Range 

Neutron Flux - High trip 

setpoints ≥ 1% for each 1% 

that the maximum allowable 

power of the AFD limits is 

reduced.

AND

B.3 Reduce Overpower ∆T trip 

setpoints ≥ 1% for each 1% 

that the maximum allowable 

power of the AFD limits is 

reduced.

AND

B.4 Perform SR 3.2.1.1 and 

SR 3.2.1.2.

4 hours

72 hours

72 hours

Prior to increasing 

THERMAL POWER 

above the maximum 

allowable power of 

the AFD limits

C. Required Action and 

associated Completion 

Time not met.

C.1 Be in MODE 2. 6 hours
FQ(Z) (RAOC-W(Z) Methodology) 

3.2.1B

Westinghouse STS 3.2.1B-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

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

During power escalation at the beginning of each cycle, THERMAL POWER may be increased 

until an equilibrium power level has been achieved, at which a power distribution map is 

obtained.

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

SURVEILLANCE FREQUENCY

SR 3.2.1.1 Verify 

)Z(F

C

Q

is within limit. Once after each 

refueling prior to 

THERMAL 

POWER 

exceeding 

75% RTP

AND

Once within 

[12] hours after 

achieving 

equilibrium 

conditions after 

exceeding, by 

≥ 10% RTP, the 

THERMAL 

POWER at which 

)Z(F

C

Q

was last 

verified

AND

[ 31 EFPD 

thereafter

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
FQ(Z) (RAOC-W(Z) Methodology) 

3.2.1B

Westinghouse STS 3.2.1B-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.2.1.2 -------------------------------NOTE------------------------------

If measurements indicate that the

maximum over z [

)Z(F

C

Q

/ K(Z) ]

has increased since the previous evaluation of 

)Z(F

C

Q

:

a. Increase 

)Z(F

W

Q

by the greater of a factor of 

[1.02] or by an appropriate factor specified in 

the COLR and reverify 

)Z(F

W

Q

is within limits or

b. Repeat SR 3.2.1.2 once per 7 EFPD until either 

a. above is met or two successive flux maps 

indicate that the

maximum over z [

)Z(F

C

Q

/ K(Z) ]

has not increased.

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

Verify 

)Z(F

W

Q

is within limit. Once after each 

refueling prior to 

THERMAL 

POWER exceeding 75% RTP

AND

Once within 

[12] hours after 

achieving 

equilibrium 

conditions after 

exceeding, by 

≥ 10% RTP, the

THERMAL 

POWER at which 

)Z(F

W

Q

was last 

verified

AND
FQ(Z) (RAOC-W(Z) Methodology) 

3.2.1B

Westinghouse STS 3.2.1B-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

[ 31 EFPD 

thereafter

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

FQ(Z) (CAOC-W(Z) Methodology) 

3.2.1C

Westinghouse STS 3.2.1C-1 Rev. 4.0 

3.2 POWER DISTRIBUTION LIMITS 

3.2.1C Heat Flux Hot Channel Factor (FQ(Z) (CAOC-W(Z) Methodology) 

LCO 3.2.1C FQ(Z), as approximated by 

)Z(F

C

Q

and 

)Z(F

W

Q

, shall be within the limits 

specified in the COLR. 

APPLICABILITY: MODE 1.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

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

Required Action A.4 

shall be completed 

whenever this Condition 

is entered.

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

)Z(F

C

Q

not within limit.

A.1 Reduce THERMAL 

POWER ≥ 1% RTP for 

each 1%

)Z(F

C

Q

exceeds 

limit.

AND

A.2 Reduce Power Range 

Neutron Flux - High trip 

setpoints ≥ 1% for each 

1%

)Z(F

C

Q

exceeds limit.

AND

A.3 Reduce Overpower ∆T trip 

setpoints ≥ 1% for each 

1%

)Z(F

C

Q

exceeds limit.

AND

A.4 Perform SR 3.2.1.1 and 

SR 3.2.1.2.

15 minutes after each 

)Z(F

C

Q

determination

72 hours after each 

)Z(F

C

Q

determination

72 hours after each 

)Z(F

C

Q

determination

Prior to increasing 

THERMAL POWER 

above the limit of 

Required Action A.1
FQ(Z) (CAOC-W(Z) Methodology) 

3.2.1C

Westinghouse STS 3.2.1C-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

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

Required Action B.4 

shall be completed 

whenever this Condition 

is entered.

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

)Z(F

W

Q

not within limits.

B.1 Reduce THERMAL 

POWER ≥ 1% RTP for 

each 1%

)Z(F

W

Q

exceeds 

limit.

AND

B.2 Reduce Power Range 

Neutron Flux - High trip 

setpoints ≥ 1% for each 1% 

)Z(F

W

Q

exceeds limit.

AND

B.3 Reduce Overpower ∆T trip 

setpoints ≥ 1% for each 1% 

)Z(F

W

Q

exceeds limit.

AND

B.4 Perform SR 3.2.1.1 and 

SR 3.2.1.2.

4 hours

72 hours

72 hours

Prior to increasing 

THERMAL POWER 

above the limit of 

Required Action B.1

C. Required Action and 

associated Completion 

Time not met.

C.1 Be in MODE 2. 6 hours
FQ(Z) (CAOC-W(Z) Methodology) 

3.2.1C

Westinghouse STS 3.2.1C-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

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

During power escalation at the beginning of each cycle, THERMAL POWER may be increased 

until an equilibrium power level has been achieved, at which a power distribution map is 

obtained.

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

SURVEILLANCE FREQUENCY

SR 3.2.1.1 Verify 

)Z(F

C

Q

is within limit. Once after each 

refueling prior to 

THERMAL 

POWER 

exceeding 

75% RTP

AND

Once within 

[12] hours after 

achieving 

equilibrium 

conditions after 

exceeding, by 

≥ 10% RTP, the 

THERMAL 

POWER at which 

)Z(F

C

Q

was last 

verified

AND

[ 31 EFPD 

thereafter

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
FQ(Z) (CAOC-W(Z) Methodology) 

3.2.1C

Westinghouse STS 3.2.1C-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.2.1.2 -------------------------------NOTE------------------------------

If measurements indicate that the maximum 

over z [

)Z(F

C

Q

/ K(Z) ] has increased since the 

previous evaluation of 

)Z(F

C

Q

:

a. Increase 

)Z(F

W

Q

by the greater of a factor of 

[1.02] or by an appropriate factor specified in 

the COLR and reverify 

)Z(F

W

Q

is within limits or

b. Repeat SR 3.2.1.2 once per 7 EFPD until either 

a. above is met or two successive flux maps 

indicate that the maximum over z [

)Z(F

C

Q

/ 

K(Z) ] has not increased.

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

Verify 

)Z(F

W

Q

is within limit. Once after each 

refueling prior to 

THERMAL 

POWER 

exceeding 

75% RTP

AND

Once within 

[12] hours after 

achieving 

equilibrium 

conditions after 

exceeding, by 

≥ 10% RTP, the

THERMAL 

POWER at which 

)Z(F

W

Q

was last 

verified

AND
FQ(Z) (CAOC-W(Z) Methodology) 

3.2.1C

Westinghouse STS 3.2.1C-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

[31 EFPD 

thereafter

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

N FH

3.2.2

Westinghouse STS 3.2.2-1 Rev. 4.0 

3.2 POWER DISTRIBUTION LIMITS 

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (

N FH

) 

LCO 3.2.2 

N FH

 shall be within the limits specified in the COLR. 

APPLICABILITY: MODE 1.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

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

Required Actions A.2 

and A.3 must be 

completed whenever 

Condition A is entered.

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

N FH

not within limit.

A.1.1 Restore 

N FH

to within limit.

OR

A.1.2.1 Reduce THERMAL 

POWER to < 50% RTP.

AND

A.1.2.2 Reduce Power Range 

Neutron Flux - High trip 

setpoints to ≤ 55% RTP.

AND

A.2 Perform SR 3.2.2.1.

AND

4 hours

4 hours

72 hours

24 hours
N FH

3.2.2

Westinghouse STS 3.2.2-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

A.3 --------------NOTE--------------

THERMAL POWER does 

not have to be reduced to 

comply with this Required 

Action.

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

Perform SR 3.2.2.1. Prior to THERMAL 

POWER exceeding 

50% RTP

AND

Prior to THERMAL 

POWER exceeding 

75% RTP

AND

24 hours after 

THERMAL POWER 

reaching ≥ 95% RTP

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 2. 6 hours
N FH

3.2.2

Westinghouse STS 3.2.2-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.2.2.1 Verify 

N FH

is within limits specified in the COLR. Once after each 

refueling prior to 

THERMAL 

POWER 

exceeding 

75% RTP

AND

[ 31 EFPD 

thereafter

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

AFD (CAOC Methodology) 

3.2.3A

Westinghouse STS 3.2.3A-1 Rev. 4.0 

3.2 POWER DISTRIBUTION LIMITS 

3.2.3A AXIAL FLUX DIFFERENCE (AFD) (Constant Axial Offset Control (CAOC) 

Methodology) 

LCO 3.2.3A The AFD: 

a. Shall be maintained within the target band about the target flux 

difference. The target band is specified in the COLR. 

b. May deviate outside the target band with THERMAL POWER 

< 90% RTP but ≥ 50% RTP, provided AFD is within the acceptable 

operation limits and cumulative penalty deviation time is ≤ 1 hour 

during the previous 24 hours. The acceptable operation limits are 

specified in the COLR. 

c. May deviate outside the target band with THERMAL POWER 

< 50% RTP. 

--------------------------------------------NOTES-------------------------------------------

1. The AFD shall be considered outside the target band when two or 

more OPERABLE excore channels indicate AFD to be outside the 

target band.

2. With THERMAL POWER ≥ 50% RTP, penalty deviation time shall 

be accumulated on the basis of a 1 minute penalty deviation for 

each 1 minute of power operation with AFD outside the target band. 

3. With THERMAL POWER < 50% RTP and > 15 % RTP, penalty 

deviation time shall be accumulated on the basis of a 0.5 minute 

penalty deviation for each 1 minute of power operation with AFD 

outside the target band. 

4. A total of 16 hours of operation may be accumulated with AFD 

outside the target band without penalty deviation time during 

surveillance of power range channels in accordance with 

SR 3.3.1.6, provided AFD is maintained within acceptable operation 

limits. 

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

APPLICABILITY: MODE 1 with THERMAL POWER > 15% RTP. 
AFD (CAOC Methodology) 

3.2.3A

Westinghouse STS 3.2.3A-2 Rev. 4.0 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. THERMAL POWER 

≥ 90% RTP.

AND

AFD not within the target 

band.

A.1 Restore AFD to within 

target band.

15 minutes

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Reduce THERMAL 

POWER to < 90% RTP.

15 minutes

C. ------------NOTE------------

Required Action C.1 

must be completed 

whenever Condition C is 

entered.

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

THERMAL POWER 

< 90% and ≥ 50% RTP 

with cumulative penalty 

deviation time > 1 hour 

during the previous 

24 hours.

OR

THERMAL POWER 

< 90% and ≥ 50% RTP 

with AFD not within the 

acceptable operation 

limits.

C.1 Reduce THERMAL 

POWER to < 50% RTP.

30 minutes

D. Required Action and 

associated Completion 

Time for Condition C not 

met.

D.1 Reduce THERMAL 

POWER to < 15% RTP.

9 hours
AFD (CAOC Methodology) 

3.2.3A

Westinghouse STS 3.2.3A-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.2.3.1 Verify AFD is within limits for each OPERABLE 

excore channel.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.2.3.2 Update target flux difference. Once within 

31 EFPD after 

each refueling

AND

[ 31 EFPD 

thereafter

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AFD (CAOC Methodology) 

3.2.3A

Westinghouse STS 3.2.3A-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.2.3.3 -------------------------------NOTE------------------------------

The initial target flux difference after each refueling 

may be determined from design predictions.

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

Determine, by measurement, the target flux 

difference.

Once within 

31 EFPD after 

each refueling

AND

[ 92 EFPD 

thereafter

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AFD (RAOC Methodology) 

3.2.3B

Westinghouse STS 3.2.3B-1 Rev. 4.0 

3.2 POWER DISTRIBUTION LIMITS 

3.2.3B AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) 

Methodology) 

LCO 3.2.3B The AFD in % flux difference units shall be maintained within the limits 

specified in the COLR. 

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

The AFD shall be considered outside limits when two or more 

OPERABLE excore channels indicate AFD to be outside limits. 

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

APPLICABILITY: MODE 1 with THERMAL POWER ≥ 50% RTP. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. AFD not within limits. A.1 Reduce THERMAL 

POWER to < 50% RTP.

30 minutes

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.2.3.1 Verify AFD within limits for each OPERABLE excore 

channel.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

QPTR 

3.2.4

Westinghouse STS 3.2.4-1 Rev. 4.0 

3.2 POWER DISTRIBUTION LIMITS 

3.2.4 QUADRANT POWER TILT RATIO (QPTR) 

LCO 3.2.4 The QPTR shall be ≤ 1.02.

APPLICABILITY: MODE 1 with THERMAL POWER > 50% RTP. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. QPTR not within limit. A.1 Reduce THERMAL 

POWER ≥ 3% from RTP for 

each 1% of QPTR > 1.00.

AND

A.2 Determine QPTR.

AND

A.3 Perform SR 3.2.1.1, 

SR 3.2.1.2, and SR 3.2.2.1.

AND

2 hours after each 

QPTR determination

Once per 12 hours

24 hours after 

achieving equilibrium 

conditions from a 

THERMAL POWER 

reduction per 

Required Action A.1

AND

Once per 7 days 

thereafter
QPTR 

3.2.4

Westinghouse STS 3.2.4-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

A.4 Reevaluate safety analyses 

and confirm results remain 

valid for duration of 

operation under this 

condition.

AND

A.5 -------------NOTES-------------

1. Perform Required 

Action A.5 only after 

Required Action A.4 is 

completed.

2. Required Action A.6 

shall be completed 

whenever Required 

Action A.5 is performed.

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

Normalize excore detectors 

to restore QPTR to within 

limit.

AND

A.6 ---------------NOTE--------------

Perform Required 

Action A.6 only after 

Required Action A.5 is 

completed.

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

Perform SR 3.2.1.1, 

SR 3.2.1.2, and SR 3.2.2.1.

Prior to increasing 

THERMAL POWER 

above the limit of 

Required Action A.1

Prior to increasing 

THERMAL POWER 

above the limit of 

Required Action A.1

Within 24 hours after 

achieving equilibrium 

conditions at RTP not 

to exceed 48 hours 

after increasing 

THERMAL POWER 

above the limit of 

Required Action A.1
QPTR 

3.2.4

Westinghouse STS 3.2.4-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B. Required Action and 

associated Completion 

Time not met.

B.1 Reduce THERMAL 

POWER to ≤ 50% RTP.

4 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.2.4.1 ------------------------------NOTES-----------------------------

1. With input from one Power Range Neutron Flux 

channel inoperable and THERMAL POWER 

≤ 75% RTP, the remaining three power range 

channels can be used for calculating QPTR.

2. SR 3.2.4.2 may be performed in lieu of this 

Surveillance.

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

Verify QPTR is within limit by calculation. [ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
QPTR 

3.2.4

Westinghouse STS 3.2.4-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.2.4.2 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours after 

input from one or more Power Range Neutron Flux 

channels are inoperable with THERMAL POWER 

> 75% RTP.

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

Verify QPTR is within limit using the movable incore 

detectors.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.1A Reactor Trip System (RTS) Instrumentation (Without Setpoint Control Program) 

LCO 3.3.1A The RTS instrumentation for each Function in Table 3.3.1-1 shall be 

OPERABLE. 

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS 

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

Separate Condition entry is allowed for each Function. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Functions 

with one or more 

required channels or 

trains inoperable.

A.1 Enter the Condition 

referenced in Table 3.3.1-1 

for the channel(s) or 

train(s).

Immediately

B. One Manual Reactor 

Trip channel inoperable.

B.1 Restore channel to 

OPERABLE status.

OR

B.2 Be in MODE 3.

48 hours

54 hours

C. One channel or train 

inoperable.

C.1 Restore channel or train to 

OPERABLE status.

OR

C.2.1 Initiate action to fully insert 

all rods.

 AND

48 hours

48 hours
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C.2.2 Place the Rod Control 

System in a condition 

incapable of rod withdrawal.

49 hours

D. One Power Range 

Neutron Flux - High 

channel inoperable.

[ -------------------NOTE-------------------

The inoperable channel may be 

bypassed for up to 12 hours for 

surveillance testing and setpoint 

adjustment of other channels.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability.

One channel may be bypassed for 

up to 12 hours for surveillance 

testing and setpoint adjustment.

---------------------------------------------- ]

D.1.1 Place channel in trip.

 AND

D.1.2 Reduce THERMAL 

POWER to ≤ 75% RTP.

OR

D.2.1 Place channel in trip.

 AND

72 hours

78 hours

72 hours
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

D.2.2 --------------NOTE--------------

Only required to be 

performed when the Power 

Range Neutron Flux input 

to QPTR is inoperable.

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

Perform SR 3.2.4.2.

OR

D.3 Be in MODE 3.

Once per 12 hours

78 hours

E. One channel inoperable. [ -------------------NOTE-------------------

The inoperable channel may be 

bypassed for up to 12 hours for 

surveillance testing of other 

channels.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability:

One channel may be bypassed for 

up to 12 hours for surveillance 

testing.

---------------------------------------------- ]

E.1 Place channel in trip.

OR

E.2 Be in MODE 3.

72 hours

78 hours

F. One Intermediate Range 

Neutron Flux channel 

inoperable.

F.1 Reduce THERMAL 

POWER to < P-6.

OR

24 hours
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-4 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

F.2 Increase THERMAL 

POWER to > P-10.

24 hours

G. Two Intermediate Range 

Neutron Flux channels 

inoperable.

G.1 --------------NOTE--------------

Limited plant cooldown or 

boron dilution is allowed 

provided the change is 

accounted for in the 

calculated SDM.

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

Suspend operations 

involving positive reactivity 

additions.

AND

G.2 Reduce THERMAL 

POWER to < P-6.

Immediately

2 hours

H. One Source Range 

Neutron Flux channel 

inoperable.

H.1 --------------NOTE--------------

Limited plant cooldown or 

boron dilution is allowed 

provided the change is 

accounted for in the 

calculated SDM.

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

Suspend operations 

involving positive reactivity 

additions.

Immediately

I. Two Source Range 

Neutron Flux channels 

inoperable.

I.1 Open reactor trip breakers 

(RTBs).

Immediately
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-5 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

J. One Source Range 

Neutron Flux channel 

inoperable.

J.1 Restore channel to 

OPERABLE status.

OR

J.2.1 Initiate action to fully insert 

all rods.

 AND

J.2.2. Place the Rod Control 

System in a condition 

incapable of rod withdrawal.

48 hours

48 hours

49 hours

K. One channel inoperable. [ -------------------NOTE-------------------

The inoperable channel may be 

bypassed for up to 12 hours for 

surveillance testing of other 

channels.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability:

One channel may be bypassed for 

up to 12 hours for surveillance 

testing.

---------------------------------------------- ]

K.1 Place channel in trip.

OR

K.2 Reduce THERMAL 

POWER to < P-7.

72 hours

78 hours
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-6 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

L. One Reactor Coolant 

Pump Breaker Position 

(Single Loop) channel 

inoperable.

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

The inoperable channel may be 

bypassed for up to [4] hours for 

surveillance testing of other 

channels.

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

L.1 Restore channel to 

OPERABLE status.

OR

L.2 Reduce THERMAL 

POWER to < P-8.

[6] hours

[10] hours

M. One Reactor Coolant 

Breaker Position (Two 

Loops) channel 

inoperable.

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

The inoperable channel may be 

bypassed for up to [4] hours for 

surveillance testing of other 

channels.

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

M.1 Place the channel in trip.

OR

M.2 Reduce THERMAL 

POWER to <P-7.

[6] hours

[12] hours
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-7 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

N. One Turbine Trip 

channel inoperable.

[ -------------------NOTE-------------------

The inoperable channel may be 

bypassed for up to 12 hours for 

surveillance testing of other 

channels.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability.

One channel may be bypassed for 

up to 12 hours for surveillance 

testing.

---------------------------------------------- ]

N.1 Place channel in trip.

OR

N.2 Reduce THERMAL 

POWER to < [P-9].

72 hours

76 hours

O. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up 

to [4] hours for surveillance testing 

provided the other train is 

OPERABLE.

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

O.1 Restore train to 

OPERABLE status.

OR

O.2 Be in MODE 3.

24 hours

30 hours
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-8 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

P. One RTB train 

inoperable.

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

One train may be bypassed for up 

to 4 hours for surveillance testing, 

provided the other train is 

OPERABLE.

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

P.1 Restore train to 

OPERABLE status.

OR

P.2 Be in MODE 3.

[24] hours

[30] hours

Q. One or more channels 

inoperable.

Q.1 Verify interlock is in 

required state for existing 

unit conditions.

OR

Q.2 Be in MODE 3.

1 hour

7 hours

R. One or more channels 

inoperable.

R.1 Verify interlock is in 

required state for existing 

unit conditions.

OR

R.2 Be in MODE 2.

1 hour

7 hours

S. One trip mechanism 

inoperable for one RTB.

S.1 Restore inoperable trip 

mechanism to OPERABLE 

status.

OR

S.2 Be in MODE 3.

48 hours

54 hours
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-9 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

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

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

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

SURVEILLANCE FREQUENCY

SR 3.3.1.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.2 -----------------------------NOTE-------------------------------

Not required to be performed until [12] hours 

after THERMAL POWER is  15% RTP.

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

Compare results of calorimetric heat balance 

calculation to power range channel output. Adjust 

power range channel output if calorimetric heat 

balance calculations results exceed power range 

channel output by more than +2% RTP.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-10 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.3 -----------------------------NOTE-------------------------------

Not required to be performed until [24] hours 

after THERMAL POWER is  [15]% RTP.

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

Compare results of the incore detector 

measurements to Nuclear Instrumentation System 

(NIS) AFD. Adjust NIS channel if absolute 

difference is  3%.

[ 31 effective full 

power days 

(EFPD)

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.4 ------------------------------NOTE-------------------------------

This Surveillance must be performed on the reactor 

trip bypass breaker prior to placing the bypass 

breaker in service.

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

Perform TADOT. [ 62 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-11 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.5 Perform ACTUATION LOGIC TEST. [ 92 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

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

Not required to be performed until [24] hours after 

THERMAL POWER is ≥ 50% RTP.

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

Calibrate excore channels to agree with incore 

detector measurements.

[ [92] EFPD

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.7 ------------------------------NOTE-------------------------------

Not required to be performed for source range 

instrumentation prior to entering MODE 3 from 

MODE 2 until 4 hours after entry into MODE 3.

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

Perform COT. [ 184 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-12 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.8 ------------------------------NOTE-------------------------------

This Surveillance shall include verification that 

interlocks P-6 and P-10 are in their required state for 

existing unit conditions.

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

Perform COT. --------NOTE--------

Only required 

when not 

performed within 

[ the Frequency 

specified in the 

Surveillance 

Frequency 

Control Program 

or previous 

184 days ]

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

Prior to reactor 

startup

AND

Four hours after 

reducing power 

below P-6 for 

source range 

instrumentation

AND

[Twelve] hours 

after reducing 

power below

P-10 for power 

and intermediate 

range 

instrumentation

AND
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-13 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

[ Every 184 days 

thereafter

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.9 ------------------------------NOTE-------------------------------

Verification of setpoint is not required.

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

Perform TADOT. [ [92] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.10 ------------------------------NOTE-------------------------------

This Surveillance shall include verification that the 

time constants are adjusted to the prescribed 

values.

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

Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-14 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.11 ------------------------------NOTE-------------------------------

Neutron detectors are excluded from CHANNEL 

CALIBRATION.

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

Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.12 ------------------------------NOTE-------------------------------

This Surveillance shall include verification of 

Reactor Coolant System resistance temperature 

detector bypass loop flow rate.

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

Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.13 Perform COT. [ 18 months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-15 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.14 ------------------------------NOTE-------------------------------

Verification of setpoint is not required.

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

Perform TADOT. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.15 ------------------------------NOTE-------------------------------

Verification of setpoint is not required.

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

Perform TADOT. Prior to exceeding 

the [P-9] interlock 

whenever the unit 

has been in 

MODE 3, if not 

performed within 

the previous 

31 days
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-16 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.16 ------------------------------NOTE-------------------------------

Neutron detectors are excluded from response time 

testing.

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

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

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-17 Rev. 4.0 

Table 3.3.1-1 (page 1 of 8) 

Reactor Trip System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

1. Manual Reactor Trip 1,2 2 B SR 3.3.1.14 NA NA

3

(a), 4(a), 5(a) 2 C SR 3.3.1.14 NA NA

2. Power Range 

Neutron Flux

a. High 1,2 4 D SR 3.3.1.1

SR 3.3.1.2

SR 3.3.1.7(b)(c)

SR 3.3.1.11(b)(c)

SR 3.3.1.16

≤ [111.2]% 

RTP

[109]% RTP

b. Low 1

(d)

,2 4 E SR 3.3.1.1

SR 3.3.1.8(b)(c)

SR 3.3.1.11(b)(c)

SR 3.3.1.16

≤ [27.2]% RTP [25]% RTP

3. Power Range 

Neutron Flux Rate

a. High Positive 

Rate

1,2 4 E SR 3.3.1.7(b)(c)

SR 3.3.1.11(b)(c)

≤ [6.8]% RTP 

with time 

constant 

≥ [2] sec

[5]% RTP with 

time constant 

≥ [2] sec

b. High Negative 

Rate

1,2 4 E SR 3.3.1.7(b)(c)

SR 3.3.1.11(b)(c)

SR 3.3.1.16

≤ [6.8]% RTP 

with time 

constant 

≥ [2] sec

[5]% RTP with 

time constant 

≥ [2] sec

(a) With Rod Control System capable of rod withdrawal or one or more rods not fully insert. 

(b) 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. 

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) 

at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the 

NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance 

procedures (field setting) to confirm channel performance. The NTSP 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]. 

(d) Below the P-10 (Power Range Neutron Flux) interlocks. 

---------------------------------------------------------------------------REVIEWER’S NOTE-------------------------------------------------------------------------------------- 

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by the unit. 

---------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-18 Rev. 4.0 

Table 3.3.1-1 (page 2 of 8) 

Reactor Trip System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

4. Intermediate Range 

Neutron Flux

1

(d), 2(e) 2 F,G SR 3.3.1.1

SR 3.3.1.8(b)(c)

SR 3.3.1.11(b)(c)

≤ [31]% RTP [25]% RTP

5. Source Range 

Neutron Flux

2

(f) 2 H,I SR 3.3.1.1 

SR 3.3.1.8(b)(c)

SR 3.3.1.11(b)(c)

SR 3.3.1.16

≤ [1.4 E5] cps [1.0 E5] cps

3

(a), 4(a), 5(a) 2 I,J SR 3.3.1.1

SR 3.3.1.7(b)(c)

SR 3.3.1.11(b)(c)

SR 3.3.1.16

≤ [1.4 E5] cps [1.0 E5] cps

6. Overtemperature ∆T 1,2 [4] E SR 3.3.1.1

SR 3.3.1.3

SR 3.3.1.6

SR 3.3.1.7(b)(c)

SR 3.3.1.12(b)(c)

SR 3.3.1.16

Refer to 

Note 1 (Page 

3.3.1-19)

Refer to 

Note 1 (Page 

3.3.1-19)

7. Overpower ∆T 1,2 [4] E SR 3.3.1.1

SR 3.3.1.7

(b)(c)

SR 3.3.1.12(b)(c)

SR 3.3.1.16

Refer to 

Note 2 (Page 

3.3.1-20)

Refer to 

Note 2 (Page 

3.3.1-20)

(a) With Rod Control System capable of rod withdrawal or one or more rods not fully insert. 

(b) 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. 

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) 

at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the 

NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance 

procedures (field setting) to confirm channel performance. The NTSP 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]. 

(d) Below the P-10 (Power Range Neutron Flux) interlocks. 

(e) Above the P-6 (Intermediate Range Neutron Flux) interlocks. 

(f) Below the P-6 (Intermediate Range Neutron Flux) interlocks. 

---------------------------------------------------------------------------REVIEWER’S NOTE-------------------------------------------------------------------------------------- 

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by the unit. 

--------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------- 
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-19 Rev. 4.0 

Table 3.3.1-1 (page 3 of 8) 

Reactor Trip System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

8. Pressurizer Pressure

a. Low 1

(h)

[4] K SR 3.3.1.1

SR 3.3.1.7(b)(c)

SR 3.3.1.10(b)(c)

SR 3.3.1.16

≥ [1886] psig [1900] psig

b. High 1,2 [4] E SR 3.3.1.1

SR 3.3.1.7(b)(c)

SR 3.3.1.10(b)(c)

SR 3.3.1.16

≤ [2396] psig [2385] psig

9. Pressurizer Water

Level - High

1

(g) 3 K SR 3.3.1.1

SR 3.3.1.7(b)(c)

SR 3.3.1.10(b)(c)

≤ [93.8]% [92]%

10. Reactor Coolant 

Flow - Low

1

(g)

3 per loop K SR 3.3.1.1

SR 3.3.1.7(b)(c)

SR 3.3.1.10(b)(c)

SR 3.3.1.16

≥ [89.2]% [90]%

11. Reactor Coolant 

Pump (RCP) Breaker

Position

a. Single Loop 1

(h)

1 per RCP L SR 3.3.1.14 NA NA

b. Two Loops 1

(i)

1 per RCP M SR 3.3.1.14 NA NA

12. Undervoltage RCPs 1

(g)

[3] per bus K SR 3.3.1.9

SR 3.3.1.10(b)(c)

SR 3.3.1.16

≥ [4760] V [4830] V

(b) 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. 

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) 

at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the 

NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance 

procedures (field setting) to confirm channel performance. The NTSP 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]. 

(g) Above the P-7 (Low Power Reactor Trips Block) interlock. 

(h) Above the P-8 (Power Range Neutron Flux) interlock. 

(i) Above the P-7 (Low Power Reactor Trips Block) interlock and below the P-8 (Power Range Neutron Flux) interlock. 

---------------------------------------------------------------------------REVIEWER’S NOTE-------------------------------------------------------------------------------------- 

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by the unit. 

---------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-20 Rev. 4.0 

Table 3.3.1-1 (page 4 of 8) 

Reactor Trip System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

13. Underfrequency 

RCPs

1

(g)

[3] per bus K SR 3.3.1.9

SR 3.3.1.10(b)(c)

SR 3.3.1.16

≥ [57.1] Hz [57.5] Hz

14. Steam Generator 

(SG) Water Level -

Low Low

1,2 [4 per SG] E SR 3.3.1.1

SR 3.3.1.7(b)(c)

SR 3.3.1.10(b)(c)

SR 3.3.1.16

≥ [30.4]% [32.3]%

15. SG Water Level -

Low

1,2 2 per SG E SR 3.3.1.1

SR 3.3.1.7(b)(c)

SR 3.3.1.10

(b)(c)

SR 3.3.1.16

≥ [30.4]% [32.3]%

Coincident with 

Steam 

Flow/Feedwater Flow 

Mismatch

1,2 2 per SG E SR 3.3.1.1

SR 3.3.1.7(b)(c)

SR 3.3.1.10(b)(c)

SR 3.3.1.16

≤ [42.5]% full 

steam flow at 

RTP

[40]% full 

steam flow at 

RTP

16. Turbine Trip

a. Low Fluid Oil 

Pressure

1

(j)

3 N SR 3.3.1.10(b)(c)

SR 3.3.1.15

≥ [750] psig [800] psig

b. Turbine Stop 

Valve Closure

1

(j)

4 N SR 3.3.1.10

SR 3.3.1.15

≥ [1]% open [1]% open

17. Safety Injection (SI) 

Input from 

Engineered Safety 

Feature Actuation 

System (ESFAS)

1,2 2 trains O SR 3.3.1.14 NA NA

(b) 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. 

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) 

at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the 

NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance 

procedures (field setting) to confirm channel performance. The NTSP 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]. 

(g) Above the P-7 (Low Power Reactor Trips Block) interlock. 

(j) Above the P-9 (Power Range Neutron Flux) interlock. 

---------------------------------------------------------------------------REVIEWER’S NOTE-------------------------------------------------------------------------------------- 

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by the unit. 

--------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------- 
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-21 Rev. 4.0 

Table 3.3.1-1 (page 5 of 8) 

Reactor Trip System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

18. Reactor Trip System 

Interlocks

a. Intermediate 

Range Neutron 

Flux, P-6

2

(f)

2 Q SR 3.3.1.11

SR 3.3.1.13

≥ [6E-11] amp [1E-10] amp

b. Low Power 

Reactor Trips 

Block, P-7

1 1 per train R SR 3.3.1.5 NA NA

c. Power Range 

Neutron Flux, 

P-8

1 4 R SR 3.3.1.11

SR 3.3.1.13

≤ [50.2]% RTP [48]% RTP

d. Power Range 

Neutron Flux, 

P-9

1 4 R SR 3.3.1.11

SR 3.3.1.13

≤ [52.2]% RTP [50]% RTP

e. Power Range 

Neutron Flux, 

P-10

1,2 4 Q SR 3.3.1.11

SR 3.3.1.13

≥ [7.8]% RTP 

and ≤ [12.2]% 

RTP

[10]% RTP

f. Turbine Impulse 

Pressure, P-13

1 2 R [SR 3.3.1.1]

SR 3.3.1.10

SR 3.3.1.13

≤ [12.2]% 

turbine power

10]% turbine 

power

19. Reactor Trip 

Breakers(k)(RTBs)

1,2 2 trains P SR 3.3.1.4 NA NA

3

(a)

, 4(a), 5(a)2 trains C SR 3.3.1.4 NA NA

(a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted. 

(f) Below the P-6 (Intermediate Range Neutron Flux) interlocks. 

(k) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB. 

---------------------------------------------------------------------------REVIEWER’S NOTE-------------------------------------------------------------------------------------- 

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by the unit. 

--------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------- 
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-22 Rev. 4.0 

Table 3.3.1-1 (page 6 of 8) 

Reactor Trip System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

20. Reactor Trip Breaker 

Undervoltage and 

Shunt Trip 

Mechanisms

1,2 1 each per 

RTB

S SR 3.3.1.4 NA NA

3

(a)

, 4(a), 5(a)1 each per 

RTB

C SR 3.3.1.4 NA NA

21. Automatic Trip Logic 1,2 2 trains O SR 3.3.1.5 NA NA

3

(a)

, 4(a), 5(a)2 trains C SR 3.3.1.5 NA NA

(a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted. 

---------------------------------------------------------------------------REVIEWER’S NOTE-------------------------------------------------------------------------------------- 

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by the unit. 

--------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------- 
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-23 Rev. 4.0 

Table 3.3.1-1 (page 7 of 8) 

Reactor Trip System Instrumentation 

Note 1: Overtemperature ∆T 

The Overtemperature ∆T Function Allowable Value shall not exceed the following [Nominal Trip 

Setpoint] by more than [3.8]% of ∆T span. 













   











 

 























 )()(

)1(

1

)1(

)1(

1

1

)1(

)1(

3 1

5 6

4

21

2 3

1

IfPPKT

ST

T

ST

ST

KKT

STST

ST

T Q

Where: ∆T is measured RCS ∆T,°F. 

 ∆TQ is the indicated ∆T at RTP,°F. 

 s is the Laplace transform operator, sec-1. 

 T is the measured RCS average temperature,°F. 

 T' is the nominal Tavg at RTP, ≤ [*]°F. 

 P is the measured pressurizer pressure, psig 

 P' is the nominal RCS operating pressure, ≥ [*] psig 

K1 ≤ [*] K2 ≥ [*]/°F K3 ≥ [*]/psig

 T1 ≥ [*] sec T2 ≤ [*] sec T3 ≤ [*] sec 

 T4 ≥ [*] sec T5 ≤ [*] sec T6 ≤ [*] sec 

 f1(∆I) = [*] {[*] - (qt - qb)} when qt - qb ≤ [*]% RTP 

 0% of RTP when [*]% RTP < qt - qb ≤ [*]% RTP 

 [*] {(qt - qb) - [*]} when qt - qb > [*]% RTP 

Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, 

and qt + qb is the total THERMAL POWER in percent RTP. 

*These values denoted with [*] are specified in the COLR. 
RTS Instrumentation (Without Setpoint Control Program) 

3.3.1A 

Westinghouse STS 3.3.1A-24 Rev. 4.0 

Table 3.3.1-1 (page 8 of 8) 

Reactor Trip System Instrumentation 

Note 2: Overpower ∆T 

The Overpower ∆T Function Allowable Value shall not exceed the following [Nominal Trip Setpoint] by 

more than [3]% of ∆T span. 













 











 



 





































 )(

1

1

1

1

1 1

1

)1(

)1(

2

6

6

7 6

7

54

2 3

1

IfT

ST

TKT

STST

ST

KKT

STST

ST

T Q

Where: ∆T is measured RCS ∆T,°F. 

 ∆TQ is the indicated ∆T at RTP,°F. 

 s is the Laplace transform operator, sec-1. 

 T is the measured RCS average temperature,°F. 

 T" is the nominal Tavg at RTP, ≤ [*]°F. 

 K4 ≤ [*] K5 ≥ [*]/°F for increasing Tavg K6 ≥ [*]/°F when T > T"

 [*]/°F for decreasing Tavg [*]/°F when T ≤ T"

T1 ≥ [*] sec T2 ≤ [*] sec T3 ≤ [*] sec

 T6 ≤ [*] sec T7 ≥ [*] sec 

 f2(∆I) = [*]

*These values denoted with [*] are specified in the COLR.
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.1B Reactor Trip System (RTS) Instrumentation (With Setpoint Control Program) 

LCO 3.3.1B The RTS instrumentation for each Function in Table 3.3.1-1 shall be 

OPERABLE. 

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS 

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

Separate Condition entry is allowed for each Function. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Functions 

with one or more 

required channels or 

trains inoperable.

A.1 Enter the Condition 

referenced in Table 3.3.1-1 

for the channel(s) or 

train(s).

Immediately

B. One Manual Reactor 

Trip channel inoperable.

B.1 Restore channel to 

OPERABLE status.

OR

B.2 Be in MODE 3.

48 hours

54 hours

C. One channel or train 

inoperable.

C.1 Restore channel or train to 

OPERABLE status.

OR

C.2.1 Initiate action to fully insert 

all rods.

 AND

48 hours

48 hours
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C.2.2 Place the Rod Control 

System in a condition 

incapable of rod withdrawal.

49 hours

D. One Power Range 

Neutron Flux - High 

channel inoperable.

[ -------------------NOTE-------------------

The inoperable channel may be 

bypassed for up to 12 hours for 

surveillance testing and setpoint 

adjustment of other channels.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability.

One channel may be bypassed for 

up to 12 hours for surveillance 

testing and setpoint adjustment.

---------------------------------------------- ]

D.1.1 Place channel in trip.

 AND

D.1.2 Reduce THERMAL 

POWER to ≤ 75% RTP.

OR

D.2.1 Place channel in trip.

 AND

72 hours

78 hours

72 hours
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

D.2.2 --------------NOTE--------------

Only required to be 

performed when the Power 

Range Neutron Flux input 

to QPTR is inoperable.

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

Perform SR 3.2.4.2.

OR

D.3 Be in MODE 3.

Once per 12 hours

78 hours

E. One channel inoperable. [ -------------------NOTE-------------------

The inoperable channel may be 

bypassed for up to 12 hours for 

surveillance testing of other 

channels.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability:

One channel may be bypassed for 

up to 12 hours for surveillance 

testing.

---------------------------------------------- ]

E.1 Place channel in trip.

OR

E.2 Be in MODE 3.

72 hours

78 hours

F. One Intermediate Range 

Neutron Flux channel 

inoperable.

F.1 Reduce THERMAL 

POWER to < P-6.

OR

24 hours
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-4 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

F.2 Increase THERMAL 

POWER to > P-10.

24 hours

G. Two Intermediate Range 

Neutron Flux channels 

inoperable.

G.1 --------------NOTE--------------

Limited plant cooldown or 

boron dilution is allowed 

provided the change is 

accounted for in the 

calculated SDM.

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

Suspend operations 

involving positive reactivity 

additions.

AND

G.2 Reduce THERMAL 

POWER to < P-6.

Immediately

2 hours

H. One Source Range 

Neutron Flux channel 

inoperable.

H.1 --------------NOTE--------------

Limited plant cooldown or 

boron dilution is allowed 

provided the change is 

accounted for in the 

calculated SDM.

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

Suspend operations 

involving positive reactivity 

additions.

Immediately

I. Two Source Range 

Neutron Flux channels 

inoperable.

I.1 Open reactor trip breakers 

(RTBs).

Immediately
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-5 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

J. One Source Range 

Neutron Flux channel 

inoperable.

J.1 Restore channel to 

OPERABLE status.

OR

J.2.1 Initiate action to fully insert 

all rods.

 AND

J.2.2. Place the Rod Control 

System in a condition 

incapable of rod withdrawal.

48 hours

48 hours

49 hours

K. One channel inoperable. [ -------------------NOTE-------------------

The inoperable channel may be 

bypassed for up to 12 hours for 

surveillance testing of other 

channels.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability:

One channel may be bypassed for 

up to 12 hours for surveillance 

testing.

---------------------------------------------- ]

K.1 Place channel in trip.

OR

K.2 Reduce THERMAL 

POWER to < P-7.

72 hours

78 hours
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-6 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

L. One Reactor Coolant 

Pump Breaker Position 

(Single Loop) channel 

inoperable.

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

The inoperable channel may be 

bypassed for up to [4] hours for 

surveillance testing of other 

channels.

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

L.1 Restore channel to 

OPERABLE status.

OR

L.2 Reduce THERMAL 

POWER to < P-8.

[6] hours

[10] hours

M. One Reactor Coolant 

Breaker Position (Two 

Loops) channel 

inoperable.

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

The inoperable channel may be 

bypassed for up to [4] hours for 

surveillance testing of other 

channels.

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

M.1 Place the channel in trip.

OR

M.2 Reduce THERMAL 

POWER to <P-7.

[6] hours

[12] hours
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-7 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

N. One Turbine Trip 

channel inoperable.

[ -------------------NOTE-------------------

The inoperable channel may be 

bypassed for up to 12 hours for 

surveillance testing of other 

channels.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability.

One channel may be bypassed for 

up to 12 hours for surveillance 

testing.

---------------------------------------------- ]

N.1 Place channel in trip.

OR

N.2 Reduce THERMAL 

POWER to < [P-9].

72 hours

76 hours

O. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up 

to [4] hours for surveillance testing 

provided the other train is 

OPERABLE.

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

O.1 Restore train to 

OPERABLE status.

OR

O.2 Be in MODE 3.

24 hours

30 hours
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-8 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

P. One RTB train 

inoperable.

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

One train may be bypassed for up 

to 4 hours for surveillance testing, 

provided the other train is 

OPERABLE.

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

P.1 Restore train to 

OPERABLE status.

OR

P.2 Be in MODE 3.

[24] hours

[30] hours

Q. One or more channels 

inoperable.

Q.1 Verify interlock is in 

required state for existing 

unit conditions.

OR

Q.2 Be in MODE 3.

1 hour

7 hours

R. One or more channels 

inoperable.

R.1 Verify interlock is in 

required state for existing 

unit conditions.

OR

R.2 Be in MODE 2.

1 hour

7 hours

S. One trip mechanism 

inoperable for one RTB.

S.1 Restore inoperable trip 

mechanism to OPERABLE 

status.

OR

S.2 Be in MODE 3.

48 hours

54 hours
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-9 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

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

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

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

SURVEILLANCE FREQUENCY

SR 3.3.1.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.2 -----------------------------NOTE-------------------------------

Not required to be performed until [12] hours 

after THERMAL POWER is  15% RTP.

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

Compare results of calorimetric heat balance 

calculation to power range channel output. Adjust 

power range channel output if calorimetric heat 

balance calculations results exceed power range 

channel output by more than +2% RTP.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-10 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.3 -----------------------------NOTE-------------------------------

Not required to be performed until [24] hours 

after THERMAL POWER is  [15]% RTP.

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

Compare results of the incore detector 

measurements to Nuclear Instrumentation System 

(NIS) AFD. Adjust NIS channel if absolute 

difference is  3%.

[ 31 effective full 

power days 

(EFPD)

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.4 ------------------------------NOTE-------------------------------

This Surveillance must be performed on the reactor 

trip bypass breaker prior to placing the bypass 

breaker in service.

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

Perform TADOT. [ 62 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-11 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.5 Perform ACTUATION LOGIC TEST. [ 92 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

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

Not required to be performed until [24] hours after 

THERMAL POWER is ≥ 50% RTP.

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

Calibrate excore channels to agree with incore 

detector measurements.

[ [92] EFPD

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.7 ------------------------------NOTE-------------------------------

Not required to be performed for source range 

instrumentation prior to entering MODE 3 from 

MODE 2 until 4 hours after entry into MODE 3.

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

Perform COT in accordance with the Setpoint 

Control Program.

[ 184 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-12 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.8 ------------------------------NOTE-------------------------------

This Surveillance shall include verification that 

interlocks P-6 and P-10 are in their required state for 

existing unit conditions.

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

Perform COT in accordance with the Setpoint 

Control Program.

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

Only required 

when not 

performed within 

[ the Frequency 

specified in the 

Surveillance 

Frequency 

Control Program 

or previous 

184 days ]

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

Prior to reactor 

startup

AND

Four hours after 

reducing power 

below P-6 for 

source range 

instrumentation

AND

[Twelve] hours

after reducing 

power below

P-10 for power 

and intermediate 

range 

instrumentation

AND
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-13 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

[ Every 184 days 

thereafter

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.9 ------------------------------NOTE-------------------------------

Verification of setpoint is not required.

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

Perform TADOT. [ [92] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.10 ------------------------------NOTE-------------------------------

This Surveillance shall include verification that the 

time constants are adjusted to the prescribed 

values.

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

Perform CHANNEL CALIBRATION in accordance 

with the Setpoint Control Program.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-14 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.11 ------------------------------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 ]

SR 3.3.1.12 ------------------------------NOTE-------------------------------

This Surveillance shall include verification of 

Reactor Coolant System resistance temperature 

detector bypass loop flow rate.

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

Perform CHANNEL CALIBRATION in accordance 

with the Setpoint Control Program.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.13 Perform COT. [ 18 months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-15 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.14 ------------------------------NOTE-------------------------------

Verification of setpoint is not required.

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

Perform TADOT. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.1.15 ------------------------------NOTE-------------------------------

Verification of setpoint is not required.

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

Perform TADOT. Prior to exceeding 

the [P-9] interlock 

whenever the unit 

has been in 

MODE 3, if not 

performed within 

the previous 

31 days
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-16 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.1.16 ------------------------------NOTE-------------------------------

Neutron detectors are excluded from response time 

testing.

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

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

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-17 Rev. 4.0 

Table 3.3.1-1 (page 1 of 4) 

Reactor Trip System Instrumentation 

FUNCTION

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

1. Manual Reactor Trip 1,2 2 B SR 3.3.1.14

3

(a), 4(a), 5(a) 2 C SR 3.3.1.14

2. Power Range Neutron Flux

a. High 1,2 4 D SR 3.3.1.1

SR 3.3.1.2

SR 3.3.1.7

SR 3.3.1.11

SR 3.3.1.16

b. Low 1

(b),2 4 E SR 3.3.1.1

SR 3.3.1.8

SR 3.3.1.11

SR 3.3.1.16

3. Power Range Neutron Flux Rate

a. High Positive Rate 1,2 4 E SR 3.3.1.7

SR 3.3.1.11

b. High Negative Rate 1,2 4 E SR 3.3.1.7

SR 3.3.1.11

SR 3.3.1.16

4. Intermediate Range Neutron Flux 1

(b), 2(c) 2 F,G SR 3.3.1.1

SR 3.3.1.8

SR 3.3.1.11

5. Source Range Neutron Flux 2

(d) 2 H,I SR 3.3.1.1 

SR 3.3.1.8

SR 3.3.1.11

SR 3.3.1.16

3

(a), 4(a), 5(a) 2 I,J SR 3.3.1.1

SR 3.3.1.7

SR 3.3.1.11

SR 3.3.1.16

6. Overtemperature ∆T 1,2 [4] E SR 3.3.1.1

SR 3.3.1.3

SR 3.3.1.6

SR 3.3.1.7

SR 3.3.1.12

SR 3.3.1.16

(a) With Rod Control System capable of rod withdrawal or one or more rods not fully insert. 

(b) Below the P-10 (Power Range Neutron Flux) interlocks. 

(c) Above the P-6 (Intermediate Range Neutron Flux) interlocks. 

(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks. 
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-18 Rev. 4.0 

Table 3.3.1-1 (page 2 of 4) 

Reactor Trip System Instrumentation 

FUNCTION

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

7. Overpower ∆T 1,2 [4] E SR 3.3.1.1

SR 3.3.1.7

SR 3.3.1.12

SR 3.3.1.16

8. Pressurizer Pressure

a. Low 1

(f) [4] K SR 3.3.1.1

SR 3.3.1.7

SR 3.3.1.10

SR 3.3.1.16

b. High 1,2 [4] E SR 3.3.1.1

SR 3.3.1.7

SR 3.3.1.10

SR 3.3.1.16

9. Pressurizer Water Level - High 1

(e) 3 K SR 3.3.1.1

SR 3.3.1.7

SR 3.3.1.10

10. Reactor Coolant Flow - Low 1

(e)

3 per loop K SR 3.3.1.1

SR 3.3.1.7

SR 3.3.1.10

SR 3.3.1.16

11. Reactor Coolant Pump (RCP) Breaker 

Position

a. Single Loop 1

(f) 1 per RCP L SR 3.3.1.14

b. Two Loops 1

(g) 1 per RCP M SR 3.3.1.14

12. Undervoltage RCPs 1

(e) [3] per bus K SR 3.3.1.9

SR 3.3.1.10

SR 3.3.1.16

13. Underfrequency RCPs 1

(e) [3] per bus K SR 3.3.1.9

SR 3.3.1.10

SR 3.3.1.16

14. Steam Generator (SG) Water Level -

Low Low

1,2 [4 per SG] E SR 3.3.1.1

SR 3.3.1.7

SR 3.3.1.10

SR 3.3.1.16

(e) Above the P-7 (Low Power Reactor Trips Block) interlock. 

(f) Above the P-8 (Power Range Neutron Flux) interlock. 

(g) Above the P-7 (Low Power Reactor Trips Block) interlock and below the P-8 (Power Range Neutron Flux) Interlock 
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-19 Rev. 4.0 

Table 3.3.1-1 (page 3 of 4) 

Reactor Trip System Instrumentation 

FUNCTION

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

15. SG Water Level - Low 1,2 2 per SG E SR 3.3.1.1

SR 3.3.1.7

SR 3.3.1.10

SR 3.3.1.16

Coincident with Steam 

Flow/Feedwater Flow Mismatch

1,2 2 per SG E SR 3.3.1.1

SR 3.3.1.7

SR 3.3.1.10

SR 3.3.1.16

16. Turbine Trip

a. Low Fluid Oil Pressure 1

(h) 3 N SR 3.3.1.10

SR 3.3.1.15

b. Turbine Stop Valve Closure 1

(h) 4 N SR 3.3.1.10

SR 3.3.1.15

17. Safety Injection (SI) Input from 

Engineered Safety Feature Actuation 

System (ESFAS)

1,2 2 trains O SR 3.3.1.14

18. Reactor Trip System Interlocks

a. Intermediate Range Neutron Flux, 

P-6

2

(d) 2 Q SR 3.3.1.11

SR 3.3.1.13

b. Low Power Reactor Trips Block, 

P-7

1 1 per train R SR 3.3.1.5

c. Power Range Neutron Flux, P-8 1 4 R SR 3.3.1.11

SR 3.3.1.13

d. Power Range Neutron Flux, P-9 1 4 R SR 3.3.1.11

SR 3.3.1.13

e. Power Range Neutron Flux, P-10 1,2 4 Q SR 3.3.1.11

SR 3.3.1.13

f. Turbine Impulse Pressure, P-13 1 2 R [SR 3.3.1.1]

SR 3.3.1.10

SR 3.3.1.13

(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks. 

(h) Above the P-9 (Power Range Neutron Flux) interlock. 
RTS Instrumentation (With Setpoint Control Program) 

3.3.1B 

Westinghouse STS 3.3.1B-20 Rev. 4.0 

Table 3.3.1-1 (page 4 of 4) 

Reactor Trip System Instrumentation 

FUNCTION

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

19. Reactor Trip Breakers(i) (RTBs) 1,2 2 trains P SR 3.3.1.4

3

(a)

, 4(a), 5(a)2 trains C SR 3.3.1.4

20. Reactor Trip Breaker Undervoltage 

and Shunt Trip Mechanisms

1,2 1 each per RTB S SR 3.3.1.4

3

(a)

, 4(a), 5(a)1 each per RTB C SR 3.3.1.4

21. Automatic Trip Logic 1,2 2 trains O SR 3.3.1.5

3

(a)

, 4(a), 5(a)2 trains C SR 3.3.1.5

(a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted. 

(i) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB. 
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.2A Engineered Safety Feature Actuation System (ESFAS) Instrumentation (Without 

Setpoint Control Program) 

LCO 3.3.2A The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be 

OPERABLE. 

APPLICABILITY: According to Table 3.3.2-1.

ACTIONS 

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

Separate Condition entry is allowed for each Function. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Functions 

with one or more 

required channels or 

trains inoperable.

A.1 Enter the Condition 

referenced in Table 3.3.2-1 

for the channel(s) or 

train(s).

Immediately

B. One channel or train 

inoperable.

B.1 Restore channel or train to 

OPERABLE status.

OR

B.2.1 Be in MODE 3.

 AND

B.2.2 Be in MODE 5.

48 hours

54 hours

84 hours
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up 

to [4] hours for surveillance testing 

provided the other train is 

OPERABLE.

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

C.1 Restore train to 

OPERABLE status.

OR

C.2.1 Be in MODE 3.

 AND

C.2.2 Be in MODE 5.

24 hours

30 hours

60 hours

D. One channel inoperable. [ ------------------NOTE-------------------

The inoperable channel may be 

bypassed for up to 12 hours for 

surveillance testing of other 

channels.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability: 

One channel may be bypassed for 

up to 12 hours for surveillance 

testing.

---------------------------------------------- ]

D.1 Place channel in trip.

OR

72 hours
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-3 Rev. 4.0 

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

D.2.1 Be in MODE 3.

 AND

D.2.2 Be in MODE 4.

78 hours

84 hours

E. One Containment 

Pressure channel 

inoperable.

[ ------------------NOTE-------------------

One additional channel may be 

bypassed for up to 12 hours for 

surveillance testing of other 

channels.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability.

One channel may be bypassed for 

up to 12 hours for surveillance 

testing.

---------------------------------------------- ]

E.1 Place channel in bypass.

OR

E.2.1 Be in MODE 3.

 AND

E.2.2 Be in MODE 4.

72 hours

78 hours

84 hours

F. One channel or train 

inoperable.

F.1 Restore channel or train to 

OPERABLE status.

OR

F.2.1 Be in MODE 3. 

 AND

48 hours

54 hours
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-4 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

F.2.2 Be in MODE 4. 60 hours

G. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up 

to [4] hours for surveillance testing 

provided the other train is 

OPERABLE.

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

G.1 Restore train to 

OPERABLE status.

OR

G.2.1 Be in MODE 3.

 AND

G.2.2 Be in MODE 4.

24 hours

30 hours

36 hours

H. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up 

to [4] hours for surveillance testing 

provided the other train is 

OPERABLE.

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

H.1 Restore train to 

OPERABLE status.

OR

H.2 Be in MODE 3.

24 hours

30 hours
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-5 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

I. One channel inoperable. [ ------------------NOTE-------------------

The inoperable channel may be 

bypassed for up to 12 hours for 

surveillance testing of other 

channels.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability.

One channel may be bypassed for 

up to 12 hours for surveillance 

testing.

---------------------------------------------- ]

I.1 Place channel in trip.

OR

I.2 Be in MODE 3.

72 hours

78 hours

J. One Main Feedwater 

Pumps trip channel 

inoperable.

J.1 Restore channel to 

OPERABLE status.

OR

J.2 Be in MODE 3.

48 hours

54 hours
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-6 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

K. One channel inoperable. [ ------------------NOTE-------------------

One additional channel may be 

bypassed for up to [4] hours for 

surveillance testing.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability:

One channel may be bypassed for 

up to 12 hours for surveillance 

testing.

---------------------------------------------- ]

K.1 Place channel in bypass.

OR

K.2.1 Be in MODE 3.

 AND

K.2.2 Be in MODE 5.

[6] hours

[12] hours

[42] hours

L. One or more channels 

inoperable.

L.1 Verify interlock is in 

required state for existing 

unit condition.

OR

L.2.1 Be in MODE 3.

 AND

L.2.2 Be in MODE 4.

1 hour

7 hours

13 hours
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-7 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

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

Refer to Table 3.3.2-1 to determine which SRs apply for each ESFAS Function. 

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

SURVEILLANCE FREQUENCY

SR 3.3.2.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.2.2 Perform ACTUATION LOGIC TEST. [ 92 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.2.3 ------------------------------NOTE-------------------------------

The continuity check may be excluded.

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

Perform ACTUATION LOGIC TEST. [ 31 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-8 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

----------------------------------REVIEWER’S NOTE---------------------------------

The Frequency remains at 31 days on a STAGGERED TEST BASIS for 

plants with a Relay Protection System.

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

SR 3.3.2.4 Perform MASTER RELAY TEST. [ 92 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.2.5 Perform COT. [ 184 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.2.6 Perform SLAVE RELAY TEST. [ [92] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-9 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

SR 3.3.2.7 ------------------------------NOTE-------------------------------

Verification of relay setpoints not required.

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

Perform TADOT. [ [92] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.2.8 ------------------------------NOTE-------------------------------

Verification of setpoint not required for manual 

initiation functions.

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

Perform TADOT. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-10 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.2.9 ------------------------------NOTE-------------------------------

This Surveillance shall include verification that the 

time constants are adjusted to the prescribed 

values.

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

Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.2.10 ------------------------------NOTE-------------------------------

Not required to be performed for the turbine driven 

AFW pump until [24] hours after SG pressure is 

≥ [1000] psig.

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

Verify ESFAS RESPONSE TIMES are within limit. [ [18] months on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.2.11 ------------------------------NOTE-------------------------------

Verification of setpoint not required.

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

Perform TADOT. Once per reactor 

trip breaker cycle
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-11 Rev. 4.0 

Table 3.3.2-1 (page 1 of 11) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

1. Safety Injection

a. Manual Initiation 1,2,3,4 2 B SR 3.3.2.8 NA NA

b. Automatic 

Actuation Logic 

and Actuation 

Relays

1,2,3,4 2 trains C SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

NA NA

c. Containment 

Pressure -

High 1

1,2,3 3 D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≤ [3.86] psig [3.6] psig

d. Pressurizer 

Pressure - Low

1,2,3 (a) [3] D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≥ [1839] psig [1850] psig

e. Steam Line 

Pressure

(1) Low 1,2,3 [(a)] 3 per 

steam line

D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≥ [635](d)psig [675](d)psig

(2) High 

Differential 

Pressure 

Between 

Steam Lines

1,2,3 3 per 

steam line

D [SR 3.3.2.1]

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≤ [106] psig [97] psig

(a) Above the P-11 (Pressurizer Pressure) interlock. 

(b) 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. 

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

Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints 

more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual 

setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTSP 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]. 

(d) Time constants used in the lead/lag controller are t1 ≥ [50] seconds and t2 ≤ [5] seconds. 

-----------------------------------------------------------------------REVIEWER'S NOTE--------------------------------------------------------------------- 

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by 

the unit. 

------------------------------------------------------------------------------------------------------------------------------------------------------------------------ 
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-12 Rev. 4.0 

Table 3.3.2-1 (page 2 of 11) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

1. Safety Injection

f. High Steam Flow 

in Two Steam 

Lines

1,2,3 (e)2 per 

steam line

D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

(f) (g)

Coincident with 

Tavg - Low Low

1,2,3 (e)1 per loop D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≥ [550.6]°F [553]°F

g. High Steam Flow 

in Two Steam 

Lines

1,2,3 (e)2 per 

steam line

D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

(f) (g)

Coincident with 

Steam Line 

Pressure - Low

1,2,3 (e)1 per 

steam line

D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≥ [635](d)

psig

[675] psig

2. Containment Spray

a. Manual Initiation 1,2,3,4 2 per train, 

2 trains

B SR 3.3.2.8 NA NA

(b) 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. 

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

Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints 

more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual 

setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTSP 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]. 

(d) Time constants used in the lead/lag controller are t1 ≥ [50] seconds and t2 ≤ [5] seconds. 

(e) Above the P-12 (Tavg - Low Low) interlock. 

(f) Less than or equal to a function defined as ∆P corresponding to [44]% full steam flow below [20]% load, and ∆P 

increasing linearly from [44]% full steam flow at [20]% load to [114]% full steam flow at [100]% load, and ∆P 

corresponding to [114]% full steam flow above 100% load. 

(g) Less than or equal to a function defined as ∆P corresponding to [40]% full steam flow between [0]% and [20]% load 

and then a ∆P increasing linearly from [40]% steam flow at [20]% load to [110]% full steam flow at [100]% load. 

-----------------------------------------------------------------------REVIEWER'S NOTE--------------------------------------------------------------------- 

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by 

the unit. 

------------------------------------------------------------------------------------------------------------------------------------------------------------------------
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-13 Rev. 4.0 

Table 3.3.2-1 (page 3 of 11) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

2. Containment Spray

b. Automatic 

Actuation Logic 

and Actuation 

Relays

1,2,3,4 2 trains C SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

NA NA

c. Containment 

Pressure High -

3 (High High)

1,2,3 4 E SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10 

≤ [12.31] psig [12.05] psig

d. Containment 

Pressure High -

3 (Two Loop 

Plants)

1,2,3 [3] sets of 

[2]

E SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≤ [12.31] psig [12.05] psig

3. Containment 

Isolation

a. Phase A 

Isolation

(1) Manual 

Initiation

1,2,3,4 2 B SR 3.3.2.8 NA NA

(2) Automatic 

Actuation Logic 

and Actuation 

Relays

1,2,3,4 2 trains C SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

NA NA

(3) Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

(b) 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. 

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

Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints 

more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual 

setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTSP 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]. 

-----------------------------------------------------------------------REVIEWER'S NOTE--------------------------------------------------------------------- 

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by 

the unit. 

------------------------------------------------------------------------------------------------------------------------------------------------------------------------ 
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-14 Rev. 4.0 

Table 3.3.2-1 (page 4 of 11) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

3. Containment 

Isolation 

b. Phase B 

Isolation

(1) Manual 

Initiation

1,2,3,4 2 per train, 

2 trains

B SR 3.3.2.8 NA NA

(2) Automatic 

Actuation Logic 

and Actuation 

Relays

1,2,3,4 2 trains C SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

NA NA

(3) Containment 

Pressure High 

- 3 (High High)

1,2,3 [4] E SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≤ [12.31] psig [12.05] psig

4. Steam Line Isolation

a. Manual Initiation 1,2 (j),3 (j) 2 F SR 3.3.2.8 NA NA

b. Automatic 

Actuation Logic 

and Actuation 

Relays

1,2 (j),3 (j) 2 trains G SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

NA NA

c. Containment 

Pressure - High 

2

1,2 (j),3 (j) [4] D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≤ [6.61] psig [6.35] psig

(b) 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. 

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

Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints 

more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual 

setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTSP 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]. 

(j) Except when all MSIVs are closed and [de-activated]. 

-----------------------------------------------------------------------REVIEWER'S NOTE--------------------------------------------------------------------- 

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by 

the unit. 

------------------------------------------------------------------------------------------------------------------------------------------------------------------------ 
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-15 Rev. 4.0 

Table 3.3.2-1 (page 5 of 11) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

4. Steam Line Isolation

d. Steam Line 

Pressure

(1) Low 1,2 (j)

,3

(j) (a)

3 per 

steam line

D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≥ [635](d)psig [675](d)psig

(2) Negative Rate 

- High

3

(h) (j) 3 per 

steam line

D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≤ [121.6](i)psi [110](i)psi

(a) Above the P-11 (Pressurizer Pressure) interlock. 

(b) 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. 

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

Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints 

more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual 

setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTSP 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]. 

(d) Time constants used in the lead/lag controller are t1 ≥ [50] seconds and t2 ≤ [5] seconds. 

(h) Below the P-11 (Pressurizer Pressure) interlock. 

(i) Time constant utilized in the rate/lag controller is ≥ [50] seconds. 

(j) Except when all MSIVs are closed and [de-activated]. 

-----------------------------------------------------------------------REVIEWER'S NOTE--------------------------------------------------------------------- 

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by 

the unit. 

------------------------------------------------------------------------------------------------------------------------------------------------------------------------
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-16 Rev. 4.0 

Table 3.3.2-1 (page 6 of 11) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

4. Steam Line Isolation

e. High Steam Flow 

in Two Steam 

Lines

1,2 (j),3

(j)

2 per 

steam line

D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

(f) (g)

Coincident with 

Tavg - Low Low

1,2 (j),3 (e) (j)1 per loop D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≥ [550.6]°F [553]°F

f. High Steam Flow 

in Two Steam 

Lines

1,2 (j),3 (j)2 per 

steam line

D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

(f) (g)

Coincident with 

Steam Line 

Pressure - Low

1,2 (j),3 (j)1 per 

steam line

D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≥ [635](d)psig [675](d)psig

(b) 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. 

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

Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints 

more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual 

setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTSP 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]. 

(d) Time constants used in the lead/lag controller are t1 ≥ [50] seconds and t2 ≤ [5] seconds. 

(e) Above the P-12 (Tavg - Low Low) interlock. 

(f) Less than or equal to a function defined as ∆P corresponding to [44]% full steam flow below [20]% load, and ∆P 

increasing linearly from [44]% full steam flow at [20]% load to [114]% full steam flow at [100]% load, and ∆P 

corresponding to [114]% full steam flow above 100% load. 

(g) Less than or equal to a function defined as ∆P corresponding to [40]% full steam flow between [0]% and [20]% load 

and then a ∆P increasing linearly from [40]% steam flow at [20]% load to [110]% full steam flow at [100]% load. 

(j) Except when all MSIVs are closed and [de-activated]. 

-----------------------------------------------------------------------REVIEWER'S NOTE---------------------------------------------------------------------

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by 

the unit. 

------------------------------------------------------------------------------------------------------------------------------------------------------------------------
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-17 Rev. 4.0 

Table 3.3.2-1 (page 7 of 11) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

4. Steam Line Isolation

g. High Steam Flow 1,2 (j)

,3

(j)

2 per 

steam line

D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≤ [25]% of full 

steam flow at 

no load steam 

pressure

[ ] full steam 

flow at no 

load steam 

pressure

Coincident with 

Safety Injection

Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

and

Coincident with

Tavg - Low Low

1,2 (j),3 (e) (j)[2] per loop D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≥ [550.6]°F [553]°F

h. High High Steam 

Flow

1,2 (j),3 (j)2 per 

steam line

D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≤ [130]% of 

full steam flow 

at full load 

steam 

pressure

[ ] of full steam 

flow at full 

load steam 

pressure

Coincident with 

Safety Injection

Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

(b) 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. 

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

Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints 

more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual 

setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTSP 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) Above the P-12 (Tavg - Low Low) interlock. 

(j) Except when all MSIVs are closed and [de-activated]. 

-----------------------------------------------------------------------REVIEWER'S NOTE--------------------------------------------------------------------- 

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by 

the unit. 

------------------------------------------------------------------------------------------------------------------------------------------------------------------------
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-18 Rev. 4.0 

Table 3.3.2-1 (page 8 of 11) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

5. Turbine Trip and 

Feedwater Isolation

a. Automatic 

Actuation Logic 

and Actuation 

Relays

1, 2 (k),[3] (k)2 trains H[G] SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

NA NA

b. SG Water Level -

High High (P-14)

1,2 (k),[3](k)[3] per SG I[D] SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≤ [84.2]% [82.4]%

c. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

6. Auxiliary Feedwater

a. Automatic 

Actuation Logic 

and Actuation 

Relays (Solid 

State Protection 

System)

1,2,3 2 trains G SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

NA NA

b. Automatic 

Actuation Logic 

and Actuation 

Relays (Balance 

of Plant ESFAS)

1,2,3 2 trains G SR 3.3.2.3 NA NA

(b) 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. 

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

Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints 

more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual 

setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTSP 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]. 

(k) Except when all MFIVs, MFRVs, [and associated bypass valves] are closed and [de-activated] [or isolated by a 

closed manual valve]. 

-----------------------------------------------------------------------REVIEWER'S NOTE---------------------------------------------------------------------

(j) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by 

the unit. 

------------------------------------------------------------------------------------------------------------------------------------------------------------------------
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-19 Rev. 4.0 

Table 3.3.2-1 (page 9 of 11) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

6. Auxiliary Feedwater

c. SG Water Level -

Low Low

1,2,3 [3] per SG D SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≥ [30.4]% [32.2]%

d. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

e. Loss of Offsite 

Power

1,2,3 [3] per bus F SR 3.3.2.7

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≥ [2912] V 

with ≤ 0.8 sec 

time delay

[2975] V with 

≤ 0.8 sec time 

delay

f. Undervoltage 

Reactor Coolant 

Pump

1,2 [3] per bus I SR 3.3.2.7

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≥ [69]% bus 

voltage

[70]% bus 

voltage

g. Trip of all Main 

Feedwater 

Pumps

1,2 [2] per 

pump

J SR 3.3.2.8(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≥ [ ] psig [ ] psig

h. Auxiliary 

Feedwater Pump 

Suction Transfer 

on Suction 

Pressure - Low

1,2,3 [2] F SR 3.3.2.1

SR 3.3.2.7

SR 3.3.2.9(b)(c)

≥ [20.53] [psia] [ ] [psia]

7. Automatic 

Switchover to 

Containment Sump

a. Automatic 

Actuation Logic 

and Actuation 

Relays

1,2,3,4 2 trains C SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

NA NA

(b) 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. 

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

Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints 

more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual 

setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTSP 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]. 

-----------------------------------------------------------------------REVIEWER'S NOTE--------------------------------------------------------------------- 

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by 

the unit. 

------------------------------------------------------------------------------------------------------------------------------------------------------------------------
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-20 Rev. 4.0 

Table 3.3.2-1 (page 10 of 11) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

7. Automatic 

Switchover to 

Containment Sump

b. Refueling Water 

Storage Tank 

(RWST) Level -

Low Low

1,2,3,4 4 K SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≥ [15]% and 

≤ [ ]%

[ ]% and [ ]%

Coincident with 

Safety Injection

Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

c. RWST Level -

Low Low

1,2,3,4 4 K SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≥ [15]% [18]%

Coincident with 

Safety Injection

Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

and

Coincident with 

Containment 

Sump Level -

High

1,2,3,4 4 K SR 3.3.2.1

SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

≥ [30] in. 

above el. 

[703] ft

[ ] in. above 

el. [ ]ft

(b) 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. 

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

Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints 

more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual 

setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The NTSP 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]. 

-----------------------------------------------------------------------REVIEWER'S NOTE--------------------------------------------------------------------- 

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by 

the unit. 

------------------------------------------------------------------------------------------------------------------------------------------------------------------------
ESFAS Instrumentation (Without Setpoint Control Program) 

3.3.2A

Westinghouse STS 3.3.2A-21 Rev. 4.0 

Table 3.3.2-1 (page 11 of 11)

Engineered Safety Feature Actuation System Instrumentation

FUNCTION

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

ALLOWABLE 

VALUE

[NOMINAL(l)

TRIP 

SETPOINT]

8. ESFAS Interlocks

a. Reactor Trip, P-4 1,2,3 1 per train, 

2 trains

F SR 3.3.2.11 NA NA

b. Pressurizer 

Pressure, P-11

1,2,3 3 L SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

≤ [1996] psig [ ] psig

c. Tavg - Low Low, 

P-12

1,2,3 [1] per 

loop

L SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

≥ [550.6]°F [553]° F

-----------------------------------------------------------------------REVIEWER'S NOTE--------------------------------------------------------------------- 

(l) Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by 

the unit. 

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

ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.2B Engineered Safety Feature Actuation System (ESFAS) Instrumentation (With 

Setpoint Control Program) 

LCO 3.3.2B The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be 

OPERABLE. 

APPLICABILITY: According to Table 3.3.2-1.

ACTIONS 

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

Separate Condition entry is allowed for each Function. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Functions 

with one or more 

required channels or 

trains inoperable.

A.1 Enter the Condition 

referenced in Table 3.3.2-1 

for the channel(s) or 

train(s).

Immediately

B. One channel or train 

inoperable.

B.1 Restore channel or train to 

OPERABLE status.

OR

B.2.1 Be in MODE 3.

 AND

B.2.2 Be in MODE 5.

48 hours

54 hours

84 hours
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up 

to [4] hours for surveillance testing 

provided the other train is 

OPERABLE.

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

C.1 Restore train to 

OPERABLE status.

OR

C.2.1 Be in MODE 3.

 AND

C.2.2 Be in MODE 5.

24 hours

30 hours

60 hours

D. One channel inoperable. [ ------------------NOTE-------------------

The inoperable channel may be 

bypassed for up to 12 hours for 

surveillance testing of other 

channels.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability: 

One channel may be bypassed for 

up to 12 hours for surveillance 

testing.

---------------------------------------------- ]

D.1 Place channel in trip.

OR

72 hours
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

D.2.1 Be in MODE 3.

 AND

D.2.2 Be in MODE 4.

78 hours

84 hours

E. One Containment

Pressure channel 

inoperable.

[ ------------------NOTE-------------------

One additional channel may be 

bypassed for up to 12 hours for 

surveillance testing of other 

channels.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability.

One channel may be bypassed for 

up to 12 hours for surveillance 

testing.

---------------------------------------------- ]

E.1 Place channel in bypass.

OR

E.2.1 Be in MODE 3.

 AND

E.2.2 Be in MODE 4.

72 hours

78 hours

84 hours

F. One channel or train 

inoperable.

F.1 Restore channel or train to 

OPERABLE status.

OR

F.2.1 Be in MODE 3. 

 AND

48 hours

54 hours
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-4 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

F.2.2 Be in MODE 4. 60 hours

G. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up 

to [4] hours for surveillance testing 

provided the other train is 

OPERABLE.

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

G.1 Restore train to 

OPERABLE status.

OR

G.2.1 Be in MODE 3.

 AND

G.2.2 Be in MODE 4.

24 hours

30 hours

36 hours

H. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up 

to [4] hours for surveillance testing 

provided the other train is 

OPERABLE.

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

H.1 Restore train to 

OPERABLE status.

OR

H.2 Be in MODE 3.

24 hours

30 hours
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-5 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

I. One channel inoperable. [ ------------------NOTE-------------------

The inoperable channel may be 

bypassed for up to 12 hours for 

surveillance testing of other 

channels.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability.

One channel may be bypassed for 

up to 12 hours for surveillance 

testing.

---------------------------------------------- ]

I.1 Place channel in trip.

OR

I.2 Be in MODE 3.

72 hours

78 hours

J. One Main Feedwater 

Pumps trip channel 

inoperable.

J.1 Restore channel to 

OPERABLE status.

OR

J.2 Be in MODE 3.

48 hours

54 hours
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-6 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

K. One channel inoperable. [ ------------------NOTE-------------------

One additional channel may be 

bypassed for up to [4] hours for 

surveillance testing.

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

----------REVIEWER’S NOTE----------

The below Note should be used for 

plants with installed bypass test 

capability:

One channel may be bypassed for 

up to 12 hours for surveillance 

testing.

---------------------------------------------- ]

K.1 Place channel in bypass.

OR

K.2.1 Be in MODE 3.

 AND

K.2.2 Be in MODE 5.

[6] hours

[12] hours

[42] hours

L. One or more channels 

inoperable.

L.1 Verify interlock is in 

required state for existing 

unit condition.

OR

L.2.1 Be in MODE 3.

 AND

L.2.2 Be in MODE 4.

1 hour

7 hours

13 hours
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-7 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

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

Refer to Table 3.3.2-1 to determine which SRs apply for each ESFAS Function. 

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

SURVEILLANCE FREQUENCY

SR 3.3.2.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.2.2 Perform ACTUATION LOGIC TEST. [ 92 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.2.3 ------------------------------NOTE-------------------------------

The continuity check may be excluded.

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

Perform ACTUATION LOGIC TEST. [ 31 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-8 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

----------------------------------REVIEWER’S NOTE---------------------------------

The Frequency remains at 31 days on a STAGGERED TEST BASIS for 

plants with a Relay Protection System.

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

SR 3.3.2.4 Perform MASTER RELAY TEST. [ 92 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.2.5 Perform COT in accordance with the Setpoint 

Control Program.

[ 184 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.2.6 Perform SLAVE RELAY TEST. [ [92] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-9 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.2.7 ------------------------------NOTE-------------------------------

Verification of relay setpoints not required.

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

Perform TADOT. [ [92] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.2.8 ------------------------------NOTE-------------------------------

Verification of setpoint not required for manual 

initiation functions.

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

Perform TADOT in accordance with the Setpoint 

Control Program.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-10 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.2.9 ------------------------------NOTE-------------------------------

This Surveillance shall include verification that the 

time constants are adjusted to the prescribed 

values.

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

Perform CHANNEL CALIBRATION in accordance 

with the Setpoint Control Program.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.2.10 ------------------------------NOTE-------------------------------

Not required to be performed for the turbine driven 

AFW pump until [24] hours after SG pressure is 

≥ [1000] psig.

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

Verify ESFAS RESPONSE TIMES are within limit. [ [18] months on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.2.11 ------------------------------NOTE-------------------------------

Verification of setpoint not required.

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

Perform TADOT. Once per reactor 

trip breaker cycle
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-11 Rev. 4.0 

Table 3.3.2-1 (page 1 of 6) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

1. Safety Injection

a. Manual Initiation 1,2,3,4 2 B SR 3.3.2.8

b. Automatic Actuation Logic and 

Actuation Relays

1,2,3,4 2 trains C SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

c. Containment Pressure - High 1 1,2,3 3 D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

d. Pressurizer Pressure - Low 1,2,3(a) [3] D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

e. Steam Line Pressure

(1) Low 1,2,3[(a)] 3 per steam line D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

(2) High Differential Pressure 

Between Steam Lines

1,2,3 3 per steam line D [SR 3.3.2.1]

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

f. High Steam Flow in Two Steam 

Lines

1,2,3 (b) 2 per steam line D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

Coincident with Tavg - Low Low 1,2,3 (b) 1 per loop D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

g. High Steam Flow in Two Steam 

Lines

1,2,3 (b) 2 per steam line D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

Coincident with Steam Line 

Pressure - Low

1,2,3 (b) 1 per steam line D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

(a) Above the P-11 (Pressurizer Pressure) interlock. 

(b) Above the P-12 (Tavg - Low Low) interlock. 
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-12 Rev. 4.0 

Table 3.3.2-1 (page 2 of 6) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

2. Containment Spray

a. Manual Initiation 1,2,3,4 2 per train, 2 

trains

B SR 3.3.2.8

b. Automatic Actuation Logic and 

Actuation Relays

1,2,3,4 2 trains C SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

c. Containment Pressure High - 3 

(High High)

1,2,3 4 E SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

d. Containment Pressure High - 3 

(Two Loop Plants)

1,2,3 [3] sets of [2] E SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

3. Containment Isolation

a. Phase A Isolation

(1) Manual Initiation 1,2,3,4 2 B SR 3.3.2.8

(2) Automatic Actuation Logic 

and Actuation Relays

1,2,3,4 2 trains C SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

(3) Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

b. Phase B Isolation

(1) Manual Initiation 1,2,3,4 2 per train, 2 

trains

B SR 3.3.2.8

(2) Automatic Actuation Logic 

and Actuation Relays

1,2,3,4 2 trains C SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

(3) Containment Pressure High -

3 (High High)

1,2,3 [4] E SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-13 Rev. 4.0 

Table 3.3.2-1 (page 3 of 6) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

4. Steam Line Isolation

a. Manual Initiation 1,2 (c)

,3 (c)2 F SR 3.3.2.8

b. Automatic Actuation Logic and 

Actuation Relays

1,2 (c),3 (c)2 trains G SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

c. Containment Pressure - High 2 1, 2 (c)

, 3 (c)[4] D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

d. Steam Line Pressure

(1) Low 1, 2 (c)

, 3 (a) (c)3 per steam line D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

(2) Negative Rate - High 3 (d) (c)

3 per steam line D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

e. High Steam Flow in Two Steam 

Lines

1, 2 (c), 3 (c) 2 per steam line D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

Coincident with Tavg - Low Low 1, 2 (c), 3 (b) (c) 1 per loop D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

f. High Steam Flow in Two Steam 

Lines

1, 2 (c), 3 (c)2 per steam line D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

Coincident with Steam Line 

Pressure - Low

1,2 (c), 3 (c)1 per steam line D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

(a) Above the P-11 (Pressurizer Pressure) interlock. 

(b) Above the P-12 (Tavg - Low Low) interlock. 

(c) Except when all MSIVs are closed and [de-activated]. 

(d) Below the P-11 (Pressurizer Pressure) interlock. 
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-14 Rev. 4.0 

Table 3.3.2-1 (page 4 of 6) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

4. Steam Line Isolation

g. High Steam Flow 1,2 (c)

, 3 (c)2 per steam line D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

and

Coincident with Tavg - Low Low 1,2 (c)

, 3 (b) (c)[2] per loop D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

h. High High Steam Flow 1,2 (c),3 (c) 2 per steam line D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

5. Turbine Trip and Feedwater 

Isolation

a. Automatic Actuation Logic and 

Actuation Relays

1, 2 (e), [3](e)2 trains H[G] SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

b. SG Water Level - High High 

(P-14)

1,2 (e),[3](e)[3] per SG I[D] SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

c. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

(b) Above the P-12 (Tavg - Low Low) interlock. 

(c) Except when all MSIVs are closed and [de-activated]. 

(e) Except when all MFIVs, MFRVs, [and associated bypass valves] are closed and [de-activated] [or isolated by a 

closed manual valve]. 
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-15 Rev. 4.0 

Table 3.3.2-1 (page 5 of 6) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS CONDITIONS

SURVEILLANCE 

REQUIREMENTS

6. Auxiliary Feedwater

a. Automatic Actuation Logic and 

Actuation Relays (Solid State 

Protection System)

1,2,3 2 trains G SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

b. Automatic Actuation Logic and 

Actuation Relays (Balance of 

Plant ESFAS)

1,2,3 2 trains G SR 3.3.2.3

c. SG Water Level - Low Low 1,2,3 [3] per SG D SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

d. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

e. Loss of Offsite Power 1,2,3 [3] per bus F SR 3.3.2.7

SR 3.3.2.9

SR 3.3.2.10

f. Undervoltage Reactor Coolant 

Pump

1,2 [3] per bus I SR 3.3.2.7

SR 3.3.2.9

SR 3.3.2.10

g. Trip of all Main Feedwater Pumps 1,2 [2] per pump J SR 3.3.2.8

SR 3.3.2.9

SR 3.3.2.10

h. Auxiliary Feedwater Pump 

Suction Transfer on Suction 

Pressure - Low

1,2,3 [2] F SR 3.3.2.1

SR 3.3.2.7

SR 3.3.2.9

7. Automatic Switchover to Containment 

Sump

a. Automatic Actuation Logic and 

Actuation Relays

1,2,3,4 2 trains C SR 3.3.2.2

SR 3.3.2.4

SR 3.3.2.6

b. Refueling Water Storage Tank 

(RWST) Level - Low Low

1,2,3,4 4 K SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
ESFAS Instrumentation (With Setpoint Control Program) 

3.3.2B 

Westinghouse STS 3.3.2B-16 Rev. 4.0 

Table 3.3.2-1 (page 6 of 6) 

Engineered Safety Feature Actuation System Instrumentation 

FUNCTION

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS REQUIRED 

CHANNELS CONDITION

S

SURVEILLANCE 

REQUIREMENTS

7. Automatic Switchover to 

Containment Sump

c. RWST Level - Low Low 1,2,3,4 4 K SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

and

Coincident with Containment 

Sump Level - High

1,2,3,4 4 K SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

SR 3.3.2.10

8. ESFAS Interlocks

a. Reactor Trip, P-4 1,2,3 1 per train, 2 

trains

F SR 3.3.2.11

b. Pressurizer Pressure, P-11 1,2,3 3 L SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9

c. Tavg - Low Low, P-12 1,2,3 [1] per loop L SR 3.3.2.1

SR 3.3.2.5

SR 3.3.2.9
PAM Instrumentation 

3.3.3

Westinghouse STS 3.3.3-1 Rev. 4.0, 

3.3 INSTRUMENTATION 

3.3.3 Post Accident Monitoring (PAM) Instrumentation 

LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 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 3.3.3-1 

for the channel.

Immediately
PAM Instrumentation 

3.3.3

Westinghouse STS 3.3.3-2 Rev. 4.0, 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

E. As required by Required 

Action D.1 and 

referenced in 

Table 3.3.3-1.

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 3.3.3-1.

F.1 Initiate action in accordance 

with Specification 5.6.5.

Immediately

SURVEILLANCE REQUIREMENTS 

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

SR 3.3.3.1 and SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1.

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

SURVEILLANCE FREQUENCY

SR 3.3.3.1 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 

3.3.3

Westinghouse STS 3.3.3-3 Rev. 4.0, 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.3.2 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL 

CALIBRATION.

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

Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
PAM Instrumentation 

3.3.3

Westinghouse STS 3.3.3-4 Rev. 4.0, 

Table 3.3.3-1 (page 1 of 1)

Post Accident Monitoring Instrumentation 

FUNCTION REQUIRED CHANNELS

CONDITION

REFERENCED

FROM REQUIRED

ACTION D.1

1. Power Range Neutron Flux 2 E

2. Source Range Neutron Flux 2 E

3. Reactor Coolant System (RCS) Hot Leg 

Temperature

2 per loop E

4. RCS Cold Leg Temperature 2 per loop E

5. RCS Pressure (Wide Range) 2 E

6. Reactor Vessel Water Level 2 F

7. Containment Sump Water Level (Wide Range) 2 E

8. Containment Pressure (Wide Range) 2 E

9. Penetration Flow Path Containment Isolation Valve 

Position

2 per penetration flow 

path(a)(b) E

10. Containment Area Radiation (High Range) 2 F

11. Pressurizer Level 2 E

12. Steam Generator Water Level (Wide Range) 2 per steam generator E

13. Condensate Storage Tank Level 2 E

14. Core Exit Temperature - Quadrant [1] 2

(c) E

15. Core Exit Temperature - Quadrant [2] 2

(c) E

16. Core Exit Temperature - Quadrant [3] 2

(c) E

17. Core Exit Temperature - Quadrant [4] 2

(c) E

18. Auxiliary Feedwater Flow 2 E

(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) A channel consists of two core exit thermocouples (CETs). 

----------------------------------------------------------------REVIEWER'S NOTE---------------------------------------------------------------- 

Table 3.3.3-1 shall be amended for each unit as necessary to list: 

1. All Regulatory Guide 1.97, Type A instruments and 

2. All Regulatory Guide 1.97, Category I, non-Type A instruments in accordance with the unit's Regulatory 

Guide 1.97, Safety Evaluation Report. 

------------------------------------------------------------------------------------------------------------------------------------------------------------
Remote Shutdown System 

3.3.4

Westinghouse STS 3.3.4-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.4 Remote Shutdown System 

LCO 3.3.4 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 3.3.4.1 [ 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 

3.3.4

Westinghouse STS 3.3.4-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SR 3.3.4.2 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 3.3.4.3 -------------------------------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 ]

SR 3.3.4.4 [ Perform TADOT of the reactor trip breaker 

open/closed indication.

[ 18 months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
LOP DG Start Instrumentation (Without Setpoint Control Program) 

3.3.5A 

Westinghouse STS 3.3.5A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.5A Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation (Without Setpoint 

Control Program) 

LCO 3.3.5A [Three] channels per bus of the loss of voltage Function and [three] 

channels per bus of the degraded voltage Function shall be OPERABLE. 

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

When associated DG 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 

bus inoperable.

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

The inoperable channel 

may be bypassed for up to 

[4] hours for surveillance 

testing of other channels.

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

Place channel in trip. [6] hours

B. One or more Functions 

with two or more 

channels per bus 

inoperable.

B.1 Restore all but one channel 

per bus to OPERABLE 

status.

1 hour

C. Required Action and 

associated Completion 

Time not met.

C.1 Enter applicable 

Condition(s) and Required 

Action(s) for the associated 

DG made inoperable by 

LOP DG start 

instrumentation.

Immediately
LOP DG Start Instrumentation (Without Setpoint Control Program) 

3.3.5A 

Westinghouse STS 3.3.5A-2 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 Perform TADOT. [ [31] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.5.3 Perform CHANNEL CALIBRATION with [Nominal 

Trip Setpoint and Allowable Value] as follows:

a. [ Loss of voltage Allowable Value ≥ [2912] V and 

≤ [ ] V with a time delay of [0.8] ± [ ] second.

Loss of voltage Nominal Trip Setpoint [2975] V 

with a time delay of [0.8]  [ ] second. ]

b. [ Degraded voltage Allowable Value ≥ [3683] V 

and ≤ [ ] V with a time delay of 

[20] ± [ ] seconds.

Degraded voltage Nominal Trip Setpoint [3746] V 

with a time delay of [20] ± [ ] seconds. ]

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
LOP DG Start Instrumentation (With Setpoint Control Program) 

3.3.5B 

Westinghouse STS 3.3.5B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.5B Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation (With Setpoint 

Control Program) 

LCO 3.3.5B [Three] channels per bus of the loss of voltage Function and [three] 

channels per bus of the degraded voltage Function shall be OPERABLE. 

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

When associated DG 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 

bus inoperable.

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

The inoperable channel 

may be bypassed for up to 

[4] hours for surveillance 

testing of other channels.

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

Place channel in trip. [6] hours

B. One or more Functions 

with two or more 

channels per bus 

inoperable.

B.1 Restore all but one channel 

per bus to OPERABLE 

status.

1 hour

C. Required Action and 

associated Completion 

Time not met.

C.1 Enter applicable 

Condition(s) and Required 

Action(s) for the associated 

DG made inoperable by 

LOP DG start 

instrumentation.

Immediately
LOP DG Start Instrumentation (With Setpoint Control Program) 

3.3.5B 

Westinghouse STS 3.3.5B-2 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 Perform TADOT 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 ]
Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 

3.3.6A 

Westinghouse STS 3.3.6A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.6A Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control 

Program) 

LCO 3.3.6A The Containment Purge and Exhaust Isolation instrumentation for each 

Function in Table 3.3.6-1 shall be OPERABLE. 

APPLICABILITY: According to Table 3.3.6-1.

ACTIONS 

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

Separate Condition entry is allowed for each Function. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. One radiation monitoring 

channel inoperable.

A.1 Restore the affected 

channel to OPERABLE 

status.

4 hours

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

Only applicable in 

MODE 1, 2, 3, or 4.

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

One or more Functions 

with one or more manual 

or automatic actuation 

trains inoperable.

OR

Two or more radiation 

monitoring channels 

inoperable.

OR

Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Enter applicable Conditions 

and Required Actions of 

LCO 3.6.3, "Containment 

Isolation Valves," for 

containment purge and 

exhaust isolation valves 

made inoperable by 

isolation instrumentation.

Immediately
Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 

3.3.6A 

Westinghouse STS 3.3.6A-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. ------------NOTE------------

Only applicable during 

movement of [recently] 

irradiated fuel 

assemblies within 

containment.

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

One or more Functions 

with one or more manual 

or automatic actuation 

trains inoperable.

OR

Two or more radiation 

monitoring channels 

inoperable.

OR

Required Action and 

associated Completion 

Time for Condition A not 

met.

C.1 Place and maintain 

containment purge and 

exhaust valves in closed 

position.

OR

C.2 Enter applicable Conditions 

and Required Actions of 

LCO 3.9.4, "Containment 

Penetrations," for 

containment purge and 

exhaust isolation valves 

made inoperable by 

isolation instrumentation.

Immediately

Immediately
Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 

3.3.6A 

Westinghouse STS 3.3.6A-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

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

Refer to Table 3.3.6-1 to determine which SRs apply for each Containment Purge and Exhaust 

Isolation Function. 

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

SURVEILLANCE FREQUENCY

SR 3.3.6.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.6.2 Perform ACTUATION LOGIC TEST. [ 31 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.6.3 Perform MASTER RELAY TEST. [ 31 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 

3.3.6A 

Westinghouse STS 3.3.6A-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

----------------------------------REVIEWER’S NOTE---------------------------------

The Frequency of 92 days on a STAGGERED TEST BASIS is 

applicable to the actuation logic processed through the Relay or Solid 

State Protection System.

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

[SR 3.3.6.4 -------------------------------NOTE------------------------------

This Surveillance is only applicable to the actuation 

logic of the ESFAS Instrumentation.

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

Perform ACTUATION LOGIC TEST. [ 92 days on a 

STAGGERED 

TEST BASIS ]

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 

3.3.6A 

Westinghouse STS 3.3.6A-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

----------------------------------REVIEWER’S NOTE---------------------------------

The Frequency of 92 days on a STAGGERED TEST BASIS is 

applicable to the master relays processed through the Solid State 

Protection System.

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

[SR 3.3.6.5 -------------------------------NOTE------------------------------

This Surveillance is only applicable to the master 

relays of the ESFAS Instrumentation.

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

Perform MASTER RELAY TEST. [ 92 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.3.6.6 Perform COT. [ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 

3.3.6A 

Westinghouse STS 3.3.6A-6 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.6.7 Perform SLAVE RELAY TEST. [ [92] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.6.8 -------------------------------NOTE------------------------------

Verification of setpoint is not required.

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

Perform TADOT. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.6.9 Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Purge and Exhaust Isolation Instrumentation (Without Setpoint Control Program) 

3.3.6A 

Westinghouse STS 3.3.6A-7 Rev. 4.0 

Table 3.3.6-1 (page 1 of 1)

Containment Purge and Exhaust Isolation Instrumentation 

FUNCTION

APPLICABLE 

MODES OR 

OTHER 

SPECIFIED

CONDITIONS

REQUIRED 

CHANNELS

SURVEILLANCE 

REQUIREMENTS TRIP SETPOINT

1. Manual Initiation 1,2,3,4, (a) 2 SR 3.3.6.8 NA

2. Automatic Actuation Logic and 

Actuation Relays

1,2,3,4, (a) 2 trains SR 3.3.6.2

SR 3.3.6.3

[SR 3.3.6.4]

[SR 3.3.6.5]

SR 3.3.6.7

NA

3. [ Containment Radiation

a. Gaseous 1,2,3,4, (a) [1] SR 3.3.6.1

SR 3.3.6.6

SR 3.3.6.9

≤ [2 x background]

b. Particulate 1,2,3,4, (a) [1] SR 3.3.6.1

SR 3.3.6.6

SR 3.3.6.9

≤ [2 x background]

c. Iodine 1,2,3,4, (a) [1] SR 3.3.6.1

SR 3.3.6.6

SR 3.3.6.9

≤ [2 x background]

d. Area Radiation 1,2,3,4, (a) [1] SR 3.3.6.1

SR 3.3.6.6

SR 3.3.6.9

≤ [2 x background] ]

4. Containment Isolation -

Phase A

Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 3.a., for all 

initiation functions and requirements.

(a) During movement of [recently] irradiated fuel assemblies within containment.

Containment Purge and Exhaust Isolation Instrumentation (With Setpoint Control Program) 

3.3.6B 

Westinghouse STS 3.3.6B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.6B Containment Purge and Exhaust Isolation Instrumentation (With Setpoint Control 

Program) 

LCO 3.3.6B The Containment Purge and Exhaust Isolation instrumentation for each 

Function in Table 3.3.6-1 shall be OPERABLE. 

APPLICABILITY: According to Table 3.3.6-1.

ACTIONS 

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

Separate Condition entry is allowed for each Function. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. One radiation monitoring 

channel inoperable.

A.1 Restore the affected 

channel to OPERABLE 

status.

4 hours

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

Only applicable in 

MODE 1, 2, 3, or 4.

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

One or more Functions 

with one or more manual 

or automatic actuation 

trains inoperable.

OR

Two or more radiation 

monitoring channels 

inoperable.

OR

Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Enter applicable Conditions 

and Required Actions of 

LCO 3.6.3, "Containment 

Isolation Valves," for 

containment purge and 

exhaust isolation valves 

made inoperable by 

isolation instrumentation.

Immediately
Containment Purge and Exhaust Isolation Instrumentation (With Setpoint Control Program) 

3.3.6B 

Westinghouse STS 3.3.6B-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. ------------NOTE------------

Only applicable during 

movement of [recently] 

irradiated fuel 

assemblies within 

containment.

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

One or more Functions 

with one or more manual 

or automatic actuation 

trains inoperable.

OR

Two or more radiation 

monitoring channels 

inoperable.

OR

Required Action and 

associated Completion 

Time for Condition A not 

met.

C.1 Place and maintain 

containment purge and 

exhaust valves in closed 

position.

OR

C.2 Enter applicable Conditions 

and Required Actions of 

LCO 3.9.4, "Containment 

Penetrations," for 

containment purge and 

exhaust isolation valves 

made inoperable by 

isolation instrumentation.

Immediately

Immediately
Containment Purge and Exhaust Isolation Instrumentation (With Setpoint Control Program) 

3.3.6B 

Westinghouse STS 3.3.6B-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

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

Refer to Table 3.3.6-1 to determine which SRs apply for each Containment Purge and Exhaust 

Isolation Function. 

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

SURVEILLANCE FREQUENCY

SR 3.3.6.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.6.2 Perform ACTUATION LOGIC TEST. [ 31 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.6.3 Perform MASTER RELAY TEST. [ 31 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Purge and Exhaust Isolation Instrumentation (With Setpoint Control Program) 

3.3.6B 

Westinghouse STS 3.3.6B-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

----------------------------------REVIEWER’S NOTE---------------------------------

The Frequency of 92 days on a STAGGERED TEST BASIS is 

applicable to the actuation logic processed through the Relay or Solid 

State Protection System.

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

[SR 3.3.6.4 -------------------------------NOTE------------------------------

This Surveillance is only applicable to the actuation 

logic of the ESFAS Instrumentation.

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

Perform ACTUATION LOGIC TEST. [ 92 days on a 

STAGGERED 

TEST BASIS ]

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Purge and Exhaust Isolation Instrumentation (With Setpoint Control Program) 

3.3.6B 

Westinghouse STS 3.3.6B-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

----------------------------------REVIEWER’S NOTE---------------------------------

The Frequency of 92 days on a STAGGERED TEST BASIS is 

applicable to the master relays processed through the Solid State 

Protection System.

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

[SR 3.3.6.5 -------------------------------NOTE------------------------------

This Surveillance is only applicable to the master 

relays of the ESFAS Instrumentation.

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

Perform MASTER RELAY TEST. [ 92 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.3.6.6 Perform COT in accordance with the Setpoint 

Control Program.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Purge and Exhaust Isolation Instrumentation (With Setpoint Control Program) 

3.3.6B 

Westinghouse STS 3.3.6B-6 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.6.7 Perform SLAVE RELAY TEST. [ [92] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.6.8 -------------------------------NOTE------------------------------

Verification of setpoint is not required.

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

Perform TADOT. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.6.9 Perform CHANNEL CALIBRATION in accordance 

with the Setpoint Control Program.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Purge and Exhaust Isolation Instrumentation (With Setpoint Control Program) 

3.3.6B 

Westinghouse STS 3.3.6B-7 Rev. 4.0 

Table 3.3.6-1 (page 1 of 1)

Containment Purge and Exhaust Isolation Instrumentation

FUNCTION

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS

SURVEILLANCE 

REQUIREMENTS

1. Manual Initiation 1,2,3,4, (a) 2 SR 3.3.6.8

2. Automatic Actuation Logic and 

Actuation Relays

1,2,3,4, (a) 2 trains SR 3.3.6.2

SR 3.3.6.3

[SR 3.3.6.4]

[SR 3.3.6.5]

SR 3.3.6.7

3. [ Containment Radiation

a. Gaseous 1,2,3,4, (a) [1] SR 3.3.6.1

SR 3.3.6.6

SR 3.3.6.9

b. Particulate 1,2,3,4, (a) [1] SR 3.3.6.1

SR 3.3.6.6

SR 3.3.6.9

c. Iodine 1,2,3,4, (a) [1] SR 3.3.6.1

SR 3.3.6.6

SR 3.3.6.9

d. Area Radiation 1,2,3,4, (a) [1] SR 3.3.6.1

SR 3.3.6.6

SR 3.3.6.9 ]

4. Containment Isolation - Phase A Refer to LCO 3.3.2 "ESFAS Instrumentation," Function 3.a., for all 

initiation functions and requirements.

(a) During movement of [recently] irradiated fuel assemblies within containment.

CREFS Actuation Instrumentation (Without Setpoint Control Program) 

3.3.7A 

Westinghouse STS 3.3.7A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.7A Control Room Emergency Filtration System (CREFS) Actuation Instrumentation 

(Without Setpoint Control Program) 

LCO 3.3.7A The CREFS actuation instrumentation for each Function in Table 3.3.7-1 

shall be OPERABLE. 

APPLICABILITY: According to Table 3.3.7-1.

ACTIONS 

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

Separate Condition entry is allowed for each Function. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Functions 

with one channel or train 

inoperable.

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

[ Place in toxic gas 

protection mode if 

automatic transfer to toxic 

gas protection mode is 

inoperable. ]

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

Place one CREFS train in 

emergency [radiation 

protection] mode.

7 days

B. One or more Functions 

with two channels or two 

trains inoperable.

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

[ Place in the toxic gas protection 

mode if automatic transfer to toxic 

gas protection mode is inoperable. ]

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

B.1.1 Place one CREFS train in 

emergency [radiation 

protection] mode.

 AND

Immediately
CREFS Actuation Instrumentation (Without Setpoint Control Program) 

3.3.7A 

Westinghouse STS 3.3.7A-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.1.2 Enter applicable Conditions 

and Required Actions for 

one CREFS train made 

inoperable by inoperable 

CREFS actuation 

instrumentation.

OR

B.2 Place both trains in 

emergency [radiation 

protection] mode.

Immediately

Immediately

C. Required Action and 

associated Completion 

Time for Condition A 

or B not met in MODE 1, 

2, 3, or 4.

C.1 Be in MODE 3.

AND

C.2 Be in MODE 5.

6 hours

36 hours

D. Required Action and 

associated Completion 

Time for Condition A 

or B not met during 

movement of [recently] 

irradiated fuel 

assemblies.

D.1 Suspend movement of 

[recently] irradiated fuel 

assemblies.

Immediately

E. [ Required Action and 

associated Completion 

Time for Condition A 

or B not met in MODE 5 

or 6.

E.1 Initiate action to restore one 

CREFS train to OPERABLE 

status.

Immediately ]
CREFS Actuation Instrumentation (Without Setpoint Control Program) 

3.3.7A 

Westinghouse STS 3.3.7A-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

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

Refer to Table 3.3.7-1 to determine which SRs apply for each CREFS Actuation Function. 

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

SURVEILLANCE FREQUENCY

SR 3.3.7.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.7.2 Perform COT. [ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.7.3 Perform ACTUATION LOGIC TEST. [ 31 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
CREFS Actuation Instrumentation (Without Setpoint Control Program) 

3.3.7A 

Westinghouse STS 3.3.7A-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.7.4 Perform MASTER RELAY TEST. [ 31 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

---------------------------------REVIEWER’S NOTE----------------------------------

The Frequency of 92 days on a STAGGERED TEST BASIS is 

applicable to the actuation logic processed through the Relay or Solid 

State Protection System.

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

SR 3.3.7.5 -------------------------------NOTE------------------------------

This Surveillance is only applicable to the actuation 

logic of the ESFAS Instrumentation.

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

Perform ACTUATION LOGIC TEST. [ 92 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
CREFS Actuation Instrumentation (Without Setpoint Control Program) 

3.3.7A 

Westinghouse STS 3.3.7A-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

---------------------------------REVIEWER’S NOTE----------------------------------

The Frequency of 92 days on a STAGGERED TEST BASIS is 

applicable to the master relays processed through the Solid State 

Protection System.

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

SR 3.3.7.6 -------------------------------NOTE------------------------------

This Surveillance is only applicable to the master 

relays of the ESFAS Instrumentation.

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

Perform MASTER RELAY TEST. [ 92 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.7.7 Perform SLAVE RELAY TEST. [ [92] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
CREFS Actuation Instrumentation (Without Setpoint Control Program) 

3.3.7A 

Westinghouse STS 3.3.7A-6 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.7.8 -------------------------------NOTE------------------------------

Verification of setpoint is not required.

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

Perform TADOT. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.7.9 Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
CREFS Actuation Instrumentation (Without Setpoint Control Program) 

3.3.7A 

Westinghouse STS 3.3.7A-7 Rev. 4.0 

Table 3.3.7-1 (page 1 of 1)

CREFS Actuation Instrumentation 

FUNCTION

APPLICABLE

MODES OR 

OTHER 

SPECIFIED 

CONDITIONS

REQUIRED 

CHANNELS

SURVEILLANCE 

REQUIREMENTS TRIP SETPOINT

1. Manual Initiation 1, 2, 3, 4, [5, 

6], (a)

2 trains SR 3.3.7.8 NA

2. Automatic Actuation Logic 

and Actuation Relays

1, 2, 3, 4, [5, 

6], (a)

2 trains SR 3.3.7.3

SR 3.3.7.4

SR 3.3.7.5

SR 3.3.7.6

SR 3.3.7.7

NA

3. Control Room Radiation

a. Control Room 

Atmosphere

1, 2, 3, 4 [5, 

6], (a)

[2] SR 3.3.7.1

SR 3.3.7.2

SR 3.3.7.9

≤ [2] mR/hr

b. Control Room Air Intakes 1, 2, 3, 4, [5, 

6], (a)

[2] SR 3.3.7.1

SR 3.3.7.2

SR 3.3.7.9

≤ [2] mR/hr

4. Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all initiation 

functions and requirements.

(a) During movement of [recently] irradiated fuel assemblies. 
CREFS Actuation Instrumentation (With Setpoint Control Program) 

3.3.7B 

Westinghouse STS 3.3.7B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.7B Control Room Emergency Filtration System (CREFS) Actuation Instrumentation 

(With Setpoint Control Program) 

LCO 3.3.7B The CREFS actuation instrumentation for each Function in Table 3.3.7-1 

shall be OPERABLE. 

APPLICABILITY: According to Table 3.3.7-1.

ACTIONS 

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

Separate Condition entry is allowed for each Function. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Functions 

with one channel or train 

inoperable.

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

[ Place in toxic gas 

protection mode if 

automatic transfer to toxic 

gas protection mode is 

inoperable. ]

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

Place one CREFS train in 

emergency [radiation 

protection] mode.

7 days

B. One or more Functions 

with two channels or two 

trains inoperable.

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

[ Place in the toxic gas protection 

mode if automatic transfer to toxic 

gas protection mode is inoperable. ]

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

B.1.1 Place one CREFS train in 

emergency [radiation 

protection] mode.

 AND

Immediately
CREFS Actuation Instrumentation (With Setpoint Control Program) 

3.3.7B 

Westinghouse STS 3.3.7B-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.1.2 Enter applicable Conditions 

and Required Actions for 

one CREFS train made 

inoperable by inoperable 

CREFS actuation 

instrumentation.

OR

B.2 Place both trains in 

emergency [radiation 

protection] mode.

Immediately

Immediately

C. Required Action and 

associated Completion 

Time for Condition A 

or B not met in MODE 1, 

2, 3, or 4.

C.1 Be in MODE 3.

AND

C.2 Be in MODE 5.

6 hours

36 hours

D. Required Action and 

associated Completion 

Time for Condition A 

or B not met during 

movement of [recently] 

irradiated fuel 

assemblies.

D.1 Suspend movement of 

[recently] irradiated fuel 

assemblies.

Immediately

E. [ Required Action and 

associated Completion 

Time for Condition A 

or B not met in MODE 5 

or 6.

E.1 Initiate action to restore one 

CREFS train to OPERABLE 

status.

Immediately ]
CREFS Actuation Instrumentation (With Setpoint Control Program) 

3.3.7B 

Westinghouse STS 3.3.7B-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

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

Refer to Table 3.3.7-1 to determine which SRs apply for each CREFS Actuation Function. 

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

SURVEILLANCE FREQUENCY

SR 3.3.7.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.7.2 Perform COT in accordance with the Setpoint

Control Program.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.7.3 Perform ACTUATION LOGIC TEST. [ 31 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
CREFS Actuation Instrumentation (With Setpoint Control Program) 

3.3.7B 

Westinghouse STS 3.3.7B-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.7.4 Perform MASTER RELAY TEST. [ 31 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

---------------------------------REVIEWER’S NOTE----------------------------------

The Frequency of 92 days on a STAGGERED TEST BASIS is 

applicable to the actuation logic processed through the Relay or Solid 

State Protection System.

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

SR 3.3.7.5 -------------------------------NOTE------------------------------

This Surveillance is only applicable to the actuation 

logic of the ESFAS Instrumentation.

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

Perform ACTUATION LOGIC TEST. [ 92 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
CREFS Actuation Instrumentation (With Setpoint Control Program) 

3.3.7B 

Westinghouse STS 3.3.7B-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

---------------------------------REVIEWER’S NOTE----------------------------------

The Frequency of 92 days on a STAGGERED TEST BASIS is 

applicable to the master relays processed through the Solid State 

Protection System.

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

SR 3.3.7.6 -------------------------------NOTE------------------------------

This Surveillance is only applicable to the master 

relays of the ESFAS Instrumentation.

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

Perform MASTER RELAY TEST. [ 92 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.7.7 Perform SLAVE RELAY TEST. [ [92] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
CREFS Actuation Instrumentation (With Setpoint Control Program) 

3.3.7B 

Westinghouse STS 3.3.7B-6 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.7.8 -------------------------------NOTE------------------------------

Verification of setpoint is not required.

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

Perform TADOT. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.7.9 Perform CHANNEL CALIBRATION in accordance 

with the Setpoint Control Program.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
CREFS Actuation Instrumentation (With Setpoint Control Program) 

3.3.7B 

Westinghouse STS 3.3.7B-7 Rev. 4.0 

Table 3.3.7-1 (page 1 of 1)

CREFS Actuation Instrumentation 

FUNCTION

APPLICABLE

MODES OR OTHER 

SPECIFIED CONDITIONS

REQUIRED 

CHANNELS

SURVEILLANCE 

REQUIREMENTS

1. Manual Initiation 1, 2, 3, 4, [5, 6], (a) 2 trains SR 3.3.7.8

2. Automatic Actuation Logic and 

Actuation Relays

1, 2, 3, 4, [5, 6], (a) 2 trains SR 3.3.7.3

SR 3.3.7.4

SR 3.3.7.5

SR 3.3.7.6

SR 3.3.7.7

3. Control Room Radiation

a. Control Room Atmosphere 1, 2, 3, 4 [5, 6], (a) [2] SR 3.3.7.1

SR 3.3.7.2

SR 3.3.7.9

b. Control Room Air Intakes 1, 2, 3, 4, [5, 6], (a) [2] SR 3.3.7.1

SR 3.3.7.2

SR 3.3.7.9

4. Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function1, for all 

initiation functions and requirements.

(a) During movement of [recently] irradiated fuel assemblies. 
FBACS Actuation Instrumentation (Without Setpoint Control Program) 

3.3.8A 

Westinghouse STS 3.3.8A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.8A Fuel Building Air Cleanup System (FBACS) Actuation Instrumentation (Without 

Setpoint Control Program) 

LCO 3.3.8A The FBACS actuation instrumentation for each Function in Table 3.3.8-1 

shall be OPERABLE. 

APPLICABILITY: According to Table 3.3.8-1.

ACTIONS 

-----------------------------------------------------------NOTES----------------------------------------------------------

1. LCO 3.0.3 is not applicable. 

2. Separate Condition entry is allowed for each Function. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Functions 

with one channel or train 

inoperable.

A.1 Place one FBACS train in 

operation.

7 days

B. One or more Functions 

with two channels or two 

trains inoperable.

B.1.1 Place one FBACS train in 

operation.

 AND

B.1.2 Enter applicable Conditions 

and Required Actions of 

LCO 3.7.13, "Fuel Building 

Air Cleanup System 

(FBACS)," for one train 

made inoperable by 

inoperable actuation 

instrumentation.

OR

B.2 Place both trains in 

emergency [radiation 

protection] mode.

Immediately

Immediately

Immediately
FBACS Actuation Instrumentation (Without Setpoint Control Program) 

3.3.8A 

Westinghouse STS 3.3.8A-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. Required Action and 

associated Completion 

Time for Condition A 

or B not met during 

movement of [recently] 

irradiated fuel 

assemblies in the fuel 

building.

C.1 Suspend movement of 

[recently] irradiated fuel 

assemblies in the fuel 

building.

Immediately

D. [ Required Action and 

associated Completion 

Time for Condition A 

or B not met in MODE 1, 

2, 3, or 4.

D.1 Be in MODE 3.

AND

D.2 Be in MODE 5.

6 hours

36 hours ]

SURVEILLANCE REQUIREMENTS 

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

Refer to Table 3.3.8-1 to determine which SRs apply for each FBACS Actuation Function. 

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

SURVEILLANCE FREQUENCY

SR 3.3.8.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
FBACS Actuation Instrumentation (Without Setpoint Control Program) 

3.3.8A 

Westinghouse STS 3.3.8A-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.8.2 Perform COT. [ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.8.3 [ Perform ACTUATION LOGIC TEST. [ 31 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.3.8.4 -------------------------------NOTE------------------------------

Verification of setpoint is not required.

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

Perform TADOT. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
FBACS Actuation Instrumentation (Without Setpoint Control Program) 

3.3.8A 

Westinghouse STS 3.3.8A-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.8.5 Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
FBACS Actuation Instrumentation (Without Setpoint Control Program) 

3.3.8A 

Westinghouse STS 3.3.8A-5 Rev. 4.0 

Table 3.3.8-1 (page 1 of 1)

FBACS Actuation Instrumentation 

FUNCTION

APPLICABLE

MODES OR

SPECIFIED

CONDITIONS

REQUIRED

CHANNELS

SURVEILLANCE 

REQUIREMENTS

TRIP

SETPOINT

1. Manual Initiation [1,2,3,4], (a) 2 SR 3.3.8.4 NA

2. [ Automatic Actuation Logic 

and Actuation Relays

1,2,3,4, (a) 2 trains SR 3.3.8.3 NA ]

3. Fuel Building Radiation

a. Gaseous [1,2,3,4], (a) [2] SR 3.3.8.1

SR 3.3.8.2

SR 3.3.8.5

≤ [2] mR/hr

b. Particulate [1,2,3,4], (a) [2] SR 3.3.8.1

SR 3.3.8.2

SR 3.3.8.5

≤ [2] mR/hr

 (a) During movement of [recently] irradiated fuel assemblies in the fuel building.

FBACS Actuation Instrumentation (With Setpoint Control Program) 

3.3.8B 

Westinghouse STS 3.3.8B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.8B Fuel Building Air Cleanup System (FBACS) Actuation Instrumentation (With Setpoint 

Control Program) 

LCO 3.3.8B The FBACS actuation instrumentation for each Function in Table 3.3.8-1 

shall be OPERABLE. 

APPLICABILITY: According to Table 3.3.8-1.

ACTIONS 

-----------------------------------------------------------NOTES----------------------------------------------------------

1. LCO 3.0.3 is not applicable. 

2. Separate Condition entry is allowed for each Function. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Functions 

with one channel or train 

inoperable.

A.1 Place one FBACS train in 

operation.

7 days

B. One or more Functions 

with two channels or two 

trains inoperable.

B.1.1 Place one FBACS train in 

operation.

 AND

B.1.2 Enter applicable Conditions 

and Required Actions of 

LCO 3.7.13, "Fuel Building 

Air Cleanup System 

(FBACS)," for one train 

made inoperable by 

inoperable actuation 

instrumentation.

OR

B.2 Place both trains in 

emergency [radiation 

protection] mode.

Immediately

Immediately

Immediately
FBACS Actuation Instrumentation (With Setpoint Control Program) 

3.3.8B 

Westinghouse STS 3.3.8B-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. Required Action and 

associated Completion 

Time for Condition A 

or B not met during 

movement of [recently] 

irradiated fuel 

assemblies in the fuel 

building.

C.1 Suspend movement of 

[recently] irradiated fuel 

assemblies in the fuel 

building.

Immediately

D. [ Required Action and 

associated Completion 

Time for Condition A 

or B not met in MODE 1, 

2, 3, or 4.

D.1 Be in MODE 3.

AND

D.2 Be in MODE 5.

6 hours

36 hours ]

SURVEILLANCE REQUIREMENTS 

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

Refer to Table 3.3.8-1 to determine which SRs apply for each FBACS Actuation Function. 

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

SURVEILLANCE FREQUENCY

SR 3.3.8.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
FBACS Actuation Instrumentation (With Setpoint Control Program) 

3.3.8B 

Westinghouse STS 3.3.8B-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.8.2 Perform COT in accordance with the Setpoint 

Control Program.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.8.3 [ Perform ACTUATION LOGIC TEST. [ 31 days on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.3.8.4 -------------------------------NOTE------------------------------

Verification of setpoint is not required.

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

Perform TADOT. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
FBACS Actuation Instrumentation (With Setpoint Control Program) 

3.3.8B 

Westinghouse STS 3.3.8B-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.8.5 Perform CHANNEL CALIBRATION in accordance 

with the Setpoint Control Program.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
FBACS Actuation Instrumentation (With Setpoint Control Program) 

3.3.8B 

Westinghouse STS 3.3.8B-5 Rev. 4.0 

Table 3.3.8-1 (page 1 of 1)

FBACS Actuation Instrumentation 

FUNCTION

APPLICABLE MODES OR

SPECIFIED CONDITIONS

REQUIRED

CHANNELS

SURVEILLANCE 

REQUIREMENTS

1. Manual Initiation [1,2,3,4], (a) 2 SR 3.3.8.4

2. [ Automatic Actuation Logic and 

Actuation Relays

1,2,3,4, (a) 2 trains SR 3.3.8.3 ]

3. Fuel Building Radiation

a. Gaseous [1,2,3,4], (a) [2] SR 3.3.8.1

SR 3.3.8.2

SR 3.3.8.5

b. Particulate [1,2,3,4], (a) [2] SR 3.3.8.1

SR 3.3.8.2

SR 3.3.8.5

 (a) During movement of [recently] irradiated fuel assemblies in the fuel building.

BDPS (Without Setpoint Control Program) 

3.3.9A 

Westinghouse STS 3.3.9A-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.9A Boron Dilution Protection System (BDPS) (Without Setpoint Control Program) 

LCO 3.3.9A Two trains of the BDPS shall be OPERABLE. 

APPLICABILITY: MODES [2,] 3, 4, and 5.

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

The boron dilution flux doubling signal may be blocked in MODES 2 and 3 

during reactor startup. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One train inoperable. A.1 Restore train to 

OPERABLE status.

72 hours

B. Two trains inoperable.

OR

Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 --------------NOTE--------------

Plant temperature changes 

are allowed provided the 

temperature change is 

accounted for in the 

calculated SDM.

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

Suspend operations 

involving positive reactivity 

additions.

AND

B.2.1 Restore one train to 

OPERABLE status.

OR

Immediately

1 hour
BDPS (Without Setpoint Control Program) 

3.3.9A 

Westinghouse STS 3.3.9A-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.2.2.1 Close unborated water 

source isolation valves.

AND

B.2.2.2 Perform SR 3.1.1.1.

1 hour

1 hour

AND

Once per 12 hours 

thereafter

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.9.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.9.2 Perform COT. [ [184] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
BDPS (Without Setpoint Control Program) 

3.3.9A 

Westinghouse STS 3.3.9A-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.9.3 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL 

CALIBRATION.

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

Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

BDPS (With Setpoint Control Program) 

3.3.9B 

Westinghouse STS 3.3.9B-1 Rev. 4.0 

3.3 INSTRUMENTATION 

3.3.9B Boron Dilution Protection System (BDPS) (With Setpoint Control Program) 

LCO 3.3.9B Two trains of the BDPS shall be OPERABLE. 

APPLICABILITY: MODES [2,] 3, 4, and 5.

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

The boron dilution flux doubling signal may be blocked in MODES 2 and 3 

during reactor startup. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One train inoperable. A.1 Restore train to 

OPERABLE status.

72 hours

B. Two trains inoperable.

OR

Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 --------------NOTE--------------

Plant temperature changes 

are allowed provided the 

temperature change is 

accounted for in the 

calculated SDM.

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

Suspend operations 

involving positive reactivity 

additions.

AND

B.2.1 Restore one train to 

OPERABLE status.

OR

Immediately

1 hour
BDPS (With Setpoint Control Program) 

3.3.9B 

Westinghouse STS 3.3.9B-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.2.2.1 Close unborated water 

source isolation valves.

AND

B.2.2.2 Perform SR 3.1.1.1.

1 hour

1 hour

AND

Once per 12 hours 

thereafter

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.3.9.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.3.9.2 Perform COT in accordance with the Setpoint 

Control Program.

[ [184] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
BDPS (With Setpoint Control Program) 

3.3.9B 

Westinghouse STS 3.3.9B-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.3.9.3 -------------------------------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 ]

RCS Pressure, Temperature, and Flow DNB Limits 

3.4.1

Westinghouse 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 pressurizer pressure, RCS average 

temperature, and RCS total flow rate shall be within the limits specified 

below: 

a. Pressurizer pressure is greater than or equal to the limit specified in 

the COLR, 

b. RCS average temperature is less than or equal to the limit specified 

in the COLR, and 

c. RCS total flow rate ≥ [284,000] gpm and greater than or equal to the 

limit specified in the COLR. 

APPLICABILITY: MODE 1.

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

 Pressurizer 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

Westinghouse STS 3.4.1-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.1.1 Verify pressurizer pressure is greater than or equal 

to the limit specified in the COLR.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.1.2 Verify RCS average temperature is less than or 

equal to the limit specified in the COLR.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.1.3 Verify RCS total flow rate is ≥ [284,000] gpm and 

greater than or equal to the limit specified in the 

COLR.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Pressure, Temperature, and Flow DNB Limits 

3.4.1

Westinghouse STS 3.4.1-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.1.4 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours after 

≥ [90]% RTP.

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

Verify by precision heat balance that RCS total flow 

rate is ≥ [284,000] gpm and greater than or equal to 

the limit specified in the COLR.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

RCS Minimum Temperature for Criticality 

3.4.2

Westinghouse 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 ≥ [541]°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 ≥ [541]°F. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

RCS P/T Limits 

3.4.3

Westinghouse 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 with RCS

pressure < [500] psig.

6 hours

36 hours

C. ------------NOTE------------

Required Action C.2 

shall be completed 

whenever this Condition 

is entered.

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

Requirements of 

LCO not met any time in 

other than MODE 1, 2, 

3, or 4.

C.1 Initiate action to restore 

parameter(s) to within 

limits.

AND

C.2 Determine RCS is 

acceptable for continued 

operation.

Immediately

Prior to entering 

MODE 4
RCS P/T Limits 

3.4.3

Westinghouse 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

Westinghouse 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 [Four] RCS loops shall be OPERABLE and in operation. 

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 each RCS loop is in operation. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

RCS Loops - MODE 3 

3.4.5

Westinghouse 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 either: 

a. [Two] RCS loops shall be in operation when the Rod Control 

System is capable of rod withdrawal or 

b. One RCS loop shall be in operation when the Rod Control System is 

not capable of rod withdrawal. 

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

All reactor coolant pumps 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. 

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

APPLICABILITY: MODE 3.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One required RCS loop 

inoperable.

A.1 Restore required 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 hour
RCS Loops - MODE 3 

3.4.5

Westinghouse STS 3.4.5-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. [ One required RCS loop 

not in operation with Rod 

Control System capable 

of rod withdrawal.

C.1 Restore required RCS loop 

to operation.

OR

C.2 Place the Rod Control 

System in a condition 

incapable of rod withdrawal.

1 hour

1 hour ]

D. [Two] [required] RCS 

loops inoperable.

OR

Required RCS loop(s) 

not in operation.

D.1 Place the Rod Control 

System in a condition 

incapable of rod withdrawal.

AND

D.2 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

D.3 Initiate action to restore 

one RCS loop to 

OPERABLE status and 

operation.

Immediately

Immediately

Immediately
RCS Loops - MODE 3 

3.4.5

Westinghouse STS 3.4.5-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.5.1 Verify required RCS loops are in operation. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.5.2 Verify steam generator secondary side water levels 

are ≥ [17]% for required RCS loops.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.5.3 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours after a 

required pump is not in operation.

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

Verify correct breaker alignment and indicated 

power are available to each required pump.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

RCS Loops - MODE 4 

3.4.6

Westinghouse 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 residual heat 

removal (RHR) loops shall be OPERABLE, and one loop shall be in 

operation. 

 --------------------------------------------NOTES-------------------------------------------

1. All reactor coolant pumps (RCPs) and RHR pumps 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. No RCP shall be started with any RCS cold leg temperature 

≤ [275°F] [Low Temperature Overpressure Protection (LTOP) 

arming temperature specified in the PTLR] unless the secondary 

side water temperature of each steam generator (SG) is ≤ [50]°F 

above each of the RCS cold leg temperatures. 

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

APPLICABILITY: MODE 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One required loop 

inoperable.

A.1 Initiate action to restore a 

second loop to OPERABLE 

status.

AND

Immediately
RCS Loops - MODE 4 

3.4.6

Westinghouse STS 3.4.6-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

A.2 --------------NOTE--------------

Only required if RHR loop is

OPERABLE.

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

Be in MODE 5. 24 hours

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 RHR or RCS loop is in operation. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Loops - MODE 4 

3.4.6

Westinghouse STS 3.4.6-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.6.2 Verify SG secondary side water levels are ≥ [17]% 

for required RCS loops.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.6.3 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours after a 

required pump is not in operation.

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

Verify correct breaker alignment and indicated 

power are 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

Westinghouse 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 residual heat removal (RHR) loop shall be OPERABLE and in 

operation, and either: 

 a. One additional RHR loop shall be OPERABLE or 

 b. The secondary side water level of at least [two] steam generators 

(SGs) shall be ≥ [17]%. 

 --------------------------------------------NOTES-------------------------------------------

 1. The RHR 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 RHR loop may be inoperable for up to 2 hours for 

surveillance testing provided that the other RHR loop is OPERABLE 

and in operation.

 3. No reactor coolant pump shall be started with one or more RCS cold 

leg temperatures ≤ [275°F] [Low Temperature Overpressure 

Protection (LTOP) arming temperature specified in the PTLR] 

unless the secondary side water temperature of each SG is ≤ [50]°F 

above each of the RCS cold leg temperatures. 

 4. All RHR loops may be removed from 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

Westinghouse STS 3.4.7-2 Rev. 4.0 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One required RHR loop 

inoperable.

AND

One RHR loop 

OPERABLE.

A.1 Initiate action to restore a 

second RHR loop to 

OPERABLE status.

OR

A.2 Initiate action to restore 

required SGs secondary 

side water level to within 

limit.

Immediately

Immediately

B. One or more required 

SGs with secondary side 

water level not within 

limit.

AND

One RHR loop 

OPERABLE.

B.1 Initiate action to restore a 

second RHR 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 RHR loops 

OPERABLE.

OR

Required RHR 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 

RHR loop to OPERABLE 

status and operation.

Immediately

Immediately
RCS Loops - MODE 5, Loops Filled 

3.4.7

Westinghouse STS 3.4.7-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.7.1 Verify required RHR loop is in operation. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.7.2 Verify SG secondary side water level is ≥ [17]% in 

required SGs.

[ 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 are available to each required RHR pump.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

RCS Loops - MODE 5, Loops Not Filled 

3.4.8

Westinghouse 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 residual heat removal (RHR) loops shall be OPERABLE and one 

RHR loop shall be in operation. 

 --------------------------------------------NOTES-------------------------------------------

1. All RHR pumps may be removed from operation for ≤ 15 minutes 

when switching from one loop to another provided: 

[ a. The core outlet temperature is maintained > 10°F below 

saturation temperature, ] 

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 RHR loop may be inoperable for ≤ 2 hours for surveillance 

testing provided that the other RHR loop is OPERABLE and in 

operation. 

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

APPLICABILITY: MODE 5 with RCS loops not filled. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One required RHR loop 

inoperable.

A.1 Initiate action to restore 

RHR loop to OPERABLE 

status.

Immediately
RCS Loops - MODE 5, Loops Not Filled 

3.4.8

Westinghouse STS 3.4.8-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B. No required RHR loop 

OPERABLE.

OR

Required RHR 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 

RHR loop to OPERABLE 

status and operation.

Immediately

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.8.1 Verify required RHR 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

Westinghouse 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 are available to each required RHR pump.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Pressurizer 

3.4.9

Westinghouse 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 ≤ [92]% and 

 b. [Two groups of] pressurizer heaters OPERABLE with the capacity 

[of each group] ≥ [125] kW [and capable of being powered from an 

emergency power supply]. 

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Pressurizer water level 

not within limit.

A.1 Be in MODE 3.

AND

A.2 Fully insert all rods.

AND

A.3 Place Rod Control System 

in a condition incapable of 

rod withdrawal.

AND

A.4 Be in MODE 4.

6 hours

6 hours

6 hours

12 hours

B. One [required] group of 

pressurizer heaters 

inoperable.

B.1 Restore [required] group of 

pressurizer heaters to 

OPERABLE status.

72 hours

C. Required Action and 

associated Completion 

Time of Condition B not 

met.

C.1 Be in MODE 3.

AND

6 hours
Pressurizer 

3.4.9

Westinghouse STS 3.4.9-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C.2 Be in MODE 4. 12 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.9.1 Verify pressurizer water level is ≤ [92]%. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

----------------------------------REVIEWER'S NOTE---------------------------------

The frequency for performing Pressurizer heater capacity testing shall 

be either 18 months or 92 days, depending on whether or not the plant 

has dedicated safety-related heaters. For dedicated safety-related 

heaters, which do not normally operate, 92 days is applied. For 

non-dedicated safety-related heaters, which normally operate,

18 months is applied.

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

SR 3.4.9.2 Verify capacity of each required group of pressurizer 

heaters is ≥ [125] kW.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Pressurizer 

3.4.9

Westinghouse STS 3.4.9-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.9.3 [ Verify required pressurizer heaters are capable of 

being powered from an emergency power supply.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

Pressurizer Safety Valves 

3.4.10

Westinghouse STS 3.4.10-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.10 Pressurizer Safety Valves 

LCO 3.4.10 [Three] pressurizer safety valves shall be OPERABLE with lift settings 

≥ [2460] psig and ≤ [2510] psig. 

APPLICABILITY: MODES 1, 2, and 3,

 MODE 4 with all RCS cold leg temperatures > [275°F] [Low Temperature 

Overpressure Protection (LTOP) arming temperature specified in the 

PTLR]. 

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

The lift settings are not required to be within the LCO limits during 

MODES 3 and 4 for the purpose of setting the pressurizer safety valves 

under ambient (hot) conditions. This exception is allowed for [54] 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 or more pressurizer 

safety valves inoperable.

B.1 Be in MODE 3.

AND

B.2 Be in MODE 4 with any 

RCS cold leg temperatures 

≤ [275F] [LTOP arming 

temperature specified in the 

PTLR].

6 hours

[24] hours
Pressurizer Safety Valves 

3.4.10

Westinghouse 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 PORVs 

3.4.11

Westinghouse STS 3.4.11-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.11 Pressurizer Power Operated Relief Valves (PORVs) 

LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS 

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

Separate Condition entry is allowed for each PORV and each block valve. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more PORVs 

inoperable and capable 

of being manually 

cycled.

A.1 Close and maintain power 

to associated block valve.

1 hour

B. One [or two] PORV[s] 

inoperable and not 

capable of being 

manually cycled.

B.1 Close associated block 

valve[s].

AND

B.2 Remove power from 

associated block valve[s].

AND

B.3 Restore PORV[s] to 

OPERABLE status.

1 hour

1 hour

72 hours
Pressurizer PORVs 

3.4.11

Westinghouse STS 3.4.11-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. One [or two] block 

valve(s) inoperable.

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

Required Actions C.1 and C.2 do 

not apply when block valve is 

inoperable solely as a result of 

complying with Required Actions 

B.2 or E.2.

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

C.1 Place associated PORV in 

manual control.

AND

C.2 Restore block valve to 

OPERABLE status.

1 hour

72 hours

D. Required Action and 

associated Completion 

Time of Condition A, B, 

or C not met.

D.1 Be in MODE 3.

AND

D.2 Be in MODE 4.

6 hours

12 hours

E. Two [or three] PORVs 

inoperable and not 

capable of being 

manually cycled.

E.1 Close associated block 

valves.

AND

E.2 Remove power from 

associated block valves.

AND

E.3 Be in MODE 3.

AND

E.4 Be in MODE 4.

1 hour

1 hour

6 hours

12 hours
Pressurizer PORVs 

3.4.11

Westinghouse STS 3.4.11-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

F. Two [or three] block 

valves inoperable.

F.1 --------------NOTE--------------

Required Action F.1 does 

not apply when block valve 

is inoperable solely as a 

result of complying with 

Required Actions B.2 or E.2

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

Restore one block valve to 

OPERABLE status [if three 

block valves are 

inoperable].

[2 hours]

G. Required Action and 

associated Completion 

Time of Condition F not 

met.

G.1 Be in MODE 3.

AND

G.2 Be in MODE 4.

6 hours

12 hours
Pressurizer PORVs 

3.4.11

Westinghouse STS 3.4.11-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.11.1 ------------------------------NOTES-----------------------------

1. Not required to be performed with block valve 

closed in accordance with the Required Actions 

of this LCO.

2. Only required to be performed in 

MODES 1 and 2.

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

Perform a complete cycle of each block valve. [ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.11.2 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

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

Perform a complete cycle of each PORV. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.11.3 [ Perform a complete cycle of each solenoid air 

control valve and check valve on the air 

accumulators in PORV control systems.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
Pressurizer PORVs 

3.4.11

Westinghouse STS 3.4.11-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.11.4 [ Verify PORVs and block valves are capable of 

being powered from emergency power sources.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

LTOP System 

3.4.12

Westinghouse 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] [high 

pressure injection (HPI)] pump [and one charging pump] capable of 

injecting into the RCS and the accumulators isolated and one of the 

following pressure relief capabilities: 

 a. Two power operated relief valves (PORVs) with lift settings within the 

limits specified in the PTLR, 

 [ b. Two residual heat removal (RHR) suction relief valves with setpoints 

 [436.5] psig and  [463.5] psig, ] 

 [ c. One PORV with a lift setting within the limits specified in the PTLR 

and one RHR suction relief valve with a setpoint  [436.5] psig and 

 [463.5] psig, ] or

 d. The RCS depressurized and an RCS vent of ≥ [2.07] square inches. 

 --------------------------------------------NOTES-------------------------------------------

 1. [Two charging pumps] may be made capable of injecting for  1 hour 

for pump swap operations. 

 2. Accumulator may be unisolated when accumulator pressure is less 

than the maximum RCS pressure for the existing RCS cold leg 

temperature allowed by the P/T limit curves provided in the PTLR. 

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

APPLICABILITY: MODE 4 when any RCS cold leg temperature is ≤ [275°F] [LTOP arming 

temperature specified in the PTLR], 

 MODE 5,

 MODE 6 when the reactor vessel head is on. 
LTOP System 

3.4.12

Westinghouse STS 3.4.12-2 Rev. 4.0 

ACTIONS 

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

LCO 3.0.4.b is not applicable when entering MODE 4. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. Two or more [HPI] 

pumps capable of 

injecting into the RCS.

A.1 Initiate action to verify a 

maximum of [one] [HPI] 

pump is capable of injecting 

into the RCS.

Immediately

B. [ Two or more charging 

pumps capable of 

injecting into the RCS.

B.1 Initiate action to verify a 

maximum of [one] charging 

pump is capable of injecting 

into the RCS.

Immediately ]

C. An accumulator not 

isolated when the 

accumulator pressure is 

greater than or equal to 

the maximum RCS 

pressure for existing 

cold leg temperature 

allowed in the PTLR.

C.1 Isolate affected 

accumulator.

1 hour

D. Required Action and 

associated Completion 

Time of Condition [C] not 

met.

D.1 Increase RCS cold leg 

temperature to > [275°F] 

[LTOP arming temperature 

specified in the PTLR].

OR

D.2 Depressurize affected 

accumulator to less than 

the maximum RCS 

pressure for existing cold 

leg temperature allowed in 

the PTLR.

12 hours

12 hours

E. One required RCS relief 

valve inoperable in 

MODE 4.

E.1 Restore required RCS relief 

valve to OPERABLE status.

7 days
LTOP System 

3.4.12

Westinghouse STS 3.4.12-3 Rev. 4.0 

ACTINS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

F. One required RCS relief 

valve inoperable in 

MODE 5 or 6.

F.1 Restore required RCS relief 

valve to OPERABLE status.

24 hours

G. Two required RCS relief 

valves inoperable.

OR

Required Action and 

associated Completion 

Time of Condition A, [B,] 

D, E, or F not met.

OR

LTOP System 

inoperable for any 

reason other than 

Condition A, [B,] C, D, E, 

or F.

G.1 Depressurize RCS and 

establish RCS vent of 

≥ [2.07] square inches.

12 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.12.1 Verify a maximum of [one] [HPI] pump is capable of 

injecting into the RCS.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
LTOP System 

3.4.12

Westinghouse STS 3.4.12-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.12.2 [ Verify a maximum of one charging pump is 

capable of injecting into the RCS.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.4.12.3 Verify each accumulator is isolated. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.12.4 [ Verify RHR suction valve is open for each required 

RHR suction relief valve.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
LTOP System 

3.4.12

Westinghouse STS 3.4.12-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.12.5 Verify required RCS vent ≥ [2.07] square inches 

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 3.4.12.6 Verify PORV block valve is open for each required 

PORV.

[ 72 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.12.7 [ Verify associated RHR suction isolation valve is 

locked open with operator power removed for each 

required RHR suction relief valve.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
LTOP System 

3.4.12

Westinghouse STS 3.4.12-6 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.12.8 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours after 

decreasing RCS cold leg temperature to ≤ [275°F] 

[LTOP arming temperature specified in the PTLR].

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

Perform a COT on each required PORV, excluding 

actuation.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.12.9 Perform CHANNEL CALIBRATION for each 

required PORV actuation channel.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Operational LEAKAGE 

3.4.13

Westinghouse 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

Westinghouse 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

Westinghouse 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 limit. 

APPLICABILITY: MODES 1, 2, and 3,

 MODE 4, except valves in the residual heat removal (RHR) flow path 

when in, or during the transition to or from, the RHR 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 in the reactor 

coolant 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

Westinghouse 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. [ RHR 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

Westinghouse 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 RHR flow path when in the 

shutdown cooling 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] psig and ≤ [2255] psig.

In accordance 

with the Inservice 

Testing Program, 

and [ [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

Westinghouse 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 RHR System 

autoclosure interlock is disabled in accordance with 

SR 3.4.12.7.

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

Verify RHR 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 RHR System 

autoclosure interlock is disabled in accordance with 

SR 3.4.12.7.

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

Verify RHR 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

Westinghouse 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 (level or discharge flow) monitor, 

 b. One containment atmosphere radioactivity monitor (gaseous or 

particulate), and 

 [ c. One containment air cooler condensate flow rate monitor. ] 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Required 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 required 

containment sump monitor 

to OPERABLE status.

Once per 24 hours

30 days
RCS Leakage Detection Instrumentation 

3.4.15

Westinghouse STS 3.4.15-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B. Required containment 

atmosphere radioactivity 

monitor inoperable.

B.1.1 Analyze grab samples of 

the containment 

atmosphere.

 OR

B.1.2 --------------NOTE--------------

Not required until 12 hours 

after establishment of 

steady state operation.

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

Perform SR 3.4.13.1.

AND

B.2.1 Restore required 

containment atmosphere 

radioactivity monitor to 

OPERABLE status.

 OR

[ B.2.2 Verify containment air 

cooler condensate flow rate 

monitor is OPERABLE.

Once per 24 hours

Once per 24 hours

30 days

30 days

C. [ Containment air cooler 

condensate flow rate 

monitor inoperable.

C.1 Perform SR 3.4.15.1.

OR

C.2 --------------NOTE--------------

Not required until 12 hours 

after establishment of 

steady state operation.

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

Perform SR 3.4.13.1.

Once per 8 hours

Once per 24 hours ]
RCS Leakage Detection Instrumentation 

3.4.15

Westinghouse STS 3.4.15-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

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

Only applicable when the 

containment atmosphere 

gaseous radiation monitor is 

the only OPERABLE 

monitor.

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

D. Required containment 

sump monitor 

inoperable.

AND

[ Containment air cooler 

condensate flow rate 

monitor inoperable. ]

D.1 Analyze grab samples of 

the containment 

atmosphere.

AND

D.2.1 Restore required 

containment sump monitor 

to OPERABLE status.

 OR

[ D.2.2 Restore containment air 

cooler condensate flow rate 

monitor to OPERABLE 

status. ]

Once per 12 hours

7 days

7 days

E. [ Required containment 

atmosphere radioactivity 

monitor inoperable.

AND

[ Containment air cooler 

condensate flow rate 

monitor inoperable. ]

E.1 Restore required 

containment atmosphere 

radioactivity monitor to 

OPERABLE status.

OR

[ E.2 Restore containment air 

cooler condensate flow rate 

monitor to OPERABLE 

status. ]

30 days

30 days ]

F. Required Action and 

associated Completion 

Time not met.

F.1 Be in MODE 3.

AND

F.2 Be in MODE 5.

6 hours

36 hours

G. All required monitors 

inoperable.

G.1 Enter LCO 3.0.3. Immediately
RCS Leakage Detection Instrumentation 

3.4.15

Westinghouse STS 3.4.15-4 Rev. 4.0 

 SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.15.1 Perform CHANNEL CHECK of the required 

containment atmosphere radioactivity monitor.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.15.2 Perform COT of the required containment 

atmosphere radioactivity monitor.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Leakage Detection Instrumentation 

3.4.15

Westinghouse STS 3.4.15-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required 

containment sump monitor.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.15.4 [ Perform CHANNEL CALIBRATION of the required 

containment atmosphere radioactivity monitor.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.4.15.5 [ Perform CHANNEL CALIBRATION of the required 

containment air cooler condensate flow rate monitor.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

RCS Specific Activity 

3.4.16

Westinghouse 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 μCi/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. Gross specific activity of 

the reactor coolant not 

within limit.

B.1 Be in MODE 3 with 

Tavg < 500°F.

6 hours
RCS Specific Activity 

3.4.16

Westinghouse STS 3.4.16-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

C. Required Action and 

associated Completion 

Time of Condition A not 

met.

OR

DOSE EQUIVALENT 

I-131 in the 

unacceptable region of 

Figure 3.4.16-1.

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 μCi/gm.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Specific Activity 

3.4.16

Westinghouse 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 μCi/gm.

[ 14 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

AND

Between 2 and 

6 hours after a 

THERMAL 

POWER change 

of ≥ 15% RTP 

within a 1 hour 

period
RCS Specific Activity 

3.4.16

Westinghouse STS 3.4.16-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.4.16.3 -------------------------------NOTE------------------------------

Not required to be performed until 31 days after a 

minimum of 2 effective full power days and 20 days 

of MODE 1 operation have elapsed since the 

reactor was last subcritical for ≥ 48 hours.

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

Determine Ē from a sample taken in MODE 1 after a 

minimum of 2 effective full power days and 20 days 

of MODE 1 operation have elapsed since the 

reactor was last subcritical for ≥ 48 hours.

[ 184 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Specific Activity 

3.4.16

Westinghouse STS 3.4.16-5 Rev. 4.0 

RCS Loop Isolation Valves 

3.4.17

Westinghouse STS 3.4.17-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.17 RCS Loop Isolation Valves 

LCO 3.4.17 Each RCS hot and cold leg loop isolation valve shall be open with power 

removed from each isolation valve operator. 

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

ACTIONS 

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

Separate Condition entry is allowed for each RCS loop isolation valve. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. Power available to one 

or more loop isolation 

valve operators.

A.1 Remove power from loop 

isolation valve operators.

30 minutes

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

All Required Actions 

shall be completed 

whenever this Condition 

is entered.

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

One or more RCS loop 

isolation valves closed.

B.1 Maintain valve(s) closed.

AND

B.2 Be in MODE 3.

AND

B.3 Be in MODE 5.

Immediately

6 hours

36 hours
RCS Loop Isolation Valves 

3.4.17

Westinghouse STS 3.4.17-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.17.1 Verify each RCS loop isolation valve is open and 

power is removed from each loop isolation valve 

operator.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RCS Isolated Loop Startup 

3.4.18

Westinghouse STS 3.4.18-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.18 RCS Isolated Loop Startup 

LCO 3.4.18 Each RCS isolated loop shall remain isolated with: 

 a. The hot and cold leg isolation valves closed if boron concentration 

of the isolated loop is less than boron concentration required to 

meet the SDM of LCO 3.1.1 or boron concentration of LCO 3.9.1 

and

 b. The cold leg isolation valve closed if the cold leg temperature of the 

isolated loop is > [20]°F below the highest cold leg temperature of 

the operating loops.

APPLICABILITY: MODES 5 and 6.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Isolated loop hot or cold 

leg isolation valve open 

with LCO requirements 

not met.

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

Only required if boron 

concentration requirement 

not met.

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

Close hot and cold leg 

isolation valves.

OR

A.2 --------------NOTE--------------

Only required if 

temperature requirement 

not met.

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

Close cold leg isolation 

valve.

Immediately

Immediately
RCS Isolated Loop Startup 

3.4.18

Westinghouse STS 3.4.18-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.18.1 Verify cold leg temperature of isolated loop is 

≤ [20]°F below the highest cold leg temperature of 

the operating loops.

Within 30 minutes 

prior to opening 

the cold leg 

isolation valve in 

isolated loop

SR 3.4.18.2 Verify boron concentration of isolated loop is greater 

than or equal to the boron concentration required to 

meet the SDM of LCO 3.1.1 or boron concentration 

of LCO 3.9.1.

Within 2 hours 

prior to opening 

the hot or cold leg 

isolation valve in 

isolated loop
RCS Loops - Test Exceptions 

3.4.19

Westinghouse STS 3.4.19-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.19 RCS Loops - Test Exceptions 

LCO 3.4.19 The requirements of LCO 3.4.4, "RCS Loops - MODES 1 and 2," may be 

suspended with THERMAL POWER < P-7.

APPLICABILITY: MODES 1 and 2 during startup and PHYSICS TESTS. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. THERMAL POWER 

≥ P-7.

A.1 Open reactor trip breakers. Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.19.1 Verify THERMAL POWER is < P-7. [ 1 hour

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.4.19.2 Perform a COT for each power range neutron flux -

low channel, intermediate range neutron flux 

channel, P-10, and P-13.

Prior to initiation 

of startup and 

PHYSICS TESTS

SR 3.4.19.3 Perform an ACTUATION LOGIC TEST on P-7. Prior to initiation 

of startup and 

PHYSICS TESTS

SG Tube Integrity 

3.4.20

Westinghouse STS 3.4.20-1 Rev. 4.0 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.20 Steam Generator (SG) Tube Integrity 

LCO 3.4.20 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 

3.4.20

Westinghouse STS 3.4.20-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.4.20.1 Verify SG tube integrity in accordance with the 

Steam Generator Program.

In accordance 

with the Steam 

Generator 

Program

SR 3.4.20.2 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
Accumulators 

3.5.1

Westinghouse STS 3.5.1-1 Rev. 4.0 

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.1 Accumulators 

LCO 3.5.1 [Four] ECCS accumulators shall be OPERABLE. 

APPLICABILITY: MODES 1 and 2,

 MODE 3 with RCS pressure > [1000] psig. 

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. One accumulator 

inoperable due to boron 

concentration not within 

limits.

A.1 Restore boron 

concentration to within 

limits.

72 hours

B. One accumulator 

inoperable for reasons 

other than Condition A.

B.1 Restore accumulator to 

OPERABLE status.

24 hours

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 

≤ [1000] psig.

6 hours

12 hours

D. Two or more 

accumulators 

inoperable.

D.1 Enter LCO 3.0.3. Immediately
Accumulators 

3.5.1

Westinghouse STS 3.5.1-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.5.1.1 Verify each accumulator 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 accumulator is 

≥ [ 7853 gallons ( )% and ≤ 8171 gallons ( )%].

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.5.1.3 Verify nitrogen cover pressure in each accumulator 

is ≥ [385] psig and ≤ [481] psig.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Accumulators 

3.5.1

Westinghouse STS 3.5.1-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.5.1.4 Verify boron concentration in each accumulator is 

≥ [1900] ppm and ≤ [2100] ppm.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

AND

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

Only required to 

be performed for 

affected 

accumulators

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

Once within 

6 hours after each 

solution volume 

increase of 

≥ [ [ ] gallons, 

( )% of indicated 

level ] that is not 

the result of 

addition from the 

refueling water 

storage tank

SR 3.5.1.5 Verify power is removed from each accumulator 

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

Westinghouse 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. 

 --------------------------------------------NOTES------------------------------------------- 

 [ 1. In MODE 3, both safety injection (SI) pump flow paths may be 

isolated by closing the isolation valves for up to 2 hours to perform 

pressure isolation valve testing per SR 3.4.14.1.

 2. In MODE 3, ECCS pumps may be made incapable of injecting to 

support transition into or from the Applicability of LCO 3.4.12, "Low 

Temperature Overpressure Protection (LTOP) System," for up to 

4 hours or until the temperature of all RCS cold legs exceeds 

[375°F] [Low Temperature Overpressure Protection (LTOP) arming 

temperature specified in the PTLR plus [25]°F], whichever comes 

first. ] 

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

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more trains 

inoperable.

A.1 Restore train(s) 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

C. Less than 100% of the 

ECCS flow equivalent to 

a single OPERABLE 

ECCS train available.

C.1 Enter LCO 3.0.3. Immediately
ECCS - Operating 

3.5.2

Westinghouse 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.

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

Westinghouse 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, for each ECCS throttle valve listed below, 

each position stop is in the correct position.

Valve Number

[ ]

[ ]

[ ]

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
ECCS - Operating 

3.5.2

Westinghouse STS 3.5.2-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.5.2.8 Verify, by visual inspection, each ECCS train 

containment sump suction inlet is not restricted by 

debris and the 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

Westinghouse 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. 

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

 An RHR train may be considered OPERABLE during alignment and 

operation for decay heat removal if capable of being manually realigned 

to the ECCS mode of operation.

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

APPLICABILITY: MODE 4.

ACTIONS 

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

LCO 3.0.4.b is not applicable to ECCS high head subsystem. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. [ Required ECCS 

residual heat removal 

(RHR) subsystem 

inoperable.

A.1 Initiate action to restore 

required ECCS RHR 

subsystem to OPERABLE 

status.

Immediately ]

B. Required ECCS [high 

head subsystem] 

inoperable.

B.1 Restore required ECCS 

[high head 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

Westinghouse STS 3.5.3-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.5.3.1 The following SRs are applicable for all equipment 

required to be OPERABLE:

[SR 3.5.2.1] [SR 3.5.2.7]

[SR 3.5.2.3] SR 3.5.2.8

SR 3.5.2.4

In accordance 

with applicable 

SRs
RWST 

3.5.4

Westinghouse STS 3.5.4-1 Rev. 4.0 

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.4 Refueling Water Storage Tank (RWST) 

LCO 3.5.4 The RWST shall be OPERABLE. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. RWST boron 

concentration not within 

limits.

OR

RWST borated water 

temperature not within 

limits.

A.1 Restore RWST to 

OPERABLE status.

8 hours

B. RWST inoperable for 

reasons other than 

Condition A.

B.1 Restore RWST to 

OPERABLE status.

1 hour

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
RWST 

3.5.4

Westinghouse 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 < [35]°F or > [100]°F. ]

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

Verify RWST borated water temperature is ≥ [35]°F 

and ≤ [100]°F.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.5.4.2 Verify RWST borated water volume is ≥ [466,200 

gallons ( )%].

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.5.4.3 Verify RWST boron concentration is ≥ [2000] ppm 

and ≤ [2200] ppm.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Seal Injection Flow 

3.5.5

Westinghouse STS 3.5.5-1 Rev. 4.0 

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.5 Seal Injection Flow 

LCO 3.5.5 Reactor coolant pump seal injection flow [resistance] shall be [≤ [40] gpm 

with [centrifugal charging pump discharge header] pressure ≥ [2480] psig 

and the [charging flow] control valve full open or ≥ [0.2117] ft/gpm2 or 

within the limits of Figure 3.5.5-1].

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Seal injection flow 

[resistance] not within 

limit.

A.1 Adjust manual seal injection 

throttle valves to give a flow 

[resistance] within limit.

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
Seal Injection Flow 

3.5.5

Westinghouse STS 3.5.5-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.5.5.1 -------------------------------NOTE------------------------------

Not required to be performed until 4 hours after the 

Reactor Coolant System pressure stabilizes at 

≥ [2215 psig and ≤ 2255 psig].

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

Verify manual seal injection throttle valves are 

adjusted to give a flow [resistance] [of ≤ [40 gpm] 

with [centrifugal charging pump discharge header] 

pressure ≥ [2480] psig and the [charging flow] 

control valve full open or ≥ [0.2117] ft/gpm2or within 

the limit of Figure 3.5.5-1.]

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Seal Injection Flow 

3.5.5

Westinghouse STS 3.5.5-3 Rev. 4.0 

Figure 3.5.5-1 (page 1 of 1) 

Seal Injection Flow Limits 

For illustration only. Do 

not use for operation.

BIT 

3.5.6

Westinghouse STS 3.5.6-1 Rev. 4.0 

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.6 Boron Injection Tank (BIT) 

LCO 3.5.6 The BIT shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. BIT inoperable. A.1 Restore BIT to OPERABLE 

status.

1 hour

B. Required Action and 

associated Completion 

Time of Condition A not 

met.

B.1 Be in MODE 3.

AND

B.2 Borate to SDM specified in 

COLR.

AND

B.3 Restore BIT to OPERABLE 

status.

6 hours

6 hours

7 days

C. Required Action and 

associated Completion 

Time of Condition B not 

met.

C.1 Be in MODE 4. 12 hours
BIT 

3.5.6

Westinghouse STS 3.5.6-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.5.6.1 Verify BIT borated water temperature is ≥ [145]°F. [ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.5.6.2 [ Verify BIT borated water volume is 

≥ [1100] gallons.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.5.6.3 Verify BIT boron concentration is ≥ [20,000] ppm 

and ≤ [22,500] ppm.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.1

Westinghouse STS 3.6.1-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.1 Containment (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

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 (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.2

Westinghouse STS 3.6.2-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.2 Containment Air Locks (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

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. 

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

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 (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.2

Westinghouse 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 (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.2

Westinghouse 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 Be in MODE 5.

6 hours

36 hours
Containment Air Locks (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.2

Westinghouse 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 (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.3

Westinghouse STS 3.6.3-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.3 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and 

Dual) 

LCO 3.6.3 Each containment isolation valve (CIV) shall be OPERABLE. 

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

ACTIONS 

-----------------------------------------------------------NOTES----------------------------------------------------------

1. Penetration flow path(s) [except for [42] inch purge valve 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 systems 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 (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.3

Westinghouse STS 3.6.3-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

A. [ One or more 

penetration flow paths 

with one containment 

isolation valve 

inoperable [for reasons 

other than Condition[s] E

[and F]].

AND

Containment isolation 

valve pressure boundary 

intact.

A.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

4 hours for 

Category 1 CIVs

AND

8 hours for 

Category 2 CIVs

AND

12 hours for 

Category 3 CIVs

AND

24 hours for 

Category 4 CIVs 

AND

48 hours for 

Category 5 CIVs

AND

72 hours for 

Category 6 CIVs

AND

7 days for Category 7 

CIVs
 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.3

Westinghouse STS 3.6.3-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

A.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.

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 (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.3

Westinghouse STS 3.6.3-4 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B. [ One or more 

penetration flow paths 

with one containment 

isolation valve 

inoperable [for reasons 

other than Condition[s] E 

[and F]].

AND

Containment isolation 

valve pressure boundary 

not intact.

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

4 hours for 

Category 8 CIVs

AND

8 hours for 

Category 9 CIVs

AND

12 hours for 

Category 10 CIVs

AND

24 hours for 

Category 11 CIVs 

AND

48 hours for 

Category 12 CIVs

AND

72 hours for 

Category 13 CIVs

AND

7 days for 

Category 14 CIVs
 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.3

Westinghouse STS 3.6.3-5 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.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 

administrative 

means.

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

Verify the affected 

penetration flow path is 

isolated.

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 ]

C. ------------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 Condition[s] E

[and F]].

C.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 (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.3

Westinghouse STS 3.6.3-6 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

D. Two or more penetration 

flow paths with one 

containment isolation 

valve inoperable [for 

reasons other than 

Condition[s] E [and F]].

D.1 Isolate all but one 

penetration flow path by 

use of at least one closed 

and de-activated automatic 

valve, closed manual valve, 

or blind flange.

4 hours

E. [ One or more shield 

building bypass leakage 

[or purge valve leakage] 

not within limit.

E.1 Restore leakage within 

limit.

4 hours for shield 

building bypass 

leakage

AND

24 hours for purge 

valve leakage ]

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 (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.3

Westinghouse STS 3.6.3-7 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 3.6.3.7 for the 

resilient seal purge valves 

closed to comply with 

Required Action F.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 [92] days ]

G. Required Action and 

associated Completion 

Time not met.

G.1 Be in MODE 3.

AND

G.2 Be in MODE 5.

6 hours

36 hours
 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.3

Westinghouse STS 3.6.3-8 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.3.1 [ Verify each [42] inch purge valve is sealed closed, 

except for one purge valve in a penetration flow path 

while in Condition E of this 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 containment 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 ] ]

SR 3.6.3.3 -------------------------------NOTE------------------------------

Valves and blind flanges in high radiation areas may 

be verified by use of administrative controls.

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

Verify each containment isolation manual valve and 

blind flange that is located outside 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.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.3

Westinghouse STS 3.6.3-9 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

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 ]

SR 3.6.3.6 [ Cycle each weight or spring loaded check valve 

testable during operation through one complete 

cycle of full travel, and verify each check valve 

remains closed when the differential pressure in the 

direction of flow is ≤ [1.2] psid and opens when the 

differential pressure in the direction of flow is 

≥ [1.2] psid and < [5.0] psid.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.3

Westinghouse STS 3.6.3-10 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.3.7 [ 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 3.6.3.8 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 3.6.3.9 [ Cycle each weight or spring loaded check valve 

not testable during operation through one complete 

cycle of full travel, and verify each check valve 

remains closed when the differential pressure in the 

direction of flow is ≤ [1.2] psid and opens when the 

differential pressure in the direction of flow is 

≥ [1.2] psid and < [5.0] psid.

[ 18 months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.3

Westinghouse STS 3.6.3-11 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.3.10 [ 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 ] ]

SR 3.6.3.11 [ Verify the combined leakage rate for all shield 

building bypass leakage paths is ≤ [La] when 

pressurized to ≥ [psig].

In accordance 

with the 

Containment 

Leakage Rate 

Testing Program ]

Containment Pressure (Atmospheric, Dual, and Ice Condenser) 

3.6.4A

Westinghouse STS 3.6.4A-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.4A Containment Pressure (Atmospheric, Dual, and Ice Condenser) 

LCO 3.6.4A Containment pressure shall be ≥ [-0.3] psig and ≤ [+1.5] 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 Be in MODE 5.

6 hours

36 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.4A.1 Verify containment pressure is within limits. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Containment Pressure (Subatmospheric) 

3.6.4B

Westinghouse STS 3.6.4B-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.4B Containment Pressure (Subatmospheric) 

LCO 3.6.4B Containment air partial pressure shall be ≥ [9.0] psia and within the 

acceptable operation range shown on Figure 3.6.4B-1.

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

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. Containment air partial 

pressure not within 

limits.

A.1 Restore containment air 

partial pressure to within 

limits.

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 3.6.4B.1 Verify containment air partial pressure is within 

limits.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Pressure (Subatmospheric) 

3.6.4B

Westinghouse STS 3.6.4B-2 Rev. 4.0 
Containment Air Temperature (Atmospheric and Dual) 

3.6.5A

Westinghouse STS 3.6.5A-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.5A Containment Air Temperature (Atmospheric and Dual) 

LCO 3.6.5A Containment average air temperature shall be ≤ [120]°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 Be in MODE 5.

6 hours

36 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.5A.1 Verify containment average air temperature is within 

limit.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Containment Air Temperature (Ice Condenser) 

3.6.5B

Westinghouse STS 3.6.5B-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.5B Containment Air Temperature (Ice Condenser) 

LCO 3.6.5B Containment average air temperature shall be: 

 a. ≥ [85]°F and ≤ [110]°F for the containment upper compartment and

 b. ≥ [100]°F and ≤ [120]°F for the containment lower compartment.

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

 The minimum containment average air temperature in MODES 2, 3, 

and 4 may be reduced to [60]°F. 

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

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Containment average air 

temperature not within 

limits.

A.1 Restore containment 

average air temperature to 

within limits.

8 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
Containment Air Temperature (Ice Condenser) 

3.6.5B

Westinghouse STS 3.6.5B-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.5B.1 Verify containment upper compartment average air 

temperature is within limits.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.5B.2 Verify containment lower compartment average air 

temperature is within limits.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Air Temperature (Subatmospheric) 

3.6.5C

Westinghouse STS 3.6.5C-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.5C Containment Air Temperature (Subatmospheric) 

LCO 3.6.5C Containment average air temperature shall be ≥ [86]°F and ≤ [120]°F. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Containment average air 

temperature not within 

limits.

A.1 Restore containment 

average air temperature to 

within limits.

8 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

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.5C.1 Verify containment average air temperature is within 

limits.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Containment Spray and Cooling Systems (Atmospheric and Dual) 

3.6.6A

Westinghouse STS 3.6.6A-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.6A Containment Spray and Cooling Systems (Atmospheric and Dual) (Credit taken for 

iodine removal by the Containment Spray System) 

LCO 3.6.6A 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.

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

84 hours

C. One [required] 

containment cooling 

train inoperable.

C.1 Restore [required] 

containment cooling train to 

OPERABLE status.

7 days

D. Two [required] 

containment cooling 

trains inoperable.

D.1 Restore one [required] 

containment cooling train to 

OPERABLE status.

72 hours

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
Containment Spray and Cooling Systems (Atmospheric and Dual) 

3.6.6A

Westinghouse STS 3.6.6A-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

F. Two containment spray 

trains inoperable.

OR

Any combination of three 

or more trains 

inoperable.

F.1 Enter LCO 3.0.3. Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.6A.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 ]

SR 3.6.6A.2 Operate each [required] containment cooling train 

fan unit for ≥ 15 minutes.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Spray and Cooling Systems (Atmospheric and Dual) 

3.6.6A

Westinghouse STS 3.6.6A-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.6A.3 Verify each [required] containment cooling train 

cooling water flow rate is ≥ [700] gpm.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.6A.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 3.6.6A.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 ]

SR 3.6.6A.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 ]
Containment Spray and Cooling Systems (Atmospheric and Dual) 

3.6.6A

Westinghouse STS 3.6.6A-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.6A.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 3.6.6A.8 Verify each spray nozzle is unobstructed. [At first refueling]

AND

[ 10 years

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Spray and Cooling Systems (Atmospheric and Dual) 

3.6.6B

Westinghouse STS 3.6.6B-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.6B Containment Spray and Cooling Systems (Atmospheric and Dual (Credit not taken 

for iodine removal by the Containment Spray System) 

LCO 3.6.6B 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. One [required] 

containment cooling 

train inoperable.

B.1 Restore [required] 

containment cooling train to 

OPERABLE status.

7 days

C. Two containment spray 

trains inoperable.

C.1 Restore one containment 

spray train to OPERABLE 

status.

72 hours

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

72 hours
Containment Spray and Cooling Systems (Atmospheric and Dual) 

3.6.6B

Westinghouse STS 3.6.6B-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 A, B, 

C, D, or E not met.

F.1 Be in MODE 3.

AND

F.2 Be in MODE 5.

6 hours

36 hours

G. Any combination of three 

or more trains 

inoperable.

G.1 Enter LCO 3.0.3. Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.6B.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 (Atmospheric and Dual) 

3.6.6B

Westinghouse STS 3.6.6B-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.6B.2 Operate each [required] containment cooling train 

fan unit for ≥ 15 minutes.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.6B.3 Verify each [required] containment cooling train 

cooling water flow rate is ≥ [700] gpm.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.6B.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 3.6.6B.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 (Atmospheric and Dual) 

3.6.6B

Westinghouse STS 3.6.6B-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.6B.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 3.6.6B.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 3.6.6B.8 Verify each spray nozzle is unobstructed. [At first refueling]

AND

[ 10 years

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Containment Spray System (Ice Condenser) 

3.6.6C

Westinghouse STS 3.6.6C-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.6C Containment Spray System (Ice Condenser) 

LCO 3.6.6C Two containment spray 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.

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 3.6.6C.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 System (Ice Condenser) 

3.6.6C

Westinghouse STS 3.6.6C-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.6C.2 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 3.6.6C.3 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 ]

SR 3.6.6C.4 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 3.6.6C.5 Verify each spray nozzle is unobstructed. [At first refueling]

AND

[ 10 years

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
QS System (Subatmospheric) 

3.6.6D

Westinghouse STS 3.6.6D-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.6D Quench Spray (QS) System (Subatmospheric) 

LCO 3.6.6D Two QS trains shall be OPERABLE. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One QS train inoperable. A.1 Restore QS train 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

36 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.6D.1 Verify each QS 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 3.6.6D.2 Verify each QS 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
QS System (Subatmospheric) 

3.6.6D

Westinghouse STS 3.6.6D-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.6D.3 Verify each QS 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 3.6.6D.4 Verify each QS pump starts automatically on an 

actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.6D.5 Verify each spray nozzle is unobstructed. [At first refueling]

AND

[ 10 years

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
RS System (Subatmospheric) 

3.6.6E

Westinghouse STS 3.6.6E-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.6E Recirculation Spray (RS) System (Subatmospheric) 

LCO 3.6.6E Four RS subsystems [and a casing cooling tank] shall be OPERABLE. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One RS subsystem 

inoperable.

A.1 Restore RS subsystem to 

OPERABLE status.

7 days

B. Two RS subsystems 

inoperable in one train.

B.1 Restore one RS subsystem 

to OPERABLE status.

72 hours

C. [ Two inside RS 

subsystems inoperable.

C.1 Restore one RS subsystem 

to OPERABLE status.

72 hours ]

D. [ Two outside RS 

subsystems inoperable.

D.1 Restore one RS subsystem 

to OPERABLE status.

72 hours ]

E. [ Casing cooling tank 

inoperable.

E.1 Restore casing cooling tank 

to OPERABLE status.

72 hours ]

F. Required Action and 

associated Completion 

Time not met.

F.1 Be in MODE 3.

AND

F.2 Be in MODE 5.

6 hours

84 hours

G. Three or more RS 

subsystems inoperable.

G.1 Enter LCO 3.0.3. Immediately
RS System (Subatmospheric) 

3.6.6E

Westinghouse STS 3.6.6E-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.6E.1 Verify casing cooling tank temperature is ≥ [35]°F 

and ≤ [50]°F.

[ 24 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.6E.2 Verify casing cooling tank contained borated water 

volume is ≥ [116,500] gal.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.6E.3 Verify casing cooling tank boron concentration is 

≥ [2300] ppm and ≤ [2400] ppm.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.6E.4 Verify each RS [and casing cooling] 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 ]
RS System (Subatmospheric) 

3.6.6E

Westinghouse STS 3.6.6E-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.6E.5 Verify each RS [and casing cooling] 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 3.6.6E.6 Verify on an actual or simulated actuation signal(s):

a. Each RS automatic valve in the flow path that is 

not locked, sealed, or otherwise secured in 

position, actuates to the correct position,

b. Each RS pump starts automatically, and

c. [ Each casing cooling pump starts 

automatically. ]

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.6E.7 Verify each spray nozzle is unobstructed. [ At first refueling ]

AND

[ 10 years

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Spray Additive System (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.7

Westinghouse STS 3.6.7-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.7 Spray Additive System (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

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 (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 

3.6.7

Westinghouse STS 3.6.7-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SR 3.6.7.2 Verify spray additive tank solution volume is 

≥ [2568] gal and ≤ [4000] 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 ≥ [30]% and ≤ [32]% by weight.

[ 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 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 3.6.7.5 Verify spray additive flow [rate] from each solution's 

flow path.

[ 5 years

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Shield Building (Dual and Ice Condenser) 

3.6.8

Westinghouse STS 3.6.8-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.8 Shield Building (Dual and Ice Condenser) 

LCO 3.6.8 The shield building shall be OPERABLE. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Shield building 

inoperable.

A.1 Restore shield building to 

OPERABLE status.

24 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

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.8.1 [ Verify annulus negative pressure is > [5] inches 

water gauge.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Shield Building (Dual and Ice Condenser) 

3.6.8

Westinghouse STS 3.6.8-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.8.2 Verify one shield building access door in each 

access opening is closed.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.8.3 [ Verify shield building structural integrity by 

performing a visual inspection of the exposed 

interior and exterior surfaces of the shield building.

During shutdown 

for SR 3.6.1.1 

Type A tests ]

SR 3.6.8.4 Verify the shield building can be maintained at a 

pressure equal to or more negative than [-0.5] inch 

water gauge in the annulus by one Shield Building 

Air Cleanup System train with final flow ≤ [ ] cfm 

within [22] seconds after a start signal.

[ [18] months on a 

STAGGERED 

TEST BASIS for 

each Shield 

Building Air 

Cleanup System 

train

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
HMS (Atmospheric, Ice Condenser, and Dual) 

3.6.9

Westinghouse STS 3.6.9-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.9 Hydrogen Mixing System (HMS) (Atmospheric, Ice Condenser, and Dual) 

LCO 3.6.9 [Two] HMS trains shall be OPERABLE. 

APPLICABILITY: MODES 1 and 2.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One HMS train 

inoperable.

A.1 Restore HMS train to 

OPERABLE status.

30 days

B. Two HMS trains 

inoperable.

B.1 Verify by administrative 

means that the hydrogen 

control function is 

maintained.

AND

B.2 Restore one HMS train to 

OPERABLE status.

1 hour

AND

Once per 12 hours 

thereafter

7 days

C. Required Action and 

associated Completion 

Time not met.

C.1 Be in MODE 3. 6 hours
HMS (Atmospheric, Ice Condenser, and Dual) 

3.6.9

Westinghouse STS 3.6.9-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.9.1 Operate each HMS train for ≥ 15 minutes. [ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.9.2 Verify each HMS train flow rate on slow speed is 

≥ [4000] cfm.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.9.3 Verify each HMS train starts on an actual or 

simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
HIS (Ice Condenser) 

3.6.10

Westinghouse STS 3.6.10-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.10 Hydrogen Ignition System (HIS) (Ice Condenser) 

LCO 3.6.10 Two HIS trains shall be OPERABLE. 

APPLICABILITY: MODES 1 and 2.

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One HIS train 

inoperable.

A.1 Restore HIS train to 

OPERABLE status.

OR

A.2 Perform SR 3.6.10.1 on the 

OPERABLE train.

7 days

Once per 7 days

B. One containment region 

with no OPERABLE 

hydrogen ignitor.

B.1 Restore one hydrogen 

ignitor in the affected 

containment region to 

OPERABLE status.

7 days

C. Required Action and 

associated Completion 

Time not met.

C.1 Be in MODE 3. 6 hours
HIS (Ice Condenser) 

3.6.10

Westinghouse STS 3.6.10-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.10.1 Energize each HIS train power supply breaker and 

verify ≥ [32] ignitors are energized in each train.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.10.2 Verify at least one hydrogen ignitor is OPERABLE in 

each containment region.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.10.3 Energize each hydrogen ignitor and verify 

temperature is ≥ [1700]°F.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
ICS (Atmospheric and Subatmospheric) 

3.6.11

Westinghouse STS 3.6.11-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.11 Iodine Cleanup System (ICS) (Atmospheric and Subatmospheric) 

LCO 3.6.11 Two ICS trains shall be OPERABLE. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One ICS train 

inoperable.

A.1 Restore ICS train 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

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.11.1 Operate each ICS train for [≥ 10 continuous hours 

with heaters operating or (for systems without 

heaters) ≥ 15 minutes].

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.11.2 Perform required ICS filter testing in accordance 

with the Ventilation Filter Testing Program (VFTP).

In accordance 

with the VFTP
ICS (Atmospheric and Subatmospheric) 

3.6.11

Westinghouse STS 3.6.11-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SR 3.6.11.3 Verify each ICS train actuates on an actual or 

simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.11.4 [ Verify each ICS filter bypass damper can be 

opened.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
Vacuum Relief Valves (Atmospheric and Ice Condenser) 

3.6.12

Westinghouse STS 3.6.12-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.12 Vacuum Relief Valves (Atmospheric and Ice Condenser) 

LCO 3.6.12 [Two] vacuum relief lines shall be OPERABLE. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One vacuum relief line 

inoperable.

A.1 Restore vacuum relief line 

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

36 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.12.1 Verify each vacuum relief line is OPERABLE in 

accordance with the Inservice Testing Program.

In accordance 

with the Inservice 

Testing Program

SBACS (Dual and Ice Condenser) 

3.6.13

Westinghouse STS 3.6.13-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.13 Shield Building Air Cleanup System (SBACS) (Dual and Ice Condenser) 

LCO 3.6.13 Two SBACS trains shall be OPERABLE. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One SBACS train 

inoperable.

A.1 Restore SBACS train 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

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.13.1 Operate each SBACS train for [≥ 10 continuous 

hours with heaters operating or (for systems without 

heaters) ≥ 15 minutes].

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.13.2 Perform required SBACS filter testing in accordance 

with the Ventilation Filter Testing Program (VFTP).

In accordance 

with the VFTP
SBACS (Dual and Ice Condenser) 

3.6.13

Westinghouse STS 3.6.13-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.13.3 Verify each SBACS train actuates on an actual or 

simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.13.4 [ Verify each SBACS filter bypass damper can be 

opened.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.6.13.5 Verify each SBACS train flow rate is ≥ [ ] cfm. [ [18] months on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
ARS (Ice Condenser) 

3.6.14

Westinghouse STS 3.6.14-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.14 Air Return System (ARS) (Ice Condenser) 

LCO 3.6.14 Two ARS trains shall be OPERABLE. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One ARS train 

inoperable.

A.1 Restore ARS train 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

36 hours

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.14.1 Verify each ARS fan starts on an actual or simulated 

actuation signal, after a delay of ≥ [9.0] minutes and 

≤ [11.0] minutes, and operates for ≥ 15 minutes.

[ [92] days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
ARS (Ice Condenser) 

3.6.14

Westinghouse STS 3.6.14-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.14.2 Verify, with the ARS fan dampers closed, each ARS 

fan motor current is ≥ [20.5] amps and ≤ [35.5] amps 

[when the fan speed is ≥ [840] rpm and ≤ [900] rpm].

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program

SR 3.6.14.3 Verify, with the ARS fan not operating, each ARS 

fan damper opens when ≤ [11.0] lb is applied to the 

counterweight.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.14.4 [ Verify each motor operated valve in the hydrogen 

collection header that is not locked, sealed, or 

otherwise secured in position, opens on an actual or 

simulated actuation signal after a delay of 

≥ [9.0] minutes and ≤ [11.0] minutes.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
Ice Bed (Ice Condenser) 

3.6.15

Westinghouse STS 3.6.15-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.15 Ice Bed (Ice Condenser) 

LCO 3.6.15 The ice bed shall be OPERABLE. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Ice bed inoperable. A.1 Restore ice bed to 

OPERABLE status.

48 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

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.15.1 Verify maximum ice bed temperature is ≤ [27]°F. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Ice Bed (Ice Condenser) 

3.6.15

Westinghouse STS 3.6.15-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.15.2 Verify total mass of stored ice is  [2,200,000] lbs by 

calculating the mass of stored ice, at a 95% 

confidence level, in each of three Radial Zones as 

defined below, by selecting a random sample of 

 30 ice baskets in each Radial Zone, and 

Verify:

1. Zone A (radial rows [7,8,9]), has a total mass of 

 [733,400] lbs.

2. Zone B (radial rows [4,5,6]), has a total mass of 

 [733,400] lbs.

3. Zone C (radial rows [1,2,3]), has a total mass of 

 [733,400] lbs.

[ 18 months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.15.3 Verify that the ice mass of each basket sampled in 

SR 3.6.15.2 is  600 lbs.

[ 18 months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.15.4 Verify, by visual inspection, accumulation of ice on 

structural members comprising flow channels 

through the ice bed is ≤ 15 percent blockage of the 

total flow area for each safety analysis section.

[ 18 months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Ice Bed (Ice Condenser) 

3.6.15

Westinghouse STS 3.6.15-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.15.5 -------------------------------NOTE------------------------------

The requirements of this SR are satisfied if the 

boron concentration and pH values obtained from 

averaging the individual sample results are within 

the limits specified below.

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

Verify, by chemical analysis of the stored ice in at 

least one randomly selected ice basket from each 

ice condenser bay, that ice bed:

a. Boron concentration is a ≥ [1800] ppm and 

≤ [2000] ppm and

b. pH is ≥ [9.0] and ≤ [9.5].

[ [54] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.15.6 Visually inspect, for detrimental structural wear, 

cracks, corrosion, or other damage, two ice baskets 

from each group of bays as defined below:

a. Group 1 - bays 1 through 8;

b. Group 2 - bays 9 through 16; and

c. Group 3 - bays 17 through 24.

[ 40 months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.15.7 -------------------------------NOTE------------------------------

The chemical analysis may be performed on either 

the liquid solution or on the resulting ice.

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

Verify, by chemical analysis, that ice added to the 

ice condenser meets the boron concentration and 

pH requirements of SR 3.6.15.5.

Each ice addition

Ice Condenser Doors (Ice Condenser) 

3.6.16

Westinghouse STS 3.6.16-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.16 Ice Condenser Doors (Ice Condenser) 

LCO 3.6.16 The ice condenser inlet doors, intermediate deck doors, and top deck 

[doors] shall be OPERABLE and closed. 

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

ACTIONS 

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

Separate Condition entry is allowed for each ice condenser door. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more ice 

condenser inlet doors 

inoperable due to being 

physically restrained 

from opening.

A.1 Restore inlet door to 

OPERABLE status.

1 hour

B. One or more ice 

condenser doors 

inoperable for reasons 

other than Condition A 

or not closed.

B.1 Verify maximum ice bed 

temperature is ≤ [27]°F.

AND

B.2 Restore ice condenser door 

to OPERABLE status and 

closed positions.

Once per 4 hours

14 days

C. Required Action and 

associated Completion 

Time of Condition B not 

met.

C.1 Restore ice condenser door 

to OPERABLE status and 

closed positions.

48 hours

D. Required Action and 

associated Completion 

Time of Condition A or C 

not met.

D.1 Be in MODE 3.

AND

D.2 Be in MODE 5.

6 hours

36 hours
Ice Condenser Doors (Ice Condenser) 

3.6.16

Westinghouse STS 3.6.16-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.16.1 Verify all inlet doors indicate closed by the Inlet Door 

Position Monitoring System.

[ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.16.2 Verify, by visual inspection, each intermediate deck 

door is closed and not impaired by ice, frost, or 

debris.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.16.3 Verify, by visual inspection, each inlet door is not 

impaired by ice, frost, or debris.

[3 months during 

first year after 

receipt of license]

AND

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Ice Condenser Doors (Ice Condenser) 

3.6.16

Westinghouse STS 3.6.16-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.16.4 Verify torque required to cause each inlet door to 

begin to open is ≤ [675] in-lb.

[3 months during 

first year after 

receipt of license]

AND

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.16.5 Perform a torque test on [a sampling of ≥ 25% of 

the] inlet doors.

[3 months during 

first year after 

receipt of license]

AND

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Ice Condenser Doors (Ice Condenser) 

3.6.16

Westinghouse STS 3.6.16-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.16.6 Verify for each intermediate deck door:

a. No visual evidence of structural deterioration,

b. Free movement of the vent assemblies, and

c. Free movement of the door.

[3 months during 

first year after 

receipt of license]

AND

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.16.7 Verify, by visual inspection, each top deck [door]:

a. Is in place; and

b. Has no condensation, frost, or ice formed on 

the [door] that would restrict its opening.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Divider Barrier Integrity (Ice Condenser) 

3.6.17

Westinghouse STS 3.6.17-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.17 Divider Barrier Integrity (Ice Condenser) 

LCO 3.6.17 Divider barrier integrity shall be maintained. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

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

For this action, separate 

Condition entry is 

allowed for each 

personnel access door 

or equipment hatch.

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

One or more personnel 

access doors or 

equipment hatches open 

or inoperable, other than 

for personnel transit 

entry.

A.1 Restore personnel access 

doors and equipment 

hatches to OPERABLE 

status and closed positions.

1 hour

B. Divider barrier seal 

inoperable.

B.1 Restore seal to OPERABLE 

status.

1 hour

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
Divider Barrier Integrity (Ice Condenser) 

3.6.17

Westinghouse STS 3.6.17-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.17.1 Verify, by visual inspection, all personnel access 

doors and equipment hatches between upper and 

lower containment compartments are closed.

Prior to entering 

MODE 4 from 

MODE 5

SR 3.6.17.2 Verify, by visual inspection, that the seals and 

sealing surfaces of each personnel access door and 

equipment hatch have:

a. No detrimental misalignments,

b. No cracks or defects in the sealing surfaces, 

and

c. No apparent deterioration of the seal material.

Prior to final 

closure after each 

opening

AND

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

Only required for 

seals made of 

resilient materials

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

[ 10 years

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.6.17.3 Verify, by visual inspection, each personnel access 

door or equipment hatch that has been opened for 

personnel transit entry is closed.

After each 

opening

SR 3.6.17.4 Remove two divider barrier seal test coupons and 

verify:

a. Both test coupons' tensile strength is ≥ [120] psi 

and

[ b. Both test coupons' elongation is ≥ [100]%. ]

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Divider Barrier Integrity (Ice Condenser) 

3.6.17

Westinghouse STS 3.6.17-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.6.17.5 Visually inspect ≥ [95]% of the divider barrier seal 

length, and verify:

a. Seal and seal mounting bolts are properly 

installed and

b. Seal material shows no evidence of 

deterioration due to holes, ruptures, chemical 

attack, abrasion, radiation damage, or changes 

in physical appearance.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Containment Recirculation Drains (Ice Condenser) 

3.6.18

Westinghouse STS 3.6.18-1 Rev. 4.0 

3.6 CONTAINMENT SYSTEMS 

3.6.18 Containment Recirculation Drains (Ice Condenser) 

LCO 3.6.18 The ice condenser floor drains and the refueling canal drains shall be 

OPERABLE. 

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One ice condenser floor 

drain inoperable.

A.1 Restore ice condenser floor 

drain to OPERABLE status.

1 hour

B. One refueling canal 

drain inoperable.

B.1 Restore refueling canal 

drain to OPERABLE status.

1 hour

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
Containment Recirculation Drains (Ice Condenser) 

3.6.18

Westinghouse STS 3.6.18-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.6.18.1 Verify, by visual inspection, that:

a. Each refueling canal drain plug is removed,

b. Each refueling canal drain is not obstructed by 

debris, and

c. No debris is present in the upper compartment 

or refueling canal that could obstruct the 

refueling canal drain.

[ 92 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

AND

Prior to entering 

MODE 4 from 

MODE 5 after 

each partial or 

complete fill of the 

canal

SR 3.6.18.2 Verify for each ice condenser floor drain that the:

a. Valve opening is not impaired by ice, frost, or 

debris,

b. Valve seat shows no evidence of damage,

c. Valve opening force is ≤ [66] lb, and

d. Drain line from the ice condenser floor to the 

lower compartment is unrestricted.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
MSSVs 

3.7.1

Westinghouse STS 3.7.1-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.1 Main Steam Safety Valves (MSSVs) 

LCO 3.7.1 [Five] MSSVs per steam generator shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS 

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

Separate Condition entry is allowed for each MSSV. 

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

--------------------------------------------------REVIEWER'S NOTE------------------------------------------------- 

The * noted text is required for units that are licensed to operate at partial power with a positive 

Moderator Temperature Coefficient (MTC). 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more steam 

generators with one 

MSSV inoperable [and 

the Moderator 

Temperature Coefficient 

(MTC) zero or negative 

at all power levels]*.

A.1 Reduce THERMAL 

POWER to ≤ [72] % RTP.

4 hours

B. One or more steam 

generators with two or 

more MSSVs 

inoperable.

[ OR

One or more steam 

generators with one 

MSSV inoperable and 

the MTC positive at any 

power level. ]*

B.1 Reduce THERMAL 

POWER to less than or 

equal to the Maximum 

Allowable % RTP specified 

in Table 3.7.1-1 for the 

number of OPERABLE 

MSSVs.

AND

4 hours
MSSVs 

3.7.1

Westinghouse STS 3.7.1-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

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

Only required in MODE 1.

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

Reduce the Power Range 

Neutron Flux - High reactor 

trip setpoint to less than or 

equal to the Maximum 

Allowable % RTP specified 

in Table 3.7.1-1 for the 

number of OPERABLE 

MSSVs.

36 hours

C. Required Action and 

associated Completion 

Time not met.

OR

One or more steam 

generators with ≥ [4] 

MSSVs inoperable.

C.1 Be in MODE 3.

AND

C.2 Be in MODE 4.

6 hours

12 hours

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 3.7.1-2 in accordance with the Inservice 

Testing Program. Following testing, lift setting shall 

be within +1%.

In accordance 

with the Inservice 

Testing Program
MSSVs 

3.7.1

Westinghouse STS 3.7.1-3 Rev. 4.0 

Table 3.7.1-1 (page 1 of 1)

OPERABLE Main Steam Safety Valves versus 

Maximum Allowable Power 

NUMBER OF OPERABLE

MSSVs PER STEAM

GENERATOR

MAXIMUM ALLOWABLE

POWER (% RTP)

[4] [65]

3 [46]

2 [28]
MSSVs 

3.7.1

Westinghouse STS 3.7.1-4 Rev. 4.0 

Table 3.7.1-2 (page 1 of 1)

Main Steam Safety Valve Lift Settings 

VALVE NUMBER

LIFT SETTING

(psig ± [3]%)

STEAM GENERATOR

#1 #2 [#3] [#4]

[ ] [ ] [ ] [ ] [ ]

[ ] [ ] [ ] [ ] [ ]

[ ] [ ] [ ] [ ] [ ]

[ ] [ ] [ ] [ ] [ ]
MSIVs 

3.7.2

Westinghouse STS 3.7.2-1 Rev. 4.04.0 

3.7 PLANT SYSTEMS 

3.7.2 Main Steam Isolation Valves (MSIVs) 

LCO 3.7.2 [Four] MSIVs shall be OPERABLE.

APPLICABILITY: MODE 1,

MODES 2 and 3 except when all MSIVs are closed [and de-activated]. 

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

Westinghouse STS 3.7.2-2 Rev. 4.04.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.2.1 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

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

Verify the 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 ]
MFIVs and MFRVs and [Associated Bypass Valves] 

3.7.3

Westinghouse STS 3.7.3-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulation Valves 

(MFRVs) and [Associated Bypass Valves] 

LCO 3.7.3 [Four] MFIVs, [four] MFRVs, [and associated bypass valves] shall be 

OPERABLE. 

APPLICABILITY: MODES 1, [and 2] [2, and 3] except when MFIV, MFRV, [or associated 

bypass valve] is closed and [de-activated] [or isolated by a closed 

manual valve]. 

ACTIONS 

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

Separate Condition entry is allowed for each valve. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more MFIVs 

inoperable.

A.1 Close or isolate MFIV.

AND

A.2 Verify MFIV is closed or 

isolated.

[72] hours

Once per 7 days

B. One or more MFRVs 

inoperable.

B.1 Close or isolate MFRV.

AND

B.2 Verify MFRV is closed or 

isolated.

[72] hours

Once per 7 days

C. [ One or more [MFRV or 

preheater] bypass 

valves inoperable.

C.1 Close or isolate bypass 

valve.

AND

C.2 Verify bypass valve is 

closed or isolated.

[72] hours

Once per 7 days ]
MFIVs and MFRVs and [Associated Bypass Valves] 

3.7.3

Westinghouse STS 3.7.3-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

D. Two valves in the same 

flow path inoperable.

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 Verify the isolation time of each MFIV, MFRV[, and 

associated bypass valve] is within limits.

In accordance 

with the Inservice 

Testing Program

SR 3.7.3.2 Verify each MFIV, MFRV[, and associated bypass 

valves] actuates to the isolation position on an 

actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
ADVs

3.7.4

Westinghouse STS 3.7.4-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.4 Atmospheric Dump Valves (ADVs) 

LCO 3.7.4 [Three] ADV lines 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 ADV line 

inoperable.

A.1 Restore required ADV line 

to OPERABLE status.

7 days

B. Two or more required 

ADV lines inoperable.

B.1 Restore all but one ADV 

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
ADVs

3.7.4

Westinghouse STS 3.7.4-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.4.1 Verify one complete cycle of each ADV. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.7.4.2 [ Verify one complete cycle of each ADV block 

valve.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
AFW System 

3.7.5

Westinghouse STS 3.7.5-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.5 Auxiliary Feedwater (AFW) System 

LCO 3.7.5 [Three] AFW trains shall be OPERABLE. 

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

 [ Only one AFW 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 AFW 

train inoperable due to 

one inoperable steam 

supply.

OR

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

Only applicable if 

MODE 2 has not been 

entered following 

refueling.

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

One turbine driven AFW 

pump inoperable in 

MODE 3 following 

refueling.

A.1 Restore affected equipment 

to OPERABLE status.

7 days ]
AFW System 

3.7.5

Westinghouse STS 3.7.5-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B. One AFW train 

inoperable in MODE 1, 

2, or 3 [for reasons other 

than Condition A].

B.1 Restore AFW train to 

OPERABLE status.

72 hours

C. Turbine driven AFW 

train inoperable due to

one inoperable steam 

supply.

AND

One motor driven AFW 

train inoperable.

C.1 Restore the steam supply 

to the turbine driven train to 

OPERABLE status.

OR

C.2 Restore the motor driven 

AFW 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 AFW 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] AFW 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 AFW train is restored 

to OPERABLE status.

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

Initiate action to restore 

one AFW train to 

OPERABLE status.

Immediately ]
AFW System 

3.7.5

Westinghouse STS 3.7.5-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

F. Required AFW train 

inoperable in MODE 4.

F.1 Initiate action to restore 

AFW train to OPERABLE 

status.

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.5.1 -------------------------------NOTE------------------------------

[ AFW train(s) may be considered OPERABLE 

during alignment and operation for steam generator 

level control, if it is capable of being manually 

realigned to the AFW mode of operation. ]

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

Verify each AFW manual, power operated, and 

automatic valve in each water flow path, [and in both 

steam supply flow paths to the steam turbine driven 

pump,] 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 

AFW pump until [24 hours] after ≥ [1000] psig in the 

steam generator. ]

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

Verify the developed head of each AFW pump at the 

flow test point is greater than or equal to the 

required developed head.

In accordance 

with the Inservice 

Testing Program
AFW System 

3.7.5

Westinghouse STS 3.7.5-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.7.5.3 -------------------------------NOTE------------------------------

[ AFW train(s) may be considered OPERABLE 

during alignment and operation for steam generator 

level control, if it is capable of being manually 

realigned to the AFW mode of operation. ]

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

Verify each AFW 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 for the turbine 

driven AFW pump until [24 hours] after 

≥ [1000] psig in the steam generator. ]

2. [ AFW train(s) may be considered OPERABLE 

during alignment and operation for steam 

generator level control, if it is capable of being 

manually realigned to the AFW mode of 

operation. ]

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

Verify each AFW pump starts automatically on an 

actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
AFW System 

3.7.5

Westinghouse STS 3.7.5-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.7.5.5 [ Verify proper alignment of the required AFW flow 

paths by verifying flow from the condensate storage 

tank to each steam generator.

Prior to entering 

MODE 2 

whenever unit has 

been in MODE 5, 

MODE 6, or 

defueled for a 

cumulative period 

of > 30 days ]

CST

3.7.6

Westinghouse STS 3.7.6-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.6 Condensate Storage Tank (CST) 

LCO 3.7.6 The CST 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. CST inoperable. A.1 Verify by administrative 

means OPERABILITY of 

backup water supply.

AND

A.2 Restore CST 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

Westinghouse STS 3.7.6-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.6.1 Verify the CST level is ≥ [110,000 gal]. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
CCW System 

3.7.7

Westinghouse 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 --------------NOTE--------------

Enter applicable Conditions 

and Required Actions of 

LCO 3.4.6, "RCS Loops -

MODE 4," for residual heat 

removal loops made 

inoperable by CCW.

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

Restore CCW train to 

OPERABLE status.

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
CCW System 

3.7.7

Westinghouse STS 3.7.7-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.7.1 -------------------------------NOTE------------------------------

Isolation of CCW flow to individual components 

does not render the 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 ]

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

Westinghouse 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 residual 

heat removal loops 

made inoperable by 

SWS.

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

Restore SWS train to 

OPERABLE status.

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
SWS 

3.7.8

Westinghouse STS 3.7.8-2 Rev. 4.0 

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 ]

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

Westinghouse 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 ]

-----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.

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

B. [ Water temperature of 

the UHS > [90]°F and 

≤ [ ]°F.

B.1 Verify water temperature of 

the UHS is ≤ [90]°F 

averaged over the previous 

24 hour period.

Once per hour]

C. [ Required Action 

and associated 

Completion Time of 

Condition A or B not 

met.

OR ]

UHS inoperable [for 

reasons other than 

Condition A or B].

C.1 Be in MODE 3.

AND

C.2 Be in MODE 5.

6 hours

36 hours
UHS

3.7.9

Westinghouse STS 3.7.9-2 Rev. 4.0 

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 ] ]

SR 3.7.9.3 [ Operate each cooling tower fan for ≥ [15] minutes. [ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
UHS

3.7.9

Westinghouse STS 3.7.9-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.7.9.4 [ Verify each cooling tower fan starts automatically 

on an actual or simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

CREFS 

3.7.10

Westinghouse STS 3.7.10-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.10 Control Room Emergency Filtration System (CREFS) 

LCO 3.7.10 Two CREFS 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 CREFS train 

inoperable for reasons 

other than Condition B.

A.1 Restore CREFS train to 

OPERABLE status.

7 days

B. One or more CREFS 

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
CREFS 

3.7.10

Westinghouse 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 Be in MODE 5.

6 hours

36 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 toxic gas 

protection mode if 

automatic transfer to toxic 

gas protection mode is 

inoperable. ]

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

Place OPERABLE CREFS 

train in emergency mode.

OR

D.2 Suspend movement of 

[recently] irradiated fuel 

assemblies.

Immediately

Immediately
CREFS 

3.7.10

Westinghouse STS 3.7.10-3 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

E. Two CREFS trains 

inoperable [in MODE 5 

or 6, or] during 

movement of [recently] 

irradiated fuel 

assemblies.

OR

One or more CREFS 

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 CREFS 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 CREFS 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 ]
CREFS 

3.7.10

Westinghouse STS 3.7.10-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.7.10.2 Perform required CREFS filter testing in accordance 

with the [Ventilation Filter Testing Program (VFTP)].

In accordance 

with the [VFTP]

SR 3.7.10.3 Verify each CREFS train actuates 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
CREATCS 

3.7.11

Westinghouse 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, 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 Be in MODE 5.

6 hours

36 hours

C. Required Action and 

associated Completion 

Time of Condition A not 

met [in MODE 5 or 6, or] 

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

D. Two CREATCS trains 

inoperable [in MODE 5 

or 6, or] during 

movement of [recently] 

irradiated fuel 

assemblies.

D.1 Suspend movement of 

[recently] irradiated fuel 

assemblies.

Immediately
CREATCS 

3.7.11

Westinghouse STS 3.7.11-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

E. Two CREATCS trains 

inoperable in 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 ]
ECCS PREACS 

3.7.12

Westinghouse STS 3.7.12-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.12 Emergency Core Cooling System (ECCS) Pump Room Exhaust Air Cleanup System 

(PREACS) 

LCO 3.7.12 Two ECCS PREACS trains shall be OPERABLE. 

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

 The ECCS pump room boundary may be opened intermittently under 

administrative control. 

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

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One ECCS PREACS 

train inoperable.

A.1 Restore ECCS PREACS 

train to OPERABLE status.

7 days

B. Two ECCS PREACS 

trains inoperable due to 

inoperable ECCS pump 

room boundary.

B.1 Restore ECCS pump room 

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
ECCS PREACS 

3.7.12

Westinghouse STS 3.7.12-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.12.1 Operate each ECCS PREACS 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 ECCS PREACS filter testing in 

accordance with the [Ventilation Filter Testing 

Program (VFTP)].

In accordance 

with the [VFTP]

SR 3.7.12.3 Verify each ECCS PREACS 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 ECCS PREACS train can maintain a 

pressure ≤ [-0.125] 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 ]
ECCS PREACS 

3.7.12

Westinghouse STS 3.7.12-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.7.12.5 [ Verify each ECCS PREACS filter bypass damper 

can be closed.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

FBACS 

3.7.13

Westinghouse STS 3.7.13-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.13 Fuel Building Air Cleanup System (FBACS) 

LCO 3.7.13 Two FBACS 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 FBACS train 

inoperable.

A.1 Restore FBACS train to 

OPERABLE status.

7 days

B. Two FBACS 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
FBACS 

3.7.13

Westinghouse 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 FBACS 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 FBACS 

train in operation.

OR

D.2 Suspend movement of 

[recently] irradiated fuel 

assemblies in the fuel 

building.

Immediately

Immediately

E. Two FBACS 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
FBACS 

3.7.13

Westinghouse STS 3.7.13-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.13.1 Operate each FBACS 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 FBACS filter testing in accordance 

with the [Ventilation Filter Testing Program (VFTP)].

In accordance 

with the [VFTP]

SR 3.7.13.3 [ Verify each FBACS 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 FBACS train can maintain a pressure 

≤ [-0.125] inches water gauge with respect to 

atmospheric pressure during the [post accident] 

mode of operation at a flow rate ≤ [20,000] cfm.

[ [18] months on a 

STAGGERED 

TEST BASIS

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
FBACS 

3.7.13

Westinghouse STS 3.7.13-4 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.7.13.5 [ Verify each FBACS filter bypass damper can be 

closed.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
PREACS 

3.7.14

Westinghouse STS 3.7.14-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.14 Penetration Room Exhaust Air Cleanup System (PREACS) 

LCO 3.7.14 Two PREACS trains shall be OPERABLE. 

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

The penetration room boundary may be opened intermittently under 

administrative control. 

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

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

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. One PREACS train 

inoperable.

A.1 Restore PREACS train to 

OPERABLE status.

7 days

B. Two PREACS trains 

inoperable due to 

inoperable penetration 

room boundary.

B.1 Restore penetration room 

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
PREACS 

3.7.14

Westinghouse STS 3.7.14-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.14.1 Operate each PREACS train for [≥ 10 continuous 

hours with heaters operating or (for systems without 

heaters) ≥ 15 minutes].

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.7.14.2 Perform required PREACS filter testing in 

accordance with the [Ventilation Filter Testing 

Program (VFTP)].

In accordance 

with the [VFTP]

SR 3.7.14.3 [ Verify each PREACS train actuates on an actual or 

simulated actuation signal.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]

SR 3.7.14.4 [ Verify one PREACS train can maintain a pressure 

≤ [-0.125] 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 ] ]
PREACS 

3.7.14

Westinghouse STS 3.7.14-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.7.14.5 [ Verify each PREACS filter bypass damper can be 

closed.

[ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control 

Program ] ]
Fuel Storage Pool Water Level 

3.7.15

Westinghouse STS 3.7.15-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.15 Fuel Storage Pool Water Level 

LCO 3.7.15 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 the 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 

the fuel storage pool.

Immediately

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.15.1 Verify the fuel storage pool water level is ≥ 23 ft 

above the top of the irradiated fuel assemblies 

seated in the storage racks.

[ 7 days

OR

In accordance

with the

Surveillance 

Frequency

Control Program ]
[Fuel Storage Pool Boron Concentration] 

3.7.16

Westinghouse STS 3.7.16-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.16 [ Fuel Storage Pool Boron Concentration ] 

LCO 3.7.16 The fuel storage pool boron concentration shall be ≥ [2300] ppm. 

APPLICABILITY: When fuel assemblies are stored in the fuel storage pool and a fuel 

storage pool verification has not been performed since the last 

movement of fuel assemblies in the fuel storage pool. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME

A. Fuel storage pool boron 

concentration not within 

limit.

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

LCO 3.0.3 is not applicable.

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

A.1 Suspend movement of fuel 

assemblies in the fuel 

storage pool.

AND

A.2.1 Initiate action to restore fuel 

storage pool boron 

concentration to within limit.

 OR

A.2.2 Initiate action to perform a 

fuel storage pool 

verification.

Immediately

Immediately

Immediately
[Fuel Storage Pool Boron Concentration] 

3.7.16

Westinghouse STS 3.7.16-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.7.16.1 Verify the fuel storage pool boron concentration is 

within limit.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
[Spent Fuel Pool Storage] 

3.7.17

Westinghouse STS 3.7.17-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.17 [ Spent Fuel Pool Storage ] 

LCO 3.7.17 The combination of initial enrichment and burnup of each fuel assembly 

stored in [Region 2] shall be within the Acceptable [Burnup Domain] of 

Figure 3.7.17-1 or in accordance with Specification 4.3.1.1.

APPLICABILITY: Whenever any fuel assembly is stored in [Region 2] of the spent fuel 

storage 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 3.7.17.1 Verify by administrative means the initial enrichment 

and burnup of the fuel assembly is in accordance 

with Figure 3.7.17-1 or Specification 4.3.1.1.

Prior to storing the 

fuel assembly in 

[Region 2]
[Spent Fuel Pool Storage] 

3.7.17

Westinghouse STS 3.7.17-2 Rev. 4.0 
Secondary Specific Activity 

3.7.18

Westinghouse STS 3.7.18-1 Rev. 4.0 

3.7 PLANT SYSTEMS 

3.7.18 Secondary Specific Activity 

LCO 3.7.18 The specific activity of the secondary coolant shall be ≤ [0.10] μCi/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 3.7.18.1 Verify the specific activity of the secondary coolant 

is ≤ [0.10] μCi/gm DOSE EQUIVALENT I-131.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

AC Sources - Operating 

3.8.1

Westinghouse 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 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) capable of supplying the onsite 

Class 1E power distribution subsystem(s), 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 

[required] OPERABLE 

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

Westinghouse 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 the 

[required] offsite circuit(s).

AND

B.2 Declare required feature(s) 

supported by the inoperable 

DG inoperable when its 

required redundant 

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

Westinghouse 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 

features

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

Westinghouse 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 Be in MODE 5.

6 hours

36 hours

H. Three or more [required] 

AC sources inoperable.

H.1 Enter LCO 3.0.3. Immediately

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 ]
AC Sources - Operating 

3.8.1

Westinghouse STS 3.8.1-5 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

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

Westinghouse 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

Westinghouse 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

Westinghouse 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

Westinghouse 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

Westinghouse 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 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

Westinghouse 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,

c. DG auto-starts from standby condition and:

1. Energizes permanently connected loads 

in ≤ [10] seconds,

2. Energizes auto-connected shutdown 

loads through [automatic load sequencer],

3.

≥ [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

Westinghouse 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 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 ≤ [10] 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

Westinghouse 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

Westinghouse 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 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 operates for ≥ 24 hours:

a. For ≥ [2] hours loaded ≥ [5250] kW and 

≤ [5500] 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

Westinghouse 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

Westinghouse 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, 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, 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

Westinghouse 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, and

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

Westinghouse 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:

a. In ≤ [10] seconds, voltage  [3740] V and 

frequency  [58.8] Hz and

b. Steady state voltage  [3744] V and  [4576] 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

Westinghouse 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

Westinghouse 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

Westinghouse 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

Westinghouse 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

Westinghouse STS 3.8.3-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

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 ]
Diesel Fuel Oil, Lube Oil, and Starting Air 

3.8.3

Westinghouse STS 3.8.3-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.8.3.2 Verify lubricating oil inventory is ≥ a [7] day supply. [ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

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

Westinghouse 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

D. Required Action and 

Associated Completion 

Time not met.

D.1 Be in MODE 3.

AND

D.2 Be in MODE 5.

6 hours

36 hours
DC Sources - Operating 

3.8.4

Westinghouse STS 3.8.4-2 Rev. 4.0 

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

Westinghouse 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

Westinghouse 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-----------------------------------

 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 DC electrical power subsystem to be OPERABLE. 

Action A 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

Westinghouse 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 Actions 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

Westinghouse 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

Westinghouse 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 Train A and Train B batteries electrical power 

subsystem 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

Westinghouse 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 subsystems

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

Westinghouse 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

Westinghouse 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 ]

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

Westinghouse STS 3.8.6-5 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

Westinghouse 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 AC vital bus deenergized.

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

Restore inverter to 

OPERABLE status.

24 hours

B. Required Action and 

associated Completion 

Time not met.

B.1 Be in MODE 3.

AND

6 hours
Inverters - Operating 

3.8.7

Westinghouse STS 3.8.7-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B.2 Be in MODE 5. 36 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

Westinghouse 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] 

inverter[s] 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

Westinghouse 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

Westinghouse 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 3.8.4, "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

Westinghouse 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 Be in MODE 5.

6 hours

36 hours

E. Two or more electrical 

power distribution 

subsystems inoperable 

that result in a loss of 

safety 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

Westinghouse 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

Westinghouse 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 residual 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

Westinghouse 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
Boron Concentration 

3.9.1

Westinghouse STS 3.9.1-2 Rev. 4.0 

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 ]
[Unborated Water Source Isolation Valves] 

3.9.2

Westinghouse STS 3.9.2-1 Rev. 4.0 

3.9 REFUELING OPERATIONS 

3.9.2 [ Unborated Water Source Isolation Valves ] 

--------------------------------------------------REVIEWER'S NOTE------------------------------------------------- 

This Technical Specification is not required for units that have analyzed a boron dilution event in 

MODE 6. It is required for those units that have not analyzed a boron dilution event in MODE 6. 

For units which have not analyzed a boron dilution event in MODE 6, the isolation of all 

unborated water sources is required to preclude this event from occurring. 

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

LCO 3.9.2 Each valve used to isolate unborated water sources shall be secured in 

the closed position. 

APPLICABILITY: MODE 6.

ACTIONS 

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

Separate Condition entry is allowed for each unborated water source isolation valve. 

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

CONDITION REQUIRED ACTION COMPLETION TIME

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

Required Action A.2

must be completed 

whenever Condition A is 

entered.

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

One or more valves not 

secured in closed 

position.

A.1 Initiate actions to secure 

valve in closed position.

AND

A.2 Perform SR 3.9.1.1.

Immediately

4 hours
[Unborated Water Source Isolation Valves] 

3.9.2

Westinghouse STS 3.9.2-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.9.2.1 Verify each valve that isolates unborated water 

sources is secured in the closed position.

[ 31 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Nuclear Instrumentation 

3.9.3

Westinghouse STS 3.9.3-1 Rev. 4.0 

3.9 REFUELING OPERATIONS 

3.9.3 Nuclear Instrumentation 

LCO 3.9.3 Two source range neutron flux monitors shall be OPERABLE. 

AND

 [ One source range audible [alarm] [count rate] circuit 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 

3.9.3

Westinghouse STS 3.9.3-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

-----REVIEWER'S NOTE-----

Condition C is included only 

for plants that assume a 

boron dilution event is 

mitigated by operator 

response to an audible 

source range indication.

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

C. [ Required source range 

audible [alarm] [count 

rate] circuit inoperable.

C.1 Initiate action to isolate 

unborated water sources.

Immediately ]

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.9.3.1 Perform CHANNEL CHECK. [ 12 hours

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]
Nuclear Instrumentation 

3.9.3

Westinghouse STS 3.9.3-3 Rev. 4.0 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY

SR 3.9.3.2 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL 

CALIBRATION.

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

Perform CHANNEL CALIBRATION. [ [18] months

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Containment Penetrations 

3.9.4

Westinghouse STS 3.9.4-1 Rev. 4.0 

3.9 REFUELING OPERATIONS 

3.9.4 Containment Penetrations 

LCO 3.9.4 The containment penetrations shall be in the following status: 

a. The equipment is 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 is 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 

3.9.4

Westinghouse STS 3.9.4-2 Rev. 4.0 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY

SR 3.9.4.1 Verify each required containment penetration is in 

the required status.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

SR 3.9.4.2 -------------------------------NOTE------------------------------

Not required to be met for containment purge and 

exhaust valve(s) in penetrations closed to comply 

with LCO 3.9.4.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 ]
RHR and Coolant Circulation - High Water Level 

3.9.5

Westinghouse STS 3.9.5-1 Rev. 4.0 

3.9 REFUELING OPERATIONS 

3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level 

LCO 3.9.5 One RHR loop shall be OPERABLE and in operation. 

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

The required RHR 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. RHR 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 

RHR loop requirements.

AND

Immediately

Immediately

Immediately
RHR and Coolant Circulation - High Water Level 

3.9.5

Westinghouse STS 3.9.5-2 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 3.9.5.1 Verify one RHR 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 ]
RHR and Coolant Circulation - Low Water Level 

3.9.6

Westinghouse STS 3.9.6-1 Rev. 4.0 

3.9 REFUELING OPERATIONS 

3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level 

LCO 3.9.6 Two RHR loops shall be OPERABLE, and one RHR loop shall be in 

operation. 

--------------------------------------------NOTES-------------------------------------------

1. All RHR 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 (RCS) 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 RHR loop may be inoperable for up to 2 hours for 

surveillance testing, provided that the other RHR 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 the required 

number of RHR loops 

OPERABLE.

A.1 Initiate action to restore 

required RHR loops to 

OPERABLE status.

OR

A.2 Initiate action to establish 

≥ 23 ft of water above the 

top of reactor vessel flange.

Immediately

Immediately
RHR and Coolant Circulation - Low Water Level 

3.9.6

Westinghouse STS 3.9.6-2 Rev. 4.0 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME

B. No RHR loop 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 

RHR loop 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
RHR and Coolant Circulation - Low Water Level 

3.9.6

Westinghouse STS 3.9.6-3 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 3.9.6.1 Verify one RHR 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 ]

SR 3.9.6.2 Verify correct breaker alignment and indicated 

power available to the required RHR pump that is 

not in operation.

[ 7 days

OR

In accordance 

with the

Surveillance 

Frequency

Control Program ]

Refueling Cavity Water Level 

3.9.7

Westinghouse STS 3.9.7-1 Rev. 4.0 

3.9 REFUELING OPERATIONS 

3.9.7 Refueling Cavity Water Level 

LCO 3.9.7 Refueling cavity water level shall be maintained ≥ 23 ft above the top of 

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 3.9.7.1 Verify refueling cavity 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

Westinghouse 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 [157] 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 Rod] Assemblies 

 The reactor core shall contain [48] [control rod] assemblies. The control 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 [9.15] inch center to center distance between fuel 

assemblies placed in [the high density fuel storage racks], ] 

 [ d. A nominal [10.95] inch center to center distance between fuel 

assemblies placed in [low density fuel storage racks], ] 
Design Features 

4.0

Westinghouse 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 [10.95] 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 [23 ft].

4.3.3 Capacity 

 The spent fuel storage pool is designed and shall be maintained with a storage 

capacity limited to no more than [1737] fuel assemblies. 
Responsibility 

5.1

Westinghouse STS 5.1-1 Rev. 4.0 

5.0 ADMINISTRATIVE CONTROLS 

5.1 Responsibility 

 ---------------------------------------REVIEWER'S NOTES---------------------------------------

 1. 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.

 2. 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

Westinghouse STS 5.2-1 Rev. 4.0 

5.0 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

Westinghouse 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

Westinghouse 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 Specification 5.3.1, perform the functions described 

in 10 CFR 50.54(m). 

Procedures 

5.4

Westinghouse 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

Westinghouse 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

Westinghouse 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 

[Recirculation Spray, Safety Injection, Chemical and Volume Control, gas 

stripper, 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 WCAP-14986, 

Rev. 1, "Post Accident Sampling System Requirements: A Technical Basis," and 

the associated NRC Safety Evaluation dated June 14, 2000, and implementation 

of the following commitments:

1. [Licensee] has developed contingency plans for obtaining and analyzing 

highly radioactive samples of reactor coolant, containment sump, and 

containment atmosphere. The contingency plans will be contained in 

emergency plan implementing procedures and implemented with the 

implementation of the License amendment. Establishment of contingency 

plans is considered a regulatory commitment. 

2. The capability for classifying fuel damage events at the Alert level threshold 

has been established for [Plant] at radioactivity levels of 300 mCi/cc dose 

equivalent iodine. This capability may utilize the normal sampling system 

and/or correlations of sampling or letdown line dose rates to coolant 

concentrations. This capability will be described in emergency plan 

implementing procedures and implemented with the implementation of the 

License amendment. The capability for classifying fuel damage events is 

considered a regulatory commitment. 

3. [Licensee] has established the capability to monitor radioactive iodines that 

have been released to offsite environs. This capability is described in our 

emergency plan implementing procedures. 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 
Programs and Manuals 

5.5

Westinghouse STS 5.5-3 Rev. 4.0 

5.5 Programs and Manuals 

5.5.3 Post Accident Sampling (continued) 

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, 

 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,
Programs and Manuals 

5.5

Westinghouse STS 5.5-4 Rev. 4.0 

5.5 Programs and Manuals 

5.5.4 Radioactive Effluent Controls Program (continued) 

 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 

accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure 

Vessel Code and applicable addenda as required by 10 CFR 50.55a, 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. ] 
Programs and Manuals 

5.5

Westinghouse STS 5.5-5 Rev. 4.0 

5.5 Programs and Manuals 

5.5.7 Reactor Coolant Pump Flywheel Inspection Program 

 This program shall provide for the inspection of each reactor coolant pump 

flywheel per the recommendations of Regulatory Position C.4.b of Regulatory 

Guide 1.14, Revision 1, August 1975.

 In lieu of Position C.4.b(1) and C.4.b(2), a qualified in-place UT examination over 

the volume from the inner bore of the flywheel to the circle one-half of the outer 

radius or a surface examination (MT and/or PT) of exposed surfaces of the 

removed flywheels may be conducted at 20 year intervals. 

 ---------------------------------------REVIEWER'S NOTE----------------------------------------

 The inspection interval and scope for RCP flywheels stated above can be applied 

to plants that satisfy the requirements in WCAP-15666, "Extension of Reactor 

Coolant Pump Motor Flywheel Examination." 

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

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 Code) 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
Programs and Manuals 

5.5

Westinghouse STS 5.5-6 Rev. 4.0 

5.5 Programs and Manuals 

5.5.8 Inservice Testing Program (continued) 

 d. Nothing in the ASME OM Code shall be construed to supersede the 

requirements of any TS. 

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 
Programs and Manuals 

5.5

Westinghouse STS 5.5-7 Rev. 4.0 

5.5 Programs and Manuals 

5.5.9 Steam Generator (SG) Program (continued)

 exceed [1 gpm] per SG [, except for specific types of degradation at 

specific locations as described in paragraph c of the Steam Generator 

Program. 

 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. 
Programs and Manuals 

5.5

Westinghouse STS 5.5-8 Rev. 4.0 

5.5 Programs and Manuals 

5.5.9 Steam Generator (SG) Program (continued)

---------------------------------------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. 

 [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. 
Programs and Manuals 

5.5

Westinghouse STS 5.5-9 Rev. 4.0 

5.5 Programs and Manuals 

5.5.9 Steam Generator (SG) Program (continued)

 [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. 

---------------------------------------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. 
Programs and Manuals 

5.5

Westinghouse STS 5.5-10 Rev. 4.0 

5.5 Programs and Manuals 

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%].

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 (fps) 

[ ] [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. 
Programs and Manuals 

5.5

Westinghouse STS 5.5-11 Rev. 4.0 

5.5 Programs and Manuals 

5.5.11 Ventilation Filter Testing Program (continued) 

 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 Efficiency * 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. 

 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.
Programs and Manuals 

5.5

Westinghouse STS 5.5-12 Rev. 4.0 

5.5 Programs and Manuals 

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"]. 

 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. 
Programs and Manuals 

5.5

Westinghouse STS 5.5-13 Rev. 4.0 

5.5 Programs and Manuals 

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. 

 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 test 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.
Programs and Manuals 

5.5

Westinghouse STS 5.5-14 Rev. 4.0 

5.5 Programs and Manuals 

5.5.14 Technical Specifications (TS) Bases Control Program (continued) 

 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 Specification 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 actions may 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: 

 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 
Programs and Manuals 

5.5

Westinghouse STS 5.5-15 Rev. 4.0 

5.5 Programs and Manuals 

5.5.15 Safety Function Determination Program (SFDP) (continued) 

 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. 

 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.
Programs and Manuals 

5.5

Westinghouse STS 5.5-16 Rev. 4.0 

5.5 Programs and Manuals 

5.5.16 Containment Leakage Rate Testing Program (continued) 

 [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. . . . ]

 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]. 
Programs and Manuals 

5.5

Westinghouse STS 5.5-17 Rev. 4.0 

5.5 Programs and Manuals 

5.5.16 Containment Leakage Rate Testing Program (continued) 

 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.

 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, [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: 
Programs and Manuals 

5.5

Westinghouse STS 5.5-18 Rev. 4.0 

5.5 Programs and Manuals 

5.5.16 Containment Leakage Rate Testing Program (continued) 

 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.

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. 
Programs and Manuals 

5.5

Westinghouse STS 5.5-19 Rev. 4.0 

5.5 Programs and Manuals 

5.5.17 Battery Monitoring and Maintenance Program (continued) 

 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; 

 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 Filtration System (CREFS), 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 
Programs and Manuals 

5.5

Westinghouse STS 5.5-20 Rev. 4.0 

5.5 Programs and Manuals 

5.5.18 Control Room Envelope (CRE) Habitability Program (continued) 

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]

 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 CREFS, 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. 
Programs and Manuals 

5.5

Westinghouse STS 5.5-21 Rev. 4.0 

5.5 Programs and Manuals 

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 Trip System (RTS) Instrumentation;" 

 2. LCO 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) 

 Instrumentation Functions;" 

 3. LCO 3.3.5, "Loss of Power (LOP) Diesel Generator (DG) Start 

 Instrumentation;" 

 4. LCO 3.3.6, "Containment Purge and Exhaust Isolation 

 Instrumentation;" 

 5. LCO 3.3.7, "Control Room Emergency Filtration System (CREFS) 

 Actuation Instrumentation;" 

 6. LCO 3.3.8, "Fuel Building Air Cleanup System (FBACS) Actuation 

 Instrumentation;" and

 7. LCO 3.3.9, "Boron Dilution Protection System (BDPS)." 

 b. The program shall require the 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 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. 
Programs and Manuals 

5.5

Westinghouse STS 5.5-22 Rev. 4.0 

5.5 Programs and Manuals 

5.5.19 Setpoint Control Program (continued) 

 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 Trip 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. 

 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 NTSP 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, CHANNEL OPERATIONAL 

TESTS, and TRIP ACTUATING DEVICE OPERATIONAL TESTS that verify 

the NTSP. 

 1 The as-found value of the instrument channel trip setting shall be 

compared with the previous as-left value or the specified NTSP. 

 2. If the as-found value of the instrument channel trip setting differs from 

the previous as-left value or the specified NTSP by more than the predefined 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. 
Programs and Manuals 

5.5

Westinghouse STS 5.5-23 Rev. 4.0 

5.5 Programs and Manuals 

5.5.19 Setpoint Control Program (continued) 

 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 NTSP at the completion of the 

surveillance test; otherwise, the channel is inoperable (setpoints may 

be more conservative than the 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]. ] 

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

Westinghouse 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 

 ----------------------------------------REVIEWER'S 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 Radioactive Effluent Release Report 

 ----------------------------------------REVIEWER'S 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

Westinghouse STS 5.6-2 Rev. 4.0 

5.6 Reporting Requirements 

5.6.3 CORE OPERATING LIMITS REPORT 

 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 Systems (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, LTOP arming, and 

PORV lift settings 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

Westinghouse 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. LTOP arming temperature limit development methodology. 
Reporting Requirements 

5.6

Westinghouse STS 5.6-4 Rev. 4.0 

5.6 Reporting Requirements 

5.6.4 RCS PRESSURE AND TEMPERATURE LIMITS REPORT (continued)

 7. The minimum temperature requirements of Appendix G to 10 CFR Part 50 

shall be incorporated into the pressure and temperature limit curves. 

 8. 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 (2σ∆) specified in Regulatory Guide 1.99, Revision 2. If the measured 

value exceeds the predicted value (increase RTNDT + 2σ∆), 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.[3], "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, 
Reporting Requirements 

5.6

Westinghouse STS 5.6-5 Rev. 4.0 

5.6 Reporting Requirements 

5.6.7 Steam Generator Tube Inspection Report (continued) 

 d. Location, orientation (if linear), and measured sizes (if available) of service 

induced indications, 

 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 insitu 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

Westinghouse 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, 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, or 
High Radiation Area 

 5.7

Westinghouse 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 of 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 designees, and 

 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

Westinghouse 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 of 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 group entering such an area shall possess: 

 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 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, or 

 (ii) Be under surveillance as specified in the RWP or equivalent, while 

in the area, by means of closed circuit television, or 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 

displaces 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

Westinghouse 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 of 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.