Standard Technical Specifications Westinghouse Plants ...

1 Standard Technical Specifications Westinghouse Plants Revision Volume 1, Specifications Office of Nuclear Reactor Regulation NUREG-1431 Volume 1 Revision Standard Technical Specifications Westinghouse Plants Revision Volume 1, Specifications Manuscript Completed: October 2011 Date Published: April 2012 Office of Nuclear Reactor Regulation NUREG-1431 Volume 1 Revision AVAILABILITY OF REFERENCE MATERIALS IN NRC PUBLICATIONS NRC Reference Material As of November 1999, you may electronically access NUREG-series publications and other NRC records at NRC=s Public Electronic Reading Room at Publicly released records include, to name a few, NUREG-series publications; Federal Register notices; applicant, licensee, and vendor documents and correspondence; NRC correspondence and internal memoranda; bulletins and information notices; inspection and investigative reports; licensee event reports; and Commission papers and their attachments.

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5 Westinghouse STS iii Rev. ABSTRACT This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse Plants . The changes reflected in Revision 4 result from the experience gained from plant operation using the improved STS and extensive public Technical meetings and discussions among the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees and the Nuclear Steam Supply System (NSSS) Owners Groups. The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132), which was subsequently codified by changes to Section 36 of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR ) (60 FR 36953). Licensees are encouraged to upgrade their Technical Specifications consistent with those criteria and conforming, to the practical extent, to Revision 4 to the improved STS.

6 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 ( ). Users may print or download copies from the NRC Web site. PAPERWORK REDUCTION ACT STATEMENT The information collections contained in this NUREG are covered by the requirements of 10 CFR Part 50, which were approved by the Office of Management and Budget, approval number 3150-0011. PUBLIC PROTECTION NOTIFICATION If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

7 Westinghouse STS v Rev. TABLE OF CONTENTS / REVISION SUMMARY Page Rev. USE AND APPLICATION Definitions .. Logical Connectors .. Completion Times .. Frequency .. SAFETY LIMITS (SLs) .. SLs SL Violations LIMITING CONDITION FOR OPERATION APPLICABILITY .. SURVEILLANCE REQUIREMENT APPLICABILITY .. REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN (SDM) .. Core Reactivity .. Moderator Temperature Coefficient (MTC) .. Rod Group Alignment Limits .. Shutdown Bank Insertion Limits .. Control Bank Insertion Limits .. Rod Position Indication .. PHYSICS TESTS Exceptions - MODE 2 .. POWER DISTRIBUTION LIMITS Heat Flux Hot Channel Factor (FQ(Z)) (CAOC-FXY Methodology) .. Heat Flux Hot Channel Factor (FQ(Z)) (RAOC-W(Z) Methodology) .. Heat Flux Hot Channel Factor (FQ(Z)) (CAOC-W(Z) Methodology).

8 Nuclear Enthalpy Rise Hot Channel Factor (NHF ) .. AXIAL FLUX DIFFERENCE (Constant Axial Offset Control Methodology) .. AXIAL FLUX DIFFERENCE (Relaxed Axial Offset Control Methodology) .. QUADRANT POWER TILT RATIO .. INSTRUMENTATION (Section Specifications with an "A" suffix include setpoints. Specifications with a "B" suffix reflect a Setpoint Control Program.) Reactor Trip System (RTS) Instrumentation .. Reactor Trip System (RTS) Instrumentation .. Engineered Safety Feature Actuation System (ESFAS) Instrumentation .. Engineered Safety Feature Actuation System (ESFAS) Instrumentation .. Post Accident Monitoring (PAM) Instrumentation .. Remote Shutdown System .. Westinghouse STS vi Rev. TABLE OF CONTENTS / REVISION SUMMARY Page Rev. INSTRUMENTATION (continued) Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.

9 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation .. Containment Purge and Exhaust Isolation Instrumentation .. Containment Purge and Exhaust Isolation Instrumentation .. Control Room Emergency Filtration System (CREFS) Actuation Instrumentation .. Control Room Emergency Filtration System (CREFS) Actuation Instrumentation .. Fuel Building Air Cleanup System (FBACS) Actuation Instrumentation .. Fuel Building Air Cleanup System (FBACS) Actuation Instrumentation .. Boron Dilution Protection System (BDPS) .. Boron Dilution Protection System (BDPS) .. REACTOR COOLANT SYSTEM (RCS) RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits .. RCS Minimum Temperature for Criticality.

10 RCS Pressure and Temperature Limits .. RCS Loops - MODES 1 and 2 .. RCS Loops - MODE 3 .. RCS Loops - MODE 4 .. RCS Loops - MODE 5, Loops Filled .. RCS Loops - MODE 5, Loops Not Filled .. Pressurizer .. Pressurizer Safety Valves .. Pressurizer Power Operated Relief Valves .. Low Temperature Overpressure Protection System .. RCS Operational LEAKAGE .. RCS Pressure Isolation Valve Leakage .. RCS Leakage Detection Instrumentation .. RCS Specific Activity .. RCS Loop Isolation Valves .. RCS Isolated Loop Startup .. RCS Loops - Test Exceptions .. Steam Generator (SG) Tube Integrity .. EMERGENCY CORE COOLING SYSTEMS (ECCS) Accumulators.