NUREG-1431 Volume 1, Rev. 5, Standard Technical Specifications Westinghouse Plants: Specifications

NUREG-1431, Vol. 1, Rev. 5, Standard Technical Specifications Westinghouse Plants: Specifications

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Issue date:	09/30/2021
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NUREG-1431 V1 R5
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NUREG-1431 Volume 1 Revision 5.0 Standard Technical Specifications Westinghouse Plants Revision 5.0 Volume 1, Specifications Office of Nuclear Reactor Regulation

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NUREG-1431 Volume 1 Revision 5.0 Standard Technical Specifications Westinghouse Plants Revision 5.0 Volume 1, Specifications Manuscript Completed: March 2021 Date Published: September 2021 Office of Nuclear Reactor Regulation

ABSTRACT This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. The changes reflected in Revision 5 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 5 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 https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/. Users may print or download copies from the NRC Web site.

PAPERWORK REDUCTION ACT STATEMENT This NUREG contains voluntary guidance for implementing the mandatory information collections covered by 10 CFR Part 50 that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et. seq.). These information collections were approved by the Office of Management and Budget (OMB), under control number 3150-0011. Send comments regarding this information collection to the FOIA, Library, and Information Collections Branch (T6-A10M),

U.S. Nuclear Regulatory Commission, Washington, DC 20555 0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of Management and Budget, Washington, DC 20503.

PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid OMB control number.

Westinghouse STS iii Rev. 5.0

TABLE OF CONTENTS Page ABSTRACT ...............................................................................................................iii 1.0 USE AND APPLICATION ........................................................................................ 1.1-1 1.1 Definitions........................................................................................................... 1.1-1 1.2 Logical Connectors............................................................................................. 1.2-1 1.3 Completion Times .............................................................................................. 1.3-1 1.4 Frequency .......................................................................................................... 1.4-1 2.0 SAFETY LIMITS (SLs) ............................................................................................. 2.0-1 2.1 SLs ................................................................................................................ 2.0-1 2.2 SL Violations ...................................................................................................... 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ........................ 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ....................................... 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS .................................................................... 3.1.1-1 3.1.1 SHUTDOWN MARGIN (SDM) ........................................................................ 3.1.1-1 3.1.2 Core Reactivity ................................................................................................ 3.1.2-1 3.1.3 Moderator Temperature Coefficient (MTC) ..................................................... 3.1.3-1 3.1.4 Rod Group Alignment Limits ........................................................................... 3.1.4-1 3.1.5 Shutdown Bank Insertion Limits ...................................................................... 3.1.5-1 3.1.6 Control Bank Insertion Limits .......................................................................... 3.1.6-1 3.1.7 Rod Position Indication.................................................................................... 3.1.7-1 3.1.8 PHYSICS TESTS Exceptions - MODE 2 ........................................................ 3.1.8-1 3.2 POWER DISTRIBUTION LIMITS ....................................................................... 3.2.1A-1 3.2.1A Heat Flux Hot Channel Factor (FQ(Z)) (CAOC-FXY Methodology) ................ 3.2.1A-1 3.2.1B Heat Flux Hot Channel Factor (FQ(Z)) (RAOC-W(Z) Methodology) ............. 3.2.1B-1 3.2.1C Heat Flux Hot Channel Factor (FQ(Z)) (CAOC-W(Z) Methodology) ............. 3.2.1C-1 N

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( FH ) ...........................................3.2.2-1 3.2.3A AXIAL FLUX DIFFERENCE (AFD) (Constant Axial Offset Control (CAOC) Methodology) ............................................................................ 3.2.3A-1 3.2.3B AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) ............................................................................ 3.2.3B-1 3.2.4 QUADRANT POWER TILT RATIO (QPTR) .................................................... 3.2.4-1 3.3 INSTRUMENTATION ............................................................................................ 3.3.1-1 3.3.1 Reactor Trip System (RTS) Instrumentation ................................................... 3.3.1-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation ......................................................................................... .3.3.2-1 3.3.3 Post Accident Monitoring (PAM) Instrumentation ........................................... .3.3.3-1 3.3.4 Remote Shutdown System ............................................................................. .3.3.4-1 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation .......................................................................................... 3.3.5-1 3.3.6 Containment Purge and Exhaust Isolation Instrumentation ............................ 3.3.6-1 3.3.7 Control Room Emergency Filtration System (CREFS) Actuation Instrumentation .......................................................................................... 3.3.7-1 3.3.8 Fuel Building Air Cleanup System (FBACS) Actuation Instrumentation .......................................................................................... 3.3.8-1 3.3.9 Boron Dilution Protection System (BDPS) ...................................................... 3.3.9-1 Westinghouse STS v Rev. 5.0

TABLE OF CONTENTS Page 3.4 REACTOR COOLANT SYSTEM (RCS)................................................................ 3.4.1-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits .................................................................................. 3.4.1-1 3.4.2 RCS Minimum Temperature for Criticality ....................................................... 3.4.2-1 3.4.3 RCS Pressure and Temperature (P/T) Limits ................................................. 3.4.3-1 3.4.4 RCS Loops - MODES 1 and 2......................................................................... 3.4.4-1 3.4.5 RCS Loops - MODE 3 ..................................................................................... 3.4.5-1 3.4.6 RCS Loops - MODE 4 ..................................................................................... 3.4.6-1 3.4.7 RCS Loops - MODE 5, Loops Filled................................................................ 3.4.7-1 3.4.8 RCS Loops - MODE 5, Loops Not Filled ......................................................... 3.4.8-1 3.4.9 Pressurizer ...................................................................................................... 3.4.9-1 3.4.10 Pressurizer Safety Valves ............................................................................. 3.4.10-1 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) .................................... 3.4.11-1 3.4.12 Low Temperature Overpressure Protection (LTOP) System ........................ 3.4.12-1 3.4.13 RCS Operational LEAKAGE ......................................................................... 3.4.13-1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ............................................... 3.4.14-1 3.4.15 RCS Leakage Detection Instrumentation ...................................................... 3.4.15-1 3.4.16 RCS Specific Activity ..................................................................................... 3.4.16-1 3.4.17 RCS Loop Isolation Valves............................................................................ 3.4.17-1 3.4.18 RCS Isolated Loop Startup............................................................................ 3.4.18-1 3.4.19 RCS Loops - Test Exceptions ....................................................................... 3.4.19-1 3.4.20 Steam Generator (SG) Tube Integrity ........................................................... 3.4.20-1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) .......................................... 3.5.1-1 3.5.1 Accumulators................................................................................................... 3.5.1-1 3.5.2 ECCS - Operating ........................................................................................... 3.5.2-1 3.5.3 ECCS - Shutdown ........................................................................................... 3.5.3-1 3.5.4 Refueling Water Storage Tank (RWST) .......................................................... 3.5.4-1 3.5.5 Seal Injection Flow .......................................................................................... 3.5.5-1 3.5.6 Boron Injection Tank (BIT) .............................................................................. 3.5.6-1 3.6 CONTAINMENT SYSTEMS .................................................................................. 3.6.1-1 3.6.1 Containment (Atmospheric, Subatmospheric, Ice Condenser, and Dual) .......................................................................................................... 3.6.1-1 3.6.2 Containment Air Locks (Atmospheric, Subatmospheric, Ice Condenser, and Dual) ............................................................................... 3.6.2-1 3.6.3 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) ............................................................................... 3.6.3-1 3.6.4A Containment Pressure (Atmospheric, Dual, and Ice Condenser) ................ 3.6.4A-1 3.6.4B Containment Pressure (Subatmospheric) .................................................... 3.6.4B-1 3.6.5A Containment Air Temperature (Atmospheric and Dual) ............................... 3.6.5A-1 3.6.5B Containment Air Temperature (Ice Condenser) ........................................... 3.6.5B-1 3.6.5C Containment Air Temperature (Subatmospheric) ......................................... 3.6.5C-1 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 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 3.6.6C Containment Spray System (Ice Condenser) ............................................... 3.6.6C-1 Westinghouse STS vi Rev. 5.0

TABLE OF CONTENTS Page 3.6 CONTAINMENT SYSTEMS (continued) 3.6.6D Quench Spray (QS) System (Subatmospheric) ........................................... 3.6.6D-1 3.6.6E Recirculation Spray (RS) System (Subatmospheric) ................................... 3.6.6E-1 3.6.7 Spray Additive System (Atmospheric, Subatmospheric, Ice Condenser, and Dual) ............................................................................... 3.6.7-1 3.6.8 Shield Building (Dual and Ice Condenser) ...................................................... 3.6.8-1 3.6.9 Hydrogen Mixing System (HMS) (Atmospheric, Ice Condenser, and Dual) ................................................................................................... 3.6.9-1 3.6.10 Hydrogen Ignition System (HIS) (Ice Condenser) ......................................... 3.6.10-1 3.6.11 Iodine Cleanup System (ICS) (Atmospheric and Subatmospheric) ..................................................................................... 3.6.11-1 3.6.12 Vacuum Relief Valves (Atmospheric and Ice Condenser) ............................ 3.6.12-1 3.6.13 Shield Building Air Cleanup System (SBACS) (Dual and Ice Condenser) .............................................................................................. 3.6.13-1 3.6.14 Air Return System (ARS) (Ice Condenser) .................................................... 3.6.14-1 3.6.15 Ice Bed (Ice Condenser) ............................................................................... 3.6.15-1 3.6.16 Ice Condenser Doors (Ice Condenser).......................................................... 3.6.16-1 3.6.17 Divider Barrier Integrity (Ice Condenser) ....................................................... 3.6.17-1 3.6.18 Containment Recirculation Drains (Ice Condenser) ...................................... 3.6.18-1 3.6.19 Containment Sump........................................................................................ 3.6.19-1 3.7 PLANT SYSTEMS ................................................................................................ 3.7.1-1 3.7.1 Main Steam Safety Valves (MSSVs) ............................................................... 3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs) ............................................................. 3.7.2-1 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulation Valves (MFRVs) [ and Associated Bypass Valves ] ................ 3.7.3-1 3.7.4 Atmospheric Dump Valves (ADVs) ................................................................. 3.7.4-1 3.7.5 Auxiliary Feedwater (AFW) System ................................................................ 3.7.5-1 3.7.6 Condensate Storage Tank (CST) .................................................................... 3.7.6-1 3.7.7 Component Cooling Water (CCW) System ..................................................... 3.7.7-1 3.7.8 Service Water System (SWS) ......................................................................... 3.7.8-1 3.7.9 Ultimate Heat Sink (UHS)................................................................................ 3.7.9-1 3.7.10 Control Room Emergency Filtration System (CREFS) .................................. 3.7.10-1 3.7.11 Control Room Emergency Air Temperature Control System (CREATCS) ............................................................................................. 3.7.11-1 3.7.12 Emergency Core Cooling System (ECCS) Pump Room Exhaust Air Cleanup System (PREACS) .................................................................... 3.7.12-1 3.7.13 Fuel Building Air Cleanup System (FBACS) ................................................. 3.7.13-1 3.7.14 Penetration Room Exhaust Air Cleanup System (PREACS) ........................ 3.7.14-1 3.7.15 Fuel Storage Pool Water Level ..................................................................... 3.7.15-1 3.7.16 [Fuel Storage Pool Boron Concentration ..................................................... 3.7.16-1 ]

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

3.7.18 Secondary Specific Activity ........................................................................... 3.7.18-1 3.8 ELECTRICAL POWER SYSTEMS ....................................................................... 3.8.1-1 3.8.1 AC Sources - Operating .................................................................................. 3.8.1-1 3.8.2 AC Sources - Shutdown .................................................................................. 3.8.2-1 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ....................................................... 3.8.3-1 3.8.4 DC Sources - Operating .................................................................................. 3.8.4-1 3.8.5 DC Sources - Shutdown .................................................................................. 3.8.5-1 Westinghouse STS vii Rev. 5.0

TABLE OF CONTENTS Page 3.8 ELECTRICAL POWER SYSTEMS (continued) 3.8.6 Battery Parameters ......................................................................................... 3.8.6-1 3.8.7 Inverters - Operating ....................................................................................... 3.8.7-1 3.8.8 Inverters - Shutdown ....................................................................................... 3.8.8-1 3.8.9 Distribution Systems - Operating..................................................................... 3.8.9-1 3.8.10 Distribution Systems - Shutdown .................................................................. 3.8.10-1 3.9 REFUELING OPERATIONS ................................................................................. 3.9.1-1 3.9.1 Boron Concentration ....................................................................................... 3.9.1-1 3.9.2 [Unborated Water Source Isolation Valves ................................................... 3.9.2-1 ]

3.9.3 Nuclear Instrumentation .................................................................................. 3.9.3-1 3.9.4 Containment Penetrations ............................................................................... 3.9.4-1 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level ............................................................................................... 3.9.5-1 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level ............................................................................................... 3.9.6-1 3.9.7 Refueling Cavity Water Level .......................................................................... 3.9.7-1 4.0 DESIGN FEATURES ............................................................................................... 4.0-1 4.1 Site Location ...................................................................................................... 4.0-1 4.2 Reactor Core ...................................................................................................... 4.0-1 4.3 Fuel Storage ....................................................................................................... 4.0-1 5.0 ADMINISTRATIVE CONTROLS .............................................................................. 5.1-1 5.1 Responsibility ..................................................................................................... 5.1-1 5.2 Organization ....................................................................................................... 5.2-1 5.3 Unit Staff Qualifications ...................................................................................... 5.3-1 5.4 Procedures ......................................................................................................... 5.4-1 5.5 Programs and Manuals ...................................................................................... 5.5-1 5.6 Reporting Requirements .................................................................................... 5.6-1 5.7 High Radiation Area ........................................................................................... 5.7-1 Westinghouse STS viii Rev. 5.0

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

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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[, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step].

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.

Westinghouse STS 1.1-1 Rev. 5.0

Definitions 1.1 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[, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step].

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 per gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes I-131, I-132, I-133, I-134, and I-135 actually present.

The determination of DOSE EQUIVALENT I-131 shall be performed using

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Reviewers Note -------------------------------

The first set of thyroid dose conversion factors shall be used for plants licensed to 10 CFR 100.11. The following Committed Dose Equivalent (CDE) or Committed Effective Dose Equivalent (CEDE) conversion factors shall be used for plants licensed to 10 CFR 50.67.

[thyroid dose conversion factors from:

a. Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites," or

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

c. ICRP-30, 1979, Supplement to Part 1, page 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity," or Westinghouse STS 1.1-2 Rev. 5.0

Definitions 1.1 1.1 Definitions DOSE EQUIVALENT I-131 (continued)

d. Table 2.1 of EPA Federal Guidance Report No. 11, 1988, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion."

OR Committed Dose Equivalent (CDE) or Committed Effective Dose Equivalent (CEDE) dose conversion factors from Table 2.1 of EPA Federal Guidance Report No. 11.]

DOSE EQUIVALENT XE-133 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides [Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138]

actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity. The determination of DOSE EQUIVALENT XE-133 shall be performed using [effective dose conversion factors for air submersion listed in Table III.1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil" or the average gamma disintegration energies as provided in ICRP Publication 38, "Radionuclide Transformations" or similar source].

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, or the components have been evaluated in accordance with an NRC approved methodology.

INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50.55a(f).

Westinghouse STS 1.1-3 Rev. 5.0

Definitions 1.1 1.1 Definitions 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 to not interfere with the operation of leakage detection systems; 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 fault in an RCS component body, pipe wall, or vessel wall. LEAKAGE past seals, packing, and gaskets is not pressure boundary LEAKAGE.

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.

Westinghouse STS 1.1-4 Rev. 5.0

Definitions 1.1 1.1 Definitions 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.

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.

Westinghouse STS 1.1-5 Rev. 5.0

Definitions 1.1 1.1 Definitions 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, or the components have been evaluated in accordance with an NRC approved methodology.

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.

[ 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. ]

Westinghouse STS 1.1-6 Rev. 5.0

Definitions 1.1 1.1 Definitions 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[, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step].

Westinghouse STS 1.1-7 Rev. 5.0

Definitions 1.1 Table 1.1-1 (page 1 of 1)

MODES REACTIVITY  % RATED AVERAGE CONDITION THERMAL REACTOR COOLANT MODE TITLE (keff) POWER(a) 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.

Westinghouse STS 1.1-8 Rev. 5.0

Logical Connectors 1.2 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.

Westinghouse STS 1.2-1 Rev. 5.0

Logical Connectors 1.2 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.

Westinghouse STS 1.2-2 Rev. 5.0

Logical Connectors 1.2 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.

Westinghouse STS 1.2-3 Rev. 5.0

Completion Times 1.3 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 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.

Unless otherwise specified, the Completion Time begins when a senior licensed operator on the operating shift crew with responsibility for plant operations makes the determination that an LCO is not met and an ACTIONS Condition is entered. The "otherwise specified" exceptions are varied, such as a Required Action Note or Surveillance Requirement Note that provides an alternative time to perform specific tasks, such as testing, without starting the Completion Time. While utilizing the Note, should a Condition be applicable for any reason not addressed by the Note, the Completion Time begins. Should the time allowance in the Note be exceeded, the Completion Time begins at that point. The exceptions may also be incorporated into the Completion Time. For example, LCO 3.8.1, "AC Sources - Operating," Required Action B.2, requires declaring required feature(s) supported by an inoperable diesel generator, inoperable when the redundant required feature(s) are inoperable. The Completion Time states, "4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery of Condition B concurrent with inoperability of redundant required feature(s)." In this case the Completion Time does not begin until the conditions in the Completion Time are satisfied.

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 Westinghouse STS 1.3-1 Rev. 5.0

Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued)

Completion Times are tracked for each Condition starting from the discovery of the situation that required entry into the Condition, unless otherwise specified.

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, unless otherwise specified.

However, when a subsequent train, subsystem, component, or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability and

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

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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.

Westinghouse STS 1.3-2 Rev. 5.0

Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued)

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 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />," 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 B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND in MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. A total of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (not 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />) is allowed for reaching MODE 5 from the time that Condition B was entered. If MODE 3 is reached within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, the time allowed for reaching MODE 5 is the next 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> because the total time allowed for reaching MODE 5 is 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

If Condition B is entered while in MODE 3, the time allowed for reaching MODE 5 is the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Westinghouse STS 1.3-3 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pump A.1 Restore pump to 7 days inoperable. OPERABLE status.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> When a pump is declared inoperable, Condition A is entered. If the pump is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered, Conditions A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

When a second pump is declared inoperable while the first pump is still inoperable, Condition A is not re-entered for the second pump.

LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable pump. The Completion Time clock for Condition A does not stop after LCO 3.0.3 is entered, but continues to be tracked from the time Condition A was initially entered.

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.

Westinghouse STS 1.3-4 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

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 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> extension to the stated 7 days is allowed, provided this does not result in the second pump being inoperable for > 7 days.

EXAMPLE 1.3-3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore Function X 7 days Function X train to OPERABLE train status.

inoperable.

B. One B.1 Restore Function Y 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Function Y train to OPERABLE train status.

inoperable.

C. One C.1 Restore Function X 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Function X train to OPERABLE train status.

inoperable.

OR AND C.2 Restore Function Y 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> One train to OPERABLE Function Y status.

train inoperable.

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 Westinghouse STS 1.3-5 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued) train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e., initial entry into Condition A).

It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.

EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action and associated AND Completion Time not met. B.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 1.3-6 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis. Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.

Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

If the Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (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 A.1 Restore valve to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> valves OPERABLE status.

inoperable.

B. Required Action B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and associated Completion AND Time not met.

B.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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, Westinghouse STS 1.3-7 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued) the Note would appear in that Condition rather than at the top of the ACTIONS Table.

The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable, Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.

If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve. If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that valve.

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 A.1 Perform SR 3.x.x.x. Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable.

OR A.2 Reduce THERMAL 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> POWER to 50% RTP.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action and associated Completion Time not met.

Westinghouse STS 1.3-8 Rev. 5.0

Completion Times 1.3 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 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 A.1 Verify affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> subsystem subsystem isolated.

inoperable. AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter AND A.2 Restore subsystem 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to OPERABLE status.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Westinghouse STS 1.3-9 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or any subsequent 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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.

---

Reviewer's Note -------------------------------------

Example 1.3-8 is only applicable to plants that have adopted the Risk Informed Completion Time Program.

[ EXAMPLE 1.3-8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore subsystem 7 days subsystem to OPERABLE inoperable. status. OR In accordance with the Risk Informed Completion Time Program B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Westinghouse STS 1.3-10 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

When a subsystem is declared inoperable, Condition A is entered. The 7 day Completion Time may be applied as discussed in Example 1.3-2.

However, the licensee may elect to apply the Risk Informed Completion Time Program which permits calculation of a Risk Informed Completion Time (RICT) that may be used to complete the Required Action beyond the 7 day Completion Time. The RICT cannot exceed 30 days. After the 7 day Completion Time has expired, the subsystem must be restored to OPERABLE status within the RICT or Condition B must also be entered.

The Risk Informed Completion Time Program requires recalculation of the RICT to reflect changing plant conditions. For planned changes, the revised RICT must be determined prior to implementation of the change in configuration. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e., not the RICT) or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the plant configuration change, whichever is less.

If the 7 day Completion Time clock of Condition A has expired and subsequent changes in plant condition result in exiting the applicability of the Risk Informed Completion Time Program without restoring the inoperable subsystem to OPERABLE status, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start.

If the RICT expires or is recalculated to be less than the elapsed time since the Condition was entered and the inoperable subsystem has not been restored to OPERABLE status, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable subsystems are restored to OPERABLE status after Condition B is entered, Condition A is exited, and therefore, the Required Actions of Condition B may be terminated. ]

IMMEDIATE When "Immediately" is used as a Completion Time, The Required Action COMPLETION TIME should be pursued without delay and in a controlled manner.

Westinghouse STS 1.3-11 Rev. 5.0

Frequency 1.4 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:

Westinghouse STS 1.4-1 Rev. 5.0

Frequency 1.4 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.

Westinghouse STS 1.4-2 Rev. 5.0

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, 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.

Westinghouse STS 1.4-3 Rev. 5.0

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after 25% RTP AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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.

Westinghouse STS 1.4-4 Rev. 5.0

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

---

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

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (plus the extension allowed by SR 3.0.2) with power 25% RTP.

Once the unit reaches 25% RTP, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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.

Westinghouse STS 1.4-5 Rev. 5.0

Frequency 1.4 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency were not met), SR 3.0.4 would require satisfying the SR.

Westinghouse STS 1.4-6 Rev. 5.0

Frequency 1.4 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.

Westinghouse STS 1.4-7 Rev. 5.0

Frequency 1.4 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency exceeded, provided the MODE change does not result in entry into MODE 2. Prior to entering MODE 2 (assuming again that the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency were not met), SR 3.0.4 would require satisfying the SR.

Westinghouse STS 1.4-8 Rev. 5.0

SLs 2.0 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

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

Westinghouse STS 2.0-1 Rev. 5.0

LCO Applicability 3.0 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit, as applicable, in:

a. MODE 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />,

b. MODE 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />, and

c. MODE 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.

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 Westinghouse STS 3.0-1 Rev. 5.0

LCO Applicability 3.0 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 5.5.14, "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.

Westinghouse STS 3.0-2 Rev. 5.0

LCO Applicability 3.0 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 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.

Westinghouse STS 3.0-3 Rev. 5.0

SR Applicability 3.0 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. The delay period is only applicable when there is a reasonable expectation the Surveillance will be met when performed. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.

Westinghouse STS 3.0-4 Rev. 5.0

SR Applicability 3.0 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.

Westinghouse STS 3.0-5 Rev. 5.0

SDM 3.1.1 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 15 minutes SDM to within limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM to be within the limits specified in the [ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> COLR.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.1.1-1 Rev. 5.0

Core Reactivity 3.1.2 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 A.1 Re-evaluate core design 7 days not within limit. and safety analysis, and determine that the reactor core is acceptable for continued operation.

AND A.2 Establish appropriate 7 days operating restrictions and SRs.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

Westinghouse STS 3.1.2-1 Rev. 5.0

Core Reactivity 3.1.2 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 Once prior to of predicted values. 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 ]

Westinghouse STS 3.1.2-2 Rev. 5.0

MTC 3.1.3 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 A.1 Establish administrative 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit. withdrawal limits for control banks to maintain MTC within limit.

B. Required Action and B.1 Be in MODE 2 with 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion keff < 1.0.

Time of Condition A not met.

C. MTC not within lower C.1 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC is within upper limit. Prior to entering MODE 1 after each refueling Westinghouse STS 3.1.3-1 Rev. 5.0

MTC 3.1.3 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 RTP-ARO 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 Westinghouse STS 3.1.3-2 Rev. 5.0

MTC 3.1.3 Figure 3.1.3 - 1 (page 1 of 1)

Moderator Temperature Coefficient Vs. Rated Thermal Power Westinghouse STS 3.1.3-3 Rev. 5.0

Rod Group Alignment Limits 3.1.4 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) A.1.1 Verify SDM to be within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. limits specified in the COLR.

OR A.1.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SDM to within limit.

AND A.2 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> B. One rod not within B.1.1 Verify SDM to be within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> alignment limits. limits specified in the COLR.

OR Westinghouse STS 3.1.4-1 Rev. 5.0

Rod Group Alignment Limits 3.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.1.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SDM to within limit.

AND B.2 Reduce THERMAL 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> POWER to 75% RTP.

AND B.3 Verify SDM is within the Once per limits specified in the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> COLR.

AND B.4 Perform SR 3.2.1.1, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> SR 3.2.1.2, and SR 3.2.2.1.

AND B.5 Re-evaluate safety 5 days analyses and confirm results remain valid for duration of operation under these conditions.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition B not met.

D. More than one rod not D.1.1 Verify SDM is within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> within alignment limit. limits specified in the COLR.

OR Westinghouse STS 3.1.4-2 Rev. 5.0

Rod Group Alignment Limits 3.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.1.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required SDM to within limit.

AND D.2 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 ---------------------------- NOTES -----------------------------

1. Not required to be performed for rods associated with inoperable rod position indicator or demand position indicator.

[2. Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after associated rod motion.]

Verify position of individual rods within alignment [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> limit.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.1.4.2 Verify rod freedom of movement (trippability) by [ 92 days moving each rod not fully inserted in the core 10 steps in either direction. OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.1.4-3 Rev. 5.0

Rod Group Alignment Limits 3.1.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.4.3 Verify rod drop time of each rod, from the fully Prior to criticality withdrawn position, is [2.2] seconds from the after each beginning of decay of stationary gripper coil voltage removal of the to dashpot entry, with: reactor head

a. Tavg 500°F and

b. All reactor coolant pumps operating.

Westinghouse STS 3.1.4-4 Rev. 5.0

Shutdown Bank Insertion Limits 3.1.5 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.

---

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

Not applicable to shutdown banks inserted while performing SR 3.1.4.2.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One shutdown bank A.1 Verify all control banks are 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inserted [16] steps within the insertion limits beyond the insertion specified in the COLR.

limits specified in the COLR. AND A.2.1 Verify SDM is within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> limits specified in the COLR.

OR A.2.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SDM to within limit.

AND A.3 Restore the shutdown bank 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to within the insertion limits specified in the COLR.

B. One or more shutdown B.1.1 Verify SDM is within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> banks not within limits limits specified in the for reasons other than COLR.

Condition A.

OR Westinghouse STS 3.1.5-1 Rev. 5.0

Shutdown Bank Insertion Limits 3.1.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.1.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SDM to within limit.

AND B.2 Restore shutdown banks to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> within limits.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 [---------------------------- NOTE ------------------------------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after associated rod motion.

---

]

Verify each shutdown bank is within the insertion [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> limits specified in the COLR.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.1.5-2 Rev. 5.0

Control Bank Insertion Limits 3.1.6 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.

---

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

Not applicable to control banks inserted while performing SR 3.1.4.2.

APPLICABILITY: MODE 1, MODE 2 with keff 1.0.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Control bank A, B, or C A.1 Verify all shutdown banks 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inserted [16] steps are within the insertion beyond the insertion, limits specified in the sequence, or overlap COLR.

limits specified in the COLR. AND A.2.1 Verify SDM is within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> limits specified in the COLR.

OR A.2.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SDM to within limit.

AND A.3 Restore the control bank to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> within the insertion, sequence, and overlap limits specified in the COLR.

Westinghouse STS 3.1.6-1 Rev. 5.0

Control Bank Insertion Limits 3.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Control bank insertion B.1.1 Verify SDM is within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> limits not met for limits specified in the reasons other than COLR.

Condition A.

OR B.1.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SDM to within limit.

AND B.2 Restore control bank(s) to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> within limits.

C. Control bank sequence C.1.1 Verify SDM is within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or overlap limits not met limits specified in the for reasons other than COLR.

Condition A.

OR C.1.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SDM to within limit.

AND C.2 Restore control bank 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> sequence and overlap to within limits.

D. Required Action and D.1 Be in MODE 2 with keff 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion < 1.0.

Time not met.

Westinghouse STS 3.1.6-2 Rev. 5.0

Control Bank Insertion Limits 3.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify estimated critical control bank position is Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> within the limits specified in the COLR. prior to achieving criticality SR 3.1.6.2 [---------------------------- NOTE ------------------------------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after associated rod motion.

---

]

Verify each control bank insertion is within the [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> insertion limits specified in the COLR.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.1.6.3 [---------------------------- NOTE ------------------------------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after associated rod motion.

---

]

Verify sequence and overlap limits specified in the [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> COLR are met for control banks not fully withdrawn from the core. OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.1.6-3 Rev. 5.0

Rod Position Indication 3.1.7 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.

---

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

[Individual RPIs are not required to be OPERABLE for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> following movement of the associated rods.]

APPLICABILITY: MODES 1 and 2.

ACTIONS

---

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

Separate Condition entry is allowed for each inoperable [D]RPI and each demand position indicator.

CONDITION REQUIRED ACTION COMPLETION TIME A. One [D]RPI per group A.1 Verify the position of the Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable in one or rods with inoperable [D]RPI more groups. indirectly by using movable incore detectors.

OR A.2 Verify the position of the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rods with inoperable [D]RPI indirectly by using the AND moveable incore detectors.

Once per 31 EFPD thereafter AND 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after discovery of each unintended rod movement AND Westinghouse STS 3.1.7-1 Rev. 5.0

Rod Position Indication 3.1.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after each movement of rod with inoperable [D]RPI

> 12 steps AND Prior to THERMAL POWER exceeding 50% RTP AND 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after reaching RTP OR A.3 Reduce THERMAL 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> POWER to 50% RTP.

B. More than one [D]RPI B.1 Place the control rods Immediately per group inoperable in under manual control.

one or more groups.

AND B.2 Restore inoperable [D]RPIs 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to OPERABLE status such that a maximum of one

[D]RPI per group is inoperable.

Westinghouse STS 3.1.7-2 Rev. 5.0

Rod Position Indication 3.1.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more [D]RPI C.1 Verify the position of the [4] hours inoperable in one or rods with inoperable more groups and [D]RPIs indirectly by using associated rod has been movable incore detectors.

moved > 24 steps in one direction since the last OR determination of the rod's position. C.2 Reduce THERMAL 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> POWER to 50% RTP.

D. One or more demand D.1.1 Verify by administrative Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> position indicators per means all [D]RPIs for the bank inoperable in one affected banks are or more banks. OPERABLE.

AND D.1.2 Verify the most withdrawn Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rod and the least withdrawn rod of the affected banks are 12 steps apart.

OR D.2 Reduce THERMAL 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> POWER to 50% RTP.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

Westinghouse STS 3.1.7-3 Rev. 5.0

Rod Position Indication 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 ----------------------------- NOTE ------------------------------

Not required to be met for [D]RPIs associated with rods that do not meet LCO 3.1.4.

Verify each [D]RPI agrees within [12] steps of the Once prior to group demand position for the [full indicated range] criticality after of rod travel. each removal of the reactor head Westinghouse STS 3.1.7-4 Rev. 5.0

PHYSICS TESTS Exceptions - MODE 2 3.1.8 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 15 minutes SDM to within limit.

AND A.2 Suspend PHYSICS TESTS 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> exceptions.

B. THERMAL POWER not B.1 Open reactor trip breakers. Immediately within limit.

C. RCS lowest loop C.1 Restore RCS lowest loop 15 minutes average temperature not average temperature to within limit. within limit.

Westinghouse STS 3.1.8-1 Rev. 5.0

PHYSICS TESTS Exceptions - MODE 2 3.1.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 15 minutes associated Completion Time of Condition C not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 Perform a CHANNEL OPERATIONAL TEST on Prior to initiation power range and intermediate range channels per of PHYSICS

[SR 3.3.1.7, SR 3.3.1.8, and Table 3.3.1-1]. TESTS SR 3.1.8.2 Verify the RCS lowest loop average temperature is [ 30 minutes

[531]°F.

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 ]

Westinghouse STS 3.1.8-2 Rev. 5.0

PHYSICS TESTS Exceptions - MODE 2 3.1.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.8.4 Verify SDM is within the limits specified in the [ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> COLR.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.1.8-3 Rev. 5.0

FQ(Z) (CAOC-Fxy Methodology) 3.2.1A 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------------ A.1 Reduce THERMAL 15 minutes after each Required Action A.4 POWER 1% RTP for FQ(Z) determination shall be completed each 1% FQ(Z) exceeds whenever this Condition limit.

is entered.

---

AND FQ(Z) not within limit. A.2 Reduce Power Range 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each Neutron Flux - High trip FQ(Z) determination setpoints 1% for each 1% FQ(Z) exceeds limit.

AND A.3 Reduce Overpower T trip 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each setpoints 1% for each FQ(Z) determination 1% FQ(Z) exceeds limit.

AND A.4 Perform SR 3.2.1.1 and Prior to increasing SR 3.2.1.2. THERMAL POWER above the limit of Required Action A.1 B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

Westinghouse STS 3.2.1A-1 Rev. 5.0

FQ(Z) (CAOC-Fxy Methodology) 3.2.1A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify measured values of FQ(Z) are within limits Once after each specified in the COLR. refueling prior to THERMAL POWER exceeding 75% RTP AND

[ 31 EFPD thereafter OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.2.1A-2 Rev. 5.0

FQ(Z) (CAOC-Fxy Methodology) 3.2.1A SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.2 ------------------------------NOTES-----------------------------

C L

1. If FXY > FXY , evaluate the effect of Fxy on the predicted FQPR to determine if FQ(Z) is within its limits.

RTP C L

2. If FXY < FXY FXY , SR 3.2.1.2 shall be repeated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after an increase in C

THERMAL POWER at which FXY was last determined, of at least 20% RTP.

C L Verify FXY < 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 ]

Westinghouse STS 3.2.1A-3 Rev. 5.0

FQ(Z) (RAOC-W(Z) Methodology) 3.2.1B 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 FQC ( Z) and FQW (Z) , shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE------------ A.1 Reduce THERMAL 15 minutes after each Required Action A.4 POWER 1% RTP for FQC ( Z) determination shall be completed each 1% FQC ( Z) exceeds whenever this Condition limit.

is entered.

---

AND FQC ( Z) not within limit. A.2 Reduce Power Range 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each Neutron Flux - High trip FQC ( Z) determination setpoints 1% for each 1% FQC ( Z) exceeds limit.

AND A.3 Reduce Overpower T trip 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each setpoints 1% for each FQC ( Z) determination 1% FQC ( Z) exceeds limit.

AND A.4 Perform SR 3.2.1.1 and Prior to increasing SR 3.2.1.2. THERMAL POWER above the limit of Required Action A.1 Westinghouse STS 3.2.1B-1 Rev. 5.0

FQ(Z) (RAOC-W(Z) Methodology) 3.2.1B ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. ------------NOTE------------ B.1 Reduce AFD limits 1% for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Required Action B.4 each 1% FQW (Z) exceeds shall be completed limit.

whenever this Condition is entered. AND B.2 Reduce Power Range 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> FQW (Z) not within limits. 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 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 Prior to increasing SR 3.2.1.2. THERMAL POWER above the maximum allowable power of the AFD limits C. Required Action and C.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

Westinghouse STS 3.2.1B-2 Rev. 5.0

FQ(Z) (RAOC-W(Z) Methodology) 3.2.1B 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 FQC ( Z) 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 FQC ( Z) was last verified AND

[ 31 EFPD thereafter OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.2.1B-3 Rev. 5.0

FQ(Z) (RAOC-W(Z) Methodology) 3.2.1B SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.2 -------------------------------NOTE------------------------------

If measurements indicate that the maximum over z [ FQC ( Z) / K(Z) ]

has increased since the previous evaluation of FQC ( Z) :

a. Increase FQW (Z) by the greater of a factor of

[1.02] or by an appropriate factor specified in the COLR and reverify FQW (Z) 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 [ FQC ( Z) / K(Z) ]

has not increased.

Verify FQW (Z) is within limit. Once after each refueling prior to THERMAL POWER exceed-ing 75% RTP AND Once within

[12] hours after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which FQW (Z) was last verified AND Westinghouse STS 3.2.1B-4 Rev. 5.0

FQ(Z) (RAOC-W(Z) Methodology) 3.2.1B SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

[ 31 EFPD thereafter OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.2.1B-5 Rev. 5.0

FQ(Z) (CAOC-W(Z) Methodology) 3.2.1C 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 FQC ( Z) and FQW (Z) , shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE------------ A.1 Reduce THERMAL 15 minutes after each Required Action A.4 POWER 1% RTP for FQC ( Z) determination shall be completed each 1% FQC ( Z) exceeds whenever this Condition limit.

is entered.

---

AND FQC ( Z) not within limit. A.2 Reduce Power Range 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each Neutron Flux - High trip FQC ( Z) determination setpoints 1% for each 1% FQC ( Z) exceeds limit.

AND A.3 Reduce Overpower T trip 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each setpoints 1% for each FQC ( Z) determination 1% FQC ( Z) exceeds limit.

AND A.4 Perform SR 3.2.1.1 and Prior to increasing SR 3.2.1.2. THERMAL POWER above the limit of Required Action A.1 Westinghouse STS 3.2.1C-1 Rev. 5.0

FQ(Z) (CAOC-W(Z) Methodology) 3.2.1C ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. ------------NOTE------------ B.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Required Action B.4 POWER 1% RTP for shall be completed each 1% FQW (Z) exceeds whenever this Condition limit.

is entered.

---

AND FQW (Z) not within limits. B.2 Reduce Power Range 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Neutron Flux - High trip setpoints 1% for each 1%

FQW (Z) exceeds limit.

AND B.3 Reduce Overpower T trip 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> setpoints 1% for each 1%

FQW (Z) exceeds limit.

AND B.4 Perform SR 3.2.1.1 and Prior to increasing SR 3.2.1.2. THERMAL POWER above the limit of Required Action B.1 C. Required Action and C.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

Westinghouse STS 3.2.1C-2 Rev. 5.0

FQ(Z) (CAOC-W(Z) Methodology) 3.2.1C 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 FQC ( Z) 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 FQC ( Z) was last verified AND

[ 31 EFPD thereafter OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.2.1C-3 Rev. 5.0

FQ(Z) (CAOC-W(Z) Methodology) 3.2.1C SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.2 -------------------------------NOTE------------------------------

If measurements indicate that the maximum over z [ FQC ( Z) / K(Z) ] has increased since the previous evaluation of FQC ( Z) :

a. Increase FQW (Z) by the greater of a factor of

[1.02] or by an appropriate factor specified in the COLR and reverify FQW (Z) 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 [ FQC ( Z) /

K(Z) ] has not increased.

Verify FQW (Z) 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 FQW (Z) was last verified AND Westinghouse STS 3.2.1C-4 Rev. 5.0

FQ(Z) (CAOC-W(Z) Methodology) 3.2.1C SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

[31 EFPD thereafter OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.2.1C-5 Rev. 5.0

FNH 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( FNH )

LCO 3.2.2 FNH shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE------------ A.1.1 Restore FNH to within limit. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Required Actions A.2 and A.3 must be OR completed whenever Condition A is entered. A.1.2.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

---

POWER to < 50% RTP.

FNH not within limit. AND A.1.2.2 Reduce Power Range 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Neutron Flux - High trip setpoints to 55% RTP.

AND A.2 Perform SR 3.2.2.1. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND Westinghouse STS 3.2.2-1 Rev. 5.0

FNH 3.2.2 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER reaching 95% RTP B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

Westinghouse STS 3.2.2-2 Rev. 5.0

FNH 3.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify FNH 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 ]

Westinghouse STS 3.2.2-3 Rev. 5.0

AFD (CAOC Methodology) 3.2.3A 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 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 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> 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.

Westinghouse STS 3.2.3A-1 Rev. 5.0

AFD (CAOC Methodology) 3.2.3A ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. THERMAL POWER A.1 Restore AFD to within 15 minutes 90% RTP. target band.

AND AFD not within the target band.

B. Required Action and B.1 Reduce THERMAL 15 minutes associated Completion POWER to < 90% RTP.

Time of Condition A not met.

C. ------------NOTE------------ C.1 Reduce THERMAL 30 minutes Required Action C.1 POWER to < 50% RTP.

must be completed whenever Condition C is entered.

THERMAL POWER

< 90% and 50% RTP with cumulative penalty deviation time > 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

OR THERMAL POWER

< 90% and 50% RTP with AFD not within the acceptable operation limits.

D. Required Action and D.1 Reduce THERMAL 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> associated Completion POWER to < 15% RTP.

Time for Condition C not met.

Westinghouse STS 3.2.3A-2 Rev. 5.0

AFD (CAOC Methodology) 3.2.3A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify AFD is within limits for each OPERABLE [ 7 days excore channel.

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 ]

Westinghouse STS 3.2.3A-3 Rev. 5.0

AFD (CAOC Methodology) 3.2.3A 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 Once within difference. 31 EFPD after each refueling AND

[ 92 EFPD thereafter OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.2.3A-4 Rev. 5.0

AFD (RAOC Methodology) 3.2.3B 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 30 minutes POWER to < 50% RTP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify AFD within limits for each OPERABLE excore [ 7 days channel.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.2.3B-1 Rev. 5.0

QPTR 3.2.4 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 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after each POWER 3% from RTP for QPTR determination each 1% of QPTR > 1.00.

AND A.2 Determine QPTR. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND A.3 Perform SR 3.2.1.1, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after SR 3.2.1.2, and SR 3.2.2.1. achieving equilibrium conditions from a THERMAL POWER reduction per Required Action A.1 AND Once per 7 days thereafter AND Westinghouse STS 3.2.4-1 Rev. 5.0

QPTR 3.2.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.4 Reevaluate safety analyses Prior to increasing and confirm results remain THERMAL POWER valid for duration of above the limit of operation under this Required Action A.1 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 Prior to increasing to restore QPTR to within THERMAL POWER limit. above the limit of Required Action A.1 AND A.6 ---------------NOTE--------------

Perform Required Action A.6 only after Required Action A.5 is completed.

Perform SR 3.2.1.1, Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after SR 3.2.1.2, and SR 3.2.2.1. achieving equilibrium conditions at RTP not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after increasing THERMAL POWER above the limit of Required Action A.1 Westinghouse STS 3.2.4-2 Rev. 5.0

QPTR 3.2.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to 50% RTP.

Time not met.

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 ]

Westinghouse STS 3.2.4-3 Rev. 5.0

QPTR 3.2.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.4.2 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> detectors.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.2.4-4 Rev. 5.0

RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 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 A.1 Enter the Condition Immediately with one or more referenced in Table 3.3.1-1 required channels or for the channel(s) or trains inoperable. train(s).

B. One Manual Reactor B.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Trip channel inoperable. OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

C. One channel or train C.1 Restore channel or train to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable. OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.3.1-1 Rev. 5.0

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One Power Range [ ------------------NOTE-------------------

Neutron Flux - High The inoperable channel may be channel inoperable. bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing and setpoint adjustment of other channels.

---

REVIEWERS NOTE----------

The below Note should be used for plants with installed bypass test capability.

One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing and setpoint adjustment.

---

]

D.1.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

[OR In accordance with the Risk Informed Completion Time Program]

AND D.1.2 Reduce THERMAL 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> POWER to 75% RTP.

[OR In accordance with the Risk Informed Completion Time Program]

OR Westinghouse STS 3.3.1-2 Rev. 5.0

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.2.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

[OR In accordance with the Risk Informed Completion Time Program]

AND 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. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.3.1-3 Rev. 5.0

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One channel inoperable. [ -------------------NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.

---

REVIEWERS NOTE----------

The below Note should be used for plants with installed bypass test capability:

One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

---

]

E.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

[OR In accordance with the Risk Informed Completion Time Program]

F. One Intermediate Range F.1 Reduce THERMAL 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Neutron Flux channel POWER to < P-6.

inoperable.

OR F.2 Increase THERMAL 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> POWER to > P-10.

Westinghouse STS 3.3.1-4 Rev. 5.0

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Two Intermediate Range G.1 --------------NOTE--------------

Neutron Flux channels Limited plant cooldown or inoperable. boron dilution is allowed provided the change is accounted for in the calculated SDM.

Suspend operations Immediately involving positive reactivity additions.

AND G.2 Reduce THERMAL 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> POWER to < P-6.

H. One Source Range H.1 --------------NOTE--------------

Neutron Flux channel Limited plant cooldown or inoperable. boron dilution is allowed provided the change is accounted for in the calculated SDM.

Suspend operations Immediately involving positive reactivity additions.

I. Two Source Range I.1 Open reactor trip breakers Immediately Neutron Flux channels (RTBs).

inoperable.

Westinghouse STS 3.3.1-5 Rev. 5.0

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME J. One Source Range J.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Neutron Flux channel OPERABLE status.

inoperable. [OR In accordance with the Risk Informed Completion Time Program]

K. Required Action and K.1 Initiate action to fully insert Immediately associated Completion all rods.

Time of Condition C or J not met. AND K.2 Place the Rod Control 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> System in a condition incapable of rod withdrawal.

L. One channel inoperable. [ -------------------NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.

---

REVIEWERS NOTE----------

The below Note should be used for plants with installed bypass test capability:

One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

---

]

L.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

[OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.3.1-6 Rev. 5.0

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME M. Required Action and M.1 Reduce THERMAL 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion POWER to < P-7.

Time of Condition L not met.

N. One Reactor Coolant --------------------NOTE-------------------

Pump Breaker Position The inoperable channel may be (Single Loop) channel bypassed for up to [4] hours for inoperable. surveillance testing of other channels.

N.1 Restore channel to [6] hours OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

O. Required Action and O.1 Reduce THERMAL [4] hours associated Completion POWER to < P-8.

Time of Condition N not met.

P. One Reactor Coolant --------------------NOTE-------------------

Breaker Position (Two The inoperable channel may be Loops) channel bypassed for up to [4] hours for inoperable. surveillance testing of other channels.

P.1 Place the channel in trip. [6] hours Westinghouse STS 3.3.1-7 Rev. 5.0

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME Q. Required Action and Q.1 Reduce THERMAL [6] hours associated Completion POWER to <P-7.

Time of Condition P not met.

R. One Turbine Trip [ -------------------NOTE-------------------

channel inoperable. The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.

---

REVIEWERS NOTE----------

The below Note should be used for plants with installed bypass test capability.

One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

---

]

R.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

[OR In accordance with the Risk Informed Completion Time Program]

S. Required Action and S.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to < [P-9].

Time of Condition R not met.

Westinghouse STS 3.3.1-8 Rev. 5.0

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME T. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up to [4] hours for surveillance testing provided the other train is OPERABLE.

T.1 Restore train to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

U. One RTB train --------------------NOTE------------------

inoperable. One train may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing, provided the other train is OPERABLE.

U.1 Restore train to [24] hours OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

V. One or more channels V.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. required state for existing unit conditions.

W. One or more channels W.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. required state for existing unit conditions.

Westinghouse STS 3.3.1-9 Rev. 5.0

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME X. Required Action and X.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition W not met.

Y. One trip mechanism Y.1 Restore trip mechanism to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable for one RTB. OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

Z. Required Action and Z.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition B, D, E, T, U, V, W, or Y not met.

Westinghouse STS 3.3.1-10 Rev. 5.0

RTS Instrumentation 3.3.1 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 [ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> calculation to power range channel output. Adjust power range channel output if calorimetric heat OR balance calculations results exceed power range channel output by more than +2% RTP. In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.3.1-11 Rev. 5.0

RTS Instrumentation 3.3.1 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 [ 31 effective full measurements to Nuclear Instrumentation System power days (NIS) AFD. Adjust NIS channel if absolute (EFPD) difference is 3%.

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 ]

Westinghouse STS 3.3.1-12 Rev. 5.0

RTS Instrumentation 3.3.1 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 [ [92] EFPD detector measurements.

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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entry into MODE 3.

Perform COT. [ 184 days OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.3.1-13 Rev. 5.0

RTS Instrumentation 3.3.1 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 Westinghouse STS 3.3.1-14 Rev. 5.0

RTS Instrumentation 3.3.1 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 ]

Westinghouse STS 3.3.1-15 Rev. 5.0

RTS Instrumentation 3.3.1 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 ]

Westinghouse STS 3.3.1-16 Rev. 5.0

RTS Instrumentation 3.3.1 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 Westinghouse STS 3.3.1-17 Rev. 5.0

RTS Instrumentation 3.3.1 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 ]

Westinghouse STS 3.3.1-18 Rev. 5.0

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 8)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE 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 [111.2]% [109]% RTP SR 3.3.1.2 RTP SR 3.3.1.7(b)(c)

SR 3.3.1.11(b)(c)

SR 3.3.1.16

b. Low 1(d),2 4 E SR 3.3.1.1 [27.2]% RTP [25]% RTP SR 3.3.1.8(b)(c)

SR 3.3.1.11(b)(c)

SR 3.3.1.16

3. Power Range Neutron Flux Rate

a. High Positive 1,2 4 E SR 3.3.1.7(b)(c) [6.8]% RTP [5]% RTP with Rate SR 3.3.1.11(b)(c) with time time constant constant [2] sec

[2] sec

b. High Negative 1,2 4 E SR 3.3.1.7(b)(c) [6.8]% RTP [5]% RTP with Rate SR 3.3.1.11(b)(c) with time time constant SR 3.3.1.16 constant [2] sec

[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.

---

REVIEWERS NOTE--------------------------------------------------------------------------------------

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

Westinghouse STS 3.3.1-19 Rev. 5.0

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 8)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

4. Intermediate Range 1(d), 2(e) 2 F,G SR 3.3.1.1 [31]% RTP [25]% RTP Neutron Flux SR 3.3.1.8(b)(c)

SR 3.3.1.11(b)(c)

5. Source Range 2(f) 2 H,I SR 3.3.1.1 [1.4 E5] cps [1.0 E5] cps Neutron Flux SR 3.3.1.8(b)(c)

SR 3.3.1.11(b)(c)

SR 3.3.1.16 3(a), 4(a), 5(a) 2 I,J SR 3.3.1.1 [1.4 E5] cps [1.0 E5] cps SR 3.3.1.7(b)(c)

SR 3.3.1.11(b)(c)

SR 3.3.1.16

6. Overtemperature T 1,2 [4] E SR 3.3.1.1 Refer to Refer to SR 3.3.1.3 Note 1 (Page Note 1 (Page SR 3.3.1.6 3.3.1-19) 3.3.1-19)

SR 3.3.1.7(b)(c)

SR 3.3.1.12(b)(c)

SR 3.3.1.16

7. Overpower T 1,2 [4] E SR 3.3.1.1 Refer to Refer to SR 3.3.1.7(b)(c) Note 2 (Page Note 2 (Page SR 3.3.1.12(b)(c) 3.3.1-20) 3.3.1-20)

SR 3.3.1.16 (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.

---

REVIEWERS NOTE--------------------------------------------------------------------------------------

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

Westinghouse STS 3.3.1-20 Rev. 5.0

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 8)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

8. Pressurizer Pressure

a. Low 1(h) [4] L SR 3.3.1.1 [1886] psig [1900] psig SR 3.3.1.7(b)(c)

SR 3.3.1.10(b)(c)

SR 3.3.1.16

b. High 1,2 [4] E SR 3.3.1.1 [2396] psig [2385] psig SR 3.3.1.7(b)(c)

SR 3.3.1.10(b)(c)

SR 3.3.1.16

9. Pressurizer Water 1(g) 3 L SR 3.3.1.1 [93.8]% [92]%

Level - High SR 3.3.1.7(b)(c)

SR 3.3.1.10(b)(c)

10. Reactor Coolant 1(g) 3 per loop L SR 3.3.1.1 [89.2]% [90]%

Flow - Low SR 3.3.1.7(b)(c)

SR 3.3.1.10(b)(c)

SR 3.3.1.16

11. Reactor Coolant Pump (RCP) Breaker Position

a. Single Loop 1(h) 1 per RCP N SR 3.3.1.14 NA NA

b. Two Loops 1(i) 1 per RCP P SR 3.3.1.14 NA NA

12. Undervoltage RCPs 1(g) [3] per bus L SR 3.3.1.9 [4760] V [4830] V SR 3.3.1.10(b)(c)

SR 3.3.1.16 (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.

---

REVIEWERS NOTE--------------------------------------------------------------------------------------

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

Westinghouse STS 3.3.1-21 Rev. 5.0

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 8)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

13. Underfrequency 1(g) [3] per bus L SR 3.3.1.9 [57.1] Hz [57.5] Hz RCPs SR 3.3.1.10(b)(c)

SR 3.3.1.16

14. Steam Generator 1,2 [4 per SG] E SR 3.3.1.1 [30.4]% [32.3]%

(SG) Water SR 3.3.1.7(b)(c)

Level - Low Low SR 3.3.1.10(b)(c)

SR 3.3.1.16

15. SG Water 1,2 2 per SG E SR 3.3.1.1 [30.4]% [32.3]%

Level - Low SR 3.3.1.7(b)(c)

SR 3.3.1.10(b)(c)

SR 3.3.1.16 Coincident with 1,2 2 per SG E SR 3.3.1.1 [42.5]% full [40]% full Steam SR 3.3.1.7(b)(c) steam flow at steam flow at Flow/Feedwater Flow SR 3.3.1.10(b)(c) RTP RTP SR 3.3.1.16 Mismatch

16. Turbine Trip

a. Low Fluid Oil 1(j) 3 R SR 3.3.1.10(b)(c) [750] psig [800] psig Pressure SR 3.3.1.15

b. Turbine Stop 1(j) 4 R SR 3.3.1.10 [1]% open [1]% open Valve Closure SR 3.3.1.15

17. Safety Injection (SI) 1,2 2 trains T SR 3.3.1.14 NA NA Input from Engineered Safety Feature Actuation System (ESFAS)

(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.

---

REVIEWERS NOTE--------------------------------------------------------------------------------------

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

Westinghouse STS 3.3.1-22 Rev. 5.0

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 8)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

18. Reactor Trip System Interlocks

a. Intermediate 2(f) 2 V SR 3.3.1.11 [6E-11] amp [1E-10] amp Range Neutron SR 3.3.1.13 Flux, P-6

b. Low Power 1 1 per train W SR 3.3.1.5 NA NA Reactor Trips Block, P-7

c. Power Range 1 4 W SR 3.3.1.11 [50.2]% RTP [48]% RTP Neutron Flux, SR 3.3.1.13 P-8

d. Power Range 1 4 W SR 3.3.1.11 [52.2]% RTP [50]% RTP Neutron Flux, SR 3.3.1.13 P-9

e. Power Range 1,2 4 V SR 3.3.1.11 [7.8]% RTP [10]% RTP Neutron Flux, SR 3.3.1.13 and [12.2]%

P-10 RTP

f. Turbine Impulse 1 2 W [SR 3.3.1.1] [12.2]% 10]% turbine Pressure, P-13 SR 3.3.1.10 turbine power power SR 3.3.1.13

19. Reactor Trip 1,2 2 trains U SR 3.3.1.4 NA NA Breakers(k) (RTBs) 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.

---

REVIEWERS NOTE--------------------------------------------------------------------------------------

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

Westinghouse STS 3.3.1-23 Rev. 5.0

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 8)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

20. Reactor Trip Breaker 1,2 1 each per Y SR 3.3.1.4 NA NA Undervoltage and RTB Shunt Trip Mechanisms 3(a), 4(a), 5(a) 1 each per C SR 3.3.1.4 NA NA RTB

21. Automatic Trip Logic 1,2 2 trains T 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.

---

REVIEWERS NOTE--------------------------------------------------------------------------------------

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

Westinghouse STS 3.3.1-24 Rev. 5.0

RTS Instrumentation 3.3.1 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 + T1S ) 1 (1 + T4S ) 1 T TQ K 1 K 2 T T + K 3 (P P ) f1 ( I )

(1 + T2S ) 1+ T3S (1 + T5S ) (1 + T6S )

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.

Westinghouse STS 3.3.1-25 Rev. 5.0

RTS Instrumentation 3.3.1 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 + T1S ) 1 T7S 1 1 T TQ K 4 K 5 T K 6 T T f2 ( I )

(1 + T2S ) 1 + T3S 1 + T7 S 1 + T6 S 1+ T6S 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.

Westinghouse STS 3.3.1-26 Rev. 5.0

ESFAS Instrumentation 3.3.2 3.3 INSTRUMENTATION 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation LCO 3.3.2 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 A.1 Enter the Condition Immediately with one or more referenced in Table 3.3.2-1 required channels or for the channel(s) or trains inoperable. train(s).

B. One channel or train B.1 Restore channel or train to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable. OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.3.2-1 Rev. 5.0

ESFAS Instrumentation 3.3.2 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 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

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

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.

---

REVIEWERS NOTE----------

The below Note should be used for plants with installed bypass test capability:

One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

---

]

D.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

[OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.3.2-2 Rev. 5.0

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One Containment [ ------------------NOTE-------------------

Pressure channel One additional channel may be inoperable. bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.

---

REVIEWERS NOTE---------

The below Note should be used for plants with installed bypass test capability.

One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

---

]

E.1 Place channel in bypass. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> F. One channel or train F.1 Restore channel or train to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable. OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.3.2-3 Rev. 5.0

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 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 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

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 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.3.2-4 Rev. 5.0

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. One channel inoperable. [ ------------------NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.

---

REVIEWERS NOTE----------

The below Note should be used for plants with installed bypass test capability.

One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

---

]

I.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

[OR In accordance with the Risk Informed Completion Time Program]

J. One Main Feedwater J.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Pumps trip channel OPERABLE status.

inoperable. [OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.3.2-5 Rev. 5.0

ESFAS Instrumentation 3.3.2 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.

---

REVIEWERS NOTE----------

The below Note should be used for plants with installed bypass test capability:

One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

---

]

K.1 Place channel in bypass. [6] hours L. One or more channels L.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. required state for existing unit condition.

M. Required Action and M.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Conditions B, C, AND or K not met.

M.2 -------------- NOTE -------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> N. Required Action and N.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Conditions D, E, AND F, G, or L not met.

N.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.3.2-6 Rev. 5.0

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME O. Required Action and O.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Conditions H, I, or J not met.

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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 ]

Westinghouse STS 3.3.2-7 Rev. 5.0

ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 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 ]

---

REVIEWERS 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 ]

Westinghouse STS 3.3.2-8 Rev. 5.0

ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.6 Perform SLAVE RELAY TEST. [ [92] days OR In accordance with the Surveillance Frequency Control Program ]

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 ]

Westinghouse STS 3.3.2-9 Rev. 5.0

ESFAS Instrumentation 3.3.2 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 Westinghouse STS 3.3.2-10 Rev. 5.0

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 1 of 11)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

1. Safety Injection

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

b. Automatic 1,2,3,4 2 trains C SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays

c. Containment 1,2,3 3 D SR 3.3.2.1 [3.86] psig [3.6] psig Pressure - SR 3.3.2.5(b)(c)

High 1 SR 3.3.2.9(b)(c)

SR 3.3.2.10

d. Pressurizer 1,2,3 (a) [3] D SR 3.3.2.1 [1839] psig [1850] psig Pressure - Low SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

e. Steam Line Pressure (1) Low 1,2,3 [(a)] 3 per D SR 3.3.2.1 [635](d) psig [675](d) psig steam line SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10 (2) High 1,2,3 3 per D [SR 3.3.2.1] [106] psig [97] psig Differential steam line SR 3.3.2.5(b)(c)

Pressure SR 3.3.2.9(b)(c)

Between SR 3.3.2.10 Steam Lines (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.

Westinghouse STS 3.3.2-11 Rev. 5.0

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 11)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

1. Safety Injection

f. High Steam Flow 1,2,3 (e) 2 per D SR 3.3.2.1 (f) (g) in Two Steam steam line SR 3.3.2.5(b)(c)

Lines SR 3.3.2.9(b)(c)

SR 3.3.2.10 Coincident with 1,2,3 (e) 1 per loop D SR 3.3.2.1 [550.6]°F [553]°F Tavg - Low Low SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

g. High Steam Flow 1,2,3 (e) 2 per D SR 3.3.2.1 (f) (g) in Two Steam steam line SR 3.3.2.5(b)(c)

Lines SR 3.3.2.9(b)(c)

SR 3.3.2.10 Coincident with 1,2,3 (e) 1 per D SR 3.3.2.1 [635](d) [675] psig Steam Line steam line SR 3.3.2.5(b)(c) psig Pressure - Low SR 3.3.2.9(b)(c)

SR 3.3.2.10

2. Containment Spray

a. Manual Initiation 1,2,3,4 2 per train, B SR 3.3.2.8 NA NA 2 trains (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.

Westinghouse STS 3.3.2-12 Rev. 5.0

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 11)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

2. Containment Spray NA NA

b. Automatic 1,2,3,4 2 trains C SR 3.3.2.2 Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays

c. Containment 1,2,3 4 E SR 3.3.2.1 [12.31] psig [12.05] psig Pressure High - SR 3.3.2.5(b)(c) 3 (High High) SR 3.3.2.9(b)(c)

SR 3.3.2.10

d. Containment 1,2,3 [3] sets of E SR 3.3.2.1 [12.31] psig [12.05] psig Pressure High - [2] SR 3.3.2.5(b)(c) 3 (Two Loop SR 3.3.2.9(b)(c)

SR 3.3.2.10 Plants)

3. Containment Isolation

a. Phase A Isolation (1) Manual 1,2,3,4 2 B SR 3.3.2.8 NA NA Initiation (2) Automatic 1,2,3,4 2 trains C SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays (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.

Westinghouse STS 3.3.2-13 Rev. 5.0

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 4 of 11)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

3. Containment Isolation

b. Phase B Isolation (1) Manual 1,2,3,4 2 per train, B SR 3.3.2.8 NA NA Initiation 2 trains (2) Automatic 1,2,3,4 2 trains C SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays (3) Containment 1,2,3 [4] E SR 3.3.2.1 [12.31] psig [12.05] psig Pressure High SR 3.3.2.5(b)(c)

- 3 (High High) SR 3.3.2.9(b)(c)

SR 3.3.2.10

4. Steam Line Isolation

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

b. Automatic 1,2 (j),3 (j) 2 trains G SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays

c. Containment 1,2 (j),3 (j) [4] D SR 3.3.2.1 [6.61] psig [6.35] psig Pressure - High SR 3.3.2.5(b)(c) 2 SR 3.3.2.9(b)(c)

SR 3.3.2.10 (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.

Westinghouse STS 3.3.2-14 Rev. 5.0

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 5 of 11)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

4. Steam Line Isolation

d. Steam Line Pressure (1) Low 1,2 (j),3 (j) (a) 3 per D SR 3.3.2.1 [635](d) psig [675](d) psig steam line SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10 (2) Negative Rate 3 (h) (j) 3 per D SR 3.3.2.1 [121.6](i) psi [110](i) psi

- High steam line SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10 (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.

Westinghouse STS 3.3.2-15 Rev. 5.0

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 6 of 11)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

4. Steam Line Isolation

e. High Steam Flow 1,2 (j),3 (j) 2 per D SR 3.3.2.1 (f) (g) in Two Steam steam line SR 3.3.2.5(b)(c)

Lines SR 3.3.2.9(b)(c)

SR 3.3.2.10 Coincident with 1,2 (j),3 (e) (j) 1 per loop D SR 3.3.2.1 [550.6]°F [553]°F Tavg - Low Low SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

f. High Steam Flow 1,2 (j),3 (j) 2 per D SR 3.3.2.1 (f) (g) in Two Steam steam line SR 3.3.2.5(b)(c)

Lines SR 3.3.2.9(b)(c)

SR 3.3.2.10 Coincident with 1,2 (j),3 (j) 1 per D SR 3.3.2.1 [635](d) psig [675](d) psig Steam Line steam line SR 3.3.2.5(b)(c)

Pressure - Low SR 3.3.2.9(b)(c)

SR 3.3.2.10 (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.

Westinghouse STS 3.3.2-16 Rev. 5.0

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 7 of 11)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

4. Steam Line Isolation

g. High Steam Flow 1,2 (j),3 (j) 2 per D SR 3.3.2.1 [25]% of full [ ] full steam steam line SR 3.3.2.5(b)(c) steam flow at flow at no SR 3.3.2.9(b)(c) no load steam load steam SR 3.3.2.10 pressure pressure Coincident with Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

Safety Injection and Coincident with 1,2 (j),3 (e) (j) [2] per loop D SR 3.3.2.1 [550.6]°F [553]°F Tavg - Low Low SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

h. High High Steam 1,2 (j),3 (j) 2 per D SR 3.3.2.1 [130]% of [ ] of full steam Flow steam line SR 3.3.2.5(b)(c) full steam flow flow at full SR 3.3.2.9(b)(c) at full load load steam SR 3.3.2.10 steam pressure pressure Coincident with Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

Safety Injection (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.

Westinghouse STS 3.3.2-17 Rev. 5.0

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 8 of 11)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

5. Turbine Trip and Feedwater Isolation

a. Automatic 1, 2 (k),[3] (k) 2 trains H[G] SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays

b. SG Water Level - 1,2 (k),[3](k) [3] per SG I[D] SR 3.3.2.1 [84.2]% [82.4]%

High High (P-14) SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

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

6. Auxiliary Feedwater

a. Automatic 1,2,3 2 trains G SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays (Solid State Protection System)

b. Automatic 1,2,3 2 trains G SR 3.3.2.3 NA NA Actuation Logic and Actuation Relays (Balance of Plant ESFAS)

(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.

Westinghouse STS 3.3.2-18 Rev. 5.0

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 9 of 11)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

6. Auxiliary Feedwater

c. SG Water Level - 1,2,3 [3] per SG D SR 3.3.2.1 [30.4]% [32.2]%

Low Low SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10

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

e. Loss of Offsite 1,2,3 [3] per bus F SR 3.3.2.7 [2912] V [2975] V with Power SR 3.3.2.9(b)(c) with 0.8 sec 0.8 sec time SR 3.3.2.10 time delay delay

f. Undervoltage 1,2 [3] per bus I SR 3.3.2.7 [69]% bus [70]% bus Reactor Coolant SR 3.3.2.9(b)(c) voltage voltage Pump SR 3.3.2.10

g. Trip of all Main 1,2 [2] per J SR 3.3.2.8(b)(c) [ ] psig [ ] psig Feedwater pump SR 3.3.2.9(b)(c)

Pumps SR 3.3.2.10

h. Auxiliary 1,2,3 [2] F SR 3.3.2.1 [20.53] [psia] [ ] [psia]

Feedwater Pump SR 3.3.2.7 Suction Transfer SR 3.3.2.9(b)(c) on Suction Pressure - Low

7. Automatic Switchover to Containment Sump

a. Automatic 1,2,3,4 2 trains C SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays (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.

Westinghouse STS 3.3.2-19 Rev. 5.0

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 10 of 11)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

7. Automatic Switchover to Containment Sump

b. Refueling Water 1,2,3,4 4 K SR 3.3.2.1 [15]% and [ ]% and [ ]%

Storage Tank SR 3.3.2.5(b)(c) [ ]%

(RWST) Level - SR 3.3.2.9(b)(c)

SR 3.3.2.10 Low Low Coincident with Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

Safety Injection

c. RWST Level - 1,2,3,4 4 K SR 3.3.2.1 [15]% [18]%

Low Low SR 3.3.2.5(b)(c)

SR 3.3.2.9(b)(c)

SR 3.3.2.10 Coincident with Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

Safety Injection and Coincident with 1,2,3,4 4 K SR 3.3.2.1 [30] in. [ ] in. above Containment SR 3.3.2.5(b)(c) above el. el. [ ]ft Sump Level - SR 3.3.2.9(b)(c) [703] ft SR 3.3.2.10 High (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.

Westinghouse STS 3.3.2-20 Rev. 5.0

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 11 of 11)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER [NOMINAL(l)

SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT]

8. ESFAS Interlocks

a. Reactor Trip, P-4 1,2,3 1 per train, F SR 3.3.2.11 NA NA 2 trains

b. Pressurizer 1,2,3 3 L SR 3.3.2.1 [1996] psig [ ] psig Pressure, P-11 SR 3.3.2.5 SR 3.3.2.9

c. Tavg - Low Low, 1,2,3 [1] per L SR 3.3.2.1 [550.6]°F [553]° F P-12 loop SR 3.3.2.5 SR 3.3.2.9

---

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

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

Westinghouse STS 3.3.2-21 Rev. 5.0

PAM Instrumentation 3.3.3 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 A.1 Restore required channel to 30 days with one required OPERABLE status.

channel inoperable.

B. Required Action and B.1 Initiate action in accordance Immediately associated Completion with Specification 5.6.5.

Time of Condition A not met.

C. One or more Functions C.1 Restore one channel to 7 days with two required OPERABLE status.

channels inoperable.

D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Table 3.3.3-1 Time of Condition C not for the channel.

met.

Westinghouse STS 3.3.3-1 Rev. 5.0

PAM Instrumentation 3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action D.1 and referenced in AND Table 3.3.3-1.

E.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> F. As required by Required F.1 Initiate action in accordance Immediately Action D.1 and with Specification 5.6.5.

referenced in Table 3.3.3-1.

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 [ 31 days instrumentation channel that is normally energized.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.3.3-2 Rev. 5.0

PAM Instrumentation 3.3.3 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 ]

Westinghouse STS 3.3.3-3 Rev. 5.0

PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 1)

Post Accident Monitoring Instrumentation CONDITION REFERENCED FROM REQUIRED FUNCTION REQUIRED CHANNELS ACTION D.1

1. Power Range Neutron Flux 2 E

2. Source Range Neutron Flux 2 E

3. Reactor Coolant System (RCS) Hot Leg 2 per loop E Temperature

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 2 per penetration flow E Position path(a)(b)

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.

Westinghouse STS 3.3.3-4 Rev. 5.0

Remote Shutdown System 3.3.4 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 A.1 Restore required Function 30 days Functions inoperable. to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 [ Perform CHANNEL CHECK for each required [ 31 days instrumentation channel that is normally energized.

OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.3.4-1 Rev. 5.0

Remote Shutdown System 3.3.4 SURVEILLANCE REQUIREMENTS (continued)

SR 3.3.4.2 Verify each required control circuit and transfer [ [18] months switch is capable of performing the intended function. 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 [ [18] months required instrumentation channel.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.3.4.4 [ Perform TADOT of the reactor trip breaker [ 18 months open/closed indication.

OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.3.4-2 Rev. 5.0

LOP DG Start Instrumentation 3.3.5 3.3 INSTRUMENTATION 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation LCO 3.3.5 [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 A.1 --------------NOTE--------------

with one channel per The inoperable channel bus inoperable. may be bypassed for up to

[4] hours for surveillance testing of other channels.

Place channel in trip. [6] hours

[OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.3.5-1 Rev. 5.0

LOP DG Start Instrumentation 3.3.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions B.1 Restore all but one channel 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with two or more per bus to OPERABLE channels per bus status. [OR inoperable.

In accordance with the Risk Informed Completion Time Program]

C. Required Action and C.1 Enter applicable Immediately associated Completion Condition(s) and Required Time not met. Action(s) for the associated DG made inoperable by LOP DG start instrumentation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 [ Perform CHANNEL CHECK. [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.3.5-2 Rev. 5.0

LOP DG Start Instrumentation 3.3.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 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 [ [18] months Trip Setpoint and Allowable Value] as follows:

OR

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

[ ] V with a time delay of [0.8] +/- [ ] second. In accordance with the Loss of voltage Nominal Trip Setpoint [2975] V Surveillance with a time delay of [0.8] [ ] second. ] Frequency Control Program ]

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. ]

Westinghouse STS 3.3.5-3 Rev. 5.0

Containment Purge and Exhaust Isolation Instrumentation 3.3.6 3.3 INSTRUMENTATION 3.3.6 Containment Purge and Exhaust Isolation Instrumentation LCO 3.3.6 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 A.1 Restore the affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> channel inoperable. channel to OPERABLE status.

B. ------------NOTE------------ B.1 Enter applicable Conditions Immediately Only applicable in and Required Actions of MODE 1, 2, 3, or 4. LCO 3.6.3, "Containment

---

Isolation Valves," for containment purge and One or more Functions exhaust isolation valves with one or more manual made inoperable by or automatic actuation isolation instrumentation.

trains inoperable.

OR Two or more radiation monitoring channels inoperable.

OR Required Action and associated Completion Time of Condition A not met.

Westinghouse STS 3.3.6-1 Rev. 5.0

Containment Purge and Exhaust Isolation Instrumentation 3.3.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. ------------NOTE------------ C.1 Place and maintain Immediately Only applicable during containment purge and movement of [recently] exhaust valves in closed irradiated fuel position.

assemblies within containment. OR C.2 Enter applicable Conditions Immediately One or more Functions and Required Actions of with one or more manual LCO 3.9.4, "Containment or automatic actuation Penetrations," for trains inoperable. containment purge and exhaust isolation valves OR made inoperable by isolation instrumentation.

Two or more radiation monitoring channels inoperable.

OR Required Action and associated Completion Time for Condition A not met.

Westinghouse STS 3.3.6-2 Rev. 5.0

Containment Purge and Exhaust Isolation Instrumentation 3.3.6 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 ]

Westinghouse STS 3.3.6-3 Rev. 5.0

Containment Purge and Exhaust Isolation Instrumentation 3.3.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

---

REVIEWERS 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 ]

Westinghouse STS 3.3.6-4 Rev. 5.0

Containment Purge and Exhaust Isolation Instrumentation 3.3.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

---

REVIEWERS 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 ]

Westinghouse STS 3.3.6-5 Rev. 5.0

Containment Purge and Exhaust Isolation Instrumentation 3.3.6 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 ]

Westinghouse STS 3.3.6-6 Rev. 5.0

Containment Purge and Exhaust Isolation Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of 1)

Containment Purge and Exhaust Isolation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS REQUIREMENTS TRIP SETPOINT

1. Manual Initiation 1,2,3,4, (a) 2 SR 3.3.6.8 NA

2. Automatic Actuation Logic and 1,2,3,4, (a) 2 trains SR 3.3.6.2 NA Actuation Relays 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 [2 x background]

SR 3.3.6.6 SR 3.3.6.9

b. Particulate 1,2,3,4, (a) [1] SR 3.3.6.1 [2 x background]

SR 3.3.6.6 SR 3.3.6.9

c. Iodine 1,2,3,4, (a) [1] SR 3.3.6.1 [2 x background]

SR 3.3.6.6 SR 3.3.6.9

d. Area Radiation 1,2,3,4, (a) [1] SR 3.3.6.1 [2 x background] ]

SR 3.3.6.6 SR 3.3.6.9

4. Containment Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 3.a., for all Isolation - Phase A initiation functions and requirements.

(a) During movement of [recently] irradiated fuel assemblies within containment.

Westinghouse STS 3.3.6-7 Rev. 5.0

CREFS Actuation Instrumentation 3.3.7 3.3 INSTRUMENTATION 3.3.7 Control Room Emergency Filtration System (CREFS) Actuation Instrumentation LCO 3.3.7 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 A.1 --------------NOTE--------------

with one channel or train [ Place in toxic gas inoperable. protection mode if automatic transfer to toxic gas protection mode is inoperable. ]

Place one CREFS train in 7 days emergency [radiation protection] mode.

B. One or more Functions --------------------NOTE-------------------

with two channels or two [ Place in the toxic gas protection trains inoperable. mode if automatic transfer to toxic gas protection mode is inoperable. ]

B.1.1 Place one CREFS train in Immediately emergency [radiation protection] mode.

AND Westinghouse STS 3.3.7-1 Rev. 5.0

CREFS Actuation Instrumentation 3.3.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.1.2 Enter applicable Conditions Immediately and Required Actions for one CREFS train made inoperable by inoperable CREFS actuation instrumentation.

OR B.2 Place both trains in Immediately emergency [radiation protection] mode.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time for Condition A AND or B not met in MODE 1, 2, 3, or 4. C.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D. Required Action and D.1 Suspend movement of Immediately associated Completion [recently] irradiated fuel Time for Condition A assemblies.

or B not met during movement of [recently]

irradiated fuel assemblies.

E. [ Required Action and E.1 Initiate action to restore one Immediately ]

associated Completion CREFS train to OPERABLE Time for Condition A status.

or B not met in MODE 5 or 6.

Westinghouse STS 3.3.7-2 Rev. 5.0

CREFS Actuation Instrumentation 3.3.7 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 ]

Westinghouse STS 3.3.7-3 Rev. 5.0

CREFS Actuation Instrumentation 3.3.7 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 ]

---

REVIEWERS 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 ]

Westinghouse STS 3.3.7-4 Rev. 5.0

CREFS Actuation Instrumentation 3.3.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

---

REVIEWERS 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 ]

Westinghouse STS 3.3.7-5 Rev. 5.0

CREFS Actuation Instrumentation 3.3.7 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 ]

Westinghouse STS 3.3.7-6 Rev. 5.0

CREFS Actuation Instrumentation 3.3.7 Table 3.3.7-1 (page 1 of 1)

CREFS Actuation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS REQUIREMENTS TRIP SETPOINT

1. Manual Initiation 1, 2, 3, 4, [5, 2 trains SR 3.3.7.8 NA 6], (a)

2. Automatic Actuation Logic 1, 2, 3, 4, [5, 2 trains SR 3.3.7.3 NA and Actuation Relays 6], (a) 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 1, 2, 3, 4 [5, [2] SR 3.3.7.1 [2] mR/hr Atmosphere 6], (a) SR 3.3.7.2 SR 3.3.7.9

b. Control Room Air Intakes 1, 2, 3, 4, [5, [2] SR 3.3.7.1 [2] mR/hr 6], (a) SR 3.3.7.2 SR 3.3.7.9

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.

Westinghouse STS 3.3.7-7 Rev. 5.0

FBACS Actuation Instrumentation 3.3.8 3.3 INSTRUMENTATION 3.3.8 Fuel Building Air Cleanup System (FBACS) Actuation Instrumentation LCO 3.3.8 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 A.1 Place one FBACS train in 7 days with one channel or train operation.

inoperable.

B. One or more Functions B.1.1 Place one FBACS train in Immediately with two channels or two operation.

trains inoperable.

AND B.1.2 Enter applicable Conditions Immediately 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 Immediately emergency [radiation protection] mode.

Westinghouse STS 3.3.8-1 Rev. 5.0

FBACS Actuation Instrumentation 3.3.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Suspend movement of Immediately associated Completion [recently] irradiated fuel Time for Condition A assemblies in the fuel or B not met during building.

movement of [recently]

irradiated fuel assemblies in the fuel building.

D. [ Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time for Condition A AND or B not met in MODE 1, 2, 3, or 4. D.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ]

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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.3.8-2 Rev. 5.0

FBACS Actuation Instrumentation 3.3.8 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 ]

Westinghouse STS 3.3.8-3 Rev. 5.0

FBACS Actuation Instrumentation 3.3.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.8.5 Perform CHANNEL CALIBRATION. [ [18] months OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.3.8-4 Rev. 5.0

FBACS Actuation Instrumentation 3.3.8 Table 3.3.8-1 (page 1 of 1)

FBACS Actuation Instrumentation APPLICABLE MODES OR SPECIFIED REQUIRED SURVEILLANCE TRIP FUNCTION CONDITIONS CHANNELS REQUIREMENTS SETPOINT

1. Manual Initiation [1,2,3,4], (a) 2 SR 3.3.8.4 NA

2. [ Automatic Actuation Logic 1,2,3,4, (a) 2 trains SR 3.3.8.3 NA ]

and Actuation Relays

3. Fuel Building Radiation

a. Gaseous [1,2,3,4], (a) [2] SR 3.3.8.1 [2] mR/hr SR 3.3.8.2 SR 3.3.8.5

b. Particulate [1,2,3,4], (a) [2] SR 3.3.8.1 [2] mR/hr SR 3.3.8.2 SR 3.3.8.5 (a) During movement of [recently] irradiated fuel assemblies in the fuel building.

Westinghouse STS 3.3.8-5 Rev. 5.0

BDPS 3.3.9 3.3 INSTRUMENTATION 3.3.9 Boron Dilution Protection System (BDPS)

LCO 3.3.9 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 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. Two trains inoperable. B.1 --------------NOTE--------------

Plant temperature changes OR are allowed provided the temperature change is Required Action and accounted for in the associated Completion calculated SDM.

Time of Condition A not -------------------------------------

met.

Suspend operations Immediately involving positive reactivity additions.

AND Westinghouse STS 3.3.9-1 Rev. 5.0

BDPS 3.3.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2.1 Restore one train to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OPERABLE status.

OR B.2.2.1 Close unborated water 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> source isolation valves.

AND B.2.2.2 Perform SR 3.1.1.1. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.9.1 Perform CHANNEL CHECK. [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 ]

Westinghouse STS 3.3.9-2 Rev. 5.0

BDPS 3.3.9 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 ]

Westinghouse STS 3.3.9-3 Rev. 5.0

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 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 A.1 Restore RCS DNB 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> parameters not within parameter(s) to within limit.

limits.

B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

Westinghouse STS 3.4.1-1 Rev. 5.0

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is greater than or equal [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to the limit specified in the COLR.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.1.2 Verify RCS average temperature is less than or [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> equal to the limit specified in the COLR.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.1.3 Verify RCS total flow rate is [284,000] gpm and [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> greater than or equal to the limit specified in the COLR. OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.1-2 Rev. 5.0

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.1.4 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after

[90]% RTP.

Verify by precision heat balance that RCS total flow [ [18] months rate is [284,000] gpm and greater than or equal to the limit specified in the COLR. OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.1-3 Rev. 5.0

RCS Minimum Temperature for Criticality 3.4.2 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 A.1 Be in MODE 2 with Keff 30 minutes loops not within limit. < 1.0.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS Tavg in each loop [541]°F. [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.2-1 Rev. 5.0

RCS P/T Limits 3.4.3 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------------ A.1 Restore parameter(s) to 30 minutes Required Action A.2 within limits.

shall be completed whenever this Condition AND is entered.

---

A.2 Determine RCS is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> acceptable for continued Requirements of operation.

LCO not met in MODE 1, 2, 3, or 4.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5 with RCS 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> pressure < [500] psig.

C. ------------NOTE------------ C.1 Initiate action to restore Immediately Required Action C.2 parameter(s) to within shall be completed limits.

whenever this Condition is entered. AND C.2 Determine RCS is Prior to entering Requirements of acceptable for continued MODE 4 LCO not met any time in operation.

other than MODE 1, 2, 3, or 4.

Westinghouse STS 3.4.3-1 Rev. 5.0

RCS P/T Limits 3.4.3 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 [ 30 minutes heatup and cooldown rates are within the limits specified in the PTLR. OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.3-2 Rev. 5.0

RCS Loops - MODES 1 and 2 3.4.4 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 A.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> LCO not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation. [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.4-1 Rev. 5.0

RCS Loops - MODE 3 3.4.5 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 A.1 Restore required RCS loop 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. to OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. Required Action and B.1 Be in MODE 4. 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not met.

Westinghouse STS 3.4.5-1 Rev. 5.0

RCS Loops - MODE 3 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. [ One required RCS loop C.1 Restore required RCS loop 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> not in operation with Rod to operation.

Control System capable [OR of rod withdrawal.

In accordance with the Risk Informed Completion Time Program]

OR 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C.2 Place the Rod Control System in a condition [OR incapable of rod withdrawal.

In accordance with the Risk Informed Completion Time Program]

D. [Two] [required] RCS D.1 Place the Rod Control Immediately loops inoperable. System in a condition incapable of rod withdrawal.

OR AND Required RCS loop(s) not in operation. D.2 Suspend operations that Immediately 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 Immediately one RCS loop to OPERABLE status and operation.

Westinghouse STS 3.4.5-2 Rev. 5.0

RCS Loops - MODE 3 3.4.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify required RCS loops are in operation. [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.5.2 Verify steam generator secondary side water levels [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> are [17]% for required RCS loops.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.5.3 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a required pump is not in operation.

Verify correct breaker alignment and indicated [ 7 days power are available to each required pump.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.5-3 Rev. 5.0

RCS Loops - MODE 4 3.4.6 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 A.1 Initiate action to restore a Immediately inoperable. second loop to OPERABLE status.

AND Westinghouse STS 3.4.6-1 Rev. 5.0

RCS Loops - MODE 4 3.4.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2 --------------NOTE--------------

Only required if RHR loop is OPERABLE.

Be in MODE 5. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B. Two required loops B.1 Suspend operations that Immediately inoperable. would cause introduction of coolant into the RCS with OR boron concentration less than required to meet SDM Required loop not in of LCO 3.1.1.

operation.

AND B.2 Initiate action to restore one Immediately loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify required RHR or RCS loop is in operation. [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.6-2 Rev. 5.0

RCS Loops - MODE 4 3.4.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.6.2 Verify SG secondary side water levels are [17]% [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for required RCS loops.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.6.3 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a required pump is not in operation.

Verify correct breaker alignment and indicated [ 7 days power are available to each required pump.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.6.4 -------------------------------NOTE------------------------------ [ 31 days Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 4. OR In accordance Verify required RHR loop locations susceptible to with the gas accumulation are sufficiently filled with water. Surveillance Frequency Control Program ]

Westinghouse STS 3.4.6-3 Rev. 5.0

RCS Loops - MODE 5, Loops Filled 3.4.7 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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.

Westinghouse STS 3.4.7-1 Rev. 5.0

RCS Loops - MODE 5, Loops Filled 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required RHR loop A.1 Initiate action to restore a Immediately inoperable. second RHR loop to OPERABLE status.

AND OR One RHR loop OPERABLE. A.2 Initiate action to restore Immediately required SGs secondary side water level to within limit.

B. One or more required B.1 Initiate action to restore a Immediately SGs with secondary side second RHR loop to water level not within OPERABLE status.

limit.

OR AND B.2 Initiate action to restore Immediately One RHR loop required SGs secondary OPERABLE. side water level to within limit.

C. No required RHR loops C.1 Suspend operations that Immediately OPERABLE. would cause introduction of coolant into the RCS with OR boron concentration less than required to meet SDM Required RHR loop not of LCO 3.1.1.

in operation.

AND C.2 Initiate action to restore one Immediately RHR loop to OPERABLE status and operation.

Westinghouse STS 3.4.7-2 Rev. 5.0

RCS Loops - MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify required RHR loop is in operation. [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.7.2 Verify SG secondary side water level is [17]% in [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> required SGs.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.7.3 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a required pump is not in operation.

Verify correct breaker alignment and indicated [ 7 days power are available to each required RHR pump.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.7-3 Rev. 5.0

RCS Loops - MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.7.4 Verify required RHR loop locations susceptible to [ 31 days gas accumulation are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.7-4 Rev. 5.0

RCS Loops - MODE 5, Loops Not Filled 3.4.8 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 A.1 Initiate action to restore Immediately inoperable. RHR loop to OPERABLE status.

Westinghouse STS 3.4.8-1 Rev. 5.0

RCS Loops - MODE 5, Loops Not Filled 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No required RHR loop B.1 Suspend operations that Immediately OPERABLE. would cause introduction of coolant into the RCS with OR boron concentration less than required to meet SDM Required RHR loop not of LCO 3.1.1.

in operation.

AND B.2 Initiate action to restore one Immediately RHR loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify required RHR loop is in operation. [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.8-2 Rev. 5.0

RCS Loops - MODE 5, Loops Not Filled 3.4.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.8.2 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a required pump is not in operation.

Verify correct breaker alignment and indicated [ 7 days power are available to each required RHR pump.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.8.3 Verify RHR loop locations susceptible to gas [ 31 days accumulation are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.8-3 Rev. 5.0

Pressurizer 3.4.9 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 A.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> not within limit.

AND A.2 Fully insert all rods. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND A.3 Place Rod Control System 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> in a condition incapable of rod withdrawal.

AND A.4 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B. One [required] group of B.1 Restore [required] group of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> pressurizer heaters pressurizer heaters to inoperable. OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.4.9-1 Rev. 5.0

Pressurizer 3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition B not AND met.

C.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level is [92]%. [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 [ [18] months heaters is [125] kW.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.9-2 Rev. 5.0

Pressurizer 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.3 [ Verify required pressurizer heaters are capable of [ [18] months being powered from an emergency power supply.

OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.4.9-3 Rev. 5.0

Pressurizer Safety Valves 3.4.10 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 A.1 Restore valve to 15 minutes valve inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND OR B.2 Be in MODE 4 with any [24] hours RCS cold leg temperatures Two or more pressurizer [275F] [LTOP arming safety valves inoperable. temperature specified in the PTLR].

Westinghouse STS 3.4.10-1 Rev. 5.0

Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is OPERABLE In accordance in accordance with the INSERVICE TESTING with the PROGRAM. Following testing, lift settings shall be INSERVICE within +/- 1%. TESTING PROGRAM Westinghouse STS 3.4.10-2 Rev. 5.0

Pressurizer PORVs 3.4.11 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 A.1 Close and maintain power 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable and capable to associated block valve.

of being manually cycled.

B. One [or two] PORV[s] B.1 Close associated block 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable and not valve[s].

capable of being manually cycled. AND B.2 Remove power from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated block valve[s].

AND B.3 Restore PORV[s] to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.4.11-1 Rev. 5.0

Pressurizer PORVs 3.4.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One [or two] block --------------------NOTE-------------------

valve(s) inoperable. 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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> manual control.

AND C.2 Restore block valve to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A, B, AND or C not met.

D.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> E. Two [or three] PORVs E.1 Close associated block 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable and not valves.

capable of being manually cycled. AND E.2 Remove power from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated block valves.

AND E.3 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND E.4 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.4.11-2 Rev. 5.0

Pressurizer PORVs 3.4.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two [or three] block F.1 --------------NOTE--------------

valves inoperable. 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 [2 hours]

OPERABLE status [if three block valves are inoperable].

G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition F not AND met.

G.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.4.11-3 Rev. 5.0

Pressurizer PORVs 3.4.11 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 [ [18] months control valve and check valve on the air accumulators in PORV control systems. OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.4.11-4 Rev. 5.0

Pressurizer PORVs 3.4.11 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.11.4 [ Verify PORVs and block valves are capable of [ [18] months being powered from emergency power sources.

OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.4.11-5 Rev. 5.0

LTOP System 3.4.12 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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.

Westinghouse STS 3.4.12-1 Rev. 5.0

LTOP System 3.4.12 ACTIONS

---

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

LCO 3.0.4.b is not applicable when entering MODE 4.

CONDITION REQUIRED ACTION COMPLETION TIME A. Two or more [HPI] A.1 Initiate action to verify a Immediately pumps capable of maximum of [one] [HPI]

injecting into the RCS. pump is capable of injecting into the RCS.

B. [ Two or more charging B.1 Initiate action to verify a Immediately ]

pumps capable of maximum of [one] charging injecting into the RCS. pump is capable of injecting into the RCS.

C. An accumulator not C.1 Isolate affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> isolated when the accumulator.

accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

D. Required Action and D.1 Increase RCS cold leg 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion temperature to > [275°F]

Time of Condition [C] not [LTOP arming temperature met. specified in the PTLR].

OR D.2 Depressurize affected 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> accumulator to less than the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

E. One required RCS relief E.1 Restore required RCS relief 7 days valve inoperable in valve to OPERABLE status.

MODE 4.

Westinghouse STS 3.4.12-2 Rev. 5.0

LTOP System 3.4.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. One required RCS relief F.1 Restore required RCS relief 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> valve inoperable in valve to OPERABLE status.

MODE 5 or 6.

G. Two required RCS relief G.1 Depressurize RCS and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> valves inoperable. establish RCS vent of

[2.07] square inches.

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.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify a maximum of [one] [HPI] pump is capable of [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> injecting into the RCS.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.12-3 Rev. 5.0

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.12.2 [ Verify a maximum of one charging pump is [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> capable of injecting into the RCS.

OR In accordance with the Surveillance Frequency Control Program ] ]

SR 3.4.12.3 Verify each accumulator is isolated. [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.12.4 [ Verify RHR suction valve is open for each required [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> RHR suction relief valve.

OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.4.12-4 Rev. 5.0

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.12.5 Verify required RCS vent [2.07] square inches [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for open. 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 [ 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> PORV.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.12.7 [ Verify associated RHR suction isolation valve is [ 31 days locked open with operator power removed for each required RHR suction relief valve. OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.4.12-5 Rev. 5.0

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.12.8 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after decreasing RCS cold leg temperature to [275°F]

[LTOP arming temperature specified in the PTLR].

Perform a COT on each required PORV, excluding [ 31 days actuation.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.12.9 Perform CHANNEL CALIBRATION for each [ [18] months required PORV actuation channel.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.12-6 Rev. 5.0

RCS Operational LEAKAGE 3.4.13 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. Pressure boundary A.1 Isolate affected component, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> LEAKAGE exists. pipe, or vessel from the RCS by use of a closed manual valve, closed and de-activated automatic valve, blind flange, or check valve.

B. RCS operational B.1 Reduce LEAKAGE to within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> LEAKAGE not within limits.

limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.

Westinghouse STS 3.4.13-1 Rev. 5.0

RCS Operational LEAKAGE 3.4.13 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND OR C.2 --------------NOTE--------------

LCO 3.0.4.a is not Primary to secondary applicable when entering LEAKAGE not within MODE 4.

limit. -------------------------------------

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 ------------------------------NOTES-----------------------------

1. Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.

2. Not applicable to primary to secondary LEAKAGE.

Verify RCS operational LEAKAGE is within limits by [ 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> performance of RCS water inventory balance.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.13-2 Rev. 5.0

RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.13.2 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.

Verify primary to secondary LEAKAGE is [ 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 150 gallons per day through any one SG.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.13-3 Rev. 5.0

RCS PIV Leakage 3.4.14 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 --------------------NOTE-------------------

with leakage from one or Each valve used to satisfy Required more RCS PIVs not Action A.1 and Required Action A.2 within limit. 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 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> portion of the affected system from the low pressure portion by use of one closed manual, deactivated automatic, or check valve.

AND Westinghouse STS 3.4.14-1 Rev. 5.0

RCS PIV Leakage 3.4.14 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2 [ Isolate the high pressure 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ]

limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time for Condition A not AND met.

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

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> C. [ RHR System C.1 Isolate the affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ]

autoclosure interlock penetration by use of one function inoperable. closed manual or deactivated automatic valve.

Westinghouse STS 3.4.14-2 Rev. 5.0

RCS PIV Leakage 3.4.14 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 In accordance 0.5 gpm per nominal inch of valve size up to a with the maximum of 5 gpm at an RCS pressure INSERVICE

[2215] psig and [2255] psig. 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 Westinghouse STS 3.4.14-3 Rev. 5.0

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 [ [18] months the valves from being opened with a simulated or actual RCS pressure signal [425] psig. 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 [ [18] months valves to close automatically with a simulated or actual RCS pressure signal [600] psig. OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.4.14-4 Rev. 5.0

RCS Leakage Detection Instrumentation 3.4.15 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 A.1 --------------NOTE--------------

sump monitor Not required until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> inoperable. after establishment of steady state operation.

Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND A.2 Restore required 30 days containment sump monitor to OPERABLE status.

Westinghouse STS 3.4.15-1 Rev. 5.0

RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required containment B.1.1 Analyze grab samples of Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> atmosphere radioactivity the containment monitor inoperable. atmosphere.

OR B.1.2 --------------NOTE--------------

Not required until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.

Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND B.2.1 Restore required 30 days containment atmosphere radioactivity monitor to OPERABLE status.

OR

[ B.2.2 Verify containment air 30 days cooler condensate flow rate monitor is OPERABLE.

C. [ Containment air cooler C.1 Perform SR 3.4.15.1. Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> condensate flow rate monitor inoperable. OR C.2 --------------NOTE--------------

Not required until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.

Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ]

Westinghouse STS 3.4.15-2 Rev. 5.0

RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

---

NOTE -------------- D.1 Analyze grab samples of Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Only applicable when the the containment containment atmosphere atmosphere.

gaseous radiation monitor is the only OPERABLE AND monitor.

---

D.2.1 Restore required 7 days containment sump monitor D. Required containment to OPERABLE status.

sump monitor inoperable. OR AND [ D.2.2 Restore containment air 7 days cooler condensate flow rate

[ Containment air cooler monitor to OPERABLE condensate flow rate status. ]

monitor inoperable. ]

E. [ Required containment E.1 Restore required 30 days atmosphere radioactivity containment atmosphere monitor inoperable. radioactivity monitor to OPERABLE status.

AND OR

[ Containment air cooler condensate flow rate [ E.2 Restore containment air 30 days ]

monitor inoperable. ] cooler condensate flow rate monitor to OPERABLE status. ]

F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND F.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.4.15-3 Rev. 5.0

RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. All required monitors G.1 Enter LCO 3.0.3. Immediately inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the required [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> containment atmosphere radioactivity monitor.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.15.2 Perform COT of the required containment [ 92 days atmosphere radioactivity monitor.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.15-4 Rev. 5.0

RCS Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required [ [18] months containment sump monitor.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.15.4 [ Perform CHANNEL CALIBRATION of the required [ [18] months containment atmosphere radioactivity monitor.

OR In accordance with the Surveillance Frequency Control Program ] ]

SR 3.4.15.5 [ Perform CHANNEL CALIBRATION of the required [ [18] months containment air cooler condensate flow rate monitor.

OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.4.15-5 Rev. 5.0

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 RCS DOSE EQUIVALENT I-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE --------------------NOTE-------------------

EQUIVALENT I-131 not LCO 3.0.4.c is applicable.

within limit. ------------------------------------------------

A.1 Verify DOSE Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> EQUIVALENT I-131

[60] Ci/gm.

AND A.2 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT I-131 to within limit.

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

EQUIVALENT XE-133 LCO 3.0.4.c is applicable.

not within limit. ------------------------------------------------

B.1 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT XE-133 to within limit.

Westinghouse STS 3.4.16-1 Rev. 5.0

RCS Specific Activity 3.4.16 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B AND not met.

C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR DOSE EQUIVALENT I-131

> [60] Ci/gm.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 -------------------------------NOTE------------------------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT XE-133 [ 7 days specific activity [280] µCi/gm.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.16-2 Rev. 5.0

RCS Specific Activity 3.4.16 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 [ 14 days specific activity [1.0] µCi/gm.

OR In accordance with the Surveillance Frequency Control Program ]

AND Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Westinghouse STS 3.4.16-3 Rev. 5.0

RCS Loop Isolation Valves 3.4.17 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 A.1 Remove power from loop 30 minutes or more loop isolation isolation valve operators.

valve operators.

B. ------------NOTE------------ B.1 Maintain valve(s) closed. Immediately All Required Actions shall be completed AND whenever this Condition is entered. B.2 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND One or more RCS loop isolation valves closed. B.3 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Westinghouse STS 3.4.17-1 Rev. 5.0

RCS Loop Isolation Valves 3.4.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify each RCS loop isolation valve is open and [ 31 days power is removed from each loop isolation valve operator. OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.4.17-2 Rev. 5.0

RCS Isolated Loop Startup 3.4.18 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 A.1 --------------NOTE--------------

leg isolation valve open Only required if boron with LCO requirements concentration requirement not met. not met.

Close hot and cold leg Immediately isolation valves.

OR A.2 --------------NOTE--------------

Only required if temperature requirement not met.

Close cold leg isolation Immediately valve.

Westinghouse STS 3.4.18-1 Rev. 5.0

RCS Isolated Loop Startup 3.4.18 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.18.1 Verify cold leg temperature of isolated loop is Within 30 minutes

[20]°F below the highest cold leg temperature of prior to opening the operating loops. the cold leg isolation valve in isolated loop SR 3.4.18.2 Verify boron concentration of isolated loop is greater Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> than or equal to the boron concentration required to prior to opening meet the SDM of LCO 3.1.1 or boron concentration the hot or cold leg of LCO 3.9.1. isolation valve in isolated loop Westinghouse STS 3.4.18-2 Rev. 5.0

RCS Loops - Test Exceptions 3.4.19 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 A.1 Open reactor trip breakers. Immediately P-7.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.19.1 Verify THERMAL POWER is < P-7. [ 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.19.2 Perform a COT for each power range neutron flux - Prior to initiation low channel, intermediate range neutron flux of startup and channel, P-10, and P-13. PHYSICS TESTS SR 3.4.19.3 Perform an ACTUATION LOGIC TEST on P-7. Prior to initiation of startup and PHYSICS TESTS Westinghouse STS 3.4.19-1 Rev. 5.0

SG Tube Integrity 3.4.20 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 plugging [or 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 A.1 Verify tube integrity of the 7 days satisfying the tube affected tube(s) is plugging [or repair] maintained until the next criteria and not plugged refueling outage or SG tube

[or repaired] in inspection.

accordance with the Steam Generator AND Program.

A.2 Plug [or repair] the affected Prior to entering tube(s) in accordance with MODE 4 following the the Steam Generator next refueling outage Program. or SG tube inspection B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR SG tube integrity not maintained.

Westinghouse STS 3.4.20-1 Rev. 5.0

SG Tube Integrity 3.4.20 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.20.1 Verify SG tube integrity in accordance with the In accordance Steam Generator Program. with the Steam Generator Program SR 3.4.20.2 Verify that each inspected SG tube that satisfies the Prior to entering tube plugging [or repair] criteria is plugged [or MODE 4 following repaired] in accordance with the Steam Generator a SG tube Program. inspection Westinghouse STS 3.4.20-2 Rev. 5.0

Accumulators 3.5.1 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 A.1 Restore boron 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable due to boron concentration to within concentration not within limits.

limits.

B. One accumulator B.1 Restore accumulator to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable for reasons OPERABLE status.

other than Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B AND not met.

C.2 Reduce RCS pressure to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

[1000] psig.

D. Two or more D.1 Enter LCO 3.0.3. Immediately accumulators inoperable.

Westinghouse STS 3.5.1-1 Rev. 5.0

Accumulators 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator isolation valve is fully open. [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance Frequency Control Program ]

SR 3.5.1.2 Verify borated water volume in each accumulator is [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

[ 7853 gallons ( )% and 8171 gallons ( )%].

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.5.1.3 Verify nitrogen cover pressure in each accumulator [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is [385] psig and [481] psig.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.5.1-2 Rev. 5.0

Accumulators 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.4 Verify boron concentration in each accumulator is [ 31 days

[1900] ppm and [2100] ppm.

OR In accordance with the Surveillance Frequency Control Program ]

AND

---

NOTE--------

Only required to be performed for affected accumulators Once within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 [ 31 days isolation valve operator when RCS pressure is

[2000] psig. OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.5.1-3 Rev. 5.0

ECCS - Operating 3.5.2 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 A.1 Restore train(s) to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.5.2-1 Rev. 5.0

ECCS - Operating 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Less than 100% of the C.1 Enter LCO 3.0.3. Immediately ECCS flow equivalent to a single OPERABLE ECCS train available.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 [ Verify the following valves are in the listed position [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with power to the valve operator removed.

OR Number Position Function

[ ] [ ] [ ] In accordance

[ ] [ ] [ ] with the

[ ] [ ] [ ] Surveillance Frequency Control Program ]

SR 3.5.2.2 ---------------------------------NOTE----------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each ECCS manual, power operated, and [ 31 days automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the OR correct position.

In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.5.2-2 Rev. 5.0

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify ECCS locations susceptible to gas [ 31 days accumulation are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.5.2.4 Verify each ECCS pump's developed head at the In accordance test flow point is greater than or equal to the with the required developed head. INSERVICE TESTING PROGRAM SR 3.5.2.5 Verify each ECCS automatic valve in the flow path [ [18] months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an OR actual or simulated actuation signal.

In accordance with the Surveillance Frequency Control Program ]

SR 3.5.2.6 Verify each ECCS pump starts automatically on an [ [18] months actual or simulated actuation signal.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.5.2-3 Rev. 5.0

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.7 [ Verify, for each ECCS throttle valve listed below, [ [18] months each position stop is in the correct position.

OR Valve Number

[ ] In accordance

[ ] with the

[ ] Surveillance Frequency Control Program ] ]

Westinghouse STS 3.5.2-4 Rev. 5.0

ECCS - Shutdown 3.5.3 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 train A.1 -------------- NOTE -------------

inoperable. LCO 3.0.4.a is not applicable when entering MODE 4.

Initiate action to restore Immediately required ECCS train to OPERABLE status.

Westinghouse STS 3.5.3-1 Rev. 5.0

ECCS - Shutdown 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 The following SRs are applicable for all equipment In accordance required to be OPERABLE: with applicable SRs

[SR 3.5.2.1] [SR 3.5.2.7]

[SR 3.5.2.3]

SR 3.5.2.4 Westinghouse STS 3.5.3-2 Rev. 5.0

RWST 3.5.4 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 A.1 Restore RWST to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> concentration not within OPERABLE status.

limits.

OR RWST borated water temperature not within limits.

B. RWST inoperable for B.1 Restore RWST to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> reasons other than OPERABLE status.

Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND C.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.5.4-1 Rev. 5.0

RWST 3.5.4 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 [ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and [100]°F.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.5.4.2 Verify RWST borated water volume is [466,200 [ 7 days gallons ( )%].

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.5.4.3 Verify RWST boron concentration is [2000] ppm [ 7 days and [2200] ppm.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.5.4-2 Rev. 5.0

Seal Injection Flow 3.5.5 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 A.1 Adjust manual seal injection 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

[resistance] not within throttle valves to give a flow limit. [resistance] within limit.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.5.5-1 Rev. 5.0

Seal Injection Flow 3.5.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.5.1 -------------------------------NOTE------------------------------

Not required to be performed until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the Reactor Coolant System pressure stabilizes at

[2215 psig and 2255 psig].

Verify manual seal injection throttle valves are [ 31 days adjusted to give a flow [resistance] [of [40 gpm]

with [centrifugal charging pump discharge header] OR pressure [2480] psig and the [charging flow]

control valve full open or [0.2117] ft/gpm2 or within In accordance the limit of Figure 3.5.5-1.] with the Surveillance Frequency Control Program ]

Westinghouse STS 3.5.5-2 Rev. 5.0

Seal Injection Flow 3.5.5 For illustration only. Do not use for operation.

Figure 3.5.5-1 (page 1 of 1)

Seal Injection Flow Limits Westinghouse STS 3.5.5-3 Rev. 5.0

BIT 3.5.6 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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.

B.2 Borate to SDM specified in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> COLR.

AND B.3 Restore BIT to OPERABLE 7 days status.

C. Required Action and C.1 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition B not met.

Westinghouse STS 3.5.6-1 Rev. 5.0

BIT 3.5.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.6.1 Verify BIT borated water temperature is [145]°F. [ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OR In accordance with the Surveillance Frequency Control Program ]

SR 3.5.6.2 [ Verify BIT borated water volume is [ 7 days

[1100] gallons.

OR In accordance with the Surveillance Frequency Control Program ] ]

SR 3.5.6.3 Verify BIT boron concentration is [20,000] ppm [ 7 days and [22,500] ppm.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.5.6-2 Rev. 5.0

Containment (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.1 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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1 Perform required visual examinations and leakage In accordance rate testing except for containment air lock testing, with the in accordance with the Containment Leakage Rate Containment Testing Program. Leakage Rate Testing Program SR 3.6.1.2 [ Verify containment structural integrity in In accordance accordance with the Containment Tendon with the Surveillance Program. Containment Tendon Surveillance Program ]

Westinghouse STS 3.6.1-1 Rev. 5.0

Containment Air Locks (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.2 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 --------------------NOTES-----------------

containment air locks 1. Required Actions A.1, A.2, with one containment air and A.3 are not applicable if lock door inoperable. 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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is closed in the affected air lock.

AND Westinghouse STS 3.6.2-1 Rev. 5.0

Containment Air Locks (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2 Lock the OPERABLE door 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 Once per 31 days is locked closed in the affected air lock.

B. One or more -------------------NOTES------------------

containment air locks 1. Required Actions B.1, B.2, with containment air lock and B.3 are not applicable if interlock mechanism both doors in the same air lock inoperable. 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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is closed in the affected air lock.

AND Westinghouse STS 3.6.2-2 Rev. 5.0

Containment Air Locks (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2 Lock an OPERABLE door 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 Once per 31 days is locked closed in the affected air lock.

C. One or more C.1 Initiate action to evaluate Immediately containment air locks overall containment inoperable for reasons leakage rate per LCO 3.6.1.

other than Condition A or B. AND C.2 Verify a door is closed in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> the affected air lock.

AND C.3 Restore air lock to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Westinghouse STS 3.6.2-3 Rev. 5.0

Containment Air Locks (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.2 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 In accordance accordance with the Containment Leakage Rate with the Testing Program. Containment Leakage Rate Testing Program SR 3.6.2.2 [ Verify only one door in the air lock can be opened [ 24 months at a time.

OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.6.2-4 Rev. 5.0

Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 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.

Westinghouse STS 3.6.3-1 Rev. 5.0

Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. [ One or more A.1 Isolate the affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for penetration flow paths penetration flow path by Category 1 CIVs with one containment use of at least one closed isolation valve and de-activated automatic AND inoperable [for reasons valve, closed manual valve, other than Condition[s] E blind flange, or check valve 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for

[and F)). with flow through the valve Category 2 CIVs secured.

AND AND Containment isolation 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for valve pressure boundary Category 3 CIVs intact.

AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Category 4 CIVs AND 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for Category 5 CIVs AND 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for Category 6 CIVs AND 7 days for Category 7 CIVs

[OR In accordance with the Risk Informed Completion Time Program]

AND Westinghouse STS 3.6.3-2 Rev. 5.0

Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 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 Once per 31 days penetration flow path is [following isolation]

isolated. 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 ]

Westinghouse STS 3.6.3-3 Rev. 5.0

Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. [ One or more B.1 Isolate the affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for penetration flow paths penetration flow path by Category 8 CIVs with one containment use of at least one closed isolation valve and de-activated AND inoperable [for reasons automatic valve, closed other than Condition[s] E manual valve, blind 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for

[and F)). flange, or check valve Category 9 CIVs with flow through the AND valve secured. AND Containment isolation 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for valve pressure boundary Category 10 CIVs not intact.

AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Category 11 CIVs AND 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for Category 12 CIVs AND 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for Category 13 CIVs AND 7 days for Category 14 CIVs

[OR In accordance with the Risk Informed Completion Time Program]

AND Westinghouse STS 3.6.3-4 Rev. 5.0

Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 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 Once per 31 days penetration flow path is [following isolation]

isolated. 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 ]

Westinghouse STS 3.6.3-5 Rev. 5.0

Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. ------------NOTE------------ C.1 Isolate the affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Only applicable to penetration flow path by penetration flow paths use of at least one closed with two [or more] and de-activated automatic containment isolation valve, closed manual valve, valves. or blind flange.

One or more penetration flow paths with two [or more] containment isolation valves inoperable [for reasons other than Condition[s] E

[and F)).

D. Two or more penetration D.1 Isolate all but one 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> flow paths with one penetration flow path by containment isolation use of at least one closed valve inoperable [for and de-activated automatic reasons other than valve, closed manual valve, Condition[s] E [and F)). or blind flange.

E. [ One or more shield E.1 Restore leakage within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for shield building bypass leakage limit. building bypass

[or purge valve leakage] leakage not within limit.

AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for purge valve leakage ]

F. [ One or more F.1 Isolate the affected 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> penetration flow paths penetration flow path by with one or more use of at least one [closed containment purge and de-activated automatic valves not within purge valve, closed manual valve, valve leakage limits. or blind flange].

AND Westinghouse STS 3.6.3-6 Rev. 5.0

Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 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 Once per 31 days for penetration flow path is isolation devices isolated. outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment AND F.3 Perform SR 3.6.3.7 for the Once per [92] days ]

resilient seal purge valves closed to comply with Required Action F.1.

G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND G.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Westinghouse STS 3.6.3-7 Rev. 5.0

Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1 [ Verify each [42] inch purge valve is sealed closed, [ 31 days except for one purge valve in a penetration flow path while in Condition E of this LCO. OR In accordance with the Surveillance Frequency Control Program ] ]

SR 3.6.3.2 [ Verify each [8] inch purge valve is closed, except [ 31 days when the [8] inch containment purge valves are open for pressure control, ALARA or air quality OR considerations for personnel entry, or for Surveillances that require the valves to be open. 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 [ 31 days blind flange that is located outside containment and not locked, sealed, or otherwise secured and OR required to be closed during accident conditions is closed, except for containment isolation valves that In accordance are open under administrative controls. with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.3-8 Rev. 5.0

Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 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 Prior to entering blind flange that is located inside containment and MODE 4 from not locked, sealed, or otherwise secured and MODE 5 if not required to be closed during accident conditions is performed within closed, except for containment isolation valves that the previous are open under administrative controls. 92 days SR 3.6.3.5 Verify the isolation time of each automatic power [In accordance operated containment isolation valve is within limits. 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 [ 92 days testable during operation through one complete cycle of full travel, and verify each check valve OR remains closed when the differential pressure in the direction of flow is [1.2] psid and opens when the In accordance differential pressure in the direction of flow is with the

[1.2] psid and < [5.0] psid. Surveillance Frequency Control Program ]

Westinghouse STS 3.6.3-9 Rev. 5.0

Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.7 [ Perform leakage rate testing for containment purge [ 184 days valves with resilient seals.

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 [ [18] months that is not locked, sealed or otherwise secured in position, actuates to the isolation position on an OR actual or simulated actuation signal.

In accordance with the Surveillance Frequency Control Program ]

SR 3.6.3.9 [ Cycle each weight or spring loaded check valve [ 18 months not testable during operation through one complete cycle of full travel, and verify each check valve OR remains closed when the differential pressure in the direction of flow is [1.2] psid and opens when the In accordance differential pressure in the direction of flow is with the

[1.2] psid and < [5.0] psid. Surveillance Frequency Control Program ] ]

Westinghouse STS 3.6.3-10 Rev. 5.0

Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.10 [ Verify each [ ] inch containment purge valve is [ [18] months blocked to restrict the valve from opening > [50]%.

OR In accordance with the Surveillance Frequency Control Program ] ]

SR 3.6.3.11 [ Verify the combined leakage rate for all shield In accordance building bypass leakage paths is [La] when with the pressurized to [psig]. Containment Leakage Rate Testing Program ]

Westinghouse STS 3.6.3-11 Rev. 5.0

Containment Pressure (Atmospheric, Dual, and Ice Condenser) 3.6.4A 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 A.1 Restore containment 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> not within limits. pressure to within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4A.1 Verify containment pressure is within limits. [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.4A-1 Rev. 5.0

Containment Pressure (Subatmospheric) 3.6.4B 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 A.1 Restore containment air 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> pressure not within partial pressure to within limits. limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4B.1 Verify containment air partial pressure is within [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> limits.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.4B-1 Rev. 5.0

Containment Pressure (Subatmospheric) 3.6.4B Westinghouse STS 3.6.4B-2 Rev. 5.0

Containment Air Temperature (Atmospheric and Dual) 3.6.5A 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 A.1 Restore containment 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> temperature not within average air temperature to limit. within limit.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5A.1 Verify containment average air temperature is within [ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.5A-1 Rev. 5.0

Containment Air Temperature (Ice Condenser) 3.6.5B 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 A.1 Restore containment 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> temperature not within average air temperature to limits. within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Westinghouse STS 3.6.5B-1 Rev. 5.0

Containment Air Temperature (Ice Condenser) 3.6.5B SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5B.1 Verify containment upper compartment average air [ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> temperature is within limits.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.5B.2 Verify containment lower compartment average air [ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> temperature is within limits.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.5B-2 Rev. 5.0

Containment Air Temperature (Subatmospheric) 3.6.5C 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 A.1 Restore containment 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> temperature not within average air temperature to limits. within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5C.1 Verify containment average air temperature is within [ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limits.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.5C-1 Rev. 5.0

Containment Spray and Cooling Systems (Atmospheric and Dual) 3.6.6A 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 A.1 Restore containment spray 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> train inoperable. train to OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.

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

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> Westinghouse STS 3.6.6A-1 Rev. 5.0

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

CONDITION REQUIRED ACTION COMPLETION TIME C. One [required] C.1 Restore [required] 7 days containment cooling containment cooling train to train inoperable. OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

D. Two [required] D.1 Restore one [required] 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> containment cooling containment cooling train to trains inoperable. OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition C or D AND not met.

E.2 -------------- NOTE -------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> F. Two containment spray F.1 Enter LCO 3.0.3. Immediately trains inoperable.

OR Any combination of three or more trains inoperable.

Westinghouse STS 3.6.6A-2 Rev. 5.0

Containment Spray and Cooling Systems (Atmospheric and Dual) 3.6.6A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6A.1 ---------------------------------NOTE----------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each containment spray manual, power [ 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in OR position is in the correct position.

In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6A.2 Operate each [required] containment cooling train [ 31 days fan unit for 15 minutes.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6A.3 Verify each [required] containment cooling train [ 31 days cooling water flow rate is [700] gpm.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.6A-3 Rev. 5.0

Containment Spray and Cooling Systems (Atmospheric and Dual) 3.6.6A SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6A.4 Verify containment spray locations susceptible to [ 31 days gas accumulation are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6A.5 Verify each containment spray pump's developed In accordance head at the flow test point is greater than or equal to with the the required developed head. INSERVICE TESTING PROGRAM SR 3.6.6A.6 Verify each automatic containment spray valve in [ [18] months the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position OR on an actual or simulated actuation signal.

In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.6A-4 Rev. 5.0

Containment Spray and Cooling Systems (Atmospheric and Dual) 3.6.6A SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6A.7 Verify each containment spray pump starts [ [18] months automatically on an actual or simulated actuation signal. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6A.8 Verify each [required] containment cooling train [ [18] months starts automatically on an actual or simulated actuation signal. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6A.9 Verify each spray nozzle is unobstructed. [At first refueling]

AND

[ 10 years OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.6A-5 Rev. 5.0

Containment Spray and Cooling Systems (Atmospheric and Dual) 3.6.6B 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 A.1 Restore containment spray 7 days train inoperable. train to OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. One [required] B.1 Restore [required] 7 days containment cooling containment cooling train to train inoperable. OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

C. Two containment spray C.1 Restore one containment 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> trains inoperable. spray train to OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.6.6B-1 Rev. 5.0

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

CONDITION REQUIRED ACTION COMPLETION TIME D. One containment spray D.1 Restore containment spray 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> train and one [required] train to OPERABLE status.

containment cooling [OR train inoperable.

In accordance with the Risk Informed Completion Time Program]

OR D.2 Restore [required] 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> containment cooling train to OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

E. Two [required] E.1 Restore one [required] 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> containment cooling containment cooling train to trains inoperable. OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A, B, AND C, D, or E not met.

F.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.6.6B-2 Rev. 5.0

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

CONDITION REQUIRED ACTION COMPLETION TIME G. Any combination of three G.1 Enter LCO 3.0.3. Immediately or more trains inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6B.1 ---------------------------------NOTE----------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each containment spray manual, power [ 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in OR position is in the correct position.

In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6B.2 Operate each [required] containment cooling train [ 31 days fan unit for 15 minutes.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.6B-3 Rev. 5.0

Containment Spray and Cooling Systems (Atmospheric and Dual) 3.6.6B SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6B.3 Verify each [required] containment cooling train [ 31 days cooling water flow rate is [700] gpm.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6B.4 Verify containment spray locations susceptible to [ 31 days gas accumulation are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6B.5 Verify each containment spray pump's developed In accordance head at the flow test point is greater than or equal to with the the required developed head. INSERVICE TESTING PROGRAM SR 3.6.6B.6 Verify each automatic containment spray valve in [ [18] months the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position OR on an actual or simulated actuation signal.

In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.6B-4 Rev. 5.0

Containment Spray and Cooling Systems (Atmospheric and Dual) 3.6.6B SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6B.7 Verify each containment spray pump starts [ [18] months automatically on an actual or simulated actuation signal. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6B.8 Verify each [required] containment cooling train [ [18] months starts automatically on an actual or simulated actuation signal. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6B.9 Verify each spray nozzle is unobstructed. [At first refueling]

AND

[ 10 years OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.6B-5 Rev. 5.0

Containment Spray System (Ice Condenser) 3.6.6C 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 A.1 Restore containment spray 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> train inoperable. train to OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> Westinghouse STS 3.6.6C-1 Rev. 5.0

Containment Spray System (Ice Condenser) 3.6.6C SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6C.1 ---------------------------------NOTE----------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each containment spray manual, power [ 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in OR position is in the correct position.

In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6C.2 Verify containment spray locations susceptible to [ 31 days gas accumulation are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6C.3 Verify each containment spray pump's developed In accordance head at the flow test point is greater than or equal to with the the required developed head. INSERVICE TESTING PROGRAM SR 3.6.6C.4 Verify each automatic containment spray valve in [ [18] months the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position OR on an actual or simulated actuation signal.

In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.6C-2 Rev. 5.0

Containment Spray System (Ice Condenser) 3.6.6C SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6C.5 Verify each containment spray pump starts [ [18] months automatically on an actual or simulated actuation signal. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6C.6 Verify each spray nozzle is unobstructed. [At first refueling]

AND

[ 10 years OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.6C-3 Rev. 5.0

QS System (Subatmospheric) 3.6.6D 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 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.6.6D-1 Rev. 5.0

QS System (Subatmospheric) 3.6.6D SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6D.1 ---------------------------------NOTE----------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each QS manual, power operated, and [ 31 days automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the OR correct position.

In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6D.2 Verify QS locations susceptible to gas accumulation [ 31 days are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6D.3 Verify each QS pump's developed head at the flow In accordance test point is greater than or equal to the required with the developed head. INSERVICE TESTING PROGRAM SR 3.6.6D.4 Verify each QS automatic valve in the flow path that [ [18] months is not locked, sealed, or otherwise secured in position, actuates to the correct position on an OR actual or simulated actuation signal.

In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.6D-2 Rev. 5.0

QS System (Subatmospheric) 3.6.6D SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6D.5 Verify each QS pump starts automatically on an [ [18] months actual or simulated actuation signal.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6D.6 Verify each spray nozzle is unobstructed. [At first refueling]

AND

[ 10 years OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.6D-3 Rev. 5.0

RS System (Subatmospheric) 3.6.6E 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 A.1 Restore RS subsystem to 7 days inoperable. OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. Two RS subsystems B.1 Restore one RS subsystem 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable in one train. to OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

C. [ Two inside RS C.1 Restore one RS subsystem 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> subsystems inoperable. to OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program] ]

Westinghouse STS 3.6.6E-1 Rev. 5.0

RS System (Subatmospheric) 3.6.6E ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. [ Two outside RS D.1 Restore one RS subsystem 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> subsystems inoperable. to OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program] ]

E. [ Casing cooling tank E.1 Restore casing cooling tank 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. to OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program] ]

F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND F.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> G. Three or more RS G.1 Enter LCO 3.0.3. Immediately subsystems inoperable.

Westinghouse STS 3.6.6E-2 Rev. 5.0

RS System (Subatmospheric) 3.6.6E SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6E.1 Verify casing cooling tank temperature is [35]°F [ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and [50]°F.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6E.2 Verify casing cooling tank contained borated water [ 7 days volume is [116,500] gal.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6E.3 Verify casing cooling tank boron concentration is [ 7 days

[2300] ppm and [2400] ppm.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.6E-3 Rev. 5.0

RS System (Subatmospheric) 3.6.6E SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6E.4 ---------------------------------NOTE----------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each RS [and casing cooling] manual, power [ 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in OR position is in the correct position.

In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6E.5 Verify RS locations susceptible to gas accumulation [ 31 days are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6E.6 Verify each RS [and casing cooling] pump's In accordance developed head at the flow test point is greater than with the or equal to the required developed head. INSERVICE TESTING PROGRAM Westinghouse STS 3.6.6E-4 Rev. 5.0

RS System (Subatmospheric) 3.6.6E SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6E.7 Verify on an actual or simulated actuation signal(s): [ [18] months

a. Each RS automatic valve in the flow path that is OR not locked, sealed, or otherwise secured in position, actuates to the correct position, In accordance with the

b. Each RS pump starts automatically, and Surveillance Frequency

c. [ Each casing cooling pump starts Control Program ]

automatically. ]

SR 3.6.6E.8 Verify each spray nozzle is unobstructed. [ At first refueling ]

AND

[ 10 years OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.6E-5 Rev. 5.0

Spray Additive System (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.7 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 A.1 Restore Spray Additive 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. System to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> Westinghouse STS 3.6.7-1 Rev. 5.0

Spray Additive System (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.7.1 Verify each spray additive manual, power operated, [ 31 days and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in OR the correct position.

In accordance with the Surveillance Frequency Control Program ]

SR 3.6.7.2 Verify spray additive tank solution volume is [ 184 days

[2568] gal and [4000] gal.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.7.3 Verify spray additive tank [NaOH] solution [ 184 days concentration is [30]% and [32]% by weight.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.7.4 Verify each spray additive automatic valve in the [ [18] months flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position OR on an actual or simulated actuation signal.

In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.7-2 Rev. 5.0

Spray Additive System (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.7.5 Verify spray additive flow [rate] from each solution's [ 5 years flow path.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.7-3 Rev. 5.0

Shield Building (Dual and Ice Condenser) 3.6.8 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 A.1 Restore shield building to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.8.1 [ Verify annulus negative pressure is > [5] inches [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> water gauge.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.8-1 Rev. 5.0

Shield Building (Dual and Ice Condenser) 3.6.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.8.2 Verify one shield building access door in each [ 31 days access opening is closed.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.8.3 [ Verify shield building structural integrity by During shutdown performing a visual inspection of the exposed for SR 3.6.1.1 interior and exterior surfaces of the shield building. Type A tests ]

SR 3.6.8.4 Verify the shield building can be maintained at a [ [18] months on a pressure equal to or more negative than [-0.5] inch STAGGERED water gauge in the annulus by one Shield Building TEST BASIS for Air Cleanup System train with final flow [ ] cfm each Shield within [22] seconds after a start signal. Building Air Cleanup System train OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.8-2 Rev. 5.0

HMS (Atmospheric, Ice Condenser, and Dual) 3.6.9 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 A.1 Restore HMS train to 30 days inoperable. OPERABLE status.

B. Two HMS trains B.1 Verify by administrative 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. means that the hydrogen control function is AND maintained.

Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND B.2 Restore one HMS train to 7 days OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

Westinghouse STS 3.6.9-1 Rev. 5.0

HMS (Atmospheric, Ice Condenser, and Dual) 3.6.9 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 [ [18] months

[4000] cfm.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.9.3 Verify each HMS train starts on an actual or [ [18] months simulated actuation signal.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.9-2 Rev. 5.0

HIS (Ice Condenser) 3.6.10 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 A.1 Restore HIS train to 7 days inoperable. OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

OR A.2 Perform SR 3.6.10.1 on the Once per 7 days OPERABLE train.

B. One containment region B.1 Restore one hydrogen 7 days with no OPERABLE ignitor in the affected hydrogen ignitor. containment region to [OR OPERABLE status.

In accordance with the Risk Informed Completion Time Program]

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

Westinghouse STS 3.6.10-1 Rev. 5.0

HIS (Ice Condenser) 3.6.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.10.1 Energize each HIS train power supply breaker and [ 92 days verify [32] ignitors are energized in each train.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.10.2 Verify at least one hydrogen ignitor is OPERABLE in [ 92 days each containment region.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.10.3 Energize each hydrogen ignitor and verify [ [18] months temperature is [1700]°F.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.10-2 Rev. 5.0

ICS (Atmospheric and Subatmospheric) 3.6.11 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 A.1 Restore ICS train to 7 days inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.11.1 Operate each ICS train for 15 continuous minutes [ 31 days

[with heaters operating].

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.11-1 Rev. 5.0

ICS (Atmospheric and Subatmospheric) 3.6.11 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.11.2 Perform required ICS filter testing in accordance In accordance with the Ventilation Filter Testing Program (VFTP). with the VFTP SR 3.6.11.3 Verify each ICS train actuates on an actual or [ [18] months simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured OR in the actuated position.

In accordance with the Surveillance Frequency Control Program ]

SR 3.6.11.4 [ Verify each ICS filter bypass damper can be [ [18] months opened, except for dampers that are locked, sealed, or otherwise secured in the open position. OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.6.11-2 Rev. 5.0

Vacuum Relief Valves (Atmospheric and Ice Condenser) 3.6.12 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 A.1 Restore vacuum relief line 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 -------------- NOTE -------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.12.1 Verify each vacuum relief line is OPERABLE in In accordance accordance with the INSERVICE TESTING with the PROGRAM. INSERVICE TESTING PROGRAM Westinghouse STS 3.6.12-1 Rev. 5.0

SBACS (Dual and Ice Condenser) 3.6.13 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 A.1 Restore SBACS train to 7 days inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.13.1 Operate each SBACS train for 15 continuous [ 31 days minutes [with heaters operating].

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.13-1 Rev. 5.0

SBACS (Dual and Ice Condenser) 3.6.13 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.13.2 Perform required SBACS filter testing in accordance In accordance with the Ventilation Filter Testing Program (VFTP). with the VFTP SR 3.6.13.3 Verify each SBACS train actuates on an actual or [ [18] months simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured OR in the actuated position.

In accordance with the Surveillance Frequency Control Program ]

SR 3.6.13.4 [ Verify each SBACS filter bypass damper can be [ [18] months opened, except for dampers that are locked, sealed, or otherwise secured in the open position. 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 ]

Westinghouse STS 3.6.13-2 Rev. 5.0

ARS (Ice Condenser) 3.6.14 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 A.1 Restore ARS train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.6.14-1 Rev. 5.0

ARS (Ice Condenser) 3.6.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.14.1 Verify each ARS fan starts on an actual or simulated [ [92] days actuation signal, after a delay of [9.0] minutes and

[11.0] minutes, and operates for 15 minutes. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.14.2 Verify, with the ARS fan dampers closed, each ARS [ 92 days fan motor current is [20.5] amps and [35.5] amps

[when the fan speed is [840] rpm and [900] rpm]. OR In accordance with the Surveillance Frequency Control Program SR 3.6.14.3 Verify, with the ARS fan not operating, each ARS [ 92 days fan damper opens when [11.0] lb is applied to the counterweight. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.14.4 [ Verify each motor operated valve in the hydrogen [ 92 days collection header that is not locked, sealed, or otherwise secured in position, opens on an actual or OR simulated actuation signal after a delay of

[9.0] minutes and [11.0] minutes. In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.6.14-2 Rev. 5.0

Ice Bed (Ice Condenser) 3.6.15 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 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.15.1 Verify maximum ice bed temperature is [27]°F. [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.15-1 Rev. 5.0

Ice Bed (Ice Condenser) 3.6.15 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.15.2 Verify total mass of stored ice is [2,200,000] lbs by [ 18 months calculating the mass of stored ice, at a 95%

confidence level, in each of three Radial Zones as OR defined below, by selecting a random sample of 30 ice baskets in each Radial Zone, and In accordance with the Verify: Surveillance Frequency

1. Zone A (radial rows [7,8,9]), has a total mass of Control Program ]

[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.

SR 3.6.15.3 Verify that the ice mass of each basket sampled in [ 18 months SR 3.6.15.2 is 600 lbs.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.15.4 Verify, by visual inspection, accumulation of ice on [ 18 months structural members comprising flow channels through the ice bed is 15 percent blockage of the OR total flow area for each safety analysis section.

In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.15-2 Rev. 5.0

Ice Bed (Ice Condenser) 3.6.15 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 [ [54] months least one randomly selected ice basket from each ice condenser bay, that ice bed: OR

a. Boron concentration is a [1800] ppm and In accordance

[2000] ppm and with the Surveillance

b. pH is [9.0] and [9.5]. Frequency Control Program ]

SR 3.6.15.6 Visually inspect, for detrimental structural wear, [ 40 months cracks, corrosion, or other damage, two ice baskets from each group of bays as defined below: OR

a. Group 1 - bays 1 through 8; In accordance with the

b. Group 2 - bays 9 through 16; and Surveillance Frequency

c. Group 3 - bays 17 through 24. 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 Each ice addition ice condenser meets the boron concentration and pH requirements of SR 3.6.15.5.

Westinghouse STS 3.6.15-3 Rev. 5.0

Ice Condenser Doors (Ice Condenser) 3.6.16 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 A.1 Restore inlet door to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> condenser inlet doors OPERABLE status.

inoperable due to being [OR physically restrained from opening. In accordance with the Risk Informed Completion Time Program]

B. One or more ice B.1 Verify maximum ice bed Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> condenser doors temperature is [27]°F.

inoperable for reasons other than Condition A AND or not closed.

B.2 Restore ice condenser door 14 days to OPERABLE status and closed positions. [OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.6.16-1 Rev. 5.0

Ice Condenser Doors (Ice Condenser) 3.6.16 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Restore ice condenser door 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> associated Completion to OPERABLE status and Time of Condition B not closed positions.

met.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or C AND not met.

D.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.16.1 Verify all inlet doors indicate closed by the Inlet Door [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Position Monitoring System.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.16.2 Verify, by visual inspection, each intermediate deck [ 7 days door is closed and not impaired by ice, frost, or debris. OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.16-2 Rev. 5.0

Ice Condenser Doors (Ice Condenser) 3.6.16 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.16.3 Verify, by visual inspection, each inlet door is not [3 months during impaired by ice, frost, or debris. first year after receipt of license]

AND

[ [18] months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.16.4 Verify torque required to cause each inlet door to [3 months during begin to open is [675] in-lb. first year after receipt of license]

AND

[ [18] months OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.16-3 Rev. 5.0

Ice Condenser Doors (Ice Condenser) 3.6.16 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.16.5 Perform a torque test on [a sampling of 25% of [3 months during the] inlet doors. first year after receipt of license]

AND

[ [18] months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.16.6 Verify for each intermediate deck door: [3 months during first year after

a. No visual evidence of structural deterioration, receipt of license]

b. Free movement of the vent assemblies, and AND

c. Free movement of the door. [ [18] months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.16.7 Verify, by visual inspection, each top deck [door]: [ 92 days

a. Is in place; and OR

b. Has no condensation, frost, or ice formed on In accordance the [door] that would restrict its opening. with the Surveillance Frequency Control Program ]

Westinghouse STS 3.6.16-4 Rev. 5.0

Divider Barrier Integrity (Ice Condenser) 3.6.17 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------------ A.1 Restore personnel access 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> For this action, separate doors and equipment Condition entry is hatches to OPERABLE [OR allowed for each status and closed positions.

personnel access door In accordance with or equipment hatch. the Risk Informed

---

Completion Time Program]

One or more personnel access doors or equipment hatches open or inoperable, other than for personnel transit entry.

B. Divider barrier seal B.1 Restore seal to OPERABLE 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Westinghouse STS 3.6.17-1 Rev. 5.0

Divider Barrier Integrity (Ice Condenser) 3.6.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.17.1 Verify, by visual inspection, all personnel access Prior to entering doors and equipment hatches between upper and MODE 4 from lower containment compartments are closed. MODE 5 SR 3.6.17.2 Verify, by visual inspection, that the seals and Prior to final sealing surfaces of each personnel access door and closure after each equipment hatch have: opening

a. No detrimental misalignments, AND

b. No cracks or defects in the sealing surfaces, --------NOTE--------

and Only required for seals made of

c. No apparent deterioration of the seal material. 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 After each door or equipment hatch that has been opened for opening personnel transit entry is closed.

SR 3.6.17.4 Remove two divider barrier seal test coupons and [ [18] months verify:

OR

a. Both test coupons' tensile strength is [120] psi and In accordance with the

[ b. Both test coupons' elongation is [100]%. ] Surveillance Frequency Control Program ]

Westinghouse STS 3.6.17-2 Rev. 5.0

Divider Barrier Integrity (Ice Condenser) 3.6.17 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.17.5 Visually inspect [95]% of the divider barrier seal [ [18] months length, and verify:

OR

a. Seal and seal mounting bolts are properly installed and In accordance with the

b. Seal material shows no evidence of Surveillance deterioration due to holes, ruptures, chemical Frequency attack, abrasion, radiation damage, or changes Control Program ]

in physical appearance.

Westinghouse STS 3.6.17-3 Rev. 5.0

Containment Recirculation Drains (Ice Condenser) 3.6.18 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 A.1 Restore ice condenser floor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> drain inoperable. drain to OPERABLE status.

B. One refueling canal B.1 Restore refueling canal 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> drain inoperable. drain to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND C.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.6.18-1 Rev. 5.0

Containment Recirculation Drains (Ice Condenser) 3.6.18 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.18.1 Verify, by visual inspection, that: [ 92 days

a. Each refueling canal drain plug is removed, OR

b. Each refueling canal drain is not obstructed by In accordance debris, and with the Surveillance

c. No debris is present in the upper compartment Frequency or refueling canal that could obstruct the Control Program ]

refueling canal drain.

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: [ [18] months

a. Valve opening is not impaired by ice, frost, or OR debris, In accordance

b. Valve seat shows no evidence of damage, with the Surveillance

c. Valve opening force is [66] lb, and Frequency Control Program ]

d. Drain line from the ice condenser floor to the lower compartment is unrestricted.

Westinghouse STS 3.6.18-2 Rev. 5.0

Containment Sump 3.6.19 3.6 CONTAINMENT SYSTEMS 3.6.19 Containment Sump LCO 3.6.19 [The][Two] containment sump[s] shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. [One or more] A.1 Initiate action to mitigate Immediately containment sump[s] containment accident inoperable due to generated and transported containment accident debris.

generated and transported debris AND exceeding the analyzed limits. A.2 Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND A.3 Restore the containment 90 days sump[s] to OPERABLE status.

Westinghouse STS 3.6.19-1 Rev. 5.0

Containment Sump 3.6.19 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. [One or more] B.1 --------------NOTES-------------

containment sump[s] 1. Enter applicable inoperable for reasons Conditions and other than Condition A. Required Actions of LCO 3.5.2, "ECCS -

Operating," and LCO 3.5.3, "ECCS -

Shutdown," for emergency core cooling trains made inoperable by the containment sump[s].

2. Enter applicable Conditions and Required Actions of LCO 3.6.6,

"[Containment Spray and Cooling Systems],"

for [containment spray]

trains made inoperable by the containment sump[s].

Restore the containment [72 hours]

sump[s] to OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Westinghouse STS 3.6.19-2 Rev. 5.0

Containment Sump 3.6.19 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.19.1 Verify, by visual inspection, the containment sump[s] [ [18] months does not show structural damage, abnormal corrosion, or debris blockage. OR In accordance with the Surveillance Frequency Control Program]

Westinghouse STS 3.6.19-3 Rev. 5.0

MSSVs 3.7.1 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 A.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> generators with one POWER to [72] % RTP.

MSSV inoperable [and the Moderator Temperature Coefficient (MTC) zero or negative at all power levels]*.

B. One or more steam B.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> generators with two or POWER to less than or more MSSVs equal to the Maximum inoperable. Allowable % RTP specified in Table 3.7.1-1 for the

[ OR number of OPERABLE MSSVs.

One or more steam generators with one AND MSSV inoperable and the MTC positive at any power level. ]*

Westinghouse STS 3.7.1-1 Rev. 5.0

MSSVs 3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2 --------------NOTE--------------

Only required in MODE 1.

Reduce the Power Range 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 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.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND OR C.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> One or more steam generators with [4]

MSSVs inoperable.

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 In accordance Table 3.7.1-2 in accordance with the INSERVICE with the TESTING PROGRAM. Following testing, lift setting INSERVICE shall be within +1%. TESTING PROGRAM Westinghouse STS 3.7.1-2 Rev. 5.0

MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)

OPERABLE Main Steam Safety Valves versus Maximum Allowable Power NUMBER OF OPERABLE MAXIMUM ALLOWABLE MSSVs PER STEAM POWER (% RTP)

GENERATOR

[4] [65]

3 [46]

2 [28]

Westinghouse STS 3.7.1-3 Rev. 5.0

MSSVs 3.7.1 Table 3.7.1-2 (page 1 of 1)

Main Steam Safety Valve Lift Settings VALVE NUMBER STEAM GENERATOR LIFT SETTING (psig +/- [3]%)

1. 1 #2 [#3] [#4]

[ ] [ ] [ ] [ ] [ ]

[ ] [ ] [ ] [ ] [ ]

[ ] [ ] [ ] [ ] [ ]

[ ] [ ] [ ] [ ] [ ]

Westinghouse STS 3.7.1-4 Rev. 5.0

MSIVs 3.7.2 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 A.1 Restore MSIV to [8] hours MODE 1. OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not met.

C. ------------NOTE------------ C.1 Close MSIV. [8] hours Separate Condition entry is allowed for each AND MSIV.

---

C.2 Verify MSIV is closed. Once per 7 days One or more MSIVs inoperable in MODE 2 or 3.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition C not AND met.

D.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.7.2-1 Rev. 5

MSIVs 3.7.2 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 In accordance limits. 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 [ [18] months on an actual or simulated actuation signal.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.7.2-2 Rev. 5

MFIVs and MFRVs and [Associated Bypass Valves]

3.7.3 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 A.1 Close or isolate MFIV. [72] hours inoperable.

AND A.2 Verify MFIV is closed or Once per 7 days isolated.

B. One or more MFRVs B.1 Close or isolate MFRV. [72] hours inoperable.

AND B.2 Verify MFRV is closed or Once per 7 days isolated.

C. [ One or more [MFRV or C.1 Close or isolate bypass [72] hours preheater] bypass valve.

valves inoperable.

AND C.2 Verify bypass valve is Once per 7 days ]

closed or isolated.

Westinghouse STS 3.7.3-1 Rev. 5.0

MFIVs and MFRVs and [Associated Bypass Valves]

3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two valves in the same D.1 Isolate affected flow path. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> flow path inoperable.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. [ AND E.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ]

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the isolation time of each MFIV, MFRV[, and In accordance associated bypass valve] is within limits. with the INSERVICE TESTING PROGRAM SR 3.7.3.2 Verify each MFIV, MFRV[, and associated bypass [ [18] months valves] actuates to the isolation position on an actual or simulated actuation signal. OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.7.3-2 Rev. 5.0

ADVs 3.7.4 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 A.1 Restore required ADV line 7 days inoperable. to OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. Two or more required B.1 Restore all but one ADV 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ADV lines inoperable. line to OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND C.2 Be in MODE 4 without [24] hours reliance upon steam generator for heat removal.

Westinghouse STS 3.7.4-1 Rev. 5.0

ADVs 3.7.4 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 [ [18] months valve.

OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.7.4-2 Rev. 5.0

AFW System 3.7.5 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 A.1 Restore affected equipment 7 days train inoperable due to to OPERABLE status.

one inoperable steam [OR supply.

In accordance with OR the Risk Informed Completion Time

---

NOTE------------ Program] ]

Only applicable if MODE 2 has not been entered following refueling.

One turbine driven AFW pump inoperable in MODE 3 following refueling.

Westinghouse STS 3.7.5-1 Rev. 5.0

AFW System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One AFW train B.1 Restore AFW train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable in MODE 1, OPERABLE status.

2, or 3 [for reasons other [OR than Condition A].

In accordance with the Risk Informed Completion Time Program]

C. Turbine driven AFW C.1 Restore the steam supply [24 or 48] hours train inoperable due to to the turbine driven train to one inoperable steam OPERABLE status.

supply.

OR AND C.2 Restore the motor driven [24 or 48] hours One motor driven AFW AFW train to OPERABLE train inoperable. status.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A [, B, AND or C] not met.

D.2 [ Be in MODE 4. [18] hours ]

[ OR Two AFW trains inoperable in MODE 1, 2, or 3 for reasons other than Condition C. ]

Westinghouse STS 3.7.5-2 Rev. 5.0

AFW System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. [ Three] AFW trains E.1 --------------NOTE--------------

inoperable in MODE 1, LCO 3.0.3 and all other 2, or 3. LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status.

Initiate action to restore Immediately ]

one AFW train to OPERABLE status.

F. Required AFW train F.1 Initiate action to restore Immediately inoperable in MODE 4. AFW train to OPERABLE status.

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 [ 31 days automatic valve in each water flow path, [and in both steam supply flow paths to the steam turbine driven OR pump,] that is not locked, sealed, or otherwise secured in position, is in the correct position. In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.7.5-3 Rev. 5.0

AFW System 3.7.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 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 In accordance flow test point is greater than or equal to the with the required developed head. INSERVICE TESTING PROGRAM 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, [ [18] months sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated OR actuation signal.

In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.7.5-4 Rev. 5.0

AFW System 3.7.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 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 [ [18] months actual or simulated actuation signal.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.7.5.5 [ Verify proper alignment of the required AFW flow Prior to entering paths by verifying flow from the condensate storage MODE 2 tank to each steam generator. whenever unit has been in MODE 5, MODE 6, or defueled for a cumulative period of > 30 days ]

Westinghouse STS 3.7.5-5 Rev. 5.0

CST 3.7.6 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 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> means OPERABILITY of backup water supply. AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND A.2 Restore CST to 7 days OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 4, without [24] hours reliance on steam generator for heat removal.

Westinghouse STS 3.7.6-1 Rev. 5.0

CST 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify the CST level is [110,000 gal]. [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.7.6-2 Rev. 5.0

CCW System 3.7.7 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 A.1 --------------NOTE--------------

inoperable. 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 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.

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

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.7.7-1 Rev. 5.0

CCW System 3.7.7 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 [ 31 days automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or OR otherwise secured in position, is in the correct position. In accordance with the Surveillance Frequency Control Program ]

SR 3.7.7.2 Verify each CCW automatic valve in the flow path [ [18] months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an OR actual or simulated actuation signal.

In accordance with the Surveillance Frequency Control Program ]

SR 3.7.7.3 Verify each CCW pump starts automatically on an [ [18] months actual or simulated actuation signal.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.7.7-2 Rev. 5.0

SWS 3.7.8 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 A.1 --------------NOTES-------------

inoperable. 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 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.7.8-1 Rev. 5.0

SWS 3.7.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.

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

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 [ 31 days automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or OR otherwise secured in position, is in the correct position. In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.7.8-2 Rev. 5.0

SWS 3.7.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.8.2 Verify each SWS automatic valve in the flow path [ [18] months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an OR actual or simulated actuation signal.

In accordance with the Surveillance Frequency Control Program ]

SR 3.7.8.3 Verify each SWS pump starts automatically on an [ [18] months actual or simulated actuation signal.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.7.8-3 Rev. 5.0

UHS 3.7.9 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 A.1 Restore cooling tower 7 days towers with one cooling fan(s) to OPERABLE tower fan inoperable. status. [OR In accordance with the Risk Informed Completion Time Program] ]

---

REVIEWER'S NOTE----- B.1 Verify water temperature of Once per hour]

The [ ]°F is the maximum the UHS is [90]°F allowed UHS temperature averaged over the previous value and is based on 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

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.

Westinghouse STS 3.7.9-1 Rev. 5.0

UHS 3.7.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. [ Required Action C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and associated Completion Time of AND Condition A or B not met. C.2 --------------NOTE--------------

LCO 3.0.4.a is not OR ] applicable when entering MODE 4.

UHS inoperable [for -------------------------------------

reasons other than Condition A or B]. Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 [ Verify water level of UHS is [562] ft [mean sea [ [24] hours level].

OR In accordance with the Surveillance Frequency Control Program ] ]

SR 3.7.9.2 [ Verify average water temperature of UHS is [ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

[90]°F.

OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.7.9-2 Rev. 5.0

UHS 3.7.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.9.3 [ Operate each cooling tower fan for [15] minutes. [ 31 days OR In accordance with the Surveillance Frequency Control Program ] ]

SR 3.7.9.4 [ Verify each cooling tower fan starts automatically [ [18] months on an actual or simulated actuation signal.

OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.7.9-3 Rev. 5.0

CREFS 3.7.10 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 A.1 Restore CREFS train to 7 days inoperable for reasons OPERABLE status.

other than Condition B.

B. One or more CREFS B.1 Initiate action to implement Immediately trains inoperable due to mitigating actions.

inoperable CRE boundary in MODE 1, 2, AND 3, or 4.

B.2 Verify mitigating actions 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.

AND B.3 Restore CRE boundary to 90 days OPERABLE status.

Westinghouse STS 3.7.10-1 Rev. 5.0

CREFS 3.7.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or 4. C.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D. Required Action and D.1 --------------NOTE--------------

associated Completion [ Place in toxic gas Time of Condition A not protection mode if met [in MODE 5 or 6, or] automatic transfer to toxic during movement of gas protection mode is

[recently] irradiated fuel inoperable. ]

assemblies. -------------------------------------

Place OPERABLE CREFS Immediately train in emergency mode.

OR D.2 Suspend movement of Immediately

[recently] irradiated fuel assemblies.

Westinghouse STS 3.7.10-2 Rev. 5.0

CREFS 3.7.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two CREFS trains E.1 Suspend movement of Immediately inoperable [in MODE 5 [recently] irradiated fuel or 6, or] during assemblies.

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.

F. Two CREFS trains F.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CREFS train for 15 continuous [ 31 days minutes [with heaters operating].

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.7.10-3 Rev. 5.0

CREFS 3.7.10 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.10.2 Perform required CREFS filter testing in accordance In accordance with the [Ventilation Filter Testing Program (VFTP)]. with the [VFTP]

SR 3.7.10.3 Verify each CREFS train actuates on an actual or [ [18] months simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured OR in the actuated position.

In accordance with the Surveillance Frequency Control Program ]

SR 3.7.10.4 Perform required CRE unfiltered air inleakage In accordance testing in accordance with the Control Room with the Control Envelope Habitability Program. Room Envelope Habitability Program Westinghouse STS 3.7.10-4 Rev. 5.0

CREATCS 3.7.11 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 A.1 Restore CREATCS train to 30 days inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met in MODE 1, 2, 3, or 4. B.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> C. Required Action and C.1 Place OPERABLE Immediately associated Completion CREATCS train in Time of Condition A not operation.

met [in MODE 5 or 6, or]

during movement of OR

[recently] irradiated fuel assemblies. C.2 Suspend movement of Immediately

[recently] irradiated fuel assemblies.

Westinghouse STS 3.7.11-1 Rev. 5.0

CREATCS 3.7.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two CREATCS trains D.1 Suspend movement of Immediately inoperable [in MODE 5 [recently] irradiated fuel or 6, or] during assemblies.

movement of [recently]

irradiated fuel assemblies.

E. Two CREATCS trains E.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify each CREATCS train has the capability to [ [18] months remove the assumed heat load.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.7.11-2 Rev. 5.0

ECCS PREACS 3.7.12 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 A.1 Restore ECCS PREACS 7 days train inoperable. train to OPERABLE status.

B. Two ECCS PREACS B.1 Restore ECCS pump room 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> trains inoperable due to boundary to OPERABLE inoperable ECCS pump status.

room boundary.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND C.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.7.12-1 Rev. 5.0

ECCS PREACS 3.7.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 Operate each ECCS PREACS train for [ 31 days 15 continuous minutes [with heaters operating].

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.7.12.2 Perform required ECCS PREACS filter testing in In accordance accordance with the [Ventilation Filter Testing with the [VFTP]

Program (VFTP)].

SR 3.7.12.3 Verify each ECCS PREACS train actuates on an [ [18] months actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or OR otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program ]

SR 3.7.12.4 Verify one ECCS PREACS train can maintain a [ [18] months on a pressure [-0.125] inches water gauge relative to STAGGERED atmospheric pressure during the [post accident] TEST BASIS mode of operation at a flow rate of [3000] cfm.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.7.12-2 Rev. 5.0

ECCS PREACS 3.7.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.12.5 [ Verify each ECCS PREACS filter bypass damper [ [18] months can be closed, except for dampers that are locked, sealed, or otherwise secured in the closed position. OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.7.12-3 Rev. 5.0

FBACS 3.7.13 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 A.1 Restore FBACS train to 7 days inoperable. OPERABLE status.

B. Two FBACS trains B.1 Restore fuel building 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable due to boundary to OPERABLE inoperable fuel building status.

boundary in MODE 1, 2, 3, or 4.

Westinghouse STS 3.7.13-1 Rev. 5.0

FBACS 3.7.13 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. [ Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or 4. C.2 --------------NOTE--------------

LCO 3.0.4.a is not OR applicable when entering MODE 4.

Two FBACS trains -------------------------------------

inoperable in MODE 1, 2, 3, or 4 for reasons Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ]

other than Condition B.

D. Required Action and D.1 Place OPERABLE FBACS Immediately associated Completion train in operation.

Time [of Condition A] not met during movement of OR

[recently] irradiated fuel assemblies in the fuel D.2 Suspend movement of Immediately building. [recently] irradiated fuel assemblies in the fuel building.

E. Two FBACS trains E.1 Suspend movement of Immediately inoperable during [recently] irradiated fuel movement of [recently] assemblies in the fuel irradiated fuel building.

assemblies in the fuel building.

Westinghouse STS 3.7.13-2 Rev. 5.0

FBACS 3.7.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Operate each FBACS train for 15 continuous [ 31 days minutes [with heaters operating].

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.7.13.2 Perform required FBACS filter testing in accordance In accordance with the [Ventilation Filter Testing Program (VFTP)]. with the [VFTP]

SR 3.7.13.3 [ Verify each FBACS train actuates on an actual or [ [18] months simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured OR in the actuated position.

In accordance with the Surveillance Frequency Control Program ] ]

SR 3.7.13.4 Verify one FBACS train can maintain a pressure [ [18] months on a

[-0.125] inches water gauge with respect to STAGGERED atmospheric pressure during the [post accident] TEST BASIS mode of operation at a flow rate [20,000] cfm.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.7.13-3 Rev. 5.0

FBACS 3.7.13 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.13.5 [ Verify each FBACS filter bypass damper can be [ [18] months closed, except for dampers that are locked, sealed, or otherwise secured in the closed position. OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.7.13-4 Rev. 5.0

PREACS 3.7.14 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 A.1 Restore PREACS train to 7 days inoperable. OPERABLE status.

B. Two PREACS trains B.1 Restore penetration room 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable due to boundary to OPERABLE inoperable penetration status.

room boundary.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND C.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.7.14-1 Rev. 5.0

PREACS 3.7.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Operate each PREACS train for 15 continuous [ 31 days minutes [with heaters operating].

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.7.14.2 Perform required PREACS filter testing in In accordance accordance with the [Ventilation Filter Testing with the [VFTP]

Program (VFTP)].

SR 3.7.14.3 [ Verify each PREACS train actuates on an actual or [ [18] months simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured OR in the actuated position.

In accordance with the Surveillance Frequency Control Program ] ]

SR 3.7.14.4 [ Verify one PREACS train can maintain a pressure [ [18] months on a

[-0.125] inches water gauge relative to STAGGERED atmospheric pressure during the [post accident] TEST BASIS mode of operation at a flow rate of [3000] cfm.

OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.7.14-2 Rev. 5.0

PREACS 3.7.14 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.14.5 [ Verify each PREACS filter bypass damper can be [ [18] months closed, except for dampers that are locked, sealed, or otherwise secured in the closed position. OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.7.14-3 Rev. 5.0

Fuel Storage Pool Water Level 3.7.15 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 A.1 --------------NOTE--------------

level not within limit. LCO 3.0.3 is not applicable.

Suspend movement of Immediately irradiated fuel assemblies in the fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify the fuel storage pool water level is 23 ft [ 7 days above the top of the irradiated fuel assemblies seated in the storage racks. OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.7.15-1 Rev. 5.0

[Fuel Storage Pool Boron Concentration]

3.7.16 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 --------------------NOTE-------------------

concentration not within LCO 3.0.3 is not applicable.

limit. ------------------------------------------------

A.1 Suspend movement of fuel Immediately assemblies in the fuel storage pool.

AND A.2.1 Initiate action to restore fuel Immediately storage pool boron concentration to within limit.

OR A.2.2 Initiate action to perform a Immediately fuel storage pool verification.

Westinghouse STS 3.7.16-1 Rev. 5.0

[Fuel Storage Pool Boron Concentration]

3.7.16 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the fuel storage pool boron concentration is [ 7 days within limit.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.7.16-2 Rev. 5.0

[Spent Fuel Pool Storage]

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

LCO not met. LCO 3.0.3 is not applicable.

Initiate action to move the Immediately noncomplying fuel assembly from [Region 2].

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.17.1 Verify by administrative means the initial enrichment Prior to storing the and burnup of the fuel assembly is in accordance fuel assembly in with Figure 3.7.17-1 or Specification 4.3.1.1. [Region 2]

Westinghouse STS 3.7.17-1 Rev. 5.0

[Spent Fuel Pool Storage]

3.7.17 Westinghouse STS 3.7.17-2 Rev. 5.0

Secondary Specific Activity 3.7.18 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 A.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> within limit.

AND A.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.18.1 Verify the specific activity of the secondary coolant [ 31 days is [0.10] µCi/gm DOSE EQUIVALENT I-131.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.7.18-1 Rev. 5.0

AC Sources - Operating 3.8.1 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 A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> circuit inoperable. [required] OPERABLE offsite circuit. AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter AND A.2 Declare required feature(s) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from with no offsite power discovery of no offsite available inoperable when power to one train its redundant required concurrent with feature(s) is inoperable. inoperability of redundant required feature(s)

AND Westinghouse STS 3.8.1-1 Rev. 5.0

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.3 Restore [required] offsite 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> circuit to OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

B. One [required] DG B.1 Perform SR 3.8.1.1 for the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. [required] offsite circuit(s).

AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter AND B.2 Declare required feature(s) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from supported by the inoperable discovery of DG inoperable when its Condition B required redundant concurrent with feature(s) is inoperable. inoperability of redundant required feature(s)

AND B.3.1 Determine OPERABLE [24] hours DG(s) is not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.2 for [24] hours OPERABLE DG(s).

AND Westinghouse STS 3.8.1-2 Rev. 5.0

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.4 Restore [required] DG to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

C. Two [required] offsite C.1 Declare required feature(s) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from circuits inoperable. inoperable when its discovery of redundant required Condition C feature(s) is inoperable. concurrent with inoperability of redundant required features AND C.2 Restore one [required] 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> offsite circuit to OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

D. One [required] offsite --------------------NOTE-------------------

circuit inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.9, AND "Distribution Systems - Operating,"

when Condition D is entered with no One [required] DG AC power source to any train.

inoperable. ------------------------------------------------

D.1 Restore [required] offsite 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> circuit to OPERABLE status. [OR OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.8.1-3 Rev. 5.0

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.2 Restore [required] DG to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

E. Two [required] DGs E.1 Restore one [required] DG 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> inoperable. to OPERABLE status.

---

REVIEWERS NOTE----- F.1 Restore [required] [12] hours This Condition may be [automatic load sequencer]

deleted if the unit design is to OPERABLE status. [OR such that any sequencer failure mode will only affect In accordance with the ability of the associated the Risk Informed DG to power its respective Completion Time safety loads following a loss Program] ]

of offsite power independent of, or coincident with, a Design Basis Event.

F. [ One [required]

[automatic load sequencer] inoperable.

G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A, B, AND C, D, E, or [F] not met.

G.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Westinghouse STS 3.8.1-4 Rev. 5.0

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. Three or more [required] H.1 Enter LCO 3.0.3. Immediately AC sources inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated [ 7 days power availability for each [required] offsite circuit.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.8.1.2 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

[ 2. A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer. When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.7 must be met. ]

Verify each DG starts from standby conditions and [ 31 days achieves steady state voltage [3740] V and

[4580] V, and frequency [58.8] Hz and OR

[61.2] Hz.

In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.8.1-5 Rev. 5.0

AC Sources - Operating 3.8.1 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 [ 31 days operates for 60 minutes at a load [4500] kW and

[5000] kW. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.8.1.4 Verify each day tank [and engine mounted tank] [ 31 days contains [220] gal of fuel oil.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.8.1-6 Rev. 5.0

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.5 Check for and remove accumulated water from each [ [31] days day tank [and engine mounted tank].

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.8.1.6 Verify the fuel oil transfer system operates to [ [92] days

[automatically] transfer fuel oil from storage tank[s]

to the day tank [and engine mounted tank]. 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 [ 184 days achieves:

OR

a. In [10] seconds, voltage [3740] V and frequency 58.8] Hz and In accordance with the

b. Steady state voltage [3740] V and [4580] V, Surveillance and frequency [58.8] Hz and [61.2] Hz. Frequency Control Program ]

Westinghouse STS 3.8.1-7 Rev. 5.0

AC Sources - Operating 3.8.1 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 [ [18] months sources from the normal offsite circuit to each alternate [required] offsite circuit. OR In accordance with the Surveillance Frequency Control Program ] ]

Westinghouse STS 3.8.1-8 Rev. 5.0

AC Sources - Operating 3.8.1 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 [ [18] months to its associated single largest post-accident load, and: OR

a. Following load rejection, the frequency is In accordance

[63] Hz, with the Surveillance

b. Within [3] seconds following load rejection, the Frequency voltage is [3740] V and [4580] V, and Control Program ]

c. Within [3] seconds following load rejection, the frequency is [58.8] Hz and [61.2] Hz.

Westinghouse STS 3.8.1-9 Rev. 5.0

AC Sources - Operating 3.8.1 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 [ [18] months maintained [5000] V during and following a load rejection of [4500] kW and [5000] kW. OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.8.1-10 Rev. 5.0

AC Sources - Operating 3.8.1 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 [ [18] months signal:

OR

a. De-energization of emergency buses, In accordance

b. Load shedding from emergency buses, with the Surveillance

c. DG auto-starts from standby condition and: Frequency Control Program ]

1. Energizes permanently connected loads in [10] seconds,

2. Energizes auto-connected shutdown loads through [automatic load sequencer],

3. Maintains steady state voltage

[3740] V and [4580] V,

4. Maintains steady state frequency

[58.8] Hz and [61.2] Hz, and

5. Supplies permanently connected [and auto-connected] shutdown loads for 5 minutes.

Westinghouse STS 3.8.1-11 Rev. 5.0

AC Sources - Operating 3.8.1 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 [ [18] months Feature (ESF) actuation signal each DG auto-starts from standby condition and: OR

a. In [10] seconds after auto-start and during In accordance tests, achieves voltage [3740] V and with the frequency [58.8] Hz, Surveillance Frequency

b. Achieves steady state voltage [3740] V and Control Program ]

[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 auto-connected through the automatic load sequencer] from the offsite power system.

Westinghouse STS 3.8.1-12 Rev. 5.0

AC Sources - Operating 3.8.1 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 [ [18] months bypassed on [actual or simulated loss of voltage signal on the emergency bus concurrent with an OR actual or simulated ESF actuation signal].

In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.8.1-13 Rev. 5.0

AC Sources - Operating 3.8.1 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 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: [ [18] months

a. For [2] hours loaded [5250] kW and OR

[5500] kW and In accordance

b. For the remaining hours of the test loaded with the

[4500] kW and [5000] kW. Surveillance Frequency Control Program ]

Westinghouse STS 3.8.1-14 Rev. 5.0

AC Sources - Operating 3.8.1 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: [ [18] months

a. In [10] seconds, voltage [3740] V and OR frequency [58.8] Hz and In accordance

b. Steady state voltage [3740] V, and [4580] V with the and frequency [58.8] Hz and [61.2] Hz. 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: [ [18] months

a. Synchronizes with offsite power source while OR loaded with emergency loads upon a simulated restoration of offsite power, In accordance with the

b. Transfers loads to offsite power source, and Surveillance Frequency

c. Returns to ready-to-load operation. Control Program ]

Westinghouse STS 3.8.1-15 Rev. 5.0

AC Sources - Operating 3.8.1 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 [ [18] months connected to its bus, an actual or simulated ESF actuation signal overrides the test mode by: OR

a. Returning DG to ready-to-load operation and In accordance with the

b. [Automatically energizing the emergency load Surveillance from offsite power]. 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 [ [18] months is within +/- [10% of design interval] for each emergency [and shutdown] load sequencer. OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.8.1-16 Rev. 5.0

AC Sources - Operating 3.8.1 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 [ [18] months signal in conjunction with an actual or simulated ESF actuation signal: OR

a. De-energization of emergency buses, In accordance with the

b. Load shedding from emergency buses, and Surveillance Frequency

c. DG auto-starts from standby condition and: Control Program ]

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.

Westinghouse STS 3.8.1-17 Rev. 5.0

AC Sources - Operating 3.8.1 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 [ 10 years condition, each DG achieves:

OR

a. In [10] seconds, voltage [3740] V and frequency [58.8] Hz and In accordance with the

b. Steady state voltage [3744] V and [4576] V, Surveillance and frequency [58.8] Hz and [61.2] Hz. Frequency Control Program ]

Westinghouse STS 3.8.1-18 Rev. 5.0

AC Sources - Shutdown 3.8.2 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 -------------------NOTE--------------------

circuit inoperable. 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 Immediately feature(s) with no offsite power available inoperable.

OR Westinghouse STS 3.8.2-1 Rev. 5.0

AC Sources - Shutdown 3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2.1 Suspend movement of Immediately

[recently] irradiated fuel assemblies.

AND A.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.2.3 Initiate action to restore Immediately required offsite power circuit to OPERABLE status.

B. One required DG B.1 Suspend movement of Immediately inoperable. [recently] irradiated fuel assemblies.

AND B.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND B.3 Initiate action to restore Immediately required DG to OPERABLE status.

Westinghouse STS 3.8.2-2 Rev. 5.0

AC Sources - Shutdown 3.8.2 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 In accordance of Specification 3.8.1, "AC Sources - Operating," with applicable except SR 3.8.1.8, SR 3.8.1.12, SR 3.8.1.17, SRs SR 3.8.1.19, and SR 3.8.1.20, are applicable.

Westinghouse STS 3.8.2-3 Rev. 5.0

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 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 A.1 Restore fuel oil level to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> fuel level less than a within limits.

[7] day supply and greater than a [6] day supply in storage tank.

B. One or more DGs with B.1 Restore lube oil inventory to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> lube oil inventory less within limits.

than a [7] day supply and greater than a

[6] day supply.

C. One or more DGs with C.1 Restore fuel oil total 7 days stored fuel oil total particulates to within limits.

particulates not within limit.

D. One or more DGs with D.1 Restore stored fuel oil 30 days new fuel oil properties properties to within limits.

not within limits.

Westinghouse STS 3.8.3-1 Rev. 5.0

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One or more DGs with E.1 Restore starting air receiver 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> starting air receiver pressure to [225] psig.

pressure < [225] psig and [125] psig.

F. Required Action and F.1 Declare associated DG Immediately associated Completion inoperable.

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.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage tank contains a [7] day [ 31 days supply of fuel.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.8.3-2 Rev. 5.0

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 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 In accordance are tested in accordance with, and maintained within with the Diesel the limits of, the Diesel Fuel Oil Testing Program. Fuel Oil Testing Program SR 3.8.3.4 Verify each DG air start receiver pressure is [ 31 days

[225] psig.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.8.3.5 Check for and remove accumulated water from each [ [31] days fuel oil storage tank.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.8.3-3 Rev. 5.0

DC Sources - Operating 3.8.4 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 A.1 Restore battery terminal 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> charger[s] on one voltage to greater than or subsystem inoperable. equal to the minimum established float voltage.

AND A.2 Verify battery float current Once per [12] hours

[2] amps.

AND A.3 Restore battery charger[s] [72] hours to OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

[B. One [or two] batter[y][ies B.1 Restore batter[y][ies] to [2] hours ]

on one subsystem] OPERABLE status.

inoperable. [OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.8.4-1 Rev. 5.0

DC Sources - Operating 3.8.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One DC electrical power C.1 Restore DC electrical [2] hours subsystem inoperable power subsystem to for reasons other than OPERABLE status. [OR Condition A [or B].

In accordance with the Risk Informed Completion Time Program]

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Associated Completion Time not met. AND D.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater than or [ 7 days equal to the minimum established float voltage.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.8.4-2 Rev. 5.0

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.2 Verify each battery charger supplies [400] amps at [ [18] months greater than or equal to the minimum established float voltage for [8] hours. OR OR In accordance with the Verify each battery charger can recharge the battery Surveillance to the fully charged state within [24] hours while Frequency supplying the largest combined demands of the Control Program ]

various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.

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 [ [18] months maintain in OPERABLE status, the required emergency loads for the design duty cycle when OR subjected to a battery service test.

In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.8.4-3 Rev. 5.0

DC Sources - Shutdown 3.8.5 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 A.1 Restore battery terminal 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> charger[s on one voltage to greater than or subsystem] inoperable. equal to the minimum established float voltage.

AND AND The redundant subsystem battery and A.2 Verify battery float current Once per [12] hours charger[s] OPERABLE. [2] amps.

AND Westinghouse STS 3.8.5-1 Rev. 5.0

DC Sources - Shutdown 3.8.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.3 Restore battery charger[s] [72] hours ]

to OPERABLE status.

B. One [or more] required B.1 Declare affected required Immediately DC electrical power feature(s) inoperable.

subsystem[s] inoperable

[for reasons other than OR Condition A.

B.2.1 Suspend movement of Immediately OR [recently] irradiated fuel assemblies.

Required Actions and associated Completion AND Time of Condition A not met]. B.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND B.2.3 Initiate action to restore Immediately required DC electrical power subsystems to OPERABLE status.

Westinghouse STS 3.8.5-2 Rev. 5.0

DC Sources - Shutdown 3.8.5 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 In accordance following SRs are applicable: with applicable SRs SR 3.8.4.1 SR 3.8.4.2 SR 3.8.4.3 Westinghouse STS 3.8.5-3 Rev. 5.0

Battery Parameters 3.8.6 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 A.1 Perform SR 3.8.4.1. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> on one subsystem] with one or more battery cells AND float voltage < [2.07] V.

A.2 Perform SR 3.8.6.1. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> AND A.3 Restore affected cell 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> voltage [2.07] V.

B. One [or two] batter[y][ies B.1 Perform SR 3.8.4.1. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> on one subsystem] with float current > [2] amps. AND B.2 Restore battery float current [12] hours to [2] amps.

Westinghouse STS 3.8.6-1 Rev. 5.0

Battery Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. -----------NOTE------------- -------------------NOTE--------------------

Required Action C.2 Required Actions C.1 and C.2 are shall be completed if only applicable if electrolyte level electrolyte level was was below the top of plates.

below the top of plates. ------------------------------------------------

C.1 Restore electrolyte level to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> One [or two] batter[y][ies above top of plates.

on one subsystem] with one or more cells AND electrolyte level less than minimum C.2 Verify no evidence of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> established design leakage.

limits.

AND C.3 Restore electrolyte level to 31 days greater than or equal to minimum established design limits.

D. One [or two] batter[y][ies D.1 Restore battery pilot cell 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on one subsystem] with temperature to greater than pilot cell electrolyte or equal to minimum temperature less than established design limits.

minimum established design limits.

E. One or more batteries in E.1 Restore battery parameters 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> redundant subsystems for batteries in one with battery parameters subsystem to within limits.

not within limits.

Westinghouse STS 3.8.6-2 Rev. 5.0

Battery Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 Declare associated battery Immediately associated Completion inoperable.

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.

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 ]

Westinghouse STS 3.8.6-3 Rev. 5.0

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.2 Verify each battery pilot cell float voltage is [ 31 days

[2.07] V.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.8.6.3 Verify each battery connected cell electrolyte level is [ 31 days greater than or equal to minimum established design limits. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.8.6.4 Verify each battery pilot cell temperature is greater [ 31 days than or equal to minimum established design limits.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.8.6.5 Verify each battery connected cell float voltage is [ 92 days

[2.07] V.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.8.6-4 Rev. 5.0

Battery Parameters 3.8.6 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 [ 60 months manufacturer's rating when subjected to a performance discharge test or a modified OR performance discharge test.

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 Westinghouse STS 3.8.6-5 Rev. 5.0

Inverters - Operating 3.8.7 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 A.1 --------------NOTE--------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.9, "Distribution Systems - Operating" with any AC vital bus de-energized.

Restore inverter to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.8.7-1 Rev. 5.0

Inverters - Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage, [frequency], and [ 7 days alignment to required AC vital buses.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.8.7-2 Rev. 5.0

Inverters - Shutdown 3.8.8 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] A.1 Declare affected required Immediately inverter[s] inoperable. feature(s) inoperable.

OR A.2.1 Suspend movement of Immediately

[recently] irradiated fuel assemblies.

AND Westinghouse STS 3.8.8-1 Rev. 5.0

Inverters - Shutdown 3.8.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.2.3 Initiate action to restore Immediately required inverters to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage, [frequency,] and [ 7 days alignments to required AC vital buses.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.8.8-2 Rev. 5.0

Distribution Systems - Operating 3.8.9 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 A.1 --------------NOTE--------------

electrical power Enter applicable Conditions distribution subsystems and Required Actions of inoperable. LCO 3.8.4, "DC Sources -

Operating," for DC trains made inoperable by inoperable power distribution subsystems.

Restore AC electrical power 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> distribution subsystem(s) to OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

B. One or more AC vital B.1 Restore AC vital bus 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> buses inoperable. subsystem(s) to OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

Westinghouse STS 3.8.9-1 Rev. 5.0

Distribution Systems - Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more DC C.1 Restore DC electrical 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> electrical power power distribution distribution subsystems subsystem(s) to [OR inoperable. OPERABLE status.

In accordance with the Risk Informed Completion Time Program]

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND D.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> E. Two or more electrical E.1 Enter LCO 3.0.3. Immediately power distribution subsystems inoperable that result in a loss of safety function.

Westinghouse STS 3.8.9-2 Rev. 5.0

Distribution Systems - Operating 3.8.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to [ 7 days

[required] AC, DC, and AC vital bus electrical power distribution subsystems. OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.8.9-3 Rev. 5.0

Distribution Systems - Shutdown 3.8.10 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 A.1 Declare associated Immediately AC, DC, or AC vital bus supported required electrical power feature(s) inoperable.

distribution subsystems inoperable. OR A.2.1 Suspend movement of Immediately

[recently] irradiated fuel assemblies.

AND A.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND Westinghouse STS 3.8.10-1 Rev. 5.0

Distribution Systems - Shutdown 3.8.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2.3 Initiate actions to restore Immediately required AC, DC, and AC vital bus electrical power distribution subsystems to OPERABLE status.

AND A.2.4 Declare associated Immediately required residual heat removal subsystem(s) inoperable and not in operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and voltage to [ 7 days required AC, DC, and AC vital bus electrical power distribution subsystems. OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.8.10-2 Rev. 5.0

Boron Concentration 3.9.1 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 A.1 Suspend positive reactivity Immediately within limit. additions.

AND A.2 Initiate action to restore Immediately boron concentration to within limit.

Westinghouse STS 3.9.1-1 Rev. 5.0

Boron Concentration 3.9.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the limit [ 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> specified in the COLR.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.9.1-2 Rev. 5.0

[Unborated Water Source Isolation Valves]

3.9.2 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------------ A.1 Initiate actions to secure Immediately Required Action A.2 valve in closed position.

must be completed whenever Condition A is AND entered.

---

A.2 Perform SR 3.9.1.1. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> One or more valves not secured in closed position.

Westinghouse STS 3.9.2-1 Rev. 5.0

[Unborated Water Source Isolation Valves]

3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify each valve that isolates unborated water [ 31 days sources is secured in the closed position.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.9.2-2 Rev. 5.0

Nuclear Instrumentation 3.9.3 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 A.1 Suspend positive reactivity Immediately range neutron flux additions.

monitor inoperable.

AND A.2 ------------ NOTE -------------

Fuel assemblies, sources, and reactivity control components may be moved if necessary to restore an inoperable source range neutron flux monitor or to complete movement of a component to a safe condition.

Suspend movement of fuel, Immediately sources, and reactivity control components within the reactor vessel.

Westinghouse STS 3.9.3-1 Rev. 5.0

Nuclear Instrumentation 3.9.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Two [required] source B.1 Initiate action to restore one Immediately range neutron flux source range neutron flux monitors inoperable. monitor to OPERABLE status.

AND B.2 Perform SR 3.9.1.1. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

---

REVIEWER'S NOTE----- C.1 Initiate action to isolate Immediately ]

Condition C is included only unborated water sources.

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.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Perform CHANNEL CHECK. [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.9.3-2 Rev. 5.0

Nuclear Instrumentation 3.9.3 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 ]

Westinghouse STS 3.9.3-3 Rev. 5.0

Containment Penetrations 3.9.4 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 A.1 Suspend movement of Immediately containment [recently] irradiated fuel penetrations not in assemblies within required status. containment.

Westinghouse STS 3.9.4-1 Rev. 5.0

Containment Penetrations 3.9.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify each required containment penetration is in [ 7 days the required status.

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 [ [18] months valve actuates to the isolation position on an actual or simulated actuation signal. OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.9.4-2 Rev. 5.0

RHR and Coolant Circulation - High Water Level 3.9.5 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 A.1 Suspend operations that Immediately not met. 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 Immediately fuel assemblies in the core.

AND A.3 Initiate action to satisfy Immediately RHR loop requirements.

AND Westinghouse STS 3.9.5-1 Rev. 5.0

RHR and Coolant Circulation - High Water Level 3.9.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.4 Close equipment hatch and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> secure with [four] bolts.

AND A.5 Close one door in each air 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> lock.

AND A.6.1 Close each penetration 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> capable of being closed by an OPERABLE Containment Purge and Exhaust Isolation System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one RHR loop is in operation and circulating [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> reactor coolant at a flow rate of [2800] gpm.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.9.5-2 Rev. 5.0

RHR and Coolant Circulation - High Water Level 3.9.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.9.5.2 Verify required RHR loop locations susceptible to [ 31 days gas accumulation are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.9.5-3 Rev. 5.0

RHR and Coolant Circulation - Low Water Level 3.9.6 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 A.1 Initiate action to restore Immediately number of RHR loops required RHR loops to OPERABLE. OPERABLE status.

OR A.2 Initiate action to establish Immediately 23 ft of water above the top of reactor vessel flange.

Westinghouse STS 3.9.6-1 Rev. 5.0

RHR and Coolant Circulation - Low Water Level 3.9.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR loop in B.1 Suspend operations that Immediately operation. 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 Immediately RHR loop to operation.

AND B.3 Close equipment hatch and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> secure with [four] bolts.

AND B.4 Close one door in each air 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> lock.

AND B.5.1 Close each penetration 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> providing direct access from the containment atmosphere to the outside atmosphere with a manual or automatic isolation valve, blind flange, or equivalent.

OR Westinghouse STS 3.9.6-2 Rev. 5.0

RHR and Coolant Circulation - Low Water Level 3.9.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.5.2 Verify each penetration is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> capable of being closed by an OPERABLE Containment Purge and Exhaust Isolation System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify one RHR loop is in operation and circulating [ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> reactor coolant at a flow rate of [2800] gpm.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.9.6.2 Verify correct breaker alignment and indicated [ 7 days power available to the required RHR pump that is not in operation. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.9.6.3 Verify RHR loop locations susceptible to gas [ 31 days accumulation are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.9.6-3 Rev. 5.0

Refueling Cavity Water Level 3.9.7 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 A.1 Suspend movement of Immediately level not within limit. irradiated fuel assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify refueling cavity water level is 23 ft above [ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the top of reactor vessel flange.

OR In accordance with the Surveillance Frequency Control Program ]

Westinghouse STS 3.9.7-1 Rev. 5.0

Design Features 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], ]

Westinghouse STS 4.0-1 Rev. 5.0

Design Features 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.

Westinghouse STS 4.0-2 Rev. 5.0

Responsibility 5.1 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.

Westinghouse STS 5.1-1 Rev. 5.0

Organization 5.2 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 non-licensed operators for the two units.

Westinghouse STS 5.2-1 Rev. 5.0

Organization 5.2 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 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.

Westinghouse STS 5.2-2 Rev. 5.0

Unit Staff Qualifications 5.3 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).

Westinghouse STS 5.3-1 Rev. 5.0

Procedures 5.4 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.

Westinghouse STS 5.4-1 Rev. 5.0

Programs and Manuals 5.5 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.

Westinghouse STS 5.5-1 Rev. 5.0

Programs and Manuals 5.5 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

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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 Westinghouse STS 5.5-2 Rev. 5.0

Programs and Manuals 5.5 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, Westinghouse STS 5.5-3 Rev. 5.0

Programs and Manuals 5.5 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 pre-stressed 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. ]

Westinghouse STS 5.5-4 Rev. 5.0

Programs and Manuals 5.5 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.

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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 Steam Generator (SG) Program An SG Program shall be established and implemented to ensure that SG tube integrity is maintained. In addition, the SG Program shall include the following:

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 SG 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), 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 Westinghouse STS 5.5-5 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program (continued) the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse. In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads.

2. Accident induced leakage performance criterion: The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to exceed [1 gpm] per SG [, except for specific types of degradation at specific locations as described in paragraph c of the SG Program.]

3. The operational LEAKAGE performance criterion is specified in LCO 3.4.13, "RCS Operational LEAKAGE."

c. Provisions for SG tube plugging [or 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].

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

Alternate tube plugging [or repair] criteria currently permitted by plant technical specifications are listed here. The description of these alternate tube plugging [or 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 plugging

[or repair] criteria.

[The following alternate tube plugging [or repair] criteria may be applied as an alternative to the 40% depth based criteria:

1. . . .]

---

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

The bracketed phrase in Paragraph d regarding exempt portions of the tube is only applicable to SGs with Alloy 600 thermally treated tubing.

Westinghouse STS 5.5-6 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program (continued)

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 [except for any portions of the tube that are exempt from inspection by alternate repair criteria], and that may satisfy the applicable tube plugging [or 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. A degradation assessment shall be performed to determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.

---

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

Plants are to include the appropriate Frequency (e.g., select the appropriate Item 2.) for their SG design. The first Item 2 is applicable to SGs with Alloy 600 mill annealed tubing. The second Item 2 is applicable to SGs with Alloy 600 thermally treated tubing. The third Item 2 is applicable to SGs with Alloy 690 thermally treated tubing.

1. Inspect 100% of the tubes in each SG during the first refueling outage following SG installation.

[2. After the first refueling outage following SG installation, inspect 100%

of the tubes in each SG at least every 24 effective full power months, which defines the inspection period. ]

[2. After the first refueling outage following SG installation, inspect 100%

of the tubes in each SG at least every 54 effective full power months, which defines the inspection period. If none of the SG tubes have ever experienced cracking other than in regions that are exempt from inspection by alternate repair criteria and the SG inspection was performed with enhanced probes, the inspection period may be extended to 72 effective full power months. Enhanced probes have a capability to detect flaws of any type equivalent to or better than array probe technology. The enhanced probes shall be used from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet except any portions of the tube that are exempt from inspection by alternate repair criteria. If there are regions where enhanced probes cannot be used, the tube inspection techniques shall Westinghouse STS 5.5-7 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program (continued) be capable of detecting all forms of existing and potential degradation in that region.]

[2. After the first refueling outage following SG installation, inspect 100%

of the tubes in each SG at least every 96 effective full power months, which defines the inspection period. ]

---

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

The bracketed phrases in Paragraph 3 are only applicable to SGs with Alloy 600 thermally treated tubing.

3. If crack indications are found in any SG tube [excluding any region that is exempt from inspection by alternate repair criteria], then the next inspection for each affected and potentially affected SG for the degradation mechanism that caused the crack indication shall be at the next refueling outage [, but may be deferred to the following refueling outage if the 100% inspection of all SGs was performed with enhanced probes as described in paragraph d.2]. If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack.

e. Provisions for monitoring operational primary to secondary LEAKAGE.

[f. Provisions for SG tube repair methods. SG 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.

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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. . . .]

Westinghouse STS 5.5-8 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit SG tube degradation and low pressure turbine disc stress corrosion cracking. The program shall include:

a. Identification of a sampling schedule for the critical variables and control points for these variables,

b. Identification of the procedures used to measure the values of the critical variables,

c. Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in leakage,

d. Procedures for the recording and management of data,

e. Procedures defining corrective actions for all off control point chemistry conditions, and

f. A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action.

5.5.10 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

[ ] [ ]

Westinghouse STS 5.5-9 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Ventilation Filter Testing Program (VFTP) (continued)

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]

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

The use of any standard other than ASTM D3803-1989 to test the charcoal sample may result in an overestimation of the capability of the charcoal to adsorb radioiodine. As a result, the ability of the charcoal filters to perform in a manner consistent with the licensing basis for the facility is indeterminate.

ASTM D 3803-1989 is a more stringent testing standard because it does not differentiate between used and new charcoal, it has a longer equilibration period performed at a temperature of 30°C (86°F) and a relative humidity (RH) of 95%

(or 70% RH with humidity control), and it has more stringent tolerances that improve repeatability of the test.

Allowable Penetration = [(100% - Methyl Iodide 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.

Westinghouse STS 5.5-10 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Ventilation Filter Testing Program (VFTP) (continued)

If the system has a face velocity greater than 110 percent of 0.203 m/s (40 ft/min), the face velocity should be specified.

• This value should be the efficiency that was incorporated in the licensee's accident analysis which was reviewed and approved by the staff in a safety evaluation.

d. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested in accordance with [Regulatory Guide 1.52, Revision 2, and ASME N510-1989] at the system flowrate specified below [+/- 10%].

ESF Ventilation System Delta P Flowrate

[ ] [ ] [ ]

[ e. Demonstrate that the heaters for each of the ESF systems dissipate the value specified below [+/- 10%] when tested in accordance with

[ASME N510-1989].

ESF Ventilation System Wattage ]

[ ] [ ]

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

5.5.11 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"].

Westinghouse STS 5.5-11 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued)

The program shall include:

a. The limits for concentrations of hydrogen and oxygen in the [Waste Gas Holdup System] and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion),

b. A surveillance program to ensure that the quantity of radioactivity contained in [each gas storage tank and fed into the offgas treatment system] is less than the amount that would result in a whole body exposure of 0.5 rem to any individual in an unrestricted area, in the event of [an uncontrolled release of the tanks' contents], and

c. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the [Liquid Radwaste Treatment System] is less than the amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

5.5.12 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.

Westinghouse STS 5.5-12 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Diesel Fuel Oil Testing Program (continued)

b. Within 31 days following addition of the new fuel oil to storage tanks, verify that the properties of the new fuel oil, other than those addressed in a.,

above, are within limits for ASTM 2D fuel oil, and

c. Total particulate concentration of the fuel oil is 10 mg/l when tested every 31 days.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program test frequencies.

5.5.13 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1. A change in the TS incorporated in the license or

2. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.

d. Proposed changes that meet the criteria of Specification 5.5.13b 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).

Westinghouse STS 5.5-13 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Safety Function Determination Program (SFDP)

This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6. The SFDP shall contain the following:

a. Provisions for cross train checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected,

b. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists,

c. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities, and

d. Other appropriate limitations and remedial or compensatory actions.

A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power, or no concurrent loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a. A required system redundant to the system(s) supported by the inoperable support system is also inoperable, or

b. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable, or

c. A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable.

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

Westinghouse STS 5.5-14 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 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.

Westinghouse STS 5.5-15 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 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, "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, 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].

Westinghouse STS 5.5-16 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 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:

Westinghouse STS 5.5-17 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 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.

5.5.16 Battery Monitoring and Maintenance Program

---

REVIEWERS 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.

Westinghouse STS 5.5-18 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 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.

5.5.17 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 Westinghouse STS 5.5-19 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.17 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.

Westinghouse STS 5.5-20 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals

[ 5.5.18 Setpoint Control Program

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

Adoption of a Setpoint Control Program requires changes to other technical specifications. See TSTF-493, Revision 4, "Clarify Application of Setpoint Methodology for LSSS Functions," Option B, for guidance (Agencywide Documents Access and Management System (ADAMS) Accession Number ML101160026).

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.

Westinghouse STS 5.5-21 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Setpoint Control Program (continued)

1. [Insert reference to NRC safety evaluation that approved the setpoint methodology.]

c. The program shall establish methods to ensure that Functions described in paragraph a. will function as required by verifying the as-left and as-found settings are consistent with those established by the setpoint methodology.

d. -----------------------------------REVIEWERS 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.

Westinghouse STS 5.5-22 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Setpoint Control Program (continued)

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 pre-defined test acceptance criteria band (i.e., the specified AFT), then the instrument channel shall be evaluated before declaring the SR met and returning the instrument channel to service. This condition shall be entered in the plant corrective action program.

3. If the as-found value of the instrument channel trip setting is less conservative than the specified AV, then the SR is not met and the instrument channel shall be immediately declared inoperable.

4. The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the 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]. ]

[ 5.5.19 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. ]

[ 5.5.20 Risk Informed Completion Time Program This program provides controls to calculate a Risk Informed Completion Time (RICT) and must be implemented in accordance with NEI 06-09-A, Revision 0, "Risk-Managed Technical Specifications (RMTS) Guidelines." The program shall include the following:

Westinghouse STS 5.5-23 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.20 Risk Informed Completion Time Program (continued)

a. The RICT may not exceed 30 days;

---

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

The Risk Informed Completion Time is only applicable in MODES supported by the licensee's PRA. Licensees applying the RICT Program to MODES other than MODES 1 and 2 must demonstrate that they have the capability to calculate a RICT in those MODES or that the risk indicated by their MODE 1 and 2 PRA model is bounding with respect to the lower MODE conditions.

b. A RICT may only be utilized in MODE 1, 2 [, and 3, and MODE 4 while relying on steam generators for heat removal];

c. When a RICT is being used, any change to the plant configuration, as defined in NEI 06-09-A, Appendix A, must be considered for the effect on the RICT.

1. For planned changes, the revised RICT must be determined prior to implementation of the change in configuration.

2. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e., not the RICT) or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the plant configuration change, whichever is less.

3. Revising the RICT is not required if the plant configuration change would lower plant risk and would result in a longer RICT.

d. For emergent conditions, if the extent of condition evaluation for inoperable structures, systems, or components (SSCs) is not complete prior to exceeding the Completion Time, the RICT shall account for the increased possibility of common cause failure (CCF) by either:

1. Numerically accounting for the increased possibility of CCF in the RICT calculation; or

2. Risk Management Actions (RMAs) not already credited in the RICT calculation shall be implemented that support redundant or diverse SSCs that perform the function(s) of the inoperable SSCs, and, if practicable, reduce the frequency of initiating events that challenge the function(s) performed by the inoperable SSCs.

Westinghouse STS 5.5-24 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.20 Risk Informed Completion Time Program (continued)

e. The risk assessment approaches and methods shall be acceptable to the NRC. The plant PRA shall be based on the as-built, as-operated, and maintained plant; and reflect the operating experience at the plant, as specified in Regulatory Guide 1.200, Revision 2. Methods to assess the risk from extending the Completion Times must be PRA methods used to support this license amendment, or other methods approved by the NRC for generic use; and any change in the PRA methods to assess risk that are outside these approval boundaries require prior NRC approval ].

[ 5.5.21 Spent Fuel Storage Rack Neutron Absorber Monitoring Program This Program provides controls for monitoring the condition of the neutron absorber used in the spent fuel pool storage racks to verify the Boron-10 areal density is consistent with the assumptions in the spent fuel pool criticality analysis. The program shall be in accordance with NEI 16-03-A, "Guidance for Monitoring of Fixed Neutron Absorbers in Spent Fuel Pools," Revision 0, May 2017 [, with the following exceptions:

1. . . . ].]

Westinghouse STS 5.5-25 Rev. 5.0

Reporting Requirements 5.6 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.

Westinghouse STS 5.6-1 Rev. 5.0

Reporting Requirements 5.6 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:

---

REVIEWERS 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. ]

Westinghouse STS 5.6-2 Rev. 5.0

Reporting Requirements 5.6 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:

---

REVIEWERS 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 NRC-approved 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.

Westinghouse STS 5.6-3 Rev. 5.0

Reporting Requirements 5.6 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 (2) specified in Regulatory Guide 1.99, Revision 2. If the measured value exceeds the predicted value (increase RTNDT + 2), the licensee should provide a supplement to the PTLR to demonstrate how the results affect the approved methodology.

5.6.5 Post Accident Monitoring Report When a report is required by Condition B or F of LCO 3.3.[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. The nondestructive examination techniques utilized for tubes with increased degradation susceptibility;

c. For each degradation mechanism found:

1. The nondestructive examination techniques utilized; Westinghouse STS 5.6-4 Rev. 5.0

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 Steam Generator Tube Inspection Report (continued)

2. The location, orientation (if linear), measured size (if available), and voltage response for each indication. For tube wear at support structures less than 20 percent through-wall, only the total number of indications needs to be reported;

3. A description of the condition monitoring assessment and results, including the margin to the tube integrity performance criteria and comparison with the margin predicted to exist at the inspection by the previous forward-looking tube integrity assessment;

4. The number of tubes plugged [or repaired] during the inspection outage; and

[5. The repair methods utilized and the number of tubes repaired by each repair method.]

d. An analysis summary of the tube integrity conditions predicted to exist at the next scheduled inspection (the forward-looking tube integrity assessment) relative to the applicable performance criteria, including the analysis methodology, inputs, and results;

e. The number and percentage of tubes plugged [or repaired] to date, and the effective plugging percentage in each SG;

f. The results of any SG secondary side inspections; and

[g. Insert any plant-specific reporting requirements, if applicable.]

Westinghouse STS 5.6-5 Rev. 5.0

High Radiation Area 5.7 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 Westinghouse STS 5.7-1 Rev. 5.0

High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

(ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:

1. All such door and gate keys shall be maintained under the administrative control of the shift supervisor, radiation protection manager, or his or her 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.

Westinghouse STS 5.7-2 Rev. 5.0

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

d. Each individual or group entering such an area shall possess:

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 displays radiation dose rates in the area.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

Westinghouse STS 5.7-3 Rev. 5.0

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

Westinghouse STS 5.7-4 Rev. 5.0

NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER (12-2010) (Assigned by NRC, Add Vol., Supp., Rev.,

NRCMD 3.7 and Addendum Numbers, if any.)

BIBLIOGRAPHIC DATA SHEET NUREG-1431, Volume 1, (See instructions on the reverse) Revision 5.0

2. TITLE AND SUBTITLE 3. DATE REPORT PUBLISHED Standard Technical Specifications, Westinghouse Plants: Specifications (Revision 5) MONTH YEAR September 2021

4. FIN OR GRANT NUMBER

5. AUTHOR(S) 6. TYPE OF REPORT Multiple Technical

7. PERIOD COVERED (Inclusive Dates)

8. PERFORMING ORGANIZATION - NAME AND ADDRESS (If NRC, provide Division, Office or Region, U. S. Nuclear Regulatory Commission, and mailing address; if contractor, provide name and mailing address.)

Division of Safety Systems Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

9. SPONSORING ORGANIZATION - NAME AND ADDRESS (If NRC, type "Same as above", if contractor, provide NRC Division, Office or Region, U. S. Nuclear Regulatory Commission, and mailing address.)

Save as above

10. SUPPLEMENTARY NOTES

11. ABSTRACT (200 words or less)

This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. The changes reflected in Revision 5 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 5 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.

12. KEY WORDS/DESCRIPTORS (List words or phrases that will assist researchers in locating the report.) 13. AVAILABILITY STATEMENT NUREG-1431 unlimited Standard Technical Specifications 14. SECURITY CLASSIFICATION STS (This Page)

Westinghouse unclassified (This Report) unclassified

15. NUMBER OF PAGES

16. PRICE NRC FORM 335 (12-2010)

NUREG-1431, Volume 1 Standard Technical Specifications September 2021 Revision 5 Westinghouse Plants: Specifications