MNS-14-088, Technical Specification Bases TOC

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Technical Specification Bases TOC
ML14342A413
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 11/04/2014
From:
Duke Energy Carolinas
To:
Office of Nuclear Reactor Regulation
Shared Package
ML14339A712 List: ... further results
References
MNS-14-088
Download: ML14342A413 (3)


Text

TABLE OF CONTENTS McGuire Units 1 and 2 i

Revision No. 87 B 2.0 SAFETY LIMITS (SLs)

B 2.1.1 Reactor Core SLs........................................................................... B 2.1.1-1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL.................................. B 2.1.2-1 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY....... B 3.0-1 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY...................... B 3.0-9 B 3.1 REACTIVITY CONTROL SYSTEMS B 3.1.1 SHUTDOWN MARGIN (SDM)........................................................ B 3.1.1-1 B 3.1.2 Core Reactivity................................................................................ B 3.1.2-1 B 3.1.3 Moderator Temperature Coefficient (MTC)..................................... B 3.1.3-1 B 3.1.4 Rod Group Alignment Limits........................................................... B 3.1.4-1 B 3.1.5 Shutdown Bank Insertion Limits...................................................... B 3.1.5-1 B 3.1.6 Control Bank Insertion Limits.......................................................... B 3.1.6-1 B 3.1.7 Rod Position Indication................................................................... B 3.1.7-1 B 3.1.8 PHYSICS TESTS Exceptions......................................................... B 3.1.8-1 B 3.2 POWER DISTRIBUTION LIMITS B 3.2.1 Heat Flux Hot Channel Factor (FQ(X,Y,Z))..................................... B 3.2.1-1 B 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FH(X,Y))................... B 3.2.2-1 B 3.2.3 AXIAL FLUX DIFFERENCE (AFD)................................................. B 3.2.3-1 B 3.2.4 QUADRANT POWER TILT RATIO (QPTR).................................... B 3.2.4-1 B 3.3 INSTRUMENTATION B 3.3.1 Reactor Trip System (RTS) Instrumentation................................... B 3.3.1-1 B 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation....................................................................... B 3.3.2-1 B 3.3.3 Post Accident Monitoring (PAM) Instrumentation............................ B 3.3.3-1 B 3.3.4 Remote Shutdown System.............................................................. B 3.3.4-1 B 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation B 3.3.5-1 B 3.3.6 Not Used......................................................................................... B 3.3.6-1 B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits................................................. B 3.4.1-1 B 3.4.2 RCS Minimum Temperature for Criticality....................................... B 3.4.2-1 B 3.4.3 RCS Pressure and Temperature (P/T) Limits.................................. B 3.4.3-1 B 3.4.4 RCS LoopsMODES 1 and 2........................................................ B 3.4.4-1 B 3.4.5 RCS LoopsMODE 3.................................................................... B 3.4.5-1 B 3.4.6 RCS LoopsMODE 4.................................................................... B 3.4.6-1 B 3.4.7 RCS LoopsMODE 5, Loops Filled............................................... B 3.4.7-1 B 3.4.8 RCS LoopsMODE 5, Loops Not Filled......................................... B 3.4.8-1 B 3.4.9 Pressurizer...................................................................................... B 3.4.9-1 B 3.4.10 Pressurizer Safety Valves............................................................... B 3.4.10-1 B 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)...................... B 3.4.11-1 B 3.4.12 Low Temperature Overpressure Protection (LTOP) System........... B 3.4.12-1 B 3.4.13 RCS Operational LEAKAGE........................................................... B 3.4.13-1

TABLE OF CONTENTS McGuire Units 1 and 2 ii Revision No. 87 B 3.4 REACTOR COOLANT SYSTEM (RCS) (continued)

B 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage................................. B 3.4.14-1 B 3.4.15 RCS Leakage Detection Instrumentation........................................ B 3.4.15-1 B 3.4.16 RCS Specific Activity....................................................................... B 3.4.16-1 B 3.4.17 RCS LoopsTest Exceptions......................................................... B 3.4.17-1 B 3.4.18 Steam Generator (SG) Tube Integrity...............................................B 3.4.18-1 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

B 3.5.1 Accumulators.................................................................................. B 3.5.1-1 B 3.5.2 ECCSOperating........................................................................... B 3.5.2-1 B 3.5.3 ECCSShutdown.......................................................................... B 3.5.3-1 B 3.5.4 Refueling Water Storage Tank (RWST).......................................... B 3.5.4-1 B 3.5.5 Seal Injection Flow.......................................................................... B 3.5.5-1 B 3.6 CONTAINMENT SYSTEMS B 3.6.1 Containment................................................................................... B 3.6.1-1 B 3.6.2 Containment Air Locks.................................................................... B 3.6.2-1 B 3.6.3 Containment Isolation Valves.......................................................... B 3.6.3-1 B 3.6.4 Containment Pressure.................................................................... B 3.6.4-1 B 3.6.5 Containment Air Temperature......................................................... B 3.6.5-1 B 3.6.6 Containment Spray System............................................................ B 3.6.6-1 B 3.6.7 Not Used.........................................................................................

B 3.6.8 Hydrogen Skimmer System (HSS).................................................. B 3.6.8-1 B 3.6.9 Hydrogen Mitigation System (HMS)................................................ B 3.6.9-1 B 3.6.10 Annulus Ventilation System (AVS).................................................. B 3.6.10-1 B 3.6.11 Air Return System (ARS)................................................................ B 3.6.11-1 B 3.6.12 Ice Bed........................................................................................... B 3.6.12-1 B 3.6.13 Ice Condenser Doors...................................................................... B 3.6.13-1 B 3.6.14 Divider Barrier Integrity................................................................... B 3.6.14-1 B 3.6.15 Containment Recirculation Drains................................................... B 3.6.15-1 B 3.6.16 Reactor Building.............................................................................. B 3.6.16-1 B 3.7 PLANT SYSTEMS B 3.7.1 Main Steam Safety Valves (MSSVs)............................................... B 3.7.1-1 B 3.7.2 Main Steam Isolation Valves (MSIVs)............................................. B 3.7.2-1 B 3.7.3 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Control Valves (MFCVs), MFCV's Bypass Valves and Main Feedwater (MFW) to Auxiliary Feedwater (AFW)

Nozzle Bypass Valves (MFW/AFW NBVs).............................. B 3.7.3-1 B 3.7.4 Steam Generator Power Operated Relief Valves (SG PORVs)....... B 3.7.4-1 B 3.7.5 Auxiliary Feedwater (AFW) System................................................ B 3.7.5-1 B 3.7.6 Component Cooling Water (CCW) System..................................... B 3.7.6-1 B 3.7.7 Nuclear Service Water System (NSWS)......................................... B 3.7.7-1 B 3.7.8 Standby Nuclear Service Water Pond (SNSWP)............................ B 3.7.8-1 B 3.7.9 Control Room Area Ventilation System (CRAVS)........................... B 3.7.9-1 B 3.7.10 Control Room Area Chilled Water System (CRACWS)................... B 3.7.10-1 B 3.7.11 Auxiliary Building Filtered Ventilation Exhaust System (ABFVES)... B 3.7.11-1

TABLE OF CONTENTS McGuire Units 1 and 2 iii Revision No. 87 B 3.7 PLANT SYSTEMS (continued)

B 3.7.12 Fuel Handling Ventilation Exhaust System (FHVES)....................... B 3.7.12-1 B 3.7.13 Spent Fuel Pool Water Level.......................................................... B 3.7.13-1 B 3.7.14 Spent Fuel Pool Boron Concentration............................................. B 3.7.14-1 B 3.7.15 Spent Fuel Assembly Storage......................................................... B 3.7.15-1 B 3.7.16 Secondary Specific Activity............................................................. B 3.7.16-1 B 3.8 ELECTRICAL POWER SYSTEMS B 3.8.1 AC SourcesOperating................................................................. B 3.8.1-1 B 3.8.2 AC SourcesShutdown................................................................. B 3.8.2-1 B 3.8.3 Diesel Fuel Oil and Starting Air....................................................... B 3.8.3-1 B 3.8.4 DC SourcesOperating................................................................. B 3.8.4-1 B 3.8.5 DC SourcesShutdown................................................................. B 3.8.5-1 B 3.8.6 Battery Cell Parameters.................................................................. B 3.8.6-1 B 3.8.7 InvertersOperating....................................................................... B 3.8.7-1 B 3.8.8 InvertersShutdown...................................................................... B 3.8.8-1 B 3.8.9 Distribution SystemsOperating.................................................... B 3.8.9-1 B 3.8.10 Distribution SystemsShutdown.................................................... B 3.8.10-1 B 3.9 REFUELING OPERATIONS B 3.9.1 Boron Concentration....................................................................... B 3.9.1-1 B 3.9.2 Unborated Water Source Isolation Valves...................................... B 3.9.2-1 B 3.9.3 Nuclear Instrumentation.................................................................. B 3.9.3-1 B 3.9.4 Containment Penetrations............................................................... B 3.9.4-1 B 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation High Water Level................................................................. B 3.9.5-1 B 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation Low Water Level.................................................................. B 3.9.6-1 B 3.9.7 Refueling Cavity Water Level.......................................................... B 3.9.7-1