Text

Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual
	ML16357A549
Person / Time
Site:	Byron, Braidwood
Issue date:	12/15/2016
From:	; Exelon Generation Co
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML16357A264	List: ML16357A507; ML16357A508; ML16357A509; ML16357A521; ML16357A523; ML16357A524; ML16357A526; ML16357A529; ML16357A530; ML16357A532; ML16357A533; ML16357A534; ML16357A535; ML16357A536; ML16357A537; ML16357A540; ML16357A545; ML16357A549; ML16357A579; ML16357A580; ML16357A583; ML16357A584; ML16357A591; ML16357A592; ML16357A593; ML17086A588; ML17086A589; ML17086A590; ML17086A591; ML17086A592; ML17086A593; ML17086A595; ML17086A596; ML17086A597; ML17086A598; ML17086A599; ML17086A600; ML17086A601; ML17094A865; ML17095A852; ML17095A866; RS-16-248, Braidwood Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-1; RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual; RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases; RS-16-248, Byron Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-1; RS-16-248, Byron Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases; RS-16-248, Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 4.0, Fire Protection Program; RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix B - Construct Material Standards and Quality Control Procedures; RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix C - Deleted; RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix D - Computer Programs; ... further results
References
	RS-16-248
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BRAIDWOOD -UNITS 1 & 2 i Revision 95AFFECTED PAGE LIST -TECHNICAL REQUIREMENTS MANUAL1.0USE AND APPLICATION1.1-1.......................................Revision 11.1-2.......................................Revision 69 1.1-3.......................................Revision 13 1.1-4.......................................Revision 841.1-5.......................................Revision 751.1-6.......................................Revision 75 1.1-7.......................................Revision 93 1.2-1.......................................Revision 1 1.2-2.......................................Revision 11.2-3.......................................Revision 11.3-1.......................................Revision 1 1.3-2.......................................Revision 1 1.3-3.......................................Revision 11.3-4.......................................Revision 11.3-5.......................................Revision 1 1.3-6.......................................Revision 1 1.3-7.......................................Revision 1 1.3-8.......................................Revision 11.3-9.......................................Revision 11.3-10......................................Revision 1 1.3-11......................................Revision 1 1.3-12......................................Revision 1 1.3-13......................................Revision 11.3-14......................................Revision 11.4-1.......................................Revision 1 1.4-2.......................................Revision 38 1.4-3.......................................Revision 1 1.4-4.......................................Revision 11.4-5.......................................Revision 11.4-6.......................................Revision 1 1.4-7.......................................Revision 1 1.5-1.......................................Revision 11.6-1.......................................Revision 132.0.aRTS INSTRUMENTATION TRIP SETPOINTS2.0.a-1.....................................Revision 522.0.a-2.....................................Revision 522.0.a-3.....................................Revision 522.0.bESFAS INSTRUMENTATION TRIP SETPOINTS2.0.b-1.....................................Revision 522.0.b-2.....................................Revision 522.0.b-3.....................................Revision 922.0.b-4.....................................Revision 952.0.cBDPS INSTRUMENTATION TRIP SETPOINT2.0.c-1.....................................Revision 52 BRAIDWOOD -UNITS 1 & 2 ii Revision 95AFFECTED PAGE LIST -TECHNICAL REQUIREMENTS MANUAL2.1.aMISCELLANEOUS TEST REQUIREMENTS2.1.a-1.....................................Revision 12.1.a-2.....................................Revision 12.1.a-3.....................................Revision 1 2.1.a-4.....................................Revision 1 2.1.a-5.....................................Revision 28 2.1.a-6.....................................Revision 282.1.a-7.....................................Revision 622.1.a-8.....................................Revision 62 2.1.a-9.....................................Revision 62 2.1-a-10....................................Revision 623.0TRM LIMITING CONDITION FOR OPERATION (TLCO) AND SURVEILLANCE REQUIREMENT (TSR) APPLICABILITY3.0-1.......................................Revision 1 3.0-2.......................................Revision 37 3.0-3.......................................Revision 13.0-4.......................................Revision 233.0-5.......................................Revision 373.1REACTIVITY CONTROL SYSTEMS3.1.a-1.....................................Revision 6 3.1.a-2.....................................Revision 1 3.1.b-1.....................................Revision 1 3.1.b-2.....................................Revision 1 3.1.b-3.....................................Revision 903.1.c-1.....................................Revision 63.1.d-1.....................................Revision 1 3.1.d-2.....................................Revision 1 3.1.e-1.....................................Revision 6 3.1.e-2.....................................Revision 13.1.e-3.....................................Revision 883.1.f-1.....................................Revision 1 3.1.f-2.....................................Revision 1 3.1.g-1.....................................Revision 11 3.1.g-2.....................................Revision 113.1.h-1.....................................Revision 13.1.h-2.....................................Revision 1 3.1.i-1.....................................Revision 18 3.1.i-2.....................................Revision 13.1.j-1.....................................Revision 13.1.j-2.....................................Revision 1 3.1.k-1.....................................Revision 14 3.1.k-2.....................................Revision 11 3.1.k-3.....................................Revision 113.2POWER DISTRIBUTION LIMITS None BRAIDWOOD -UNITS 1 & 2 iii Revision 95AFFECTED PAGE LIST -TECHNICAL REQUIREMENTS MANUAL3.3INSTRUMENTATION3.3.a-1.....................................Revision 293.3.a-2.....................................Revision 12 3.3.b-1.....................................Revision 1 3.3.b-2.....................................Revision 1 3.3.b-3.....................................Revision 13.3.b-4.....................................Revision 883.3.c-1.....................................Revision 1 3.3.c-2.....................................Revision 1 3.3.c-3.....................................Revision 1 3.3.d-1.....................................Revision 13.3.d-2.....................................Revision 13.3.d-3.....................................Revision 1 3.3.e-1.....................................Revision 1 3.3.e-2.....................................Revision 1 3.3.e-3.....................................Revision 13.3.e-4.....................................Revision 463.3.f-1.....................................Revision 1 3.3.f-2.....................................Revision1 3.3.f-3.....................................Revision 493.3.g-1.....................................Revision 573.3.g-2.....................................Revision 57 3.3.g-3.....................................Revision 57 3.3.g-4.....................................Revision 8 3.3.g-5.....................................Revision 703.3.g-6.....................................Revision 573.3.h-1.....................................Revision 16 3.3.h-2.....................................Revision 16 3.3.h-3.....................................Revision 16 3.3.h-4.....................................Revision 163.3.h-5.....................................Revision 163.3.i-1.....................................Revision 37 3.3.i-2.....................................Revision 1 3.3.i-3.....................................Revision 1 3.3.i-4.....................................Revision 13.3.j-1.....................................Revision 383.3.j-2.....................................Revision 38 3.3.k-1.....................................Revision 84 3.3.k-2.....................................Revision 913.3.o-1.....................................Revision 13.3.o-2.....................................Revision 1 3.3.o-3.....................................Revision 1 3.3.o-4.....................................Revision 1 3.3.p-1.....................................Revision 13.3.p-2.....................................Revision 13.3.p-3.....................................Revision 1 3.3.p-4.....................................Revision 87 3.3.y-1.....................................Revision 78 BRAIDWOOD -UNITS 1 & 2 iv Revision 95AFFECTED PAGE LIST -TECHNICAL REQUIREMENTS MANUAL3.3.y-2.....................................Revision 783.3.y-3.....................................Revision 783.4REACTOR COOLANT SYSTEM (RCS)3.4.b-1.....................................Revision 1 3.4.b-2.....................................Revision 1 3.4.b-3.....................................Revision 403.4.b-4.....................................Revision 1 3.4.c-1.....................................Revision 1 3.4.c-2.....................................Revision 1 3.4.d-1.....................................Revision 1 3.4.e-1.....................................Revision 343.4.e-2.....................................Revision 373.4.e-3.....................................Revision 34 3.4.f-1.....................................Revision 82 3.4.f-2.....................................Revision 823.5EMERGENCY CORE COOLING SYSTEMS (ECCS)3.5.a-1.....................................Revision 1 3.5.a-2.....................................Revision 13.6CONTAINMENT SYSTEMS None3.7PLANT SYSTEMS3.7.a-1.....................................Revision 13.7.a-2.....................................Revision 13.7.b-1.....................................Revision 81 3.7.b-2.....................................Revision 81 3.7.b-3.....................................Revision 60 3.7.b-4.....................................Revision 813.7.c-1.....................................Revision 13.7.c-2.....................................Revision 1 3.7.c-3.....................................Revision 1 3.7.d-1.....................................Revision 1 3.7.d-2.....................................Revision 13.7.d-3.....................................Revision 243.7.i-1.....................................Revision 77 3.7.i-2.....................................Revision 1 3.7.j-1.....................................Revision 13.7.k-1.....................................Revision 21 BRAIDWOOD -UNITS 1 & 2 v Revision 95AFFECTED PAGE LIST -TECHNICAL REQUIREMENTS MANUAL3.8ELECTRICAL POWER SYSTEMS3.8.a-1.....................................Revision 373.8.a-2.....................................Revision 13.8.a-3.....................................Revision 1 3.8.a-4.....................................Revision 1 3.8.a-5.....................................Revision 1 3.8.a-6.....................................Revision 13.8.a-7.....................................Revision 463.8.a-8.....................................Revision 46 3.8.a-9.....................................Revision 46 3.8.a-10....................................Revision 46 3.8.a-11....................................Revision 463.8.a-12....................................Revision 463.8.a-13....................................Revision 46 3.8.a-14....................................Revision 46 3.8.a-15....................................Revision 46 3.8.a-16....................................Revision 463.8.a-17....................................Revision 463.8.a-18....................................Revision 46 3.8.a-19....................................Revision 46 3.8.a-20....................................Revision 463.8.b-1.....................................Revision 13.8.b-2.....................................Revision 1 3.8.b-3.....................................Revision 88 3.8.b-4.....................................Revision 1 3.8.b-5.....................................Revision 763.8.b-6.....................................Revision 883.8.b-7.....................................Revision 1 3.8.b-8.....................................Revision 85 3.8.c-1.....................................Revision 26 3.8.c-2.....................................Revision 263.8.c-3.....................................Revision 633.8.c-4.....................................Revision 63 3.8.c-5.....................................Revision 263.9REFUELING OPERATIONS3.9.a-1.....................................Revision 89 3.9.a-2.....................................Revision 89 3.9.a-3.....................................Revision 89 3.9.a-4.....................................Revision 893.9.a-5.....................................Revision 893.9.a-6.....................................Revision 89 3.9.a-7.....................................Revision 89 3.9.a-8.....................................Revision 89 3.9.a-9.....................................Revision 893.9.a-10....................................Revision 893.9.a-11....................................Revision89 3.9.b-1.....................................Revision 1 3.9.c-1.....................................Revision 17 BRAIDWOOD -UNITS 1 & 2 vi Revision 95AFFECTED PAGE LIST -TECHNICAL REQUIREMENTS MANUAL3.9.c-2.....................................Revision 173.9.d-1.....................................Revision 753.9.d-2.....................................Revision 753.9.e-1.....................................Revision 14.0DESIGN FEATURES None5.0ADMINISTRATIVE CONTROLS5.1-1.......................................Revision 1 5.2-1.......................................Revision 1 5.2-2.......................................Revision 15.2-3.......................................Revision 15.3-1.......................................Revision 1 5.3-2.......................................Revision 1 5.3-3.......................................Revision 1 APPENDICESAppendix AODCM AND RADIOLOGICAL CONTROLS REPORTS AND PROGRAM1 of 5......................................Revision 332 of 5......................................Revision 33 3 of 5......................................Revision 33 4 of 5......................................Revision 33 5 of 5......................................Revision 33Appendix BPRIMARY COOLANT SOURCES OUTSIDE CONTAINMENT1 of 4......................................Revision 58 2 of 4......................................Revision 58 3 of 4......................................Revision 584 of 4......................................Revision 58Appendix CNot usedAppendix DRADIOACTIVE EFFLUENT CONTROLS PROGRAM1 of 5......................................Revision 332 of 5......................................Revision 33 3 of 5......................................Revision 33 4 of 5......................................Revision 335 of 5......................................Revision 33Appendix ETRANSIENT MONITORING PROGRAM1 of 6......................................Revision 12 of 6......................................Revision 13 of 6......................................Revision 14 of 6......................................Revision 1 5 of 6......................................Revision 1 6 of 6......................................Revision1 BRAIDWOOD -UNITS 1 & 2 vii Revision 95AFFECTED PAGE LIST -TECHNICAL REQUIREMENTS MANUALAppendix FPRE-STRESSED CONCRETE CONTAINMENT TENDON SURVEILLANCE PROGRAM1 of 5......................................Revision 612 of 5......................................Revision 613 of 5......................................Revision 61 4 of 5......................................Revision 61 5 of 5......................................Revision 61Appendix GREACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM1 of 5......................................Revision 71 2 of 5......................................Revision 71 3 of 5......................................Revision 71 4 of 5......................................Revision 715 of 5......................................Revision 71Appendix HINSERVICE TESTING PROGRAM1 of 4......................................Revision 592 of 4......................................Revision 593 of 4......................................Revision 594 of 4......................................Revision 59Appendix ISTEAM GENERATOR PROGRAM1 of 9......................................Revision 89 2 of 9......................................Revision 89 3 of 9......................................Revision 89 4 of 9......................................Revision 89 5 of 9......................................Revision 896 of 9......................................Revision 897 of 9......................................Revision 89 8 of 9......................................Revision 89 9 of 9......................................Revision 89Appendix JSECONDARY WATER CHEMISTRY1 of 5......................................Revision 1 2 of 5......................................Revision 1 3 of 5......................................Revision 1 4 of 5......................................Revision 15 of 5......................................Revision 1 BRAIDWOOD -UNITS 1 & 2 viii Revision 95AFFECTED PAGE LIST -TECHNICAL REQUIREMENTS MANUALAppendix KVENTILATION FILTER TESTING PROGRAM1 of 15.....................................Revision 652 of 15.....................................Revision 653 of 15.....................................Revision 65 4 of 15.....................................Revision 65 5 of 15.....................................Revision 65 6 of 15.....................................Revision 657 of 15.....................................Revision 658 of 15.....................................Revision 65 9 of 15.....................................Revision 65 10 of 15....................................Revision 65 11 of 15....................................Revision 6512 of 15....................................Revision 6513 of 15....................................Revision 65 14 of 15....................................Revision 65 15 of 15....................................Revision 65Appendix LEXPLOSIVE GAS AND STORAGE TANK RADIOACTIVITY MONITORING PROGRAM1 of 7......................................Revision 44 2 of 7......................................Revision 44 3 of 7......................................Revision 444 of 7......................................Revision 445 of 7......................................Revision 44 6 of 7......................................Revision 44 7 of 7......................................Revision 44Appendix MDIESEL FUEL OIL TESTING PROGRAM1 of 9......................................Revision 48 2 of 9......................................Revision 48 3 of 9......................................Revision 48 4 of 9......................................Revision 485 of 9......................................Revision 486 of 9......................................Revision 48 7 of 9......................................Revision 48 8 of 9......................................Revision 48 9 of 9......................................Revision 48Appendix NTECHNICAL SPECIFICATION BASES CONTROL PROGRAM1 of 13.....................................Revision 64 2 of 13.....................................Revision 643 of 13.....................................Revision 644 of 13.....................................Revision 64 5 of 13.....................................Revision 64 6 of 13.....................................Revision 64 7 of 13.....................................Revision 648 of 13.....................................Revision 649 of 13.....................................Revision 64 10 of 13....................................Revision 64 BRAIDWOOD -UNITS 1 & 2 ix Revision 95AFFECTED PAGE LIST -TECHNICAL REQUIREMENTS MANUALAppendix N11 of 13....................................Revision 64(continued)12 of 13....................................Revision 6413 of 13....................................Revision 64Appendix OSAFETY FUNCTION DETERMINATION PROGRAM1 of 43.....................................Revision 87 2 of 43.....................................Revision 873of 43.....................................Revision 874 of 43.....................................Revision 87 5 of 43.....................................Revision 87 6 of 43.....................................Revision 87 7 of 43.....................................Revision 878 of 43.....................................Revision 879 of 43.....................................Revision 87 10 of 43....................................Revision 87 11 of 43....................................Revision 87 12 of 43....................................Revision 8713 of 43....................................Revision 8714 of 43....................................Revision 87 15 of 43....................................Revision 87 16 of 43....................................Revision 8717 of 43....................................Revision 8718 of 43....................................Revision 87 19 of 43....................................Revision 87 20 of 43....................................Revision 87 21 of 43....................................Revision 8722 of 43....................................Revision 8723 of 43....................................Revision 87 24of 43....................................Revision 87 25 of 43....................................Revision 87 26 of 43....................................Revision 8727 of 43....................................Revision 8728 of 43....................................Revision 87 29 of 43....................................Revision 87 30 of 43....................................Revision 87 31 of 43....................................Revision 8732 of 43....................................Revision 8733 of 43....................................Revision 87 34 of 43....................................Revision 87 35 of43....................................Revision 8736 of 43....................................Revision8737 of 43....................................Revision 87 38 of 43....................................Revision 87 39 of 43....................................Revision 87 40 of 43....................................Revision 8741 of 43....................................Revision 8742 of 43....................................Revision 87 43 of 43....................................Revision 87 BRAIDWOOD -UNITS 1 & 2 x Revision 95AFFECTED PAGE LIST -TECHNICAL REQUIREMENTS MANUALAppendix PCONTAINMENT LEAKAGE RATE TESTING PROGRAM1 of 6......................................Revision 572 of 6......................................Revision 57 3 of 6......................................Revision 57 4 of 6......................................Revision 57 5 of 6......................................Revision 576 of 6......................................Revision 57Appendix QNot UsedAppendix RNot UsedAppendix STECHNICAL REQUIREMENTS MANUAL CONTROL PROGRAM1 of 12.....................................Revision 642 of 12.....................................Revision 64 3 of 12.....................................Revision 644 of 12.....................................Revision 645 of 12.....................................Revision 64 6 of 12.....................................Revision 64 7 of 12.....................................Revision 648 of 12.....................................Revision 649 of 12.....................................Revision 64 10 of 12....................................Revision 64 11 of 12....................................Revision 64 12 of 12....................................Revision 64Appendix TCONFIGURATION RISK MANAGEMENT PROGRAM1 of 4......................................Revision 9 2 of 4......................................Revision 9 3 of 4......................................Revision 94 of 4......................................Revision 9Appendix UBATTERY MONITORING AND MAINTENANCE PROGRAM1 of 4......................................Revision 262 of 4......................................Revision263 of 4......................................Revision 264 of 4......................................Revision 26 B 3.8.c-1...................................Revision 26 B 3.8.c-2...................................Revision 26B 3.8.c-3...................................Revision 26B 3.8.c-4...................................Revision 26 B 3.8.c-5...................................Revision 26 B 3.8.c-6...................................Revision 26 B 3.8.c-7...................................Revision 26B 3.8.c-8...................................Revision 26B 3.8.c-9...................................Revision 26 BRAIDWOOD -UNITS 1 & 2 xi Revision 95AFFECTED PAGE LIST -TECHNICAL REQUIREMENTS MANUALAppendix V1 of 7......................................Revision 562 of 7......................................Revision 563 of 7......................................Revision 564 of 7......................................Revision 56 5 of 7......................................Revision 56 6 of 7......................................Revision 56 7 of 7......................................Revision 56Appendix W1 of 4......................................Revision 742 of 4......................................Revision 74 3 of 4......................................Revision 74 4 of 4......................................Revision 74 BRAIDWOOD -UNITS 1 & 2 i Revision 1 Technical Requirements ManualTABLE OF CONTENTS -TECHNICAL REQUIREMENTS MANUAL1.0USE AND APPLICATION........................................1.0-11.1Definitions............................................1.1-11.2Logical Connectors.....................................1.2-1 1.3Completion Times.......................................1.3-11.4Frequency..............................................1.4-11.5TLCO and TSR Implementation............................1.5-1 1.6TRM Revisions..........................................1.6-12.0.aRTS Instrumentation Trip Setpoints...................2.0.a-12.0.bESFAS Instrumentation Trip Setpoints.................2.0.b-1 2.1.aMiscellaneous Test Requirements......................2.1.a-13.0TLCO Applicability.........................................3.0-13.0TSR Applicability..........................................3.0-43.1REACTIVITY CONTROL SYSTEMS...........................3.1.a-13.1.aBoration Flow Path -Shutdown...................3.1.a-13.1.bBoration Flow Paths -Operating.................3.1.b-1 3.1.cCharging Pump -Shutdown........................3.1.c-13.1.dCharging Pumps -Operating......................3.1.d-13.1.eBorated Water Source -Shutdown.................3.1.e-1 3.1.fBorated Water Sources -Operating...............3.1.f-1 3.1.gPosition Indication System -Shutdown...........3.1.g-1 3.1.hSDM -MODE 1 and MODE 2 with k eff!1.0...........3.1.h-13.1.iSDM -MODE 5....................................3.1.i-1 3.1.jShutdown and Control Rods.......................3.1.j-1 3.1.kPosition Indication System -Shutdown (Special Test Exception)..............................3.1.k-13.2Not Used BRAIDWOOD -UNITS 1 & 2 ii Revision 84 Technical Requirements ManualTABLE OF CONTENTS -TECHNICAL REQUIREMENTS MANUAL 3.3INSTRUMENTATION......................................3.3.a-1 3.3.aMovable Incore Detectors........................3.3.a-1 3.3.bSeismic Monitoring Instrumentation..............3.3.b-1 3.3.cMeteorological Monitoring Instrumentation.......3.3.c-1 3.3.dLoose-Part Detection System.....................3.3.d-1 3.3.eExplosive Gas Monitoring Instrumentation........3.3.e-1 3.3.fHigh Energy Line Break Isolation Sensors........3.3.f-1 3.3.gTurbine Overspeed Protection....................3.3.g-1 3.3.hPDMS Instrumentation............................3.3.h-1 3.3.iPAM Instrumentation.............................3.3.i-1 3.3.jHydrogen Monitors...............................3.3.j-1 3.3.kFeedwater Flow..................................3.3.k-1 3.3.l Not Used 3.3.m Not Used 3.3.n Not Used 3.3.o FHB Ventilation System Actuation Instrumentation..............................3.3.o-1 3.3.pRadiation Monitoring Instrumentation............3.3.p-1 3.3.q Not Used 3.3.r Not Used 3.3.s Not Used 3.3.t Not Used 3.3.u Not Used 3.3.v Not Used 3.3.w Not Used 3.3.x Not Used 3.3.y Engineereed Safety Feature Actuation System (ESFAS)

Instrumentation..............................3.3.y-1 3.4REACTOR COOLANT SYSTEM (RCS).........................3.4.b-1 3.4.a Not Used 3.4.bRCS Chemistry...................................3.4.b-1 3.4.cPressurizer Temperature Limits..................3.4.c-1 3.4.dPressurizer PORVs...............................3.4.d-1 3.4.eReactor Vessel Head Vents.......................3.4.e-1 3.4.fStructural Integrity............................3.4.f-1 BRAIDWOOD -UNITS 1& 2 iiiRevision26 Technical Requirements ManualTABLE OF CONTENTS -TECHNICAL REQUIREMENTS MANUAL 3.5EMERGENCY CORE COOLING SYSTEMS (ECCS)................3.5.a-1 3.5.aECCS Subsystems -T avg200#F and Pressurizer Level 5%...................................3.5.a-13.6Not Used3.7PLANT SYSTEMS........................................3.7.a-13.7.aSteam Generator Pressure/Temperature Limitations..................................3.7.a-13.7.bSnubbers........................................3.7.b-13.7.cSealed Source Contamination.....................3.7.c-1 3.7.dArea Temperature Monitoring.....................3.7.d-13.7.eNot Used3.7.fNot Used 3.7.gNot Used 3.7.hNot Used 3.7.iFHB Ventilation Systems.........................3.7.i-13.7.jSpent Fuel Pool Water Level.....................3.7.j-13.7.kSpent Fuel Pool Boron Concentration.............3.7.k-13.8ELECTRICAL POWER SYSTEMS.............................3.8.a-13.8.aContainment Penetration Conductor Overcurrent Protective Devices...........................3.8.a-13.8.bMotor Operated Valves Thermal Overload Protection Devices......................................3.8.b-1 3.8.cBattery Monitoring and Maintenance..............3.8.c-1 3.9REFUELING OPERATIONS.................................3.9.a-1 3.9.aDecay Time......................................3.9.a-1 3.9.bCommunications..................................3.9.b-1 3.9.cRefueling Machine/Auxiliary Hoist...............3.9.c-1 3.9.dCrane Travel -Spent Fuel Pool..................3.9.d-1 3.9.eRefueling Cavity Water Level....................3.9.e-1 4.0 Not Used BRAIDWOOD -UNITS 1 & 2 ivRevision1 Technical Requirements ManualTABLE OF CONTENTS -TECHNICAL REQUIREMENTS MANUAL5.0ADMINISTRATIVE CONTROLS..................................5.1-15.1Safety Limit Violation...............................5.1-15.2Procedures and Programs..............................5.2-15.2.aProcess Control Program.........................5.2-15.2.bIn-Plant Radiation Monitoring...................5.2-2 5.2.cRadiological Environmental Monitoring Program...5.2-2 5.2.dRadiation Protection Program....................5.2-3 5.2.eOffsite Dose Calculation Manual.................5.2-35.3Reporting Requirements...............................5.3-15.3.aStartup Report..................................5.3-15.3.bAnnual Specific Activity Report.................5.3-25.3.cSpecial Reports.................................5.3-2 BRAIDWOOD -UNITS 1 & 2 vRevision88 Technical Requirements ManualTABLE OF CONTENTS -TECHNICAL REQUIREMENTS MANUAL TABLESTABLE T1.1-1MODES...........................................1.1-7TABLE T2.0.a-1Reactor Trip System Instrumentation Trip Setpoints....................................2.0.a-1TABLE T2.0.b-1Engineered Safety Feature Actuation System Instrumentation Trip Setpoints...............2.0.b-1TABLE T2.0.c-1Boron Dilution Protection System Instrumentation Trip Setpoint................................2.0.c-1TABLE T3.3.b-1Seismic Monitoring Instrumentation..............3.3.b-4 TABLE T3.3.c-1Meteorological Monitoring Instrumentation.......3.3.c-3TABLE T3.3.d-1Loose-Part Detection Instrumentation............3.3.d-3TABLE T3.3.e-1Explosive Gas Monitoring Instrumentation........3.3.e-4 TABLE T3.3.f-1High Energy Line Break Instrumentation..........3.3.f-3 TABLE T3.3.g-1Turbine Overspeed Protection....................3.3.g-5TABLE T3.3.g-2Extraction Steam Non-Return Check Valves and the Associated MOV or Manual Isolation Valve........................................3.3.g-6TABLE T3.3.i-1Post Accident Monitoring Instrumentation........3.3.i-4 TABLE T3.3.o-1FHB Ventilation System Actuation Instrumentation..............................3.3.o-4TABLE T3.3.p-1Radiation Monitoring Instrumentation for Plant Operations.............................3.3.p-4TABLE T3.3.y-1Engineered Safety Feature Actuation System Instrumentation..............................3.3.y-3TABLE T3.4.b-1RCS Chemistry Limits............................3.4.b-4 TABLE T3.7.b-1Snubber Inservice Inspection Program Elements...3.7.b-4 TABLE T3.7.d-1Area Temperature Monitoring.....................3.7.d-3 TABLE T3.8.a-1Containment Penetration Conductor Overcurrent Protective Devices (Unit 1)..................3.8.a-7TABLE T3.8.a-2Containment Penetration Conductor Overcurrent Protective Devices (Unit 2)..................3.8.a-14TABLE T3.8.b-1Motor-Operated Valves Thermal Overload Protective Devices (Unit 1).............................3.8.b-3TABLE T3.8.b-2Motor-Operated Valves Thermal Overload Protective Devices (Unit 2).............................3.8.b-6 BRAIDWOOD -UNITS 1 & 2 viRevision89 Technical Requirements ManualTABLE OF CONTENTS -TECHNICAL REQUIREMENTS MANUAL FIGURESFIGURE 3.9.a-141 MBTU/hr SFP Heat Load Margin.................3.9.a-3FIGURE 3.9.a-242 MBTU/hr SFP Heat Load Margin.................3.9.a-4FIGURE 3.9.a-343MBTU/hr SFP Heat Load Margin.................3.9.a-5FIGURE 3.9.a-444MBTU/hr SFP Heat Load Margin.................3.9.a-6FIGURE 3.9.a-544MBTU/hr SFP Heat Load Margin.................3.9.a-7FIGURE 3.9.a-645MBTU/hr SFP Heat Load Margin.................3.9.a-8FIGURE 3.9.a-746MBTU/hr SFP Heat Load Margin.................3.9.a-9FIGURE 3.9.a-847 MBTU/hr SFP Heat Load Margin.................3.9.a-10FIGURE 3.9.a-948 MBTU/hr SFP Heat Load Margin.................3.9.a-11 BRAIDWOOD -UNITS 1 & 2 viiRevision74 Technical Requirements ManualTABLE OF CONTENTS -TECHNICAL REQUIREMENTS MANUAL APPENDICESAppendix A:ODCM AND RADIOLOGICAL CONTROLS REPORTS AND PROGRAMAppendix B:PRIMARY COOLANT SOURCES OUTSIDE CONTAINMENT Appendix C:Not Used Appendix D:RADIOACTIVE EFFLUENT CONTROLS PROGRAMAppendix E:TRANSIENT MONITORING PROGRAMAppendix F:PRE-STRESSED CONCRETE CONTAINMENT TENDON SURVEILLANCE PROGRAM Appendix G:REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM Appendix H:INSERVICE TESTING PROGRAM Appendix I:STEAM GENERATOR PROGRAMAppendix J:SECONDARY WATER CHEMISTRY PROGRAMAppendix K:VENTILATION FILTER TESTING PROGRAM Appendix L:EXPLOSIVE GAS AND STORAGE TANK RADIOACTIVITY MONITORING PROGRAM Appendix M:DIESEL FUELOIL TESTING PROGRAMAppendix N:ITS BASES CONTROL PROGRAMAppendix O:SAFETY FUNCTION DETERMINATION PROGRAM Appendix P:CONTAINMENT LEAKAGE RATE TESTING PROGRAM Appendix Q:Not used Appendix R:Not usedAppendix S:TECHNICAL REQUIREMENTS MANUAL CONTROL PROGRAMAppendix T:CONFIGURATION RISK MANAGEMENT PROGRAM Appendix U:BATTERY MONITORING AND MAINTENANCE PROGRAM

Appendix V: CONTROL ROOM ENVELOPE HABITABILITY PROGRAM Appendix W:SURVEILLANCE FREQUENCY CONTROL PROGRAM TRM Definitions 1.1BRAIDWOOD -UNITS 1 & 21.1 -1Revision1 Technical Requirements Manual 1.0 USE AND APPLICATION

1.1 Definitions

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

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

applicable throughout this Technical Requirements Manual.

TermDefinition ACTIONS ACTIONS shall be that part of a Requirement that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.CHANNEL CALIBRATIONA CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel so that it responds within the required range and accuracy to known inputs. The CHANNEL CALIBRATION shall encompass

the entire channel, including the required sensor, alarm, interlock, display, and trip functions.

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 calibrations or total channel steps so that the entire channel

is calibrated.

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.

TRM Definitions 1.1BRAIDWOOD -UNITS 1 & 21.1 -2Revision69TechnicalRequirements Manual 1.1 DefinitionsCHANNEL OPERATIONALA COT shall be the injection of a simulated orTEST (COT)actual signal into thechannel as close to the sensor as practicable to verify the OPERABILITY of

required alarm, interlock, display, and trip functions. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpointsare within

the required range and accuracy.CORE ALTERATIONCORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within

the reactor vessel with the vessel head removed

and fuel in the vessel. Suspension of CORE

ALTERATIONS shall not preclude completion of movement of a component to a safe position.CORE OPERATING LIMITSThe COLR is the unitspecific document thatREPORT (COLR)provides cycle specific parameter limits for the current reload cycle. These cycle specific

parameter limits shall be determined for each

reload cycle in accordance with Specification5.6.5. Unit operation within these

limits is addressed in individual Specifications.DOSE EQUIVALENT I-131DOSE EQUIVALENT I-131 shall be that concentrationof I-131 (microcurieper 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 the Committed Effective Dose Equivalent (CEDE) dose conversion factors from 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."

TRM Definitions 1.1BRAIDWOOD -UNITS 1 & 21.1 -3Revision13 Technical Requirements Manual 1.1 DefinitionsMEMBER(S)OFTHE PUBLICMEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees

of the licensee, its contractors or vendors and persons who enter the site to service equipment or to make deliveries. This category doesinclude

persons who use portions of the site for

recreational, occupational, or other purposes not

associated with the plant.MODEA MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolanttemperature, and

reactor vessel head closure bolt tensioning specified in TableT1.1-1 with fuel in the reactor vessel.OFFSITE DOSE CALCULATION The ODCM shall contain the methodology and MANUAL (ODCM)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/Trip

Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls

and Radiological Environmental Monitoring Programs

and (2) descriptions of the information that

should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports.OPERABLE -OPERABILITYA 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).

TRM Definitions 1.1BRAIDWOOD -UNITS 1 & 21.1 -4Revision84 Technical Requirements Manual 1.1 DefinitionsPROCESS CONTROL PROGRAMThe PCP shall contain the current formulas,(PCP)sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of

solid radioactive wastes based on demonstrated processing of actual orsimulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFRParts 20, 61, and 71, State

regulations, burial ground requirements, and other

requirements governing the disposal of solid radioactive waste.PURGE -PURGINGPURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify theconfinement.QUADRANT POWER TILTQPTR shall be the ratio of the maximum upper RATIO (QPTR)excore 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)RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3645MWt.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. With any RCCA not capable of being fully inserted, the reactivity worth

of the RCCA must be accounted for in the

determination of SDM; andb.In MODES1 and2, the fuel and moderator temperatures are changed to the hot zero power

temperature.

TRM Definitions 1.1BRAIDWOOD -UNITS 1 & 21.1 -5Revision75 Technical Requirements Manual 1.1 DefinitionsSINGLE-FAILURE PROOFCranes meeting requirements of ASME NOG-1-2004,LOAD HANDLING SYSTEMNUREG-0554 and NUREG-0612, as applicable.

Special Lifting Devices meeting requirements of NUREG-0612, Section 5.1.6(1)(a).

Lifting devices that are not specially designed that meet the requirements of NUREG-0612, Section 5.1.6(1)(b).

Interfacing lift points such as lifting lugs or cask trunions meetingrequirements of NUREG-0612, Section 5.1.6(3).SITEBOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.TRIP ACTUATING DEVICEA TADOTshall consist of operating the trip

OPERATIONAL TEST actuating device and verifying the OPERABILITY (TADOT)of required alarm, interlock, display, and trip functions. The TADOT shall include adjustment, as

necessary, of the trip actuating device so that it

actuates at the required setpoint within the

required accuracy.UNRESTRICTEDAREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not

controlled by the licensee for purposes of

protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential

quarters or for industrial, commercial, institutional, and/or recreational purposes.

TRM Definitions 1.1BRAIDWOOD -UNITS 1 & 21.1 -6Revision75 Technical Requirements Manual 1.1 DefinitionsVENTILATIONEXHAUSTA VENTILATION EXHAUST TREATMENT SYSTEM shallTREATMENTSYSTEMbe any system designed and installed to reduce gaseous radioiodine or radioactive material in

particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of

removing iodines or particulates from the gaseous

exhaust stream prior to the release to the

environment. Such a system is not considered to have any effect on noble gas effluents.

Engineered Safety Features Atmospheric Cleanup Systems arenot considered to be VENTILATION

EXHAUST TREATMENT SYSTEM components.WASTEGASHOLDUPA WASTE GAS HOLDUP SYSTEM shall be any system SYSTEMdesigned and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off-gases fromthe Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to

release to the environment.

TRM Definitions 1.1BRAIDWOOD -UNITS 1 & 21.1 -7Revision93 Technical Requirements ManualTableT1.1-1 (page1 of1)

MODES MODE TITLE REACTIVITY CONDITION (k eff)%RATED THERMAL POWER (a)AVERAGE REACTOR COOLANT TEMPERATURE

(!F)1Power Operation0.99>5NA2Startup0.99#5NA3Hot Standby<0.99NA3504Hot Shutdown (b)<0.99NA350>T avg>2005Cold Shutdown (b)<0.99NA#2006Refueling (c)NA NA NA(a)Excluding decay heat.(b)All required reactor vessel head closure bolts fully tensioned.(c)One or more required reactor vessel head closure bolts less than fully tensioned.

TRM Logical Connectors 1.2 BRAIDWOOD - UNITS 1 & 2 1.2 - 1 Revision 1 Technical Requirements Manual 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 the Technical Requirements Manual (TRM) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in the TRM 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.

TRM Logical Connectors 1.2 BRAIDWOOD - UNITS 1 & 2 1.2 - 2 Revision 1 Technical Requirements Manual 1.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. TLCO 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.

TRM Logical Connectors 1.2 BRAIDWOOD - UNITS 1 & 2 1.2 - 3 Revision 1 Technical Requirements Manual 1.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. TLCO 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.

TRM Completion Times 1.3 BRAIDWOOD - UNITS 1 & 2 1.3 - 1 Revision 1 Technical Requirements Manual 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 Technical Requirements Manual Limiting Conditions for Operation (TLCOs) specify minimum requirements for ensuring

safe operation of the unit. The ACTIONS associated with a

TLCO state Conditions that typically describe the ways in which the requirements of the TLCO can fail to be met.

Specified with each stated Condition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time

of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the

Applicability of the TLCO. 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 TLCO Applicability.

If situations are discovered that require entry into more

than one Condition at a time within a single TLCO (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of

the situation that required entry into the Condition.

TRM Completion Times 1.3 BRAIDWOOD - UNITS 1 & 2 1.3 - 2 Revision 1 Technical Requirements Manual 1.3 Completion Times DESCRIPTION (continued)

Once a Condition has been entered, subsequent trains, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition, unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

However, when a subsequent train, subsystem, component, or variable expressed in the Condition is discovered to be

inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two

criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability; and b. Must remain inoperable or not within limits after the first inoperability is resolved.

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

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

The above Completion Time extension does not apply to those TLCOs 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 TLCOs.

TRM Completion Times 1.3 BRAIDWOOD - UNITS 1 & 2 1.3 - 3 Revision 1 Technical Requirements Manual 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," 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 . . ." Example 1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Conditions A and B in Example 1.3-3 may not be extended.

EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing

Conditions.

EXAMPLE 1.3-1

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and

associated Completion Time not met. B.1 Be in MODE 3.

AND B.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 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.

TRM Completion Times 1.3 BRAIDWOOD - UNITS 1 & 2 1.3 - 4 Revision 1 Technical Requirements Manual 1.3 Completion Times EXAMPLES (continued)

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

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND in MODE 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is allowed for reaching MODE 3 and a total of

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months ) 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 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , the time allowed for reaching MODE 5 is the next 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months because the total time allowed for reaching MODE 5 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

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

TRM Completion Times 1.3 BRAIDWOOD - UNITS 1 & 2 1.3 - 5 Revision 1 Technical Requirements Manual 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pump inoperable.

A.1 Restore pump to OPERABLE status.

7 days B. Required Action and

associated

Completion Time not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours When a pump is declared inoperable, Condition A is entered.

If the pump is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered, Condition 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. TLCO 3.0.c 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 TLCO 3.0.c is entered, but continues to be tracked from the time Condition A was initially entered.

While in TLCO 3.0.c, if one of the inoperable pumps is

restored to OPERABLE status and the Completion Time for Condition A has not expired, TLCO 3.0.c may be exited and operation continued in accordance with Condition A.

TRM Completion Times 1.3 BRAIDWOOD - UNITS 1 & 2 1.3 - 6 Revision 1 Technical Requirements Manual 1.3 Completion Times EXAMPLES (continued)

While in TLCO 3.0.c, if one of the inoperable pumps is

restored to OPERABLE status and the Completion Time for Condition A has expired, TLCO 3.0.c may be exited and operation continued in accordance with Condition B. The Completion Time for Condition B is tracked from the time the

Condition A Completion Time expired.

On restoring one of the pumps to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first pump was declared inoperable. This Completion Time may be extended if the pump restored to OPERABLE status was the first inoperable pump. A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

extension to the stated 7 days is allowed, provided this does not result in the second pump being inoperable for

> 7 days.

TRM Completion Times 1.3 BRAIDWOOD - UNITS 1 & 2 1.3 - 7 Revision 1 Technical Requirements Manual 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Function X

train inoperable.

A.1 Restore Function X train

to OPERABLE status. 7 days AND 10 days from discovery of

failure to meet the TLCO B. One Function Y train inoperable.

B.1 Restore Function Y train to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND 10 days from discovery of failure to meet the TLCO C. One Function X

train inoperable.

AND One Function Y

train inoperable.

C.1 Restore Function X train

to OPERABLE status. OR C.2 Restore Function Y train

to OPERABLE status. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 72 hours TRM Completion Times 1.3 BRAIDWOOD - UNITS 1 & 2 1.3 - 8 Revision 1 Technical Requirements Manual 1.3 Completion Times EXAMPLES (continued)

When one Function X train and one Function Y train are

inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the

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

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the

Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e., initial entry into Condition A).

The Completion Times of Conditions A and B are modified by a logical connector with a separate 10 day Completion Time measured from the time it was discovered the TLCO was not met. In this example, without the separate Completion Time, it would be 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 TLCO. The separate Completion Time modified by the phrase "from discovery of failure to meet the TLCO" is designed to prevent indefinite continued operation while not meeting the TLCO. This Completion Time allows for an exception to the normal "time zero" for beginning the Completion Time "clock". In this instance, the Completion Time "time zero" is specified as commencing at the time the TLCO was initially not met, instead of at the time the associated Condition was entered.

TRM Completion Times 1.3 BRAIDWOOD - UNITS 1 & 2 1.3 - 9 Revision 1 Technical Requirements Manual 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more valves inoperable.

A.1 Restore valve(s) to OPERABLE

status.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours A single Completion Time is used for any number of valves

inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis.

Declaring subsequent valves inoperable, while Condition A is

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

Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Completion Time may be extended if the valve restored to

OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (plus the extension) expires while one or more valves are still inoperable, Condition B is entered.

TRM Completion Times 1.3 BRAIDWOOD - UNITS 1 & 2 1.3 - 10 Revision 1 Technical Requirements Manual 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-5 ACTIONS ----------------------------NOTE----------------------------

Separate Condition entry is allowed for each inoperable valve. ------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more valves inoperable.

A.1 Restore valve to OPERABLE status.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours The Note above the ACTIONS Table is a method of modifying

how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

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

entered for each valve and separate Completion Times start and are tracked for each valve.

TRM Completion Times 1.3 BRAIDWOOD - UNITS 1 & 2 1.3 - 11 Revision 1 Technical Requirements Manual 1.3 Completion Times EXAMPLES (continued)

If the Completion Time associated with a valve in

Condition A expires, Condition B is entered for that valve.

If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are

tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that valve.

Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply.

EXAMPLE 1.3-6

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel inoperable.

A.1 Perform TSR 3.x.x.x.

OR A.2 Reduce THERMAL POWER to 50% RTP.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 hours B. Required Action and

associated Completion Time not met. B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months TRM Completion Times 1.3 BRAIDWOOD - UNITS 1 & 2 1.3 - 12 Revision 1 Technical Requirements Manual 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 TSR 3.0.b, to each performance after the initial performance. The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Action A.1 is followed, and the Required Action is not met within the Completion Time (plus the extension allowed by TSR 3.0.b), Condition B is entered. If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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.

TRM Completion Times 1.3 BRAIDWOOD - UNITS 1 & 2 1.3 - 13 Revision 1 Technical Requirements Manual 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One subsystem

inoperable.

A.1 Verify affected subsystem

isolated.

AND A.2 Restore subsystem to OPERABLE

status. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required Action and

associated Completion

Time not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered

and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Required Action A.1.

TRM Completion Times 1.3 BRAIDWOOD - UNITS 1 & 2 1.3 - 14 Revision 1 Technical Requirements Manual 1.3 Completion Times EXAMPLES (continued)

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

met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by TSR 3.0.b), Condition B is entered.

The Completion Time clock for Condition A does not stop

after Condition B is entered, but continues from the time Condition A was initially entered. If Required Action A.1 is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired.

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

TRM Frequency 1.4 BRAIDWOOD - UNITS 1 & 2 1.4 - 1 Revision 1 Technical Requirements Manual 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 Technical Requirements Manual Surveillance Requirement (TSR) has a specified Frequency in which the Surveillance must be met in order to meet the associated Limiting

Condition for Operation (TLCO). An understanding of the correct application of the specified Frequency is necessary for compliance with the TSR.

The "specified Frequency" is referred to throughout this section and Section 3.0, Surveillance Requirement (TSR)

Applicability. The "specified Frequency" consists of the

requirements of the Frequency column of each TSR as well as certain Notes in the Surveillance column that modify performance requirements.

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 TLCO is within its Applicability, represent potential TSR 3.0.d conflicts. To avoid these conflicts, the TSR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With a TSR satisfied, TSR 3.0.d imposes no

restriction.

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by TSR 3.0.a. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance, or both. Example 1.4-5 discusses these

special situations.

TRM Frequency 1.4 BRAIDWOOD - UNITS 1 & 2 1.4 - 2 Revision 38 Technical Requirements Manual 1.4 Frequency DESCRIPTION (continued)

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

specific meaning. 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. TSR 3.0.d restrictions would not apply if both the following conditions are satisfied:

a. The Surveillance is not required to be performed; and

b. The Surveillance is not required to be met or, even if required to be met, is not known to be failed.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the TLCO (TLCO not shown) is MODES 1, 2, and 3. The examples do not reflect the potential application of TLCO 3.0.d.2.

TRM Frequency 1.4 BRAIDWOOD - UNITS 1 & 2 1.4 - 3 Revision 1 Technical Requirements Manual 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of TSR most often

encountered in the Technical Requirements Manual (TRM). The

Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the stated Frequency is allowed by TSR 3.0.b for operational flexibility. The measurement of this interval continues at

all times, even when the TSR is not required to be met per TSR 3.0.a (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the TLCO). If the interval specified by TSR 3.0.b is exceeded while the unit is in a MODE or

other specified condition in the Applicability of the TLCO, and the performance of the Surveillance is not otherwise modified (refer to Example 1.4-3), then TSR 3.0.c becomes applicable.

If the interval as specified by TSR 3.0.b is exceeded while the unit is not in a MODE or other specified condition in

the Applicability of the TLCO for which performance of the TSR is required, the Surveillance must be performed within the Frequency requirements of TSR 3.0.b prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of TSR 3.0.d.

TRM Frequency 1.4 BRAIDWOOD - UNITS 1 & 2 1.4 - 4 Revision 1 Technical Requirements Manual 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND

"). This type of Frequency does not qualify for the extension allowed by TSR 3.0.b.

"Thereafter" indicates future performances must be

established per TSR 3.0.b, 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.

TRM Frequency 1.4 BRAIDWOOD - UNITS 1 & 2 1.4 - 5 Revision 1 Technical Requirements Manual 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 TSR 3.0.b) interval, but operation was < 25% RTP, it would not constitute a failure of the TSR or failure to meet the TLCO. Also, no violation of TSR 3.0.d occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power 25% RTP.

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

a failure to perform a Surveillance within the specified Frequency, and the provisions of TSR 3.0.c would apply.

TRM Frequency 1.4 BRAIDWOOD - UNITS 1 & 2 1.4 - 6 Revision 1 Technical Requirements Manual 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-4 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 TLCO) 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 MODE 1. Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by TSR 3.0.b) interval, but operation was not in MODE 1, it would not constitute a failure of the TSR or failure to meet the TLCO. Also, no violation of TSR 3.0.d 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 MODE 1, there would then be a failure to perform a

Surveillance within the specified Frequency, and the provisions of TSR 3.0.c would apply.

TRM Frequency 1.4 BRAIDWOOD - UNITS 1 & 2 1.4 - 7 Revision 1 Technical Requirements Manual 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Only required to be met in MODE 1. --------------------------------------

Verify leakage rates are within limits.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-5 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by TSR 3.0.b), but the unit was not in MODE 1, there would be no failure of the TSR nor failure to meet the TLCO. Therefore, no

violation of TSR 3.0.d occurs when changing MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), TSR 3.0.d would require satisfying the TSR.

TRM TLCO and TSR Implementation 1.5 BRAIDWOOD - UNITS 1 & 2 1.5 - 1 Revision 1 Technical Requirements Manual 1.0 USE AND APPLICATION 1.5 TLCO and TSR Implementation The Technical Requirements Manual (TRM) provides those limitations upon plant operations which are part of the licensing basis for the station but do not meet the criteria for continued inclusion in the Technical Specifications.

It also provides information which supplements the Technical Specifications such as specific plant setpoints for Technical Specification equipment. Nothing in the TRM shall supersede any Technical Specification requirement.

TLCOs and TSRs are implemented the same as Technical Specifications (see

TRM 3.0). However, TLCOs and TSRs are treated as plant procedures and are not part of the Technical Specifications. Therefore the following exceptions apply:

a. Violations of the Action or Surveillance requirements in a TLCO are not reportable as conditions prohibited by, or deviations from, the Technical Specifications per 10 CFR 50.72 or 10 CFR 50.73, unless specifically required by the TRM.

b. Power reduction or plant shutdowns required to comply with the Actions of a TLCO or as a result of the application of TLCO 3.0.c

are not reportable per 10 CFR 50.72 or 10 CFR 50.73.

c. Violations of TLCO or TSR requirements, except as provided for in TLCO 3.0 of this manual, shall be treated the same as plant

procedure violations.

BRAIDWOOD - UNITS 1 & 2 1.6 - 1 Revision 13 Technical Requirements Manual TRM Technical Requirements Manual Revisions 1.6 1.0 USE AND APPLICATION 1.6 Technical Requirements Manual Revisions Changes to this manual shall be made under the following provisions:

a. Changes to the TRM shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to TRM without prior NRC approval provided the change does not require prior NRC approval pursuant to 10 CFR 50.59.

c. The TRM revision process shall contain provisions to ensure that the TRM is maintained consistent with the UFSAR.

d. Proposed changes that require NRC approval pursuant to 10 CFR 50.59 shall be reviewed and approved by the NRC prior to implementation. Changes to the TRM implemented without prior NRC approval shall be provided to the NRC on a frequency consistent

with 10 CFR 50.71(e) as modified by approved exemptions.

TRM RTS Instrumentation Trip Setpoints 2.0.a BRAIDWOOD - UNITS 1 & 2 2.0.a - 1 Revision 52 Technical Requirements Manual Table T2.0.a-1 (page 1 of 3) Reactor Trip System Instrumentation Trip Setpoints FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS NOMINAL TRIP SETPOINT 1. Manual Reactor Trip

1,2, 3 (a), 4 (a), 5 (a) NA

2. Power Range Neutron Flux

a. High b. Low

1,2 1 (b),2

109% RTP(h) 25% RTP 3. Power Range Neutron Flux Rate - High Positive Rate 1,2 5% RTP with time constant 2 sec 4. Intermediate Range Neutron Flux 1 (b), 2 (c) 25% RTP 5. Source Range Neutron Flux 2 (d) 3 (a), 4 (a), 5 (a) 1.0 E5 cps 1.0 E5 cps

6. Overtemperature T 1,2 See LCO 3.3.1

7. Overpower T 1,2 See LCO 3.3.1 (continued)

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

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

(c) Above the P-6 (Source Range Block Permissive) interlock.

(d) Below the P-6 (Source Range Block Permissive) interlock.

(h) Trip setpoint may be set more conservative than Nominal Trip Setpoint as necessary in response to plant conditions.

TRM RTS Instrumentation Trip Setpoints 2.0.a BRAIDWOOD - UNITS 1 & 2 2.0.a - 2 Revision 52 Technical Requirements Manual Table T2.0.a-1 (page 2 of 3) Reactor Trip System Instrumentation Trip Setpoints FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS NOMINAL TRIP SETPOINT 8. Pressurizer Pressure

a. Low b. High 1 (e) 1,2 1885 psig 2385 psig

9. Pressurizer Water Level-High 1 (e) 92% of instrument span

10. Reactor Coolant Flow-Low (per loop)

1 (e) 90% of loop minimum measured flow

11. Reactor Coolant Pump (RCP) Breaker Position (per train) 1 (e) NA 12. Undervoltage RCPs (per train) 1 (e) 5268 V 13. Underfrequency RCPs (per train) 1 (e) 57.0 Hz 14. Steam Generator (SG) Water Level-Low Low (per SG)

a. Unit 1

b. Unit 2 1,2 1,2 18.0% of narrow range instrument span 36.3% of narrow range instrument span

15. Turbine Trip

a. Emergency Trip Header Pressure (per train)

b. Turbine Throttle Valve Closure (per train)

1 (f) 1 (f)

1000 psig

1% open (continued)

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

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

TRM RTS Instrumentation Trip Setpoints 2.0.a BRAIDWOOD - UNITS 1 & 2 2.0.a - 3 Revision 52 Technical Requirements Manual Table T2.0.a-1 (page 3 of 3) Reactor Trip System Instrumentation Trip Setpoints FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS NOMINAL TRIP SETPOINT 16. Safety Injection (SI) Input from Engineered Safety Feature Actuation System (ESFAS) 1,2 NA 17. Reactor Trip System Interlocks

a. Source Range Block Permissive, P-6 b. Low Power Reactor Trips Block, P-7 (1) P-10 Input (2) P-13 Input

c. Power Range Neutron Flux, P-8

d. Power Range Neutron Flux, P-10

e. Turbine Impulse Pressure, P-13 2 (d) 1 1 1 1,2 1 1E-10 amp

NA NA 30% RTP 10% RTP 10% turbine power

18. Reactor Trip Breakers (RTBs)(g) 1,2 3 (a), 4 (a), 5 (a) NA NA 19. Reactor Trip Breaker Undervoltage and Shunt Trip Mechanisms 1,2 3 (a), 4 (a), 5 (a) NA NA 20. Automatic Trip Logic

1,2 3 (a), 4 (a), 5 (a) NA NA

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

(d) Below the P-6 (Source Range Block Permissive) interlock.

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

TRM ESFAS Instrumentation Trip Setpoints 2.0.bBRAIDWOOD -UNITS 1 & 22.0.b -1Revision52 Technical Requirements ManualTableT2.0.b-1 (page1 of4)

Engineered Safety Feature Actuation System Instrumentation Trip Setpoints FUNCTIONAPPLICABLE MODESOR OTHER SPECIFIED CONDITIONS NOMINAL TRIP SETPOINT1.Safety Injectiona.Manual Initiation1,2,3,4NAb.Automatic Actuation Logic and Actuation Relays1,2,3,4NAc.Containment Pressure-High11,2,33.4 p sigd.Pressurizer Pressure-Low 1,2,3 (a)1829 psige.Steam Line Pressure-Low 1,2,3 (a)640 psig (b)2.Containment Spraya.Manual Initiation1,2,3,4NAb.Automatic Actuation Logic and Actuation Relays1,2,3,4NAc.Containment Pressure High-31,2,320.0 psig (continued)(a)Above the P-11 (Pressurizer Pressure) interlock.(b)Time constants used in the lead/lag controller are t 1!50seconds and t 25seconds.

TRM ESFAS Instrumentation Trip Setpoints 2.0.bBRAIDWOOD -UNITS 1 & 22.0.b -2Revision52 Technical Requirements ManualTableT2.0.b-1 (page2 of4)

Engineered Safety Feature Actuation System Instrumentation Trip Setpoints FUNCTIONAPPLICABLE MODESOROTHER SPECIFIED CONDITIONS NOMINAL TRIP SETPOINT3.Containment Isolationa.PhaseA Isolation(1)Manual Initiation1,2,3,4NA(2)Automatic Actuation Logic and Actuation Relays1,2,3,4NA(3)Safety InjectionRefer to Function1 (Safety Injection) for all initiation functions and re q uirements.b.PhaseB Isolation(1)Manual Initiation1,2,3,4NA(2)Automatic Actuation Logic and Actuation Relays1,2,3,4NA(3)Containment Pressure High-31,2,320.0psig4.Steam Line Isolationa.Manual Initiation 1,2 (c),3 (c)NAb.Automatic Actuation Logic and Actuation Relays 1,2 (g),3 (g)NAc.Containment Pressure-High 2 1,2 (g),3 (g)8.2psigd.Steam Line Pressure(1)Low 1,2 (g),3(a)(f)(g)640 psig (b)(2)Negative Rate-High 3(d)(g)100.0psi (e)(continued)(a)Above the P-11 (Pressurizer Pressure) interlock.(b)Time constants used in the lead/lag controller are t 1!50seconds and t 25seconds.(c)Except when all Main Steam Isolation Valves (MSIVs) are closed.(d)Below the P-11 (Pressurizer Pressure) interlock with Function4.d.1 blocked.

(e)Time constant utilized in the rate/lag controller is

!50seconds.(f)Below the P-11 (Pressurizer Pressure) interlock with Function4.d.2 not enabled.

(g)Except when all Main Steam Isolation Valves (MSIVs) and MSIV bypass valves are closed.

TRM ESFAS Instrumentation Trip Setpoints 2.0.bBRAIDWOOD -UNITS 1 & 22.0.b -3Revision92 Technical Requirements ManualTableT2.0.b-1 (page3 of4)

Engineered Safety Feature Actuation System Instrumentation Trip Setpoints FUNCTIONAPPLICABLE MODESOR OTHER SPECIFIED CONDITIONS NOMINAL TRIP SETPOINT5.Turbine Trip and Feedwater Isolationa.Automatic Actuation Logic and Actuation Relays 1,2 (h),3 (h)NAb.Steam Generator (SG) Water Level-High High (P-14)1)Unit12)Unit2 1,2 (h),3 (h)1,2 (h),3 (h)88.0% of narrow range instrument span 80.8% of narrow range instrument s p anc.Safety InjectionRefer to Function1 (Safety Injection) for all initiation functions and requirements.6.Auxiliary Feedwatera.Automatic Actuation Logic and Actuation Relays1,2,3NAb.SG WaterLevel-Low Low1) Unit12) Unit2 1,2,3 1,2,3 18.0% of narrow range instrument span 36.3% of narrow range instrument s p anc.Safety InjectionRefer to Function1 (Safety Injection) for all initiation functions and re q uirements.d.Loss of Offsite Power(Undervoltage on Bus141(241))1,2,32870Ve.Undervoltage Reactor Coolant Pum p (p er train)1,25268Vf.Auxiliary Feedwater Pump Suction Transfer on SuctionPressure-Low Pressure Transmitter Pressure Switch 1,2,3 18.1 psia 20.5 psia (continued)(h)Except when all Feedwater Isolation Valves are closed or isolated by a closed manual valve.

TRM ESFAS Instrumentation Trip Setpoints 2.0.bBRAIDWOOD -UNITS 1 & 22.0.b -4Revision95 Technical Requirements ManualTableT2.0.b-1 (page4 of4)Engineered Safety Feature Actuation System Instrumentation Trip Setpoints FUNCTIONAPPLICABLE MODESOR OTHER SPECIFIED CONDITIONS NOMINAL TRIP SETPOINT7.Switchover to Containment Sumpa.Automatic Actuation Logic and Actuation Relays1,2,3,4NAb.Refueling Water Storage Tank (RWST) Level-Low Low1,2,3,446.7% of instrument s p anCoincident with Safety InjectionRefer to Function1 (Safety Injection) for all initiation functions and requirements.8.ESFAS Interlocksa.Reactor Trip, P-4b.Pressurizer Pressure, P-11c.T avg-Low Low, P-12 1,2,3 1,2,3 1,2,3 NA 1930 psig 550#F9.Loss of Powera.Loss of Voltage1,2,3,4,5 (i),6 (i)2870V with time delay of 1.8secb.Degraded Voltage1,2,3,4,5 (i),6 (i)3987V with a timedelay of 310secc.Low Degraded Voltage 1,2,3,4,5 (i),6 (i)3244.15Vwith a time delay of 3.0 sec(i)When associated DG is required to be OPERABLE by LCO3.8.2, "AC Sources-Shutdown."

TRM BDPS Instrumentation Trip Setpoint 2.0.c BRAIDWOOD - UNIT 1 2.0.c - 1 Revision 52 Technical Requirements Manual Table T2.0.c-1 (page 1 of 1)

Boron Dilution Protection System Instrumentation Trip Setpoint FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS NOMINAL TRIP SETPOINT Boron Dilution Alert Channels

Volume Control Tank Level High

3,4,5

70.0%

TRM Miscellaneous Test Requirements 2.1.a BRAIDWOOD - UNITS 1 & 2 2.1.a - 1 Revision 1 Technical Requirements Manual 2.1.a MISCELLANEOUS TEST REQUIREMENTS -------------------------------------NOTES----------------------------------- 1. Each of the following Surveillances shall be completed within its specified frequency.

2. Failure to meet the surveillance requirement require immediate actions to determine OPERABILITY of the associated equipment. LCOs potentially impacted are identified in the TSR with ().

APPLICABILITY: Defined in the TSR SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 2.4.a.1 -------------------NOTES------------------- 1. Only applicable in MODE 1.

2. TSR 3.0.d is not applicable.

Perform CHANNEL CALIBRATION on Reactor

Coolant System total flow rate indicators.

(LCO 3.4.1)

18 months

TSR 2.5.a.1 -------------------NOTE--------------------

Required to be met in MODES 1, 2; and MODE 3 with the RCS pressure 1000 psig.

Perform CHANNEL CALIBRATION on accumulator

water level channels.

(LCO 3.5.1)

18 months (continued)

TRM Miscellaneous Test Requirements 2.1.a BRAIDWOOD - UNITS 1 & 2 2.1.a - 2 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 2.5.a.2 -------------------NOTE--------------------

Required to be met in MODES 1, 2; and

MODE 3 with the RCS pressure > 1000 psig.

Perform CHANNEL CALIBRATION on accumulator pressure channels.

(LCO 3.5.1)

18 months TSR 2.5.b.1 -------------------NOTE--------------------

Required to be met in MODES 1, 2, 3, and 4.

Verify, through a visual inspection of all accessible areas of the containment, loose debris which could be transported to the containment sump during LOCA conditions has been removed.

(LCO 3.5.2/3.5.3)

Prior to entering MODE 4 (continued)

TRM Miscellaneous Test Requirements 2.1.a BRAIDWOOD - UNITS 1 & 2 2.1.a - 3 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 2.5.b.2 -------------------NOTES------------------- 1. Required to be met in MODES 1, 2, 3, and 4.

2. Only required to be performed once TSR 2.5.b.1 has been completed.

3. TSR 3.0.d is not applicable.

Verify, through a visual inspection of the areas affected within containment, loose debris which could be transported to the containment sump during LOCA conditions has

been removed.

(LCO 3.5.2/3.5.3)

Following each containment entry (continued)

TRM Miscellaneous Test Requirements 2.1.a BRAIDWOOD - UNITS 1 & 2 2.1.a - 4 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 2.5.c.1 -------------------NOTES------------------- 1. Only applicable to the following ECCS throttle valves:

a. High Head SI System -

SI8810A,B,C,D

b. SI System - SI8822A,B,C,D and SI8816A,B,C,D

2. Required to be met in MODES 1, 2, 3; and MODE 4 when the associated ECCS subsystems are required to be OPERABLE.

3. Only required to be performed for affected valves following valve stroking operation or maintenance on the valve.

Verify the correct position of each position stop for the ECCS throttle valves.

(LCO 3.5.2)

Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (continued)

TRM Miscellaneous Test Requirements 2.1.a BRAIDWOOD - UNITS 1 & 2 2.1.a - 5 Revision 28 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 2.5.c.2 -------------------NOTES------------------- 1. A flow balance test that introduces flow to the loops shall not be performed in MODE 1, 2, 3, or 4.

2. Only required to be performed following alterations to the CV pump and/or piping system that alter the ECCS flow characteristics.

3. Required to be met in MODES 1, 2, 3; and MODE 4 when the associated ECCS

subsystems are required to be OPERABLE.

Verify through analytical means or a flow balance test that the CV pump performance curve and/or the following CV ECCS cold leg injection flow characteristics are met with a single pump running:

a. The sum of the injection line flow rates, excluding the highest flow rate, is 330 gpm; and

b. The total pump flow rate is 550 gpm, including a simulated seal injection flow of 80 gpm. OR

Prior to associated subsystems being declared OPERABLE (continued)

TRM Miscellaneous Test Requirements 2.1.a BRAIDWOOD - UNITS 1 & 2 2.1.a - 6 Revision 28 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY (continued) -------------------NOTE--------------------

Only applicable in MODES 1, 2, 3, 4, and 5.

Verify the CV pump performance curve and/or CV ECCS cold leg injection flow characteristics are acceptable by a technical evaluation that concludes the evaluation results are:

1. within the acceptance criteria of the accident analyses of record; and

2. acceptable for continued equipment operation.

AND Demonstrate by a flow balance test that the flow rates specified in a. and b. above are within limits prior to the associated subsystems being declared OPERABLE following the next refueling.

(LCO 3.5.2)

(continued)

TRM Miscellaneous Test Requirements 2.1.a BRAIDWOOD - UNITS 1 & 2 2.1.a - 7 Revision 62 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 2.5.c.3 -------------------NOTES------------------- 1. A flow balance test that introduces flow to the loops shall not be performed in MODE 1, 2, 3, or 4.

2. Only required to be performed following alterations to the SI pump and/or piping system that alter the ECCS flow characteristics.

3. Required to be met in MODES 1, 2, 3; and MODE 4 when the associated ECCS subsystems are required to be OPERABLE.

Verify through analytical means or a flow balance test that the SI pump performance curve and/or the following SI ECCS cold leg injection flow characteristics are met with a single pump running:

a. The sum of the injection line flow rates, excluding the highest flow rate, is 439 gpm; and

b. The total pump flow rate is 655 gpm.

OR

Prior to associated subsystems being declared OPERABLE (continued)

TRM Miscellaneous Test Requirements 2.1.a BRAIDWOOD - UNITS 1 & 2 2.1.a - 8 Revision 62 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY (continued)

Verify the SI pump performance curve and/or SI ECCS cold leg injection flow characteristics are acceptable by a technical evaluation that concludes the evaluation results are:

1. within the acceptance criteria of the accident analyses of record; and

2. acceptable for continued equipment operation (e.g., pump NPSH, pump runout, etc.).

Flow rates specified in a. and b. above shall be returned to within limits prior to the associated subsystems being declared OPERABLE if in a refueling outage or no later than the end of the next refueling if in MODES 1, 2, 3, 4, or 5.

(LCO 3.5.2)

(continued)

TRM Miscellaneous Test Requirements 2.1.a BRAIDWOOD - UNITS 1 & 2 2.1.a - 9 Revision 62 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 2.5.c.4 -------------------NOTES-------------------

1. Only required to be performed following alterations to the RHR pump

and/or piping system that alter the

ECCS flow characteristics.

2. Required to be met in MODES 1, 2, 3; and MODE 4 when the associated ECCS

subsystems are required to be OPERABLE.

Verify the RHR pump performance curve and/or RHR ECCS cold leg injection flow characteristics are consistent with the assumptions used in the safety analyses.

(LCO 3.5.2/LCO 3.5.3)

Prior to associated ECCS subsystems required to be

OPERABLE TSR 2.6.a.1 Deleted.

(continued)

TRM Miscellaneous Test Requirements 2.1.a BRAIDWOOD - UNITS 1 & 2 2.1.a - 10 Revision 62 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 2.7.a.1 -------------------NOTES------------------- 1. This surveillance shall not be performed in MODE 1, 2, or 3.

2. Required to be met in MODES 1, 2, and

3. -------------------------------------------

Perform an inspection of the B Train Auxiliary Feedwater Pump diesel engine in accordance with manufacturer's recommendation for this class of service.

(LCO 3.7.5)

18 months

TSR 2.7.a.2 -------------------NOTE--------------------

Required to be met in MODES 1, 2, 3, and 4.

Perform a hydrographic survey to verify the

Essential Service Cooling Pond (ESCP) slopes exhibit no excess degradation.

(LCO 3.7.9)

18 months

TRM TLCO Applicability 3.0 BRAIDWOOD - UNITS 1 & 2 3.0 - 1 Revision 1 Technical Requirements Manual 3.0 TECHNICAL REQUIREMENTS MANUAL (TRM) LIMITING CONDITION FOR OPERATION (TLCO) APPLICABILITY TLCO 3.0.a TLCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in

TLCO 3.0.b and TLCO 3.0.f.

TLCO 3.0.b Upon discovery of a failure to meet a TLCO, the Required Actions of the associated Conditions shall be met, except as

provided in TLCO 3.0.e.

If the TLCO 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.

TLCO 3.0.c When a TLCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by

the associated ACTIONS, action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to:

1. Implement appropriate compensatory actions as needed,

2. Verify that the plant is not in an unanalyzed condition or that a required safety function is not

compromised by the inoperabilities, and

3. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , obtain Station Duty Officer approval of the compensatory actions and plan for exiting

TLCO 3.0.c.

Exceptions to this TLCO are stated in the individual TLCOs.

Where corrective measures are completed that permit operation in accordance with the TLCO or ACTIONS, completion of the actions required by TLCO 3.0.c is not required.

TLCO 3.0.c is only applicable in MODES 1, 2, 3, and 4.

TRM TLCO Applicability 3.0 BRAIDWOOD - UNITS 1 & 2 3.0 - 2 Revision 37 Technical Requirements Manual 3.0 TECHNICAL REQUIREMENTS MANUAL (TRM) LIMITING CONDITION FOR OPERATION (TLCO) APPLICABILITY TLCO 3.0.d When a TLCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

1. 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;

2. 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; or

3. When an allowance is stated in the individual value, parameter, or other TLCO This TLCO 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.

TLCO 3.0.e 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 TLCO 3.0.b for the system returned to service under administrative control to perform the required testing to demonstrate OPERABILITY.

TRM TLCO Applicability 3.0 BRAIDWOOD - UNITS 1 & 2 3.0 - 3 Revision 1 Technical Requirements Manual 3.0 TECHNICAL REQUIREMENTS MANUAL (TRM) LIMITING CONDITION FOR OPERATION (TLCO) APPLICABILITY TLCO 3.0.f Exception TLCOs allow specified TRM requirements to be changed to permit performance of special tests and

operations. Unless otherwise specified, all other TRM requirements remain unchanged. Compliance with Exception TLCOs is optional. When an Exception TLCO is desired to be

met but is not met, the ACTIONS of the Exception TLCO shall be met. When an Exception TLCO 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 TLCOs.

TLCO 3.0.g TLCOs, including associated ACTIONs, shall apply to each unit individually, unless otherwise indicated. Whenever the

TLCO refers to a system or component that is shared by both

units, the ACTIONs will apply to both units simultaneously.

TRM TSR Applicability 3.0 BRAIDWOOD - UNITS 1 & 2 3.0 - 4 Revision 23 Technical Requirements Manual 3.0 TECHNICAL REQUIREMENTS MANUAL (TRM) SURVEILLANCE REQUIREMENT (TSR)

APPLICABILITY TSR 3.0.a TSRs shall be met during the MODES or other specified conditions in the Applicability for individual TLCOs, unless

otherwise stated in the TSR. Failure to meet a TSR, whether such failure is experienced during the performance of the TSR or between performances of the TSR, shall be failure to

meet the TLCO. Failure to perform a TSR within the specified Frequency shall be failure to meet the TLCO except as provided in TSR 3.0.c. TSRs do not have to be performed on inoperable equipment or variables outside specified limits.

TSR 3.0.b The specified Frequency for each TSR is met if the TSR 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 TSR are stated in the individual TSRs.

TSR 3.0.c If it is discovered that a TSR was not performed within its specified Frequency, then compliance with the requirement to declare the TLCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the

specified Frequency, whichever is greater. This delay period is permitted to allow performance of the TSR. A risk evaluation shall be performed for any TSR delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

If the TSR is not performed within the delay period, the TLCO must immediately be declared not met, and the

applicable Condition(s) must be entered.

When the TSR is performed within the delay period and the TSR is not met, the TLCO must immediately be declared not met, and the applicable Condition(s) must be entered.

TRM TSR Applicability 3.0 BRAIDWOOD - UNITS 1 & 2 3.0 - 5 Revision 37 Technical Requirements Manual 3.0 TECHNICAL REQUIREMENTS MANUAL (TRM) SURVEILLANCE REQUIREMENT (TSR)

APPLICABILITY TSR 3.0.d Entry into a MODE or other specified condition in the Applicability of a TLCO shall only be made when the TLCO's TSRs have been met within their specified Frequency, except as provided by TSR 3.0.c. When a TLCO is not met due to TSRs not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with TLCO 3.0.d.

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.

TSR 3.0.e TSRs shall apply to each unit individually, unless otherwise indicated.

TRM Boration Flow Path - Shutdown 3.1.a BRAIDWOOD - UNITS 1 & 2 3.1.a - 1 Revision 6 Technical Requirements Manual 3.1 REACTIVITY CONTROL SYSTEMS 3.1.a Boration Flow Path - Shutdown

TLCO 3.1.a One of the following boron injection flow paths via the Chemical & Volume Control (CV) System shall be OPERABLE and

capable of being powered from an OPERABLE emergency power source: 1. A flow path via a boric acid transfer pump from the Boric Acid Storage System, which is OPERABLE as specified in TLCO 3.1.e for MODE 5 or as specified in TLCO 3.1.f for MODE 4; or

2. A flow path from the Refueling Water Storage Tank (RWST) which is OPERABLE as specified in TLCO 3.1.e for MODE 5 or as specified in LCO 3.5.4 for MODE 4.

APPLICABILITY: MODES 4 and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

A. Required flow path inoperable.

OR Required flow path not capable of being powered from an OPERABLE emergency

power source.

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

Not applicable if positive reactivity

addition is the direct result of a RCS cooldown required by Technical Specifications.

Suspend positive reactivity additions.

Immediately

TRM Boration Flow Path - Shutdown 3.1.a BRAIDWOOD - UNITS 1 & 2 3.1.a - 2 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.a.1 -------------------NOTE--------------------

Only required to be performed when

complying with TLCO 3.1.a.1.

Verify Boric Acid Storage System solution temperature is 65°F.

7 days TSR 3.1.a.2 Verify each manual, power operated, or automatic valve in the required flow path

that is not locked, sealed, or otherwise secured in position, is in its correct

position.

31 days TRMBoration Flow Paths -Operating 3.1.bBRAIDWOOD -UNITS 1 & 23.1.b -1Revision1 Technical Requirements Manual 3.1 REACTIVITY CONTROL SYSTEMS3.1.b Boration Flow Paths -OperatingTLCO 3.1.bOne boron injection flow path via the Chemical & Volume (CV)

Control System from the Refueling Water Storage Tank (RWST) shall be OPERABLE, and either:1.One additionalOPERABLE flow path from the RWST, or2.An OPERABLE flow path via a boric acid transfer pump from the Boric Acid Storage System.APPLICABILITY:MODES1, 2, and 3.

ACTIONSCONDITIONREQUIRED ACTIONCOMPLETION TIMEA.One required flow path inoperable.A.1Restore required flow path to OPERABLE status.72hours (continued)

TRMBoration Flow Paths -Operating 3.1.bBRAIDWOOD -UNITS 1 & 23.1.b -2Revision1 Technical Requirements Manual ACTIONS (continued)CONDITIONREQUIRED ACTIONCOMPLETION TIMEB.Required Action and associated Completion Time of Condition A not met.B.1Be in MODE3.

ANDB.2Borate to the SHUTDOWN MARGIN specified in the COLR

at 200!F.ANDB.3.1Restore required flow path to OPERABLE status.ORB.3.2Be in MODE4.6hours6hours174hours180hours SURVEILLANCE REQUIREMENTSSURVEILLANCEFREQUENCYTSR3.1.b.1-------------------NOTE--------------------

Only required to be performed when complying with TLCO3.1.b.2.

Verify Boric Acid Storage System solution temperature is 65!F.7 days (continued)

TRMBoration Flow Paths -Operating 3.1.bBRAIDWOOD -UNITS 1 & 23.1.b -3Revision90 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)SURVEILLANCEFREQUENCYTSR 3.1.b.2Verify each manual, power operated, or automatic valve in the required flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.31daysTSR 3.1.b.3-------------------NOTE--------------------

This Surveillance shall not be performed in MODE1, 2, 3, or 4.

Verify each automatic valve in the required flow path actuates to its correct position on an actual or simulated safety injection actuation signal.36monthsTSR 3.1.b.4-------------------NOTE--------------------

Only required to be performed when complying with TLCO3.1.b.2.

Verify required flow path from the Boric Acid Storage System delivers 30 gpm to theRCS.18months TRM Charging Pump - Shutdown 3.1.c BRAIDWOOD - UNITS 1 & 2 3.1.c - 1 Revision 6 Technical Requirements Manual 3.1 REACTIVITY CONTROL SYSTEMS 3.1.c Charging Pump - Shutdown

TLCO 3.1.c One centrifugal charging pump in the boron injection flow path required by TLCO 3.1.a shall be OPERABLE and capable of

being powered from an OPERABLE emergency power source.

APPLICABILITY: MODES 4 and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required charging pump inoperable.

OR Required charging pump not capable of being powered from an OPERABLE emergency power source.

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

Not applicable if positive reactivity addition is the direct result of a

RCS cooldown required by Technical Specifications.

Suspend positive reactivity additions.

Immediately

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.c.1 Verify the required centrifugal charging pump's developed head at the test flow

point is greater than or equal to the required developed head.

In accordance with the Inservice Testing Program

TRM Charging Pumps - Operating 3.1.d BRAIDWOOD - UNITS 1 & 2 3.1.d - 1 Revision 1 Technical Requirements Manual 3.1 REACTIVITY CONTROL SYSTEMS 3.1.d Charging Pumps - Operating

TLCO 3.1.d Two centrifugal charging pumps shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

A. One charging pump inoperable.

A.1 Restore charging pump to OPERABLE status.

7 days B. Required Action and associated Completion

Time of Condition A not met. B.1 Be in MODE 3.

AND B.2 Borate to the SHUTDOWN MARGIN

specified in the COLR at 200°F. AND B.3 Be in MODE 4.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 6 hours 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

TRM Charging Pumps - Operating 3.1.d BRAIDWOOD - UNITS 1 & 2 3.1.d - 2 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.d.1 Verify each centrifugal charging pump's developed head at the test flow point is

greater than or equal to the required developed head.

In accordance with the Inservice Testing Program

TRMBorated Water Source -Shutdown 3.1.eBRAIDWOOD -UNITS 1 & 23.1.e -1Revision6 Technical Requirements Manual 3.1 REACTIVITY CONTROL SYSTEMS3.1.e Borated Water Source -ShutdownTLCO 3.1.eOne of the following borated water sources shall be OPERABLE:1.A Boric Acid Storage System, or2.The Refueling Water Storage Tank (RWST).APPLICABILITY:MODE5.

ACTIONSCONDITIONREQUIRED ACTIONCOMPLETION TIMEA.Required borated water source inoperable.A.1Suspend positive reactivity additions.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCYTSR 3.1.e.1-------------------NOTE--------------------

Only required to be performed when complying with TLCO3.1.e.2 and the outside air temperature <35

!F.-------------------------------------------

Verify RWST solution temperature 35!F.24hours (continued)

TRMBorated Water Source -Shutdown 3.1.eBRAIDWOOD -UNITS 1 & 23.1.e -2Revision1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)SURVEILLANCEFREQUENCYTSR 3.1.e.2-------------------NOTE--------------------

Only required to be performed when complying with TLCO3.1.e.2.

Verify RWST boron concentration 2300ppm and #2500 ppm.7daysTSR 3.1.e.3-------------------NOTE--------------------

Only required to be performed when complying with TLCO3.1.e.2.

Verify RWST borated water level is 9.0%.7daysTSR 3.1.e.4-------------------NOTE--------------------

Only required to be performed when complying with TLCO3.1.e.1.

Verify Boric Acid Storage System solution temperature is 65!F.7 daysTSR 3.1.e.5-------------------NOTE--------------------

Only required to be performed when complying with TLCO3.1.e.1.

Verify Boric Acid Storage System boron concentration is 7000ppm.7 days (continued)

TRMBorated Water Source -Shutdown 3.1.eBRAIDWOOD -UNITS 1 & 23.1.e -3Revision88 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)SURVEILLANCEFREQUENCYTSR 3.1.e.6-------------------NOTE--------------------

Only required to be performed when complying with TLCO3.1.e.1.

Verify Boric Acid Storage System borated water level is 12.0%.7 days TRM Borated Water Sources - Operating 3.1.f BRAIDWOOD - UNITS 1 & 2 3.1.f - 1 Revision 1 Technical Requirements Manual 3.1 REACTIVITY CONTROL SYSTEMS 3.1.f Borated Water Sources - Operating

TLCO 3.1.f The Boric Acid Storage System shall be OPERABLE when required as a borated water source by TLCO 3.1.b for

MODES 1, 2, and 3 or TLCO 3.1.a for MODE 4.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required Boric Acid Storage System

inoperable in MODE 1, 2, or 3. A.1 Restore the Boric Acid Storage System

to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required Action and associated Completion

Time of Condition A not met. B.1 Be in MODE 3.

AND B.2 Borate to the SHUTDOWN MARGIN specified in the COLR at 200°F.

AND B.3.1 Restore the required Boric Acid Storage System to OPERABLE status. OR B.3.2 Be in MODE 4.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 174 hours

180 hours0.00208 days 0.05 hours 2.97619e-4 weeks 6.849e-5 months

(continued)

TRM Borated Water Sources - Operating 3.1.f BRAIDWOOD - UNITS 1 & 2 3.1.f - 2 Revision 1 Technical Requirements Manual ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. Required Boric Acid Storage System

inoperable in MODE 4.

C.1 Restore the required Boric Acid Storage

System to OPERABLE status.

OR C.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.f.1 Verify Boric Acid Storage System solution temperature is 65°F.

7 days TSR 3.1.f.2 Verify Boric Acid Storage System boron concentration is 7000 ppm.

7 days TSR 3.1.f.3 Verify Boric Acid Storage System borated water level is 40%.

7 days

TRM Position Indication System - Shutdown 3.1.g BRAIDWOOD - UNITS 1 & 2 3.1.g - 1 Revision 11 Technical Requirements Manual 3.1 REACTIVITY CONTROL SYSTEMS 3.1.g Position Indication System - Shutdown

TLCO 3.1.g One Digital Rod Position Indication (DRPI), excluding bank demand position indication, shall be OPERABLE and capable of

determining the control rod position within 12 steps for

each shutdown or control rod not fully inserted.

APPLICABILITY: MODES 3, 4, and 5 with the Rod Control System capable of rod withdrawal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more shutdown or control rods with required DRPI inoperable.

A.1 Restore required OPERABLE DRPI.

15 minutes

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

B.1 Initiate action to fully insert all rods. OR B.2 Initiate boration to restore RCS boron concentration to within the limits specified in the COLR. OR B.3 Open Reactor Trip Breakers (RTBs) and

Reactor Trip Bypass Breakers (RTBBs).

Immediately Immediately

Immediately

TRM Position Indication System - Shutdown 3.1.g BRAIDWOOD - UNITS 1 & 2 3.1.g - 2 Revision 11 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.g.1 Verify each DRPI agrees within 12 steps of the group demand position for the full

indicated range of rod travel.

18 months

TRM SDM - MODE 1 and MODE 2 with k eff 1.0 3.1.h BRAIDWOOD - UNITS 1 & 2 3.1.h - 1 Revision 1 Technical Requirements Manual 3.1 REACTIVITY CONTROL SYSTEM 3.1.h Shutdown Margin (SDM) - MODE 1 and MODE 2 with k eff 1.0 TLCO 3.1.h SDM shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1, and MODE 2 with k eff 1.0. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit.

A.1 Initiate and continue boration.

AND A.2 Restore required SDM to within limits specified in the COLR. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

TRM SDM - MODE 1 and MODE 2 with k eff 1.0 3.1.h BRAIDWOOD - UNITS 1 & 2 3.1.h - 2 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.h.1 Verify SDM is within limit with control banks at the maximum insertion limit

specified in LCO 3.1.6 and considering the following factors:

a. Reactor Coolant System boron concentration,

b. Control rod position, c. Reactor Coolant System average temperature, d. Fuel burnup based on gross thermal energy generation,

e. Xenon concentration, and

f. Samarium concentration.

Prior to operation above 5% RATED THERMAL POWER after each fuel loading

TRM SDM - MODE 5 3.1.i BRAIDWOOD - UNITS 1 & 2 3.1.i - 1 Revision 18 Technical Requirements Manual 3.1 REACTIVITY CONTROL SYSTEMS 3.1.i Shutdown Margin (SDM) - MODE 5

TLCO 3.1.i SDM shall be within the limits specified in the COLR.

APPLICABILITY: MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

A. SDM not within limit.

A.1 Declare both Boron Dilution Protection System subsystems inoperable and enter Condition C of LCO 3.3.9, "Boron

Dilution Protection

System (BDPS)," for "Two Boron Dilution Alert channels inoperable or no reactor coolant pump in operation or one or more RCS loop isolation valve(s) not open."

AND A.2 Enter Condition A of LCO 3.1.1, "Shutdown Margin (SDM)," for SDM not within limit.

Immediately

TRM SDM - MODE 5 3.1.i BRAIDWOOD - UNITS 1 & 2 3.1.i - 2 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY NONE TRM Shutdown and Control Rods 3.1.j BRAIDWOOD - UNITS 1 & 2 3.1.j - 1 Revision 1 Technical Requirements Manual 3.1 REACTIVITY CONTROL SYSTEM 3.1.j Shutdown and Control Rods

TLCO 3.1.j All shutdown and control rods not fully inserted shall be OPERABLE.

APPLICABILITY: MODES 3, 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more rods inoperable.

A.1 Verify SDM is within the limits specified

in the COLR.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter B. Required Action and associated Completion

Time of Condition A

not met. OR SDM not within the limits specified in the COLR for Required

Action A.1.

B.1 Initiate and continue boration to restore

the required SDM to

within limits specified in the COLR.

15 minutes

TRM Shutdown and Control Rods 3.1.j BRAIDWOOD - UNITS 1 & 2 3.1.j - 2 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY NONE

TRM Position Indication System - Shutdown (Special Test Exception) 3.1.k BRAIDWOOD - UNITS 1 & 2 3.1.k - 1 Revision 14 Technical Requirements Manual 3.1 REACTIVITY CONTROL SYSTEMS 3.1.k Position Indication System - Shutdown (Special Test Exception)

TLCO 3.1.k The requirements of TLCO 3.1.g may be suspended provided either: 1. Only one shutdown or control bank is withdrawn from the fully inserted position at a time, or

2. The Reactor Coolant System (RCS) boron concentration is within the limits specified in the COLR for maintaining k eff 0.987 with all shutdown and control rods fully withdrawn.

APPLICABILITY: MODES 3, 4, and 5 during performance of rod drop time measurements and during the surveillance of Digital Rod

Position Indication (DRPI) for OPERABILITY.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

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

Only applicable when invoking TLCO 3.1.k.1. ---------------------

More than one bank of rods withdrawn.

OR ---------NOTE--------

Only applicable when invoking TLCO 3.1.k.2.

RCS boron concentration not

within limit.

A.1 Restore required OPERABLE DRPI.

15 minutes

(continued)

TRM Position Indication System - Shutdown (Special Test Exception) 3.1.k BRAIDWOOD - UNITS 1 & 2 3.1.k - 2 Revision 11 Technical Requirements Manual ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. Required Actions and associated Completion Times of Condition A not met. B.1 Initiate action to fully insert all rods. OR B.2 Initiate boration to restore RCS boron concentration to within the limits specified in the COLR. OR B.3 Open Reactor Trip Breakers (RTBs) and Reactor Trip Bypass Breakers (RTBBs).

Immediately Immediately Immediately

TRM Position Indication System - Shutdown (Special Test Exception) 3.1.k BRAIDWOOD - UNITS 1 & 2 3.1.k - 3 Revision 11 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.k.1 -------------------NOTE--------------------

Only required to be performed when invoking TLCO 3.1.k.1.

Verify each DRPI agrees within 12 steps of the group demand position when the rods are

stationary and within 24 steps of the group demand position during rod motion.

Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior

to the start of rod drop time measurements AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter TSR 3.1.k.2 -------------------NOTE--------------------

Only required to be performed when invoking TLCO 3.1.k.2.

Verify the RCS boron concentration is within the limits specified in the COLR for maintaining k eff 0.987 with all shutdown and control rods fully withdrawn.

Once within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to the start of either rod drop time measurements or the surveillance of DRPI for OPERABILITY AND 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thereafter

TRM Movable Incore Detectors 3.3.a BRAIDWOOD - UNITS 1 & 2 3.3.a - 1 Revision 29 Technical Requirements Manual 3.3 INSTRUMENTATION 3.3.a Movable Incore Detectors TLCO 3.3.a The Movable Incore Detection System shall be OPERABLE with:

1. 75% of the detector thimbles, 2. 2 detector thimbles per core quadrant, and

3. Sufficient movable detectors, drive, and readout equipment to map these thimbles.

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

Only 50% of the detector thimbles are required for:

1. Power Distribution Monitoring System (PDMS) calibrations after the initial PDMS calibration following each refueling.

2. Monitoring normalized symmetric power distribution, i.e., Quadrant Power Tilt Ratio (QPTR) via an incore flux map, provided there are 2 detector thimbles per core quadrant and at least 2 of the detector thimbles per core quadrant have a symmetric thimble in at least one other quadrant. ----------------------------------------------------------

APPLICABILITY: When the Movable Incore Detection System is used for:

1. Recalibration of the Excore Neutron Flux Detection System, 2. Calibration of the PDMS, 3. Monitoring normalized symmetric power distribution, or

4. Measurement of N H F,F C Q (Z), and F W Q (Z).

TRM Movable Incore Detectors 3.3.a BRAIDWOOD - UNITS 1 & 2 3.3.a - 2 Revision 12 Technical Requirements Manual ACTIONS -------------------------------------NOTE-------------------------------------

TLCO 3.0.c is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Movable Incore Detection System

inoperable.

A.1 Suspend use of the Movable Incore

Detection System data for applicable

recalibration, measurement, or monitoring.

Immediately

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.a.1 Normalize each detector output when required for:

a. Recalibration of the Excore Neutron Flux Detection System, b. Calibration of the PDMS, c. Monitoring normalized symmetric power distribution, or

d. Measurement of N H F, F C Q (Z), and F W Q (Z). 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TRM Seismic Monitoring Instrumentation 3.3.bBRAIDWOOD -UNITS 1 & 23.3.b -1Revision1 Technical Requirements Manual

3.3 INSTRUMENTATION

3.3.b Seismic Monitoring InstrumentationTLCO 3.3.bThe seismic monitoring instrumentation in TableT3.3.b-1 shall be OPERABLE.APPLICABILITY:At all times.

ACTIONS-------------------------------------NOTES-----------------------------------1.Separate Condition entry is allowed for each instrument.2.TLCO3.0.c is not applicable.

CONDITIONREQUIRED ACTIONCOMPLETION TIMEA.One or more seismic monitoring instruments

inoperable.A.1Restore required instrument to

OPERABLE status.30daysB.Required Action and associated Completion Time of ConditionA

not met.B.1Prepare and submit a report to the Plant

Operating Review

Committee outlining

the cause of the malfunction and the plans for restoring

the instrument to

OPERABLE status.10days (continued)

TRM Seismic Monitoring Instrumentation 3.3.bBRAIDWOOD -UNITS 1 & 23.3.b -2Revision1 Technical Requirements Manual ACTIONS (continued)CONDITIONREQUIRED ACTIONCOMPLETION TIMEC.---------NOTE---------Required ActionsC.2 and C.3 shall be completed whenever ConditionC is

entered.

One or more required seismic instruments

actuated during a

confirmed seismic event.C.1Restore required instrument to

OPERABLE status.

ANDC.2Analyze data retrieved from instrument to

determine the

magnitude of the

vibratory ground motion.ANDC.3Prepare and submit a report to the Plant Operating Review

Committee describing

the magnitude, frequency spectrum, and resultant effect

upon facility

features important to

safety.24hours14days14days SURVEILLANCE REQUIREMENTSSURVEILLANCEFREQUENCYTSR 3.3.b.1Verify OPERABLE status indications of the seismic monitoring instrumentation.31days (continued)

TRM Seismic Monitoring Instrumentation 3.3.bBRAIDWOOD -UNITS 1 & 23.3.b -3Revision1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)SURVEILLANCEFREQUENCYTSR 3.3.b.2Verify the triaxial acceleration sensors and the time-history accelerographs properly process the equipment internal test signals.92daysTSR 3.3.b.3Verify the response spectrum analyzer properly executes its diagnostic routine.92daysTSR 3.3.b.4-------------------NOTE--------------------TSR3.3.b.4 may be performed in lieu of the test required by TSR3.3.b.2.

Verify the triaxial acceleration sensors and the time-history accelerographs

properly record the equipment internal test signals.184daysTSR 3.3.b.5Verify the electronic calibration of the time-history accelerographs.18monthsTSR 3.3.b.6Install fresh magnetic recording plates in the triaxial peak accelerographs. 18months TRM Seismic Monitoring Instrumentation 3.3.bBRAIDWOOD -UNITS 1 & 23.3.b -4Revision88 Technical Requirements ManualTableT3.3.b-1 (page1 of1)

Seismic Monitoring InstrumentationINSTRUMENTS AND SENSOR LOCATIONSMEASUREMENT RANGE REQUIRED INSTRUMENTS1.Time -History Accelerographs (Central Recorder)

Auxiliary Electrical Equipment Room, OPA02J NA 12.Triaxial Peak Accelerographsa.Containment/Reactor Equipment Accumulatorsb.Containment/Reactor Piping c.Auxiliary Building/Category I Piping-2g to +2g-2g to +2g

-2g to +2g 1

1 13.Response-Spectrum Analyzer (Computer)

Auxiliary Electrical Equipment Room, OPA02J None 14.Triaxial Acceleration Sensorsa.Containment/10W -377ft b.Containment/10W -502ft c.Containment/10X -426ftd.Free Field/38 + 01S, 34 + 15Ee.Auxiliary Building/18N -426ft f.Auxiliary Building/18L -335ft-2g to +2g

-2g to +2g

-2g to +2g-2g to +2g-2g to +2g

-2g to +2g 1

1 1 1 1 1

TRM Meteorological Monitoring Instrumentation 3.3.c BRAIDWOOD - UNITS 1 & 2 3.3.c - 1 Revision 1 Technical Requirements Manual 3.3 INSTRUMENTATION 3.3.c Meteorological Monitoring Instrumentation

TLCO 3.3.c The meteorological monitoring instrumentation channels in Table T3.3.c-1 shall be OPERABLE.

APPLICABILITY: At all times.

ACTIONS ------------------------------------NOTES------------------------------------

1. Separate Condition entry is allowed for each channel.

2. TLCO 3.0.c is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more meteorological

monitoring instrument channels inoperable.

A.1 Restore channel to OPERABLE status.

7 days B. Required Action and associated Completion Time of Condition A not met.

B.1 Prepare and submit a report to the Plant Operating Review Committee outlining the cause of the malfunction and the plans for restoring the channel to

OPERABLE status.

10 days

TRM Meteorological Monitoring Instrumentation 3.3.c BRAIDWOOD - UNITS 1 & 2 3.3.c - 2 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.c.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TSR 3.3.c.2 Perform CHANNEL CALIBRATION.

184 days TRM Meteorological Monitoring Instrumentation 3.3.c BRAIDWOOD - UNITS 1 & 2 3.3.c - 3 Revision 1 Technical Requirements Manual Table T3.3.c-1 (page 1 of 1) Meteorological Monitoring Instrumentation INSTRUMENT AND LOCATION REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS

1. Wind Speed

a. Nominal Elevation 34 ft

b. Nominal Elevation 203 ft

1 1 TSR 3.3.c.1 TSR 3.3.c.2 TSR 3.3.c.1 TSR 3.3.c.2

2. Wind Direction

a. Nominal Elevation 34 ft

b. Nominal Elevation 203 ft

1 1 TSR 3.3.c.1 TSR 3.3.c.2 TSR 3.3.c.1 TSR 3.3.c.2

3. Air Temperature - T (Nominal Elevation 30 ft/199 ft) 1 TSR 3.3.c.1 TSR 3.3.c.2

TRM Loose-Part Detection System 3.3.d BRAIDWOOD - UNITS 1 & 2 3.3.d - 1 Revision 1 Technical Requirements Manual 3.3 INSTRUMENTATION 3.3.d Loose-Part Detection System

TLCO 3.3.d The Loose-Part Detection instrumentation in Table T3.3.d-1 shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS -------------------------------------NOTES-----------------------------------

1. Separate Condition entry is allowed for each instrument.

2. TLCO 3.0.c is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required Loose-Part Detection

System instruments

inoperable.

A.1 Restore required instrument to

OPERABLE status.

30 days B. Required Action and associated Completion

Time of Condition A not met. B.1 Prepare and submit a report to the Plant

Operating Review Committee outlining the cause of the malfunction and the plans for restoring

the instrument to OPERABLE status.

10 days TRM Loose-Part Detection System 3.3.d BRAIDWOOD - UNITS 1 & 2 3.3.d - 2 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.d.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TSR 3.3.d.2 -------------------NOTE--------------------

Verification of setpoint not required.

Perform CHANNEL OPERATIONAL TEST.

31 days TSR 3.3.d.3 Perform CHANNEL CALIBRATION.

18 months

TRM Loose-Part Detection System 3.3.d BRAIDWOOD - UNITS 1 & 2 3.3.d - 3 Revision 1 Technical Requirements Manual Table T3.3.d-1 (page 1 of 1) Loose-Part Detection Instrumentation

NOTE------------------------------------------------------------ The Loose-Part Detection Instrumentation is considered OPERABLE if one of the two sensor channels for each instrument in Table T3.3.d-1 and the associated amplifier are OPERABLE. ------------------------------------------------------------------------------------------------------------------

INSTRUMENT AND LOCATION REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS

1. Reactor Head

a. _VE-LM001 (270

°) OR b. _VE-LM002 (0

°) 1 TSR 3.3.d.1 TSR 3.3.d.2 TSR 3.3.d.3

2. Reactor Bottom

a. _VE-LM003 (G-9)

OR b. _VE-LM004 (H-13) 1 TSR 3.3.d.1 TSR 3.3.d.2 TSR 3.3.d.3

3. "A" Steam Generator Channel Head

a. _VE-LM005 (Hot Side)

OR b. _VE-LM006 (Cold Side) 1 TSR 3.3.d.1 TSR 3.3.d.2 TSR 3.3.d.3

4. "B" Steam Generator Channel Head

a. _VE-LM007 (Hot Side)

OR b. _VE-LM008 (Cold Side) 1 TSR 3.3.d.1 TSR 3.3.d.2 TSR 3.3.d.3

5. "C" Steam Generator Channel Head

a. _VE-LM009 (Hot Side)

OR b. _VE-LM010 (Cold Side) 1 TSR 3.3.d.1 TSR 3.3.d.2 TSR 3.3.d.3

6. "D" Steam Generator Channel Head

a. _VE-LM011 (Hot Side)

OR b. _VE-LM012 (Cold Side) 1 TSR 3.3.d.1 TSR 3.3.d.2 TSR 3.3.d.3

TRM Explosive Gas Monitoring Instrumentation 3.3.e BRAIDWOOD - UNITS 1 & 2 3.3.e - 1 Revision 1 Technical Requirements Manual 3.3 INSTRUMENTATION 3.3.e Explosive Gas Monitoring Instrumentation

TLCO 3.3.e The explosive gas monitoring instrumentation channels in Table T3.3.e-1 shall be OPERABLE with their Alarm/Trip

setpoints set to ensure that the limits of the Explosive Gas and Storage Tank Radioactivity Monitoring Program are not

exceeded.

APPLICABILITY: According to Table T3.3.e-1.

ACTIONS ------------------------------------NOTES------------------------------------ 1. Separate Condition entry is allowed for each channel.

2. TLCO 3.0.c is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more required channels inoperable.

A.1.1 Suspend affected system operation.

OR

Immediately

(continued)

TRM Explosive Gas Monitoring Instrumentation 3.3.e BRAIDWOOD - UNITS 1 & 2 3.3.e - 2 Revision 1 Technical Requirements Manual ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)

A.1.2.1 ---------NOTE--------

Only applicable during degassing operation.

Take and analyze grab samples. AND A.1.2.2 ---------NOTE--------

Only applicable

during non-degassing

operations.

Take and analyze grab samples.

AND A.2.1 Restore channel to OPERABLE status.

OR A.2.2 Prepare and submit a report to the Plant Operating Review Committee explaining the reason for not correcting the

inoperability in a timely manner.

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 30 days 60 days

TRM Explosive Gas Monitoring Instrumentation 3.3.e BRAIDWOOD - UNITS 1 & 2 3.3.e - 3 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.e.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TSR 3.3.e.2 Perform CHANNEL OPERATIONAL TEST.

31 days TSR 3.3.e.3 -------------------NOTES------------------- 1. For the Hydrogen Analyzer, the CHANNEL CALIBRATION shall include the use of standard gas samples containing hydrogen and nitrogen.

2. For the Oxygen Analyzer and the Waste Gas Compressor Discharge Oxygen

Analyzer, the CHANNEL CALIBRATION shall include the use of standard gas samples containing oxygen and nitrogen.

Perform CHANNEL CALIBRATION.

92 days

TRM Explosive Gas Monitoring Instrumentation 3.3.e BRAIDWOOD - UNITS 1 & 2 3.3.e - 4 Revision 46 Technical Requirements Manual Table T3.3.e-1 (page 1 of 1) Explosive Gas Monitoring Instrumentation

INSTRUMENT APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS

1. Hydrogen Analyzer (0AT-GW8000)

(a) 1 TSR 3.3.e.1 TSR 3.3.e.2 TSR 3.3.e.3

2. Oxygen Analyzer (0AIT-GW8003)

(a) 1 TSR 3.3.e.1 TSR 3.3.e.2 TSR 3.3.e.3

3. Waste Gas Compressor Discharge Oxygen Analyzer (0AIT-GW004)

(b) 1 TSR 3.3.e.1 TSR 3.3.e.2 TSR 3.3.e.3

(a) During WASTE GAS HOLDUP SYSTEM operation.

(b) During Waste Gas Compressor operation.

TRM HELB Isolation Sensors 3.3.f BRAIDWOOD - UNITS 1 & 2 3.3.f - 1 Revision 1 Technical Requirements Manual 3.3 INSTRUMENTATION 3.3.f High Energy Line Break (HELB) Isolation Sensors

TLCO 3.3.f The HELB instrumentation channels shown in Table T3.3.f-1 shall be OPERABLE.

APPLICABILITY: According to Table T3.3.f-1.

ACTIONS ------------------------------------NOTES------------------------------------

1. Separate Condition entry is allowed for each channel.

2. TLCO 3.0.c is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required auxiliary steam

isolation

instrumentation channels inoperable.

A.1 Restore the required channel to OPERABLE

status. OR A.2 Suspend the supply of auxiliary steam to

the Auxiliary Building.

OR A.3 Establish a continuous watch in

the affected area.

7 days 7 days 7 days (continued)

TRM HELB Isolation Sensors 3.3.f BRAIDWOOD - UNITS 1 & 2 3.3.f - 2 Revision 1 Technical Requirements Manual ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required steam generator

blowdown line isolation instrumentation channels inoperable.

B.1 Restore the required channel to OPERABLE

status.

OR B.2 Limit the total steam generator blowdown flow rate to 60 gpm on the affected unit.

OR B.3 Establish a continuous watch in the affected area.

7 days 7 days 7 days

SURVEILLANCE REQUIREMENTS

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

TSR 3.3.f.1 and TSR 3.3.f.2 apply to each HELB instrument in Table T3.3.f-1.

SURVEILLANCE FREQUENCY

TSR 3.3.f.1 Perform CHANNEL OPERATIONAL TEST.

18 months

TSR 3.3.f.2 Perform CHANNEL CALIBRATION.

18 months

TRM HELB Isolation Sensors 3.3.f BRAIDWOOD - UNITS 1 & 2 3.3.f - 3 Revision 49 Technical Requirements Manual Table T3.3.f-1 (page 1 of 1) High Energy Line Break Instrumentation INSTRUMENT AND LOCATION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS

1. Auxiliary Steam Isolation

a. 0TS-AS031A 0TS-AS032A

b. 0TS-AS031B 0TS-AS032B

c. 0TS-AS031C 0TS-AS032C

d. 0TS-AS031D 0TS-AS032D

e. 0TS-AS031E 0TS-AS032E

f. 0TS-AS031F 0TS-AS032F

(a)

(a) (b) (b)

(b) (b)

1 1 1 1 1 1 2. Steam Generator Blowdown Line Isolation

a. TS-SD045A TS-SD045B

b. TS-SD046A TS-SD046B

c. TS-SD045C TS-SD045D

d. TS-SD046C TS-SD046D 1,2,3,4 1,2,3,4 1,2,3,4 1,2,3,4 1 1 1 1 (a) When auxiliary steam is supplied from any source to the Auxiliary Building, except when the Recycle Evaporator Auxiliary Steam blank-off flange is installed in line 0AS96A-10".

(b) When auxiliary steam is supplied from any source to the Auxiliary Building, except when the Radwaste Evaporator Auxiliary Steam blank-off flange is installed in line 0AS03F-16".

TRM Turbine Overspeed Protection 3.3.gBRAIDWOOD - UNITS 1 & 23.3.g -1Revision57 Technical Requirements Manual

3.3 INSTRUMENTATION

3.3.g Turbine Overspeed ProtectionTLCO 3.3.gAt least one Turbine Overspeed Protection System, as shown in TableT3.3.g-1, shall be OPERABLE.APPLICABILITY:MODES1, 2, and 3.

ACTIONS-------------------------------------NOTE-------------------------------------

Separate Condition entry is allowed for each valve.

CONDITIONREQUIRED ACTION COMPLETION TIMEA.One throttle valve or one governor valve per

high pressure turbine

steam line inoperable.A.1Restore the valve to OPERABLE status.72hoursB.One reheat stop valve or one reheat

intercept valve per

low pressure turbine

steam line inoperable.B.1Restore the valve to OPERABLE status.72hoursC.Required Action and associated Completion Time of ConditionA or B not met.C.1Close at least one valve in the affected steam line.

ORC.2Isolate the turbine from the steam supply.6hours6hours (continued)

TRM Turbine Overspeed Protection 3.3.gBRAIDWOOD - UNITS 1 & 23.3.g -2Revision57 Technical Requirements Manual ACTIONS (continued)CONDITIONREQUIRED ACTION COMPLETION TIMED.Turbine Overspeed Protection System inoperable for reasons other than ConditionA

or B.D.1---------NOTE--------

For additional guidance, reference Tables T3.3.g-1 and T3.3.g-2.---------------------

Isolate the turbine from the steam

supply.6hours SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------TSR3.0.d is not applicable.

SURVEILLANCEFREQUENCYTSR3.3.g.1Cycle each of the 12 extraction steam nonreturn check valves from the closed

position.Once within 7days prior to entering MODE3 from MODE4.TSR 3.3.g.2-------------------NOTE--------------------

Only required to be performed during

turbine operation.

Verify, by direct observation, freedom of movement of each of the 12 extraction steam

nonreturn check valve weight arms.31days (continued)

TRM Turbine Overspeed Protection 3.3.gBRAIDWOOD - UNITS 1 & 23.3.g -3Revision57 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)SURVEILLANCEFREQUENCYTSR3.3.g.3-------------------NOTE--------------------

Only required to be performed during turbine operation.

Verify, by direct observation, closure of each of the following valves from the running position.a.Six turbine reheat stop valves; andb.Six turbine reheat intercept valves.31daysTSR3.3.g.4-------------------NOTE--------------------

Only required to be performed during turbine operation.

Verify, by direct observation, closure of

each of the following valves from the running position.a.Four high pressure turbine throttle valves; andb.Four high pressure turbine governor valves.184 daysTSR 3.3.g.5Perform CHANNEL CALIBRATION.18months (continued)

TRM Turbine Overspeed Protection 3.3.gBRAIDWOOD - UNITS 1 & 23.3.g -4Revision8 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)SURVEILLANCEFREQUENCYTSR 3.3.g.6Disassemble at least one of each type of the following valves and perform a visual and surface inspection of valve seats, disks, and stems to verify no unacceptable

flaws or corrosion:a.Four high pressure turbine throttle valves,b.Four high pressure turbine governor valves,c.Six turbine reheat stop valves,d.Six turbine reheat intercept valves; ande.Twelve extraction steam nonreturn check valves.40months TRM Turbine Overspeed Protection 3.3.gBRAIDWOOD - UNITS 1 & 23.3.g -5Revision 70 Technical Requirements Manual TABLE T3.3.g-1 (page 1 of 1)

Turbine Overspeed Protection ----------------------------------------------------------------NOTE-------------------------------------------------------------

TLCO3.3.g requires at least one Turbine Overspeed Protection System to be OPERABLE. This TLCO is satisfied by the operability of one overspeed trip network along with the turbine throttle, governor, reheat stop, reheat intercept, and nonreturn check valves.

---OVERSPEED TRIP NETWORK #1 OVERSPEED TRIP NETWORK #2 OVERSPEED TRIP NETWORK #3Speed Probes(1/2SE-TS013_)

Turbine Emergency Trip Cabinet

1/2PA38J OST-2 Turbine Overspeed Trip System Panel 1/2TG09J High Pressure Trip Manifold Solenoids 1/2FSV-EH5021A, B, C and D and 1/2FSV-EH5022A, B, C and D (a)Speed Probes (1/2SE-TS011_)

DEH Control Cabinet 1/2PA22J High Pressure Trip Manifold Solenoids 1/2FSV-EH5022A, B, C and D (b)Speed Probes (1/2SE-TS014_)

DEH Control Cabinet 1/2PA22J High Pressure Trip Manifold Solenoids 1/2FSV-EH5021A, B, C and D (c)(a)The high pressure trip manifold solenoid portion of Overspeed Trip Network #1 is OPERABLE provided any one of the following combinations of solenoids are OPERABLE: 1/2FSV-EH5021A and 1/2FSV-EH5021B; 1/2FSV-EH5021A and 1/2FSV-EH5021D; 1/2FSV-EH5021B and 1/2FSV-EH5021C; 1/2FSV-EH5021C and 1/2FSV-EH5021D; 1/2FSV-EH5022A and 1/2FSV-EH5022B; 1/2FSV-EH5022A and 1/2FSV-EH5022D; 1/2FSV-EH5022B and 1/2FSV-EH5022C; or 1/2FSV-EH5022C and

1/2FSV-EH5022D.(b)The high pressure trip manifold solenoid portion of Overspeed Trip Network #2 is OPERABLE provided any one of the following combinations of solenoids are OPERABLE: 1/2FSV-EH5022A and 1/2FSV-EH5022B; 1/2FSV-EH5022A and

1/2FSV-EH5022D; 1/2FSV-EH5022B and 1/2FSV-EH5022C; or 1/2FSV-EH5022C and 1/2FSV-EH5022D.(c)The high pressure trip manifold solenoid portion of Overspeed Trip Network #3 is OPERABLE provided any one of the following combinations of solenoids are OPERABLE: 1/2FSV-EH5021A and 1/2FSV-EH5021B; 1/2FSV-EH5021A and 1/2FSV-EH5021D; 1/2FSV-EH5021B and 1/2FSV-EH5021C; or 1/2FSV-EH5021C and 1/2FSV-EH5021D.Entry into TLCO3.3.g, CONDITIONS A or B is only required when a problem exists with one of the specified valves

prohibiting it from closing. The inability of the valve to close requires it to be declared inoperable.Entry into TLCO3.3.g, CONDITION D requires isolation of the turbine from the steam supply within 6hours for the Turbine Overspeed Protection System being inoperable for reasons other than those identified in CONDITIONS A and B.

Examples could include:1.NO OVERSPEED TRIP NETWORK The main turbine has three separate electrical overspeed trip networks. Overspeed Trip Network #1 is comprised of speed probes 1/2SE-TS013_, 1/2PA38J, OST-2, 1/2TG09J and High Pressure Trip Manifold Solenoids 1/2FSV-EH5021A, B, C and D and 1/2FSV-EH5022A, B, C and D. Overspeed Trip Network #2 is comprised of speed

probes 1/2SE-TS011_, 1/2PA22J and High Pressure Trip Manifold Solenoids 1/2FSV-EH5022A, B, C and D.

Overspeed Trip Network #3 is comprised of speed probes 1/2SE-TS014_, 1/2PA22J and High Pressure Trip Manifold Solenoids 1/2FSV-EH5021A, B, C and D. With no overspeed trip network, the turbine must be isolated from the steamsupply.2.FAILURE ON A NONRETURN CHECK VALVE Failure of a nonreturn check valve to move freely would require the valve to be declared inoperable and entry in to CONDITIOND. Isolation of the steam flow path is accomplished by closing the MOV and/or manual isolation valve. Closing the MOV and/or manual isolation valve prohibits the reflux of extraction steam from the isolated steam line and satisfies Required Action of CONDITION D. Reference TableT3.3.g-2 for

determining the correct valve (MOV or manual) to isolate the flow path.

TRM Turbine Overspeed Protection 3.3.gBRAIDWOOD - UNITS 1 & 23.3.g -6Revision57 Technical Requirements ManualTABLE T3.3.g-2 (page 1 of 1)

Extraction Steam Nonreturn Check Valves and the Associated MOV or Manual Isolation Valve HEATER FAILED EXTRACTION STEAM NONRETURN CHECK VALVE MOTOR-OPERATED ISOLATION VALVE MANUAL ISOLATION VALVES_2A_ES011A_ES010A NA_2B_ES011B_ES010B NA_2C_ES011C_ES010C NA_3A_ES015A_ES013A NA_3B_ES015B_ES013B NA_3C_ES015C_ES013C NA_4A_ES017A_ES016A NA_4B_ES017B_ES016B NA_4C_ES017C_ES016C NA_5A_ES008_ES007_ES009A_5B_ES008_ES007_ES009B_6A_ES002_ES001_ES003A_6B_ES002_ES001_ES003B_7A_ES005_ES004_ES006A_7B_ES005_ES004_ES006B TRM PDMS 3.3.h BRAIDWOOD - UNITS 1 & 2 3.3.h - 1 Revision 16 Technical Requirements Manual 3.3 INSTRUMENTATION 3.3.h Power Distribution Monitoring System (PDMS)

TLCO 3.3.h The PDMS shall be OPERABLE with required PDMS instrumentation in Table T3.3.h-1 OPERABLE.

APPLICABILITY: MODE 1 with THERMAL POWER > 25% RTP.

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

Separate Condition entry is allowed for each Function.

One or more Functions with one or more

required channels inoperable.

A.1 Restore required channel to OPERABLE

status. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (continued)

TRM PDMS 3.3.h BRAIDWOOD - UNITS 1 & 2 3.3.h - 2 Revision 16 Technical Requirements Manual ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. PDMS inoperable for reasons other than

Condition A.

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

B.1 Apply LCO 3.1.4, "Rod Group Alignment Limits," as applicable, with PDMS inoperable.

AND B.2 Apply LCO 3.2.1, "Heat Flux Hot Channel Factor (F Q (Z))," as applicable, with PDMS inoperable.

AND B.3 Apply LCO 3.2.2, "Nuclear Enthalpy Rise Hot Channel Factor (F)H N," as applicable, with PDMS inoperable.

AND B.4 Apply LCO 3.2.3, "Axial Flux Difference (AFD)," as applicable, with PDMS inoperable.

AND B.5 Apply LCO 3.2.4, "Quadrant Power Tilt Ratio (QPTR)," as applicable, with PDMS inoperable.

Immediately Immediately Immediately Immediately Immediately TRM PDMS 3.3.h BRAIDWOOD - UNITS 1 & 2 3.3.h - 3 Revision 16 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.h.1 Perform CHANNEL CHECK for each required instrumentation channel.

7 days TSR 3.3.h.2 -------------------NOTE--------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION for each required instrumentation channel.

18 months (continued)

TRM PDMS 3.3.h BRAIDWOOD - UNITS 1 & 2 3.3.h - 4 Revision 16 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.3.h.3 Perform PDMS calibration.

Prior to declaring PDMS OPERABLE after each refueling

AND

NOTE------

Not required to be performed until 31 Effective Full Power Days (EFPD) after the Core Exit Thermocouple (CETC) chess knight move

pattern not satisfied

31 EFPD thereafter with the CETC chess

knight move pattern not satisfied AND 180 EFPD thereafter with the CETC chess knight move pattern satisfied

TRM PDMS 3.3.h BRAIDWOOD - UNITS 1 & 2 3.3.h - 5 Revision 16 Technical Requirements Manual Table T3.3.h-1 (Page 1 of 1)

Power Distribution Monitoring System Instrumentation FUNCTION REQUIRED CHANNELS

1. Power Range Neutron Flux Monitors 3 2. Reactor Coolant System (RCS) Cold Leg Temperature 2 3. Reactor Power 1 (a) 4. Control Bank Position (per bank) 1 (b)

5. Core Exit Temperature 17 with 2 per core quadrant

(a) Either calorimetric power, the average power of the power range neutron flux monitors, or the average power of the T channels.

(b) Either the Demand Position Indication System or the Digital Rod Position Indication (DRPI) System.

TRM PAM Instrumentation 3.3.i BRAIDWOOD - UNITS 1 & 2 3.3.i - 1 Revision 37 Technical Requirements Manual 3.3 INSTRUMENTATION 3.3.i Post Accident Monitoring (PAM) Instrumentation

TLCO 3.3.i The PAM instrumentation for each Function shown in Table T3.3.i-1 shall be OPERABLE.

APPLICABILITY: According to Table T3.3.i-1.

ACTIONS ------------------------------------NOTES------------------------------------

1. Separate Condition entry is allowed for each Function.

2. TLCO 3.0.d.3 is applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with one or more

required channel

inoperable.

A.1 Enter the Condition referenced in

Table T3.3.i-1 for

the channel.

Immediately B. As required by Required Action A.1

and referenced in

Table T3.3.i-1.

B.1 Restore required channel to OPERABLE

status.

30 days C. As required by Required Action A.1 and referenced in Table T3.3.i-1.

C.1 Restore one required channel to OPERABLE status. 7 days (continued)

TRM PAM Instrumentation 3.3.i BRAIDWOOD - UNITS 1 & 2 3.3.i - 2 Revision 1 Technical Requirements Manual ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. ---------NOTE---------

Required Action D.2.2

shall be completed whenever Required

Action D.2.1 is not met. ----------------------

As required by Required Action A.1 and referenced in

Table T3.3.i-1.

D.1 Initiate alternate method of monitoring

the appropriate parameters.

AND D.2.1 Restore one required channel to OPERABLE

status. OR D.2.2 Submit a report to the Plant Operating

Review Committee outlining 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. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 7 days 14 days E. One or more Functions with two required

channels inoperable.

E.1 Restore one required channel to OPERABLE

status.

7 days F. Required Action and associated Completion

Time of Condition B, C, D or E not met.

F.1 Enter TLCO 3.0.c.

Immediately

TRM PAM Instrumentation 3.3.i BRAIDWOOD - UNITS 1 & 2 3.3.i - 3 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.i.1 Perform CHANNEL CHECK.

31 days TSR 3.3.i.2 Perform CHANNEL CALIBRATION.

18 months

TRM PAM Instrumentation 3.3.i BRAIDWOOD - UNITS 1 & 2 3.3.i - 4 Revision 1 Technical Requirements Manual Table T3.3.i-1 (page 1 of 1) Post Accident Monitoring Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS

1. Auxiliary Feedwater Flow Rate (per SG) 1,2,3 2 B TSR 3.3.i.1 TSR 3.3.i.2

2. PORV Position Indicator(a) (open/closed) (per valve) 1,2,3 1 C TSR 3.3.i.1

3. PORV Block Valve Position Indicator(b) (open/closed) (per valve) 1,2,3 1 C TSR 3.3.i.1

4. Safety Valve Position Indicator (open/closed) (per valve) 1,2,3 1 C TSR 3.3.i.1

5. Containment Floor Drain Sump Water Level (Narrow Range) 1,2,3 2 B TSR 3.3.i.1 TSR 3.3.i.2

6. Auxiliary Building Vent Stack (Wide Range Noble Gas) (per stack) 1,2,3 1 D TSR 3.3.i.1 TSR 3.3.i.2

7. Reactor Coolant Subcooling Margin Monitor(c) 1,2,3 2 B None (a) Not applicable if the associated block valve is in the closed position.

(b) Not applicable if the block valve is verified in the closed position and power is removed.

(c) Use monitoring channels (10 highest average core exit temperatures) in conjunction with RCS pressure to determine the subcooling margin.

TRM Hydrogen Monitor 3.3.j BRAIDWOOD - UNITS 1 & 2 3.3.j - 1 Revision 38 Technical Requirements Manual 3.3 INSTRUMENTATION 3.3.j Hydrogen Monitor TLCO 3.3.j One containment hydrogen monitor channel shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS -------------------------------------NOTE------------------------------------

TLCO 3.0.d.3 is applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTES-------- 1. The monitor must be in standby mode to meet the requirement in NUREG-0737, Item II.F.1.6.

2. Not applicable if hydrogen monitor is in operation.

Required hydrogen monitor not in the standby mode.

A.1 Place the hydrogen monitor in the standby mode.

OR A.2 Declare the hydrogen monitor inoperable.

Immediately Immediately (continued)

TRM Hydrogen Monitor 3.3.j BRAIDWOOD - UNITS 1 & 2 3.3.j - 2 Revision 38 Technical Requirements Manual ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required hydrogen monitor channel inoperable.

B.1 Confirm readiness for utilizing alternate method of monitoring.

AND B.2 Restore required hydrogen monitor channel to OPERABLE status. Immediately 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. Required Action and associated Completion Time of Condition B not met. C.1 Submit a report to the Plant Operating Review Committee outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the hydrogen monitor channel to OPERABLE status. 14 days SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

TSR 3.3.j.1 Verify hydrogen monitor is in standby mode.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months TSR 3.3.j.2 Perform CHANNEL CHECK.

31 days TSR 3.3.j.3 Perform CHANNEL OPERATIONAL TEST.

92 days TSR 3.3.j.4 Perform CHANNEL CALIBRATION.

18 months

TRM Feedwater Flow 3.3.kBRAIDWOOD -UNITS 1 & 23.3.k-1Revision84 Technical Requirements Manual

3.3 INSTRUMENTATION

3.3.k Feedwater FlowTLCO 3.3.kThe Leading Edge Flow Meter system shall be OPERABLE.APPLICABILITY:MODE 1, with THERMAL POWER > 98.3% RTP.

ACTIONS-------------------------------------NOTE------------------------------------TLCO3.0.d.2is not applicable.

CONDITIONREQUIRED ACTIONCOMPLETION TIMEA.LEFMsystem inoperable.A.1Restore LEFM system to OPERABLE status.

72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months sB.REQUIRED ACTION and associated COMPLETION

TIME of CONDITION A

not met.B.1Reduce power to <98.3% RTP.

Immediately (continued)

TRM Feedwater Flow 3.3.kBRAIDWOOD -UNITS 1 & 23.3.k -2Revision91 Technical Requirements Manual SURVEILLANCE REQUIREMENTSSURVEILLANCEFREQUENCYTSR 3.3.k.1Perform CHANNEL CHECK.

Prior to exceeding 98.3%

RTP AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafterTSR 3.3.k.2Perform CHANNEL CALIBRATION.

Once per 24 months TRM FHB Ventilation System Actuation Instrumentation 3.3.o BRAIDWOOD - UNITS 1 & 2 3.3.o - 1 Revision 1 Technical Requirements Manual 3.3 INSTRUMENTATION 3.3.o Fuel Handling Building Exhaust Filter Plenum (FHB) Ventilation System Actuation Instrumentation

TLCO 3.3.o The FHB Ventilation System actuation instrumentation in Table T3.3.o-1 shall be OPERABLE.

APPLICABILITY: According to Table T3.3.o-1.

ACTIONS

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

TLCO 3.0.c is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One channel inoperable.

A.1 Restore channel to OPERABLE status.

7 days (continued)

TRM FHB Ventilation System Actuation Instrumentation 3.3.o BRAIDWOOD - UNITS 1 & 2 3.3.o - 2 Revision 1 Technical Requirements Manual ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and associated Completion

Time for Condition A not met. OR Two channels inoperable.

B.1.1 Place in emergency mode one FHB

Ventilation System train capable of

being powered by an OPERABLE emergency power source.

AND B.1.2 Take actions to provide an appropriate portable continuous monitor with the same alarm setpoint in the fuel pool area.

OR B.2 Suspend crane operations with

loads, including new fuel assemblies, over or within the spent

fuel storage pool.

Immediately

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.o.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

TRM FHB Ventilation System Actuation Instrumentation 3.3.o BRAIDWOOD - UNITS 1 & 2 3.3.o - 3 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.3.o.2 Perform CHANNEL OPERATIONAL TEST.

92 days TSR 3.3.o.3 Perform CHANNEL CALIBRATION.

18 months

TRM FHB Ventilation System Actuation Instrumentation 3.3.o BRAIDWOOD - UNITS 1 & 2 3.3.o - 4 Revision 1 Technical Requirements Manual TABLE T3.3.o-1 (page 1 of 1) FHB Ventilation System Actuation Instrumentation FUNCTIONAL UNIT APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS ALARM/TRIP SETPOINT REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS Fuel Building Isolation Radioactivity-High and Criticality (0RE-AR055/56)

(a) 5 mR/h 2 TSR 3.3.o.1 TSR 3.3.o.2 TSR 3.3.o.3

(a) During crane operations with loads, including new fuel assemblies, over or within the spent fuel storage pool.

TRM Radiation Monitoring Instrumentation 3.3.pBRAIDWOOD -UNITS 1 & 23.3.p -1Revision1 Technical Requirements Manual

3.3 INSTRUMENTATION

3.3.p Radiation Monitoring InstrumentationTLCO 3.3.pThe Radiation Monitoring instrumentation Alarm/Trip Setpoints for each Function in Table T3.3.p-1 shall be OPERABLE.APPLICABILITY:According to TableT3.3.p-1.

ACTIONS-------------------------------------NOTE-------------------------------------

Separate Condition entry is allowed for each Function.

CONDITIONREQUIRED ACTIONCOMPLETION TIMEA.One or more Functions with one or more required channels

Alarm/Trip Setpoint(s)

not within limits specified in TableT3.3.p-1.A.1Adjust the Setpoint to within limit.4hours (continued)

TRM Radiation Monitoring Instrumentation 3.3.pBRAIDWOOD -UNITS 1 & 23.3.p -2Revision1 Technical Requirements Manual ACTIONS (continued)CONDITIONREQUIRED ACTIONCOMPLETION TIMEB.Required Action and associated Completion Time of Condition A

not met.B.1Declare the channel inoperable and enter

applicable Condition

and Required Actions of LCO3.3.6, "Containment Ventilation Isolation Instrumentation,"

LCO3.3.7, "VC

Filtration System

Actuation Instrumentation," LCO3.3.8, "FHB

Ventilation System

Actuation

Instrumentation," TLCO3.3.o, "FHB Ventilation System

Actuation

Instrumentation," and TLCO3.7.i, "FHB Ventilation Systems,"

for one or more

radiation monitors

inoperable, as applicable.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCYTSR 3.3.p.1Perform CHANNEL CHECK.12hoursTSR 3.3.p.2Perform CHANNEL OPERATIONAL TEST.

92 days (continued)

TRM Radiation Monitoring Instrumentation 3.3.pBRAIDWOOD -UNITS 1 & 23.3.p -3Revision1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)SURVEILLANCEFREQUENCYTSR 3.3.p.3Perform CHANNEL CALIBRATION.18months TRM Radiation Monitoring Instrumentation 3.3.pBRAIDWOOD -UNITS 1 & 23.3.p -4Revision87 Technical Requirements Manual TABLE T3.3.p-1 (page 1 of 1)

Radiation Monitoring Instrumentation for Plant Operations FUNCTIONAL UNIT APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS ALARM/TRIP SETPOINT REQUIRED CHANNELS CHANNELS TO TRIP/ALARM SURVEILLANCE

REQUIREMENTS1.Fuel Building Isolation Radioactivity-High and

Criticality (0RE-AR055/56)(a)!5mR/hr21TSR3.3.p.1TSR3.3.p.2TSR3.3.p.32.Containment Isolation Containment Radioactivity-Higha)U-1 (1RE-AR011/12)b)U-2 (2RE-AR011/12)

All All (b)

(b)2 2 1 1TSR3.3.p.1TSR3.3.p.2TSR3.3.p.3TSR3.3.p.1TSR3.3.p.2 TSR3.3.p.33.Main Control Room Isolation-Outside Air

Intake-Gaseous Radioactivity-Higha)TrainA (0RE-PR031B/32B)b)TrainB (0RE-PR033B/34B)

All All!2mR/hr!2mR/hr 2 2 1 1TSR3.3.p.1TSR3.3.p.2TSR3.3.p.3TSR3.3.p.1TSR3.3.p.2 TSR3.3.p.3(a)During crane operations with loads, including new fuel assemblies, over or within the spent fuel storage pool.(b)Trip Setpoint shall be established at 2 x background in the Containment Building at RTP.

TRM ESFAS Instrumentation 3.3.yBRAIDWOOD - UNITS 1 & 23.3.y -1Revision78 Technical Requirements Manual

3.3 INSTRUMENTATION

3.3.y Engineered Safety Feature Actuation System (ESFAS) InstrumentationTLCO 3.3.yThe ESFAS Instrumentation in TableT3.3.y-1 shall be OPERABLE.APPLICABILITY:According to TableT3.3.y-1.

ACTIONS CONDITIONREQUIRED ACTIONCOMPLETION TIMEA.One or more required channel(s) inoperable.A.1Enter the Condition referenced in TableT3.3.y-1 for

the channel.

ImmediatelyB.One Auxiliary Feedwater - Manual

Initiation channel

inoperable.B.1Restore channel to OPERABLE status.72hoursC.Required Action and associated Completion

Time of Condition B

not met.OR Two Auxiliary Feedwater - Manual Initiation channels inoperable.C.1Enter TLCO 3.0.c.Immediately TRM ESFAS Instrumentation 3.3.yBRAIDWOOD - UNITS 1 & 23.3.y -2Revision78 Technical Requirements Manual SURVEILLANCE REQUIREMENTSSURVEILLANCEFREQUENCYTSR 3.3.y.1Perform TRIP ACTUATING DEVICE OPERATIONAL TEST.18months TRM ESFAS Instrumentation 3.3.yBRAIDWOOD - UNITS 1 & 23.3.y -3Revision78 Technical Requirements ManualTableT3.3.y-1 (page1 of1)

Engineered Safety Feature Actuation System Instrumentation FUNCTIONAPPLICABLE MODESOR OTHER SPECIFIED CONDITIONS CONDITIONS REQUIRED CHANNELS SURVEILLANCE

REQUIREMENTSAuxiliary Feedwater - Manual Initiation 1,2,3 B, C 2TSR3.3.y.1 TRM RCS Chemistry 3.4.b BRAIDWOOD - UNITS 1 & 2 3.4.b - 1 Revision 1 Technical Requirements Manual 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.b RCS Chemistry

TLCO 3.4.b RCS Chemistry shall be maintained within the limits of Table T3.4.b-1.

APPLICABILITY: According to Table T3.4.b-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more chemistry parameters in excess

of its Steady-State Limit but within its Transient Limit.

A.1 Restore parameter to within its

Steady-State Limit.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months B. Dissolved Oxygen concentration in

excess of its Steady-State Limit for

> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

OR Dissolved Oxygen concentration in excess of its Transient Limit.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4 with T avg 250°F.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

TRM RCS Chemistry 3.4.b BRAIDWOOD - UNITS 1 & 2 3.4.b - 2 Revision 1 Technical Requirements Manual ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. Chloride or Fluoride concentration in

excess of its Steady-State Limit for

> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

OR Chloride or Fluoride concentration in

excess of its Transient Limit.

C.1 Initiate action to reduce pressurizer

pressure 500 psig.

AND C.2 Be in MODE 3.

AND C.3 Be in MODE 5.

AND C.4 Perform an engineering

evaluation to determine the effects

of the out-of-limit condition on the structural integrity of the RCS and to determine that the

RCS remains acceptable for continued operation.

Immediately

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Prior to increasing pressurizer pressure above

500 psig OR Prior to proceeding to MODE 4 from

MODE 5 TRM RCS Chemistry 3.4.b BRAIDWOOD - UNITS 1 & 2 3.4.b - 3 Revision 40 Technical Requirements Manual SURVEILLANCE REQUIREMENTS

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

TSR 3.4.b.1 applies to each RCS Chemistry parameter in Table T3.4.b-1.

SURVEILLANCE FREQUENCY TSR 3.4.b.1 ------------------NOTES--------------------

1. Not required to be performed for Dissolved Oxygen if RCS T avg 250°F. 2. Not required to be performed for Dissolved Oxygen in Mode 1 if Dissolved Hydrogen concentration is >

15 cc/kg and is sampled at the same frequency as Dissolved Oxygen.

Verify RCS chemistry parameters within limits specified in Table T3.4.b-1.

In accordance with EPRI PWR Primary Water Chemistry Guidelines

TRM RCS Chemistry 3.4.b BRAIDWOOD - UNITS 1 & 2 3.4.b - 4 Revision 1 Technical Requirements Manual Table T3.4.b-1 RCS Chemistry Limits PARAMETER APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS STEADY STATE LIMIT TRANSIENT LIMIT

1. Dissolved Oxygen MODES 1,2,3, and MODE 4 with T avg > 250°F 100 ppb 1000 ppb

2. Chloride At All Times 150 ppb 1500 ppb

3. Fluoride At All Times 150 ppb 1500 ppb

TRM Pressurizer Temperature Limits 3.4.c BRAIDWOOD - UNITS 1 & 2 3.4.c - 1 Revision 1 Technical Requirements Manual 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.c Pressurizer Temperature Limits

TLCO 3.4.c The pressurizer temperature shall be limited to:

1. 100°F heatup in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period;

2. 200°F cooldown in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period; and

3. 320°F spray water temperature differential.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

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

Required Actions A.2 and A.3 shall be completed whenever this Condition is entered. ----------------------

Pressurizer temperature not within limits.

A.1 Restore pressurizer temperature to within limits.

AND A.2 Perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity

of the pressurizer.

AND A.3 Determine that the pressurizer remains

acceptable for

continued operation.

30 minutes

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (continued)

TRM Pressurizer Temperature Limits 3.4.c BRAIDWOOD - UNITS 1 & 2 3.4.c - 2 Revision 1 Technical Requirements Manual ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. Required Actions and associated Completion

Times of Condition A not met. B.1 ---------NOTE--------

Required Action B.1

is only applicable when in MODES 1 and

2. ---------------------

Be in MODE 3.

AND B.2 Reduce pressurizer pressure to

< 500 psig.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.c.1 -------------------NOTE--------------------

Only required to be performed during system

heatup and cooldown.

Verify pressurizer heatup or cooldown rates

are within limits.

30 minutes

TSR 3.4.c.2 -------------------NOTE--------------------

Only required to be performed during

auxiliary spray operation.

Verify auxiliary spray water temperature differential is within limit.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months TRM Pressurizer Power Operated Relief Valves (PORVs) 3.4.d BRAIDWOOD - UNITS 1 & 2 3.4.d - 1 Revision 1 Technical Requirements Manual 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.d Pressurizer Power Operated Relief Valves (PORVs)

TLCO 3.4.d One PORV shall be unisolated and capable of responding in automatic to relieve pressurizer pressure.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Both PORVs unable to automatically perform

a pressure relief actuation.

A.1 Restore the automatic pressure relief

function to at least one PORV.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required Action and associated Completion Time of Condition A not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

TSR 3.4.d.1 Perform CHANNEL CALIBRATION on the actuation instrumentation.

18 months

TRM Reactor Vessel Head Vents 3.4.e BRAIDWOOD - UNITS 1 & 2 3.4.e - 1 Revision 34 Technical Requirements Manual 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.e Reactor Vessel Head Vents

TLCO 3.4.e Two reactor vessel head vent paths, each consisting of two valves in series powered from emergency buses, shall be

OPERABLE and closed.

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

The reactor vessel head vent valves may be cycled for the purposes of re-seating to eliminate identified seat leakage, correcting indication problems, or Inservice Inspection in MODES 3 and 4 provided:

1. Only one valve in each train is cycled at a time; and

2. The same train redundant valve is verified closed and de-energized.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One reactor vessel head vent path

inoperable.

A.1 Initiate action to maintain the

inoperable vent path closed.

AND A.2 Initiate action to remove power from the

valve actuators of the valves in the

inoperable vent path.

Immediately

Immediately (continued)

TRM Reactor Vessel Head Vents 3.4.e BRAIDWOOD - UNITS 1 & 2 3.4.e - 2 Revision 37 Technical Requirements Manual ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. ---------NOTE---------

TLCO 3.0.d.3 is applicable in MODES 1 and 2 provided Required Actions B.1 and B.2 are complete.

Both reactor vessel head vent paths inoperable.

B.1 Initiate action to maintain the

inoperable vent paths closed. AND B.2 Initiate action to remove power from the

valve actuators of the valves in the

inoperable vent paths.

AND B.3 Restore one vent path to OPERABLE status.

Immediately

30 days C. Required Actions and associated Completion

Times of Condition B

not met.

C.1 Enter TLCO 3.0.c.

Immediately

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

TSR 3.4.e.1 Verify all manual isolation valves in each vent path are locked in the open position.

18 months

(continued)

TRM Reactor Vessel Head Vents 3.4.e BRAIDWOOD - UNITS 1 & 2 3.4.e - 3 Revision 34 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.4.e.2 -------------------NOTE--------------------

This Surveillance shall not be performed in

MODE 1, 2, 3, or 4 except as allowed by TLCO Note.

Perform a complete cycle of each valve in the vent path from the control room.

18 months TSR 3.4.e.3 ------------------ NOTE--------------------

This Surveillance shall not be performed in

MODE 1, 2, 3, or 4.

Verify flow through the reactor vessel head

vent paths during venting operation.

18 months

TRM Structural Integrity 3.4.fBRAIDWOOD - UNITS 1 & 23.4.f-1Revision82 Technical Requirements Manual 3.4 Reactor Coolant System (RCS) 3.4.f Structural IntegrityTLCO 3.4.fThe structural integrity of all ASME Code Class 1, 2, and 3 plant components shall be maintained in accordance with the Inservice Inspection and Testing Programs.APPLICABILITY:MODES1, 2, 3, 4, 5, and 6.

ACTIONS-------------------------------------NOTES-----------------------------------1.Separate Condition entry is allowed for each component.2.TLCO3.0.d.3 is applicable.

CONDITION REQUIRED ACTION COMPLETION TIMEA.---------NOTE---------

Only applicable to ASME Code Class 1 and 2 components.

Structural integrity of one or more ASME component(s) not in conformance.A.1Restore the structural integrity of the affected component to within its limits.

ORA.2Isolate the affected component.

Prior to increasing the RCS temperature to !200F Prior to increasing the RCS temperature to !200F (continued)

TRM Structural Integrity 3.4.fBRAIDWOOD - UNITS 1 & 23.4.f-2Revision82 Technical Requirements Manual ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIMEB.---------NOTE---------

Only applicable to ASME Code Class 3 components.

Structural integrity of one or more ASME component(s) not in conformance.B.1Restore the structural integrity of the affected component to within its limits.

ORB.2Isolate the affected component.

Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCYTSR3.4.f.1Perform an inspection of each RCP flywheel.

In accordance with the RCP Flywheel Inspection Program.TSR3.4.f.2Verify the structural integrity of ASME Code Class 1, 2, and 3 components.

In accordance with the Inservice Inspection and Testing Programs.

TRM ECCS Subsystems - T avg 200°F and Pressurizer Level 5% 3.5.a BRAIDWOOD - UNITS 1 & 2 3.5.a - 1 Revision 1 Technical Requirements Manual 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) 3.5.a ECCS Subsystems - T avg 200°F and Pressurizer Level 5% TLCO 3.5.a One of the following means of decay heat removal shall be available:

1. One Safety Injection (SI) pump and flow path, or

2. A flow path to permit gravity feed from the RWST to the Reactor Coolant System (RCS) with the reactor vessel

head removed.

APPLICABILITY: MODES 5 and 6 with pressurizer level 5%.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No means of decay heat removal available.

A.1 Initiate action to restore an available

means of decay heat removal.

OR A.2 Initiate action to establish pressurizer

level > 5%.

Immediately

TRM ECCS Subsystems - T avg 200°F and Pressurizer Level 5% 3.5.a BRAIDWOOD - UNITS 1 & 2 3.5.a - 2 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.5.a.1 -------------------NOTE--------------------

Only required to be performed when complying with TLCO 3.5.a.1.

Verify the required SI pump motor circuit breaker is racked in.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months TSR 3.5.a.2 -------------------NOTE--------------------

Only required to be performed when complying with TLCO 3.5.a.1.

Verify an OPERABLE flow path available from the RWST to the RCS.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months TSR 3.5.a.3 -------------------NOTE--------------------

Only required to be performed when complying with TLCO 3.5.a.2.

Verify the reactor vessel head is removed.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months TSR 3.5.a.4 -------------------NOTE--------------------

Only required to be performed when

complying with TLCO 3.5.a.2.

Verify an OPERABLE flow path available to

permit gravity feed from the RWST to the RCS. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

TRM Steam Generator Pressure/Temperature Limitations 3.7.a BRAIDWOOD - UNITS 1 & 2 3.7.a - 1 Revision 1 Technical Requirements Manual 3.7 PLANT SYSTEMS 3.7.a Steam Generator Pressure/Temperature Limitations

TLCO 3.7.a Reactor and Secondary coolant pressure shall be 200 psig.

APPLICABILITY: When either Reactor or Secondary coolant temperature in the steam generator is 70°F. ACTIONS -------------------------------------NOTE-------------------------------------

Separate Condition entry is allowed for each side (Primary or Secondary) of each steam generator.

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

Required Actions A.2

and A.3 shall be completed whenever

this Condition is entered. ----------------------

Reactor coolant pressure > 200 psig.

OR Secondary coolant pressure > 200 psig.

A.1 Reduce the steam generator pressure of

the applicable side to 200 psig.

AND A.2 Perform an engineering

evaluation to determine the effect

of the overpressurization on the structural integrity of the steam generator.

AND A.3 Determine that the steam generator

remains acceptable for continued

operation.

30 minutes

Prior to increasing temperature to

> 200°F Prior to increasing temperature to

> 200°F TRM Steam Generator Pressure/Temperature Limitations 3.7.a BRAIDWOOD - UNITS 1 & 2 3.7.a - 2 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.a.1 -------------------NOTE--------------------

Only required to be performed when the

temperature of either Reactor or Secondary coolant 70°F. -------------------------------------------

Verify pressure in each side of the steam

generator is 200 psig.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

TRM Snubbers 3.7.bBRAIDWOOD - UNITS 1 & 23.7.b -1Revision81 Technical Requirements Manual 3.7 PLANT SYSTEMS 3.7.b SnubbersTLCO 3.7.bAll required snubbers shall be OPERABLE.---------------------------NOTES---------------------------1.Not applicable to snubbers installed on nonsafety related systems unless their failure, or failure of the associated system(s), would adversely affect any safety

related system.2.Required snubber(s) are those installed in a system, subsystem, or train required to be OPERABLE.3.Verification of Steam Generator snubber fluid levels shall be through local examination of reservoirs and snubbers, not based on remote panel lighting indication.

APPLICABILITY:MODES1, 2, 3, 4, and MODES5, and 6 for snubbers located on systems required OPERABLE in those MODES.

TRM Snubbers 3.7.bBRAIDWOOD - UNITS 1 & 23.7.b -2Revision81 Technical Requirements Manual ACTIONS-------------------------------------NOTE-------------------------------------

Separate Condition entry is allowed for each snubber.

CONDITION REQUIRED ACTION COMPLETION TIMEA.One or more required snubber(s) removed or

inoperable.A.1Declare the applicable portion of the attached system inoperable.

ANDA.2Follow the appropriate Required Actions for that system.Immediately Immediately TRM Snubbers 3.7.bBRAIDWOOD - UNITS 1 & 23.7.b -3Revision60 Technical Requirements Manual SURVEILLANCE REQUIREMENTS----------------------------------NOTE---------------------------------------The provisions of TSR3.0.b are applicable for all inspection intervals up to and including 48months.

SURVEILLANCEFREQUENCYTSR 3.7.b.1Perform required inservice examinations and testingof snubbers in accordance with the Inservice Inspection Program.

In accordance

with the Inservice Inspection Program TRM Snubbers 3.7.bBRAIDWOOD - UNITS 1 & 23.7.b -4Revision81 Technical Requirements ManualTableT3.7.b-1 (page1 of1)

Snubber Inservice Inspection Program ElementsA.TransientEventInspection An inspection shall be performed of all snubbers attached to sections of

systems that have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems within 6months following such an event. In

addition to satisfying the visual inspection acceptance criteria, freedom of motion of mechanical snubbers shall be verified using at least one of the following: (1)manually induced snubber movement; or (2)evaluation of in-place snubber piston setting; or (3)stroking the mechanical snubber through its full range of travel.B.Inoperable Snubbers Discovered During Functional Tests When the acceptance criteria as specified in the snubber functional test program and procedures is exceeded, an Engineering Evaluation shall be performed to determine if the attachedsystem and/or component is acceptablefor continued operation.C.Removal of Required Snubber(s)for Testing or Maintenance When required snubber(s) are to be removed for the purpose of functional testing or maintenance from operable systems or components, an evaluation shall be performed demonstrating seismic operability with the snubber(s) removed prior to removing the snubber(s)or the applicable portion of the attached system shall be declared inoperable.D.Locations with Two Snubbers Configurations that utilize two snubbers at the same location shall be consideredas one required snubber.

TRM Sealed Source Contamination 3.7.c BRAIDWOOD - UNITS 1 & 2 3.7.c - 1 Revision 1 Technical Requirements Manual 3.7 PLANT SYSTEMS 3.7.c Sealed Source Contamination

TLCO 3.7.c Each sealed source containing radioactive material either in excess of 100

µCi of beta and/or gamma emitting material or 5 µCi of alpha emitting material shall be free of 0.005 µCi of removable contamination.

APPLICABILITY: At all times.

ACTIONS

NOTES------------------------------------ 1. Separate Condition entry is allowed for each source.

2. TLCO 3.0.c is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME

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

Required Actions A.2 and A.3 shall be completed whenever Condition A is entered. ----------------------

One or more sealed

sources with removable contamination not within limits.

A.1 Withdraw the sealed source from use.

AND A.2.1 Decontaminate and repair the sealed

source. OR A.2.2 Dispose of the sealed source in accordance

with Commission Regulations.

AND A.3 Submit report to the Plant Operating

Review Committee.

Immediately

Prior to use or transfer to another licensee

Immediately

12 months

TRM Sealed Source Contamination 3.7.c BRAIDWOOD - UNITS 1 & 2 3.7.c - 2 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS

NOTES------------------------------------ 1. Each sealed source shall be tested for leakage and/or contamination by the licensee, or other persons specifically authorized by the Commission or Agreement State.

2. The test method shall have a detection sensitivity of at least 0.005

µCi per test sample.

3. Startup sources and fission detectors previously subjected to core flux are exempted from the TSRs. Startup sources do not include "secondary

startup sources" which do not contain radioactive material.

4. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

SURVEILLANCE FREQUENCY TSR 3.7.c.1 -------------------NOTE--------------------

Only required to be performed on sources in

use. -------------------------------------------

Perform leakage testing for all sealed sources containing radioactive materials

with a half-life

> 30 days (excluding Hydrogen 3) and in any form other than gas.

6 months (continued)

TRM Sealed Source Contamination 3.7.c BRAIDWOOD - UNITS 1 & 2 3.7.c - 3 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.7.c.2 -------------------NOTES------------------- 1. Only required to be performed on stored sources not in use.

2. Only required to be performed if not tested within the previous 6 months.

Perform leakage testing for each sealed source and fission detector.

Prior to use or transfer to another licensee TSR 3.7.c.3 -------------------NOTE--------------------

Only required to be performed on stored sources not in use.

Perform leakage testing on sealed sources and fission detectors transferred without a

certificate indicating the last test date.

Prior to use or transfer to

another licensee TSR 3.7.c.4 -------------------NOTE--------------------

Only required to be performed on sealed startup sources and fission detectors not previously subjected to core flux.

Perform leakage testing for each sealed startup source and fission detector.

Once within 31 days prior to

being subjected to core flux or installed in the core or following

repair or maintenance to sources TRM Area Temperature Monitoring 3.7.d BRAIDWOOD - UNITS 1 & 2 3.7.d - 1 Revision 1 Technical Requirements Manual 3.7 PLANT SYSTEMS 3.7.d Area Temperature Monitoring

TLCO 3.7.d The temperature limit of each area in Table T3.7.d-1 shall not be exceeded for > 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or by > 30

° F.

APPLICABILITY: Whenever the equipment in the affected area is required to be OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each area.

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

Required Actions A.2

and A.3 shall be completed whenever Condition A is entered. ----------------------

One or more area temperatures exceeding the temperature limit by > 30°F.

A.1.1 Restore area temperature to within

limit. OR A.1.2 Declare the equipment in the affected area inoperable.

AND A.2 Submit a report to the Plant Operating Review Committee outlining the cumulative time and the amount by which the temperature in

the affected area exceeded the limit.

AND 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 30 days

(continued)

TRM Area Temperature Monitoring 3.7.d BRAIDWOOD - UNITS 1 & 2 3.7.d - 2 Revision 1 Technical Requirements Manual ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)

A.3 Perform an analysis to demonstrate the

continued OPERABILITY of the affected

equipment.

30 days B. One or more area temperatures exceeding the temperature limit for > 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

B.1 Submit a report to the Plant Operating Review Committee outlining the cumulative time and the amount by which the temperature in the affected area exceeded the limit.

AND B.2 Perform an analysis to demonstrate the

continued OPERABILITY of the affected

equipment.

30 days

30 days SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.d.1 Verify each area temperature is within limits in accordance with Table T3.7.d-1.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months TRM Area Temperature Monitoring 3.7.d BRAIDWOOD - UNITS 1 & 2 3.7.d - 3 Revision 24 Technical Requirements Manual Table T3.7.d-1 (page 1 of 1) Area Temperature Monitoring AREA TEMPERATURE LIMIT

(°F) 1. Miscellaneous Electrical Equipment and Battery Rooms 108 2. ESF Switchgear Rooms 108 3. Division 12 (Division 22) Cable Spreading Room 108 4. Upper Cable Spreading Rooms 90 5. Diesel Generator Rooms 132 6. Diesel Oil Storage Rooms 132 7. Auxiliary Building Vent Exhaust Filter Cubicle 105 8. Centrifugal Charging Pump Rooms 122 9. Containment Spray Pump Rooms 130 10. RHR Pump Rooms 130 11. Safety Injection Pump Rooms 130 12. Control Room 90 13. Lower Cable Spreading Rooms 108 TRM Fuel Handling Building Ventilation Systems 3.7.iBRAIDWOOD - UNITS 1 & 23.7.i -1Revision77 Technical Requirements Manual 3.7 PLANT SYSTEMS 3.7.i Fuel Handling Building (FHB) Ventilation SystemsTLCO 3.7.iTwo FHB Ventilation System trains shall be OPERABLE.

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

The TLCO requirements do not apply when the main hoist/load block travels over the spent fuel pool without a load due to the design of the load block.

APPLICABILITY:During crane operation with loads, including new fuel assemblies, over or within the spent fuel storage pool.

ACTIONS-------------------------------------NOTE-------------------------------------TLCO3.0.c is not applicable.

CONDITIONREQUIRED ACTIONCOMPLETION TIMEA.One FHB Ventilation System train

inoperable.A.1Restore FHB Ventilation System

train to OPERABLE

status.7daysB.Required Action and associated Completion

Time of Condition A

not met.B.1 Place in emergency mode one OPERABLE FHB

Ventilation System

train capable of

being powered by an OPERABLE emergency power source.

ORB.2Suspend crane operation with loads, including new fuel

assemblies, over or within the spent fuel storage pool.

Immediately Immediately (continued)

TRM Fuel Handling Building Ventilation Systems 3.7.iBRAIDWOOD - UNITS 1 & 23.7.i -2Revision1 Technical Requirements Manual ACTIONS (continued)CONDITIONREQUIRED ACTIONCOMPLETION TIMEC.Two FHB Ventilation System trains inoperable.C.1Suspend crane operation with loads, including new fuel

assemblies, over or

within the spent fuel

storage pool.

Immediately SURVEILLANCE REQUIREMENTSSURVEILLANCEFREQUENCYTSR3.7.i.1For FHB Ventilation Systems required to be OPERABLE, the following SRs are applicable:SR3.7.13.1SR3.7.13.4 SR3.7.13.2SR3.7.13.5 In accordance

with applicable SRs TRM Spent Fuel Pool Water Level 3.7.j BRAIDWOOD - UNITS 1 & 2 3.7.j - 1 Revision 1 Technical Requirements Manual 3.7 PLANT SYSTEMS 3.7.j Spent Fuel Pool Water Level

TLCO 3.7.j The spent fuel pool water level shall be 23 ft over the top of irradiated fuel assemblies seated in the storage

racks. APPLICABILITY: During movement of loads, including new fuel assemblies, over or within the spent fuel pool.

ACTIONS

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

TLCO 3.0.c is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool water level not within

limit.

A.1 Suspend movement of loads, including new

fuel assemblies, over or within the spent fuel pool.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.j.1 Verify spent fuel pool water level is 23 ft above the top of the irradiated fuel assemblies seated in the storage racks. 7 days

TRM Spent Fuel Pool Boron Concentration 3.7.k BRAIDWOOD - UNITS 1 & 2 3.7.k - 1 Revision 21 Technical Requirements Manual 3.7 PLANT SYSTEMS 3.7.k Spent Fuel Pool Boron Concentration

TLCO 3.7.k The spent fuel pool boron concentration shall be 2000 ppm.

APPLICABILITY: Whenever fuel assemblies are stored in the spent fuel pool.

ACTIONS -------------------------------------NOTE-------------------------------------

TLCO 3.0.c is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME

A. Spent fuel pool boron concentration not within limit.

A.1 Suspend movement of loads, including new fuel assemblies, over or within the spent fuel pool.

AND A.2 Initiate action to restore spent fuel pool boron concentration to within limit.

Immediately

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

TSR 3.7.k.1 Verify the spent fuel pool boron concentration is within limit.

7 days TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 1 Revision 37 Technical Requirements Manual 3.8 ELECTRICAL POWER SYSTEMS 3.8.a Containment Penetration Conductor Overcurrent Protective Devices

TLCO 3.8.a The containment penetration conductor overcurrent protective devices in Table T3.8.a-1 for Unit 1 (Table T3.8.a-2 for

Unit 2) shall be OPERABLE.

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

ACTIONS

NOTES----------------------------------- 1. Separate Condition entry is allowed for each device.

2. TLCO 3.0.d.3 is applicable to overcurrent devices in circuits which have the circuit breakers tripped, inoperable circuit breakers racked out or

removed. -----------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment

penetration conductor overcurrent protective devices inoperable.

A.1 Restore the protective device to

OPERABLE status.

OR 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 2 Revision 1 Technical Requirements Manual ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)

A.2.1 Verify the circuit is de-energized with the

associated circuit breaker tripped.

AND A.2.2 Determine operability status of the

affected system or component.

OR A.3.1 Verify the circuit is de-energized with the

associated circuit

breaker racked out or removed.

AND A.3.2 Determine operability status of the affected system or component.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND 7 days thereafter

Immediately following initial performance of Required Action A.2.1 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND 7 days thereafter Immediately

following initial performance of Required Action A.3.1

B. Required Actions and associated Completion

Times of Condition A not met. B.1 Be in MODE 3.

AND B.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 3 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.8.a.1 -------------------NOTES------------------- 1. A representative sample shall consist of 10% of the circuit breakers selected, on a rotating basis, from

6.9 kV and 4.16 kV circuit breakers.

2. For each circuit breaker found inoperable during these functional tests, an additional representative sample of 10% of all circuit breakers of the inoperable type shall

be functionally tested until no more

failures are found or all circuit breakers of the inoperable type have been functionally tested.

Perform CHANNEL CALIBRATION on the associated protective relays of the sampled

circuit breakers.

18 months (continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 4 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.8.a.2 -------------------NOTES------------------- 1. A representative sample shall consist of 10% of the circuit breakers selected, on a rotating basis, from

6.9 kV and 4.16 kV circuit breakers.

2. For each circuit breaker found inoperable during these functional tests, an additional representative sample of 10% of all circuit breakers of the inoperable type shall

be functionally tested until no more

failures are found or all circuit breakers of the inoperable type have been functionally tested.

Perform an integrated system functional

test on a representative sample of each

circuit breaker type, which includes simulated automatic actuation of the system to demonstrate that the overall penetration design remains within operable limits.

18 months (continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 5 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.8.a.3 -------------------NOTES------------------- 1. A representative sample shall consist of 10% of the circuit breakers selected, on a rotating basis, from

each type of 480 V circuit breakers.

2. Testing of these circuit breakers shall consist of injecting a current in excess of the breakers nominal setpoint and measuring the response time. The measured response time will be compared to the manufacturers data

to ensure that it is a value specified by the manufacturer.

3. Circuit breakers found inoperable during functional tests shall be

restored to OPERABLE or replaced with OPERABLE circuit breakers prior to

resuming operation.

4. For each circuit breaker found inoperable during these functional

tests, an additional representative sample of 10% of all circuit breakers of the inoperable type shall be functionally tested until no more failures are found or all circuit breakers of the inoperable type have been functionally tested.

Functionally test a representative sample of each 480 V circuit breaker type.

18 months

(continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 6 Revision 1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.8.a.4 -------------------NOTES------------------- 1. A representative sample shall consist of 10% of the fuses selected, on a rotating basis, from each type of

fuse.

2. Testing of these fuses shall consist of a nondestructive resistance measurement test which demonstrates that the fuse meets the manufacturer's design criteria.

3. Fuses found inoperable during functional tests shall be replaced with OPERABLE fuses prior to resuming operation.

4. For each fuse found inoperable during these functional tests, an additional representative sample of 10% of all fuses of the inoperable type shall be

functionally tested until no more failures are found or all fuses of the inoperable type have been functionally tested. -------------------------------------------

Functionally test a representative sample of each fuse type.

18 months

TSR 3.8.a.5 -------------------NOTE--------------------

Only applicable to 6.9 kV and 4.16 kV circuit breakers.

Perform an inspection and preventative maintenance for each breaker in accordance with the manufacturer's recommendation.

60 months

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 7 Revision 46 Technical Requirements Manual Table T3.8.a-1 (page 1 of 7) Containment Penetration Conductor Overcurrent Protective Devices (Unit 1)

PROTECTIVE DEVICE NUMBER AND LOCATION DEVICE 1. 6.9 kV Switchgear 1RC01PA - RCP A Bus 157 Cub 1

Bus 157 Normal (UAT) Feed ACB 1571 Bus 157 Emergency (SAT) Feed ACB 1572

1RC01PB - RCP B Bus 156 Cub 2

Bus 156 Normal (UAT) Feed ACB 1561 Bus 156 Emergency (SAT) Feed ACB 1562

1RC01PC - RCP C Bus 158 Cub 5

Bus 158 Normal (SAT) Feed ACB 1582 Bus 158 Emergency (UAT) Feed ACB 1581

1RC01PD - RCP D Bus 159 Cub 5

Bus 159 Normal (SAT) Feed ACB 1592 Bus 159 Emergency (UAT) Feed ACB 1591

Primary Backup Backup Primary Backup Backup Primary Backup Backup Primary Backup Backup

2. 480 V Pressurizer Heater Switchgear

1RY03EA - Pressurizer Heater Backup Group A, Compt. A1A-A6A, B1A

Compt. A1B-A6B, B1B

1RY03EB - Pressurizer Heater Backup Group B, Compt. B1A-B6A, A1A Compt. B1B-B6B, A1B

1RY03EC - Pressurizer Heater Backup Group C, Compt. A1A-A6A Compt. A1B-A6B 1RY03ED - Pressurizer Heater Backup Group D, Compt. B1A-B6A Compt. B1B-B6B

Primary Backup Primary Backup Primary Backup Primary Backup (continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 8 Revision 46 Technical Requirements Manual Table T3.8.a-1 (page 2 of 7) Containment Penetration Conductor Overcurrent Protective Devices (Unit 1)

PROTECTIVE DEVICE NUMBER AND LOCATION DEVICE 3. 480 V A.C. Switchgear Circuit Breakers

1VP01CA - RCFC Fan 1A

1A Low Speed Feed Breaker Switchgear 131X Cub 4C

1A Hi Speed Feed Breaker Switchgear 131X Cub 5C Bus 131X Normal Feed 141 Switchgear Cub 19 ACB 1415X 1VP01CC - RCFC Fan 1C 1C Low Speed Feed Breaker Switchgear 131X Cub 2C 1C Hi Speed Feed Breaker Switchgear 131X Cub 3C

Bus 131X Normal Feed 141 Switchgear Cub 19 ACB 1415X

1VP01CB - RCFC Fan 1B 1B Low Speed Feed Breaker Switchgear 132X Cub 4C 1B Hi Speed Feed Breaker Switchgear 132X Cub 5C Bus 132X Normal Feed 142 Switchgear Cub 14 ACB 1425X

1VP01CD - RCFC Fan 1D 1D Low Speed Feed Breaker Switchgear 132X Cub 2C 1D Hi Speed Feed Breaker Switchgear 132X Cub 3C

Bus 132X Normal Feed 142 Switchgear Cub 14 ACB 1425X

1EW39E - Containment Stinger Bus Rectifier Containment Stinger Bus 134Y Cub 2C Fuses in Bus 134Y Cub 2C

1AP200EA/ED Containment Outage Pwr Distr Panels - Unit 1 Circuit Breaker in Bus 233X Cub 2C Fuses in Bus 233X Cub 2C

1AP200EB/EC Containment Outage Pwr Distr Panels - Unit 1 Circuit Breakers in Bus 234X Cub 5D

Fuses in Bus 234X Cub 5D

Primary Primary Backup Primary Primary Backup Primary Primary Backup Primary Primary Backup Primary Backup Primary Backup Primary Backup (continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 9 Revision 46 Technical Requirements Manual Table T3.8.a-1 (page 3 of 7) Containment Penetration Conductor Overcurrent Protective Devices (Unit 1)

PROTECTIVE DEVICE NUMBER AND LOCATION DEVICE 4. 480 V Molded Case Circuit Breakers (MCCB)

1RC01PA-A - Cub B1 Front Cub B1 Rear

1RC01PA-B - Cub B2 Front Cub B2 Rear

1HC22G - Cub B3 Front Cub B3 Rear

1FH03G - Cub B4 Front Cub B4 Rear

1VP05CA - Cub C1 Front Cub C1 Rear 1RF03P - Cub C2 Front Cub C2 Rear 1RC01PD-A - Cub D1 Front Cub D1 Rear 1RC01PD-B - Cub D2 Front Cub D2 Rear 1RF02PB - Cub D4 Front Cub D4 Rear 1RF01P - Cub D5 Front Cub D5 Rear 1RE01PA - Cub D6 Front Cub D6 Rear

1VP02CA - Cub E1 Front Cub E1 Rear

1VP04CA - Cub E2 Front Cub E2 Rear

1VP04CC - Cub F1 Front Cub F1 Rear

1EW11EA,B,C - Cub F3 Front Cub F3 Rear

1IC02EA - Cub F5 Front Cub F5 Rear

1IC02EB - Cub G1 Front Cub G1 Rear

1IC02EC - Cub G2 Front Cub G2 Rear MCC 133X4 Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup (continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 10 Revision 46 Technical Requirements Manual Table T3.8.a-1 (page 4 of 7) Containment Penetration Conductor Overcurrent Protective Devices (Unit 1)

PROTECTIVE DEVICE NUMBER AND LOCATION DEVICE 5. 480 V Molded Case Circuit Breakers (MCCB)

1IC02EF - Cub A1 Front Cub A1 Rear

1IC02EE - Cub A2 Front Cub A2 Rear 1IC02ED - Cub A3 Front Cub A3 Rear 1FH02J - Cub G1 Front Cub G1 Rear 1FH03J - Cub G2 Front Cub G2 Rear 1RC01PB-B - Cub B1 Front Cub B1 Rear

1RE01PB - Cub B3 Front Cub B3 Rear

1RC01PC-A - Cub C1 Front Cub C1 Rear

1RC01PC-B - Cub C2 Front Cub C2 Rear

1VP05CB - Cub J1 Front Cub J1 Rear

1RC01PB-A - Cub C3 Front Cub C3 Rear

1HC65G-A - Cub D3 Front Cub D3 Rear

1VP02CB - Cub F1 Front Cub F1 Rear 1RC01R-A - Cub F2-A Cub F2-B 1RF02PA - Cub G3 Front Cub G3 Rear 1EW12EA,B,C - Cub F3-A Cub F3-B 1VP04CB - Cub F4 Front Cub F4 Rear

1VP04CD - Cub F5 Front Cub F5 Rear MCC 134X5

Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup (continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 11 Revision 46 Technical Requirements Manual Table T3.8.a-1 (page 5 of 7) Containment Penetration Conductor Overcurrent Protective Devices (Unit 1)

PROTECTIVE DEVICE NUMBER AND LOCATION DEVICE

6. 480 V Molded Case Circuit Breakers (MCCB)

1SI8808C - Cub A2 MCC 132X2 Cub B2 1SI8808B - Cub A3 MCC 132X2 Cub B2 MCC 132X2A Primary Backup Primary Backup

7. 480 V Molded Case Circuit Breakers (MCCB)

1RH8702B - Cub B1 Front Cub B1 Rear

1RH8701B - Cub B3 Front Cub B3 Rear

1CV8112 - Cub B4 Front Cub B4 Rear

1OG079 - Cub C1 Front Cub C1 Rear

1WO056A - Cub C2 Front Cub C2 Rear

1OG080- Cub C3 Front Cub C3 Rear

1RY8000B - Cub C4 Front Cub C4 Rear 1RC8003C - Cub D5 Front Cub D5 Rear 1RC8003B - Cub D4 Front Cub D4 Rear 1RC8002A - Cub G1 Front Cub G1 Rear 1RC8002B - Cub G2 Front Cub G2 Rear

1RC8002C - Cub G3 Front Cub G3 Rear

1RC8002D - Cub G4 Front Cub G4 Rear MCC 132X2 Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup (continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 12 Revision 46 Technical Requirements Manual Table T3.8.a-1 (page 6 of 7) Containment Penetration Conductor Overcurrent Protective Devices (Unit 1)

PROTECTIVE DEVICE NUMBER AND LOCATION DEVICE

8. 480 V Molded Case Circuit Breakers (MCCB)

1SI8808D - Cub A2 MCC 131X2 Cub B2 1SI8808A - Cub A3 MCC 131X2 Cub B2 MCC 131X2A Primary Backup Primary Backup

9. 480 V Molded Case Circuit Breakers (MCCB)

1RC8001A - Cub G1 Front Cub G1 Rear

1RC8001B - Cub G2 Front Cub G2 Rear

1RC8001C - Cub G3 Front Cub G3 Rear

1RC8001D - Cub G4 Front Cub G4 Rear

1RH8701A - Cub B1 Front Cub B1 Rear

1RH8702A - Cub B4 Front Cub B4 Rear

1LL42J - Cub C1 Front Cub C1 Rear 1VQ001A - Cub C3 Front Cub C3 Rear 1VQ002A - Cub F1 Front Cub F1 Rear 1RC8003D - Cub C4 Front Cub C4 Rear 1RC8003A - Cub C5 Front Cub C5 Rear

1OG057A - Cub D1 Front Cub D1 Rear

1CC9416 - Cub D3 Front Cub D3 Rear

1CC9438 - Cub D4 Front Cub D4 Rear

1OG081 - Cub E2 Front Cub E2 Rear MCC 131X2 Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup (continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 13 Revision 46 Technical Requirements Manual Table T3.8.a-1 (page 7 of 7) Containment Penetration Conductor Overcurrent Protective Devices (Unit 1)

PROTECTIVE DEVICE NUMBER AND LOCATION DEVICE

10. 480 V Molded Case Circuit Breakers (MCCB)

1HC01G - Cub B2 Cub B1 1LL04E - Cub C2 Cub C1

1VP03CA - Cub A3 Front Cub A3 Rear

1VP03CD - Cub C4 Front Cub C4 Rear MCC 133X6 Primary Backup Primary Backup Primary Backup Primary Backup

11. 480 V Molded Case Circuit Breakers (MCCB)

1LL05E - Cub B2 Cub B1

1VP03CB - Cub A3 Front Cub A3 Rear

1VP03CC - Cub B4 Front Cub B4 Rear

MCC 134X7 Primary Backup Primary Backup Primary Backup 12. 480 V Molded Case Circuit Breakers (MCCB)

1WO056B - Cub A4 Front Cub A4 Rear 1RY8000A - Cub A5 Front Cub A5 Rear

MCC 131X2B

Primary Backup Primary Backup

13. 260 VAC RCD Power (53 rods, 5 panels)

Stationary Gripper Coils fuse (all panels) Stationary Gripper Coils fuse (all panels)

Lift Coils fuse (all panels) Lift Coils fuse (all panels)

Movable Gripper Coils fuse (all panels) Movable Gripper Coils fuse (all panels)

Primary Backup Primary Backup Primary Backup TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 14 Revision 46 Technical Requirements Manual Table T3.8.a-2 (page 1 of 7) Containment Penetration Conductor Overcurrent Protective Devices (Unit 2)

PROTECTIVE DEVICE NUMBER AND LOCATION DEVICE 1. 6.9 kV Switchgear 2RC01PA - RCP A Bus 257 Cub 7 Bus 257 Normal (UAT) Feed ACB 2571 Bus 257 Emergency (SAT) Feed ACB 2572

2RC01PB - RCP B Bus 256 Cub 5 Bus 256 Normal (UAT) Feed ACB 2561 Bus 256 Emergency (SAT) Feed ACB 2562

2RC01PC - RCP C Bus 258 Cub 3

Bus 258 Normal (SAT) Feed ACB 2582 Bus 258 Emergency (UAT) Feed ACB 2581

2RC01PD - RCP D Bus 259 Cub 3

Bus 259 Normal (SAT) Feed ACB 2592 Bus 259 Emergency (UAT) Feed ACB 2591

Primary Backup Backup Primary Backup Backup Primary Backup Backup Primary Backup Backup 2. 480 V Pressurizer Heater Switchgear

2RY03EA - Pressurizer Heater Backup Group A, Compt. B1A-B6A, A1A

Compt. B1B-B6B, A1B 2RY03EB - Pressurizer Heater Backup Group B, Compt. A1A-A6A, B1A

Compt. A1B-A6B, B1B

2RY03EC - Pressurizer Heater Backup Group C, Compt. B1A-B6A

Compt. B1B-B6B

2RY03ED - Pressurizer Heater Backup Group D, Compt. A1A-A6A Compt. A1B-A6B

Primary Backup Primary Backup Primary Backup Primary Backup (continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 15 Revision 46 Technical Requirements Manual Table T3.8.a-2 (page 2 of 7) Containment Penetration Conductor Overcurrent Protective Devices (Unit 2)

PROTECTIVE DEVICE NUMBER AND LOCATION DEVICE 3. 480 V A.C. Switchgear Circuit Breakers

2VP01CA - RCFC Fan 2A 2A Low Speed Feed Breaker Switchgear 231X Cub 4C

2A Hi Speed Feed Breaker Switchgear 231X Cub 5C Bus 231X Normal Feed 241 Switchgear Cub 4 ACB 2415X

2VP01CC - RCFC Fan 2C 2C Low Speed Feed Breaker Switchgear 231X Cub 2C 2C Hi Speed Feed Breaker Switchgear 231X Cub 3C

Bus 231X Normal Feed 241 Switchgear Cub 4 ACB 2415X

2VP01CB - RCFC Fan 2B 2B Low Speed Feed Breaker Switchgear 232X Cub 4C 2B Hi Speed Feed Breaker Switchgear 232X Cub 5C Bus 232X Normal Feed 242 Switchgear Cub 8 ACB 2425X 2VP01CD - RCFC Fan 2D 2D Low Speed Feed Breaker Switchgear 232X Cub 2C 2D Hi Speed Feed Breaker Switchgear 232X Cub 3C

Bus 232X Normal Feed 242 Switchgear Cub 8 ACB 2425X

2EW39E - Containment Stinger Bus Rectifier Containment Stinger Bus 234Y Cub 2C Fuses in Bus 234Y Cub 2C

2AP200EA/ED Containment Outage Pwr Distr Panels - Unit 2 Circuit Breaker in Bus 133X Cub 2C Fuses in Bus 133X Cub 2C

2AP200EB/EC Containment Outage Pwr Distr Panels - Unit 2 Circuit Breaker in Bus 134X Cub 5D

Fuses in Bus 134X Cub 5D

Primary Primary Backup Primary Primary Backup Primary Primary Backup Primary Primary Backup Primary Backup Primary Backup Primary Backup (continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 16 Revision 46 Technical Requirements Manual Table T3.8.a-2 (page 3 of 7) Containment Penetration Conductor Overcurrent Protective Devices (Unit 2)

PROTECTIVE DEVICE NUMBER AND LOCATION DEVICE

4. 480 V Molded Case Circuit Breakers (MCCB)

2RC01PA-A - Cub B1 Front Cub B1 Rear

2RC01PA-B - Cub B2 Front Cub B2 Rear

2HC22G - Cub B3 Front Cub B3 Rear

2FH03G - Cub B4 Front Cub B4 Rear

2VP05CA - Cub C1 Front Cub C1 Rear

2RF03P - Cub C2 Front Cub C2 Rear

2RC01PD-A - Cub D1 Front Cub D1 Rear 2RC01PD-B - Cub D2 Front Cub D2 Rear 2RF02PB - Cub D4 Front Cub D4 Rear 2RF01P - Cub D5 Front Cub D5 Rear 2RE01PA - Cub D6 Front Cub D6 Rear

2VP02CA - Cub E1 Front Cub E1 Rear

2VP04CA - Cub E2 Front Cub E2 Rear

2VP04CC - Cub F1 Front Cub F1 Rear

2EW11EA,B,C - Cub F3 Front Cub F3 Rear

2IC02EA - Cub F5 Front Cub F5 Rear

2IC02EB - Cub G1 Front Cub G1 Rear

2IC02EC - Cub G2 Front Cub G2 Rear MCC 233X4 Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup (continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 17 Revision 46 Technical Requirements Manual Table T3.8.a-2 (page 4 of 7) Containment Penetration Conductor Overcurrent Protective Devices (Unit 2)

PROTECTIVE DEVICE NUMBER AND LOCATION DEVICE

5. 480 V Molded Case Circuit Breakers (MCCB)

2IC02EF - Cub A1 Front Cub A1 Rear

2IC02EE - Cub A2 Front Cub A2 Rear

2IC02ED - Cub A3 Front Cub A3 Rear

2FH02J - Cub G1 Front Cub G1 Rear

2FH03J - Cub G2 Front Cub G2 Rear

2RC01PB-B - Cub B1 Front Cub B1 Rear

2RE01PB - Cub B3 Front Cub B3 Rear 2RC01PC-A - Cub C1 Front Cub C1 Rear 2RC01PC-B - Cub C2 Front Cub C2 Rear 2VP05CB - Cub J1 Front Cub J1 Rear 2RC01PB-A - Cub C3 Front Cub C3 Rear

2HC65G-A - Cub D3 Front Cub D3 Rear

2VP02CB - Cub F1 Front Cub F1 Rear

2RC01R-A - Cub F2-A Cub F2-B

2RF02PA - Cub G3 Front Cub G3 Rear

2EW12EA,B,C - Cub F3-A Cub F3-B

2VP04CB - Cub F4 Front Cub F4 Rear

2VP04CD - Cub F5 Front Cub F5 Rear MCC 234X5 Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup (continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 18 Revision 46 Technical Requirements Manual Table T3.8.a-2 (page 5 of 7) Containment Penetration Conductor Overcurrent Protective Devices (Unit 2)

PROTECTIVE DEVICE NUMBER AND LOCATION DEVICE

6. 480 V Molded Case Circuit Breakers (MCCB)

2SI8808C - Cub A2 MCC 232X2 Cub B2

2SI8808B - Cub A3 MCC 232X2 Cub B2

MCC 232X2A Primary Backup Primary Backup

7. 480 V Molded Case Circuit Breakers (MCCB)

2RH8702B - Cub B1 Front Cub B1 Rear 2RH8701B - Cub B3 Front Cub B3 Rear 2CV8112 - Cub B4 Front Cub B4 Rear 2OG079 - Cub C1 Front Cub C1 Rear 2WO056A - Cub C2 Front Cub C2 Rear 2OG080 - Cub C3 Front Cub C3 Rear

2RY8000B - Cub C4 Front Cub C4 Rear

2RC8003C - Cub D5 Front Cub D5 Rear

2RC8003B - Cub D4 Front Cub D4 Rear

2RC8002A - Cub G1 Front Cub G1 Rear

2RC8002B - Cub G2 Front Cub G2 Rear

2RC8002C - Cub G3 Front Cub G3 Rear

2RC8002D - Cub G4 Front Cub G4 Rear MCC 232X2

Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup (continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 19 Revision 46 Technical Requirements Manual Table T3.8.a-2 (page 6 of 7) Containment Penetration Conductor Overcurrent Protective Devices (Unit 2)

PROTECTIVE DEVICE NUMBER AND LOCATION DEVICE

8. 480 V Molded Case Circuit Breakers (MCCB)

2SI8808D - Cub A2 MCC 231X2 Cub B2

2SI8808A - Cub A3 MCC 231X2 Cub B2

MCC 231X2A Primary Backup Primary Backup

9. 480 V Molded Case Circuit Breakers (MCCB)

2RC8001A - Cub G1 Front Cub G1 Rear 2RC8001B - Cub G2 Front Cub G2 Rear 2RC8001C - Cub G3 Front Cub G3 Rear 2RC8001D - Cub G4 Front Cub G4 Rear 2RH8701A - Cub B1 Front Cub B1 Rear 2RH8702A - Cub B4 Front Cub B4 Rear

2LL42J - Cub C1 Front Cub C1 Rear

2VQ001A - Cub C3 Front Cub C3 Rear

2VQ002A - Cub F1 Front Cub F1 Rear

2RC8003D - Cub C4 Front Cub C4 Rear

2RC8003A - Cub C5 Front Cub C5 Rear

2OG057A - Cub D1 Front Cub D1 Rear

2CC9416 - Cub D3 Front Cub D3 Rear 2CC9438 - Cub D4 Front Cub D4 Rear 2OG081 - Cub E2 Front Cub E2 Rear MCC 231X2

Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup Primary Backup (continued)

TRM Containment Penetration Conductor Overcurrent Protective Devices 3.8.a BRAIDWOOD - UNITS 1 & 2 3.8.a - 20 Revision 46 Technical Requirements Manual Table T3.8.a-2 (page 7 of 7) Containment Penetration Conductor Overcurrent Protective Devices (Unit 2)

PROTECTIVE DEVICE NUMBER AND LOCATION DEVICE

10. 480 V Molded Case Circuit Breakers (MCCB)

2HC01G - Cub B2 Cub B1

2LL04E - Cub C2 Cub C1

2VP03CA - Cub A3 Front Cub A3 Rear 2VP03CD - Cub C4 Front Cub C4 Rear MCC 233X6 Primary Backup Primary Backup Primary Backup Primary Backup 11. 480 V Molded Case Circuit Breakers (MCCB)

2LL05E - Cub B2 Cub B1 2VP03CB - Cub A3 Front Cub A3 Rear 2VP03CC - Cub B4 Front Cub B4 Rear MCC 234X7

Primary Backup Primary Backup Primary Backup

12. 480 V Molded Case Circuit Breakers (MCCB) 2WO056B - Cub A4 Front Cub A4 Rear 2RY8000A - Cub A5 Front Cub A5 Rear MCC 231X2B

Primary Backup Primary Backup

13. 260 VAC RCD Power (53 rods, 5 panels)

Stationary Gripper Coils fuse (all panels) Stationary Gripper Coils fuse (all panels)

Lift Coils fuse (all panels) Lift Coils fuse (all panels)

Movable Gripper Coils fuse (all panels) Movable Gripper Coils fuse (all panels)

Primary Backup Primary Backup Primary Backup TRM Motor Operated Valves Thermal Overload Protection Devices 3.8.bBRAIDWOOD -UNITS 1 & 23.8.b -1Revision1 Technical Requirements Manual 3.8 ELECTRICAL POWER SYSTEMS 3.8.b Motor Operated Valves Thermal Overload Protection DevicesTLCO 3.8.bThe thermal overload protection devices integral with the motor starter of each valve listed in TableT3.8.b-1 for Unit1 (TableT3.8.b-2 for Unit2) shall be OPERABLE.APPLICABILITY:Whenever the motor operated valve is required to be OPERABLE.ACTIONS-------------------------------------NOTE-------------------------------------

Separate Condition entry is allowed for each thermal overload protection device.

CONDITIONREQUIRED ACTIONCOMPLETION TIMEA.Oneor more thermal overload protection

devices inoperable.A.1Declare the affected valve inoperable.

ANDA.2Enter the applicable Conditions and

Required Actions for the affected valve.

Immediately Immediately TRM Motor Operated Valves Thermal Overload Protection Devices 3.8.bBRAIDWOOD -UNITS 1 & 23.8.b -2Revision1 Technical Requirements Manual SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------TSR3.8.b.1 applies to each thermal overload protection device in TableT3.8.b-1 (TableT3.8.b-2).

SURVEILLANCEFREQUENCYTSR 3.8.b.1-------------------NOTES-------------------

A representative sample shall consist of

!25% of all thermal overload protection devices such that:1.Each device is calibrated at least once per 6years, and2.Each thermal overload is calibrated and each valve is cycled through at least one complete cycle of full

travel with the motor operator when

the thermal overload is OPERABLE at least once per 6years.

Perform CHANNEL CALIBRATION of a representative sample of thermal overload devices.18months TRM Motor Operated Valves Thermal Overload Protection Devices 3.8.bBRAIDWOOD -UNITS 1 & 23.8.b -3Revision88 Technical Requirements ManualTableT3.8.b-1 (page1 of3)Thermal Overload Protection Devices -Unit1VALVE NUMBERFUNCTION 1OG057A OA H 2 Recombiner Discharge Isolation Valve1OG079H 2 Recombiner Discharge Containment Isolation Valve1OG080H 2 Recombiner Suction Containment Isolation Valve1OG081H 2 Recombiner Suction Containment Isolation Valve1OG082OA H 2 Recombiner Discharge Containment Isolation Valve1OG083OA H 2 Recombiner Discharge Containment Isolation Valve1OG084OA H 2 Recombiner Containment Outlet Isolation Valve1OG085H 2 Recombiner Containment Outlet Isolation Valve1AF006A1A AF Pump SX Suction Isolation Valve1AF006B1B AF Pump SX Suction Downstream Isolation Valve1AF013AAF Motor Driven Pump Discharge Header Downstream Isolation Valve1AF013BAF Motor Driven Pump Discharge Header Downstream Isolation Valve 1AF013CAF Motor Driven Pump Discharge Header Downstream Isolation Valve 1AF013DAF Motor Driven Pump Discharge Header Downstream Isolation Valve 1AF013EAF Diesel Driven Pump Discharge Header Downstream Isolation Valve 1AF013FAF Diesel Driven Pump Discharge Header Downstream Isolation Valve 1AF013GAF Diesel Driven Pump Discharge Header Downstream Isolation Valve1AF013HAF Diesel Driven Pump Discharge Header Downstream Isolation Valve1AF017A1A AF Pump SX Suction Upstream Isolation Valve 1AF017B1B AF Pump SX Suction Upstream Isolation Valve1CC201A1A SX to CC Makeup Isolation Valve 1CC201B 1B SX to CC Makeup Isolation Valve 1CC202A 1A SX to CC Makeup Isolation Valve 1CC202B 1B SX to CC Makeup Isolation Valve 1CC685 RCP Thermal Barrier Outlet Header Containment Isolation Valve 1CC9412A CC to RHR HX 1A Isolation Valve 1CC9412B CC to RHR HX 1B Isolation Valve 1CC9413A RCPs CC Supply Downstream Containment Isolation Valve 1CC9413B RCPs CC Supply Upstream Containment Isolation Valve 1CC9414 CC Water from RCPs Isolation Valve 1CC9415 Service Loop Isolation Valve 1CC9416 CC Water from RCPs Isolation Valve 1CC9438 CC Water from RCPs Thermal Barrier Isolation Valve 1CC9473ADischarge Header X-tie Isolation Valve 1CC9473BDischarge Header X-tie Isolation Valve 1CS001A 1A CS Pump Suction from RWST 1CS001B 1B CS Pump Suction from RWST 1CS007A 1A CS Pump Discharge Line Downstream Isolation Valve 1CS007B 1B CS Pump Discharge Line Downstream Isolation Valve 1CS009A 1A CS Pump Suction from 1A Recirc Sump 1CS009B1B CS PumpSuction from 1B Recirc Sump 1CS019A CS Eductor 1A Suction Conn Isolation Valve 1CS019B CS Eductor 1B Suction Conn Isolation Valve (continued)

TRM Motor Operated Valves Thermal Overload Protection Devices 3.8.bBRAIDWOOD -UNITS 1 & 23.8.b -4Revision1 Technical Requirements ManualTableT3.8.b-1 (page2 of3)Thermal Overload Protection Devices -Unit1VALVE NUMBERFUNCTION 1CV112B MOV VCT Outlet Upstream Isolation VCT Valve 1CV112C MOV VCT Outlet Downstream Isolation VCT Valve 1CV112D MOV RWST to Charging Pump Suction Header 1CV112E MOV RWST to Charging Pump Suction Header 1CV8100 MOV RCP Seal Leakoff Header Isolation 1CV8104 MOV Emergency Boration Valve 1CV8105 MOV Charging Pumps Discharge Header Isolation Valve 1CV8106 MOV Charging Pumps Discharge Header Isolation Valve 1CV8110 MOV A & B Charging Pump Recirc Downstream Isolation 1CV8111 MOV A & B Charging Pump Recirc Upstream Isolation 1CV8112 RCP Seal Water Return Isolation Valve 1CV8355A MOV RCP 1A Seal Injection Inlet to Containment Isolation 1CV8355B MOV RCP 1B Seal Injection Inlet Isolation 1CV8355C MOV RCP 1C Seal Injection Isolation 1CV8355D MOV RCP 1D Seal Injection Isolation 1CV8804A MOV RHR System X-Tie Valve to Charging Pump Suction Header A/B 1RH610 1A RHR Pump Recirc Line Isolation Valve 1RH611 1B RHR Pump Recirc Line Isolation Valve 1RH8701A RC Loop 1A to RHR Pump Isolation Valve 1RH8702A RC Loop 1C to RHR Pump Isolation Valve 1RH8701B RC Loop 1A to RHR Pump Isolation Valve 1RH8702B RC Loop 1C to RHR Pump Isolation Valve 1RH8716A RHR HX 1RH02AA Downstream Isolation Valve 1RH8716B RHR HX 1RH02AB Downstream Isolation Valve 1RY8000APressurizer Relief Isolation Valve1A 1RY8000B Pressurizer Relief Isolation Valve 1B 1SI8801A SI Charging Pump Discharge Isolation Valve 1SI8801B SI Charging Pump Discharge Isolation Valve 1SI8802A 1A SI Pump Discharge Line Downstream Containment Isolation Valve 1SI8802B 1B SI Pump Discharge Line Downstream Isolation Valve 1SI8804B 1B SI Pump Suction X-tie from RHR HX 1SI8806 SI Pumps Upstream Suction Isolation Valve 1SI8807ASI to Charging Pump Suction X-tie Isolation Valve 1SI8807BSI to Charging Pump Suction X-tie Isolation Valve 1SI8808A Accumulator 1A Discharge Isolation Valve 1SI8808B Accumulator 1B Discharge Isolation Valve 1SI8808C Accumulator 1C Discharge Isolation Valve 1SI8808D Accumulator 1D Discharge Isolation Valve 1SI8809A SI RHR HX 1A Discharge Line Downstream Isolation Valve 1SI8809B SI RHR HX 1B Discharge Line Downstream Isolation Valve 1SI8811A SI Containment Sump A Outlet Isolation Valve 1SI8811B SI Containment Sump B Outlet Isolation Valve 1SI8812A SI RWST to RH Pump 1A Outlet Isolation Valve 1SI8812BSI RWST to RH Pump 1B Outlet Isolation Valve 1SI8813 SI Pumps 1A-1B Recirc Line Downstream Isolation Valve 1SI8814 SI Pump 1A Recirc Line Isolation Valve 1SI8835 SI Pumps X-tie Discharge Isolation Valve 1SI8840 SI RHR HX Discharge Line Upstream Containment Penetration Isolation Valve 1SI8821A 1A SI Pump Discharge Line X-tie Isolation Valve 1SI8821B 1B SI Pump Discharge Line X-tie Isolation Valve 1SI8920 1B SI Pump Recirc Line Isolation Valve 1SI8923A 1A SI Pump Suction Isolation Valve 1SI8923B 1B SI Pump Suction Isolation Valve 1SI8924 1A SI Pump Suction X-tie Downstream Isolation Valve (continued)

TRM Motor Operated Valves Thermal Overload Protection Devices 3.8.bBRAIDWOOD -UNITS 1 & 23.8.b -5Revision76 Technical Requirements ManualTableT3.8.b-1 (page3 of3)Thermal Overload Protection Devices -Unit1VALVE NUMBERFUNCTION 1SX016B RCFC B&D SX Supply MOV 1SX016A RCFC A&C SX Supply MOV 1SX027ARCFCA&C SX Return MOV 1SX027B RCFC B&D SX Return MOV 0SX007 CC HX Outlet Valve 0SX063A SX to Control Room Refrig Condenser OA 0SX063B SX to Control Room Refrig Condenser OB 0SX146 CC HX "O" Outlet Valve 0SX147 CC HX "O" Outlet Valve 1SX001A 1A SX Pump Suction Valve MOV 1SX001B 1B SX Pump Suction Valve MOV 1SX004Unit1 SX Supply to Unit1 CCW HX MOV 1SX005 1B SX Pump Supply to CCW HX "O" MOV 1SX007 CC HX Outlet Valve 1SX010Unit1 TrainA Return Valve AB 1SX011TrainA TrainB Unit1 Return X-tie Valve AB 1SX033 1A SX Pump Discharge X-tie MOV 1SX034 1B SX Pump Discharge X-tie MOV 1SX136Unit1 TrainB Return Valve AB 1SX150A SX Strainer 1A Backwash to Waste Treatment Building MOV 1SX150B SX Strainer 1B Backwash to Waste Treatment Building MOV 1W0006AChilledWater Coils 1A & 1C Supply Isolation Valve 1W0006B Chilled Water Coils 1B & 1D Supply Isolation Valve 1W0020A Chilled Water Coils 1A & 1C Return Isolation Valve 1W0020B Chilled Water Coils 1B & 1D Return Isolation Valve 1W0056A Chilled Water Containment Isolation Valve 1W0056B Chilled Water Containment Isolation Valve TRM Motor Operated Valves Thermal Overload Protection Devices 3.8.bBRAIDWOOD -UNITS 1 & 23.8.b -6Revision88 Technical Requirements ManualTableT3.8.b-2 (page1 of3)Thermal Overload Protection Devices -Unit2VALVE NUMBERFUNCTION 2OG057A OB H 2 Recombiner Discharge Isolation Valve2OG079H 2Recombiner Discharge Containment Isolation Valve2OG080H 2 Recombiner Suction Containment Isolation Valve2OG081H 2 Recombiner Suction Containment Isolation Valve2OG082OB H 2 Recombiner Discharge Containment Isolation Valve2OG083OB H 2 Recombiner Discharge Containment Isolation Valve2OG084OB H 2 Recombiner Containment Outlet Isolation Valve2OG085H 2 Recombiner Containment Outlet Isolation Valve2AF006A2A AF Pump SX Suction Isolation Valve2AF006B2B AF Pump SX Suction Downstream Isolation Valve 2AF013AAF Motor Driven PumpDischarge Header Downstream Isolation Valve 2AF013BAF Motor Driven Pump Discharge Header Downstream Isolation Valve 2AF013CAF Motor Driven Pump Discharge Header Downstream Isolation Valve 2AF013DAF Motor Driven Pump Discharge Header Downstream Isolation Valve 2AF013EAF Diesel Driven Pump Discharge Header Downstream Isolation Valve2AF013FAF Diesel Driven Pump Discharge Header Downstream Isolation Valve2AF013GAF Diesel Driven Pump Discharge Header Downstream Isolation Valve 2AF013HAF Diesel Driven Pump Discharge Header Downstream Isolation Valve 2AF017A2A AF Pump SX Suction Upstream Isolation Valve 2AF017B2B AF Pump SX Suction Upstream Isolation Valve2CC201A2A SX to CC Makeup Isolation Valve 2CC201B 2B SX to CC Makeup Isolation Valve 2CC202A 2A SX to CC Makeup Isolation Valve 2CC202B 2B SX to CC Makeup Isolation Valve 2CC685 RCP Thermal Barrier Outlet Header Containment Isolation Valve 2CC9412A CC to RHR HX 2A Isolation Valve 2CC9412B CC to RHR HX 2B Isolation Valve 2CC9413A RCP CC Supply Downstream Containment Isolation 2CC9413B RCPs CC Supply Upstream Containment Isolation 2CC9414 CC Water from RCPs Isolation Valve 2CC9415 Service Loop Isolation Valve 2CC9416 CC Water from RCPs Isolation Valve 2CC9438CC Water from RCPs Thermal Barrier IsolationValve 2CC9473ADischarge Header X-tie Isolation Valve 2CC9473BDischarge Header X-tie Isolation Valve 2CS001A 2A CS Pump Suction from RWST 2CS001B 2B CS Pump Suction from RWST 2CS007A 2A CS Pump Discharge Line Downstream Isolation Valve 2CS007B 2B CS Pump Discharge Line Downstream Isolation Valve 2CS009A 2A CS Pump Suction from 2A Recirc Sump 2CS009B 2B CS Pump Suction from 2B Recirc Sump 2CS019A CS Eductor 2A Suction Conn Isolation Valve 2CS019B CS Eductor 2B Suction Conn Isolation Valve (continued)

TRM Motor Operated Valves Thermal Overload Protection Devices 3.8.bBRAIDWOOD -UNITS 1 & 23.8.b -7Revision1 Technical Requirements ManualTableT3.8.b-2 (page2 of3)Thermal Overload Protection Devices -Unit2VALVE NUMBERFUNCTION 2CV112B MOV VCT Outlet Upstream Isolation VCT Valve 2CV112C MOV VCT Outlet Downstream Isolation VCT Valve 2CV112D MOV RWST to Charging Pump Suction Header 2CV112E MOV RWST to Charging Pump Suction Header 2CV8100 MOV RCP Seal Leakoff Header Isolation 2CV8104 MOV Emergency Boration Valve 2CV8105 MOV Charging Pumps Discharge Header Isolation Valve 2CV8106 MOV Charging Pumps Discharge Header Isolation Valve 2CV8110 MOV A & B Charging Pump Recirc Downstream Isolation 2CV8111 MOV A & B Charging Pump Recirc Upstream Isolation 2CV8112 RCP Seal Water Return Isolation Valve 2CV8355A MOV RCP 2A Seal Injection Inlet to Containment Isolation 2CV8355BMOV RCP 2B SealInjection Inlet Isolation 2CV8355C MOV RCP 2C Seal Injection Isolation 2CV8355D MOV RCP 2D Seal Injection Isolation 2CV8804A MOV RHR System X-Tie Valve to Charging Pump Suction Header A/B 2RH610 2A RHR Pump Recirc Line Isolation Valve 2RH611 2B RHR Pump Recirc Line Isolation Valve 2RH8701A RC Loop 2A to RHR Pump Isolation Valve 2RH8702A RC Loop 2C to RHR Pump Isolation Valve 2RH8701B RC Loop 2A to RHR Pump Isolation Valve 2RH8702B RC Loop 2C to RHR Pump Isolation Valve 2RH8716A RHR HX 2RH02AA Downstream Isolation Valve 2RH8716B RHR HX 2RH02AB Downstream Isolation Valve 2RY8000A Pressurizer Relief Isolation Valve 2A 2RY8000B Pressurizer Relief Isolation Valve 2B 2SI8801A SI Charging Pump Discharge Isolation Valve 2SI8801B SI Charging Pump Discharge Isolation Valve 2SI8802A 2A SI Pump Discharge Line Downstream Containment Isolation Valve 2SI8802B 2B SI Pump Discharge Line Downstream Isolation Valve 2SI8804B 2B SI Pump Suction X-tie from RHR HX 2SI8806 SI Pumps Upstream Suction Isolation Valve 2SI8807ASI to Charging Pump Suction X-tie Isolation Valve 2SI8807BSI to Charging Pump Suction X-tie Isolation Valve 2SI8808A Accumulator 2A Discharge Isolation Valve 2SI8808B Accumulator 2B Discharge Isolation Valve 2SI8808C Accumulator 2C Discharge Isolation Valve 2SI8808D Accumulator 2D Discharge Isolation Valve 2SI8809A SI RHR HX 2A Discharge Line Downstream Isolation Valve 2SI8809B SI RHR HX 2B Discharge Line Downstream Isolation Valve 2SI8811A SI Containment Sump A Outlet Isolation Valve 2SI8811B SI Containment Sump B Outlet Isolation Valve 2SI8812A SI RWST to RHR Pump 2A Outlet Isolation Valve 2SI8812B SI RWST to RHR Pump 2B Outlet Isolation Valve 2SI8813 SI Pumps 2A-2B Recirc Line Downstream Isolation Valve 2SI8814 SI Pump 2A Recirc Line Isolation Valve 2SI8835SIPumps X-tie Discharge Isolation Valve 2SI8840 SI RHR HX Discharge Line Upstream Containment Penetration Isolation Valve 2SI8821A 2A SI Pump Discharge Line X-tie Isolation Valve 2SI8821B 2B SI Pump Discharge Line X-tie Isolation Valve 2SI8920 2B SI Pump Recirc Line Isolation Valve 2SI8923A 2A SI Pump Suction Isolation Valve 2SI8923B 2B SI Pump Suction Isolation Valve 2SI8924 2A SI Pump Suction X-tie Downstream Isolation Valve (continued)

TRM Motor Operated Valves Thermal Overload Protection Devices 3.8.bBRAIDWOOD -UNITS 1 & 23.8.b -8Revision85 Technical Requirements ManualTableT3.8.b-2 (page3 of3)Thermal Overload Protection Devices -Unit2VALVE NUMBERFUNCTION 2SX016B RCFC B&D SX Supply MOV 2SX016A RCFC A&C SX Supply MOV 2SX027A RCFC A&C SX Return MOV 2SX027B RCFC B&D SX Return MOV 0SX007 CC HX Outlet Valve 0SX063A SX to Control Room Refrig Condenser 0A 0SX063B SX to Control Room Refrig Condenser 0B 0SX146 CC HX "0" Outlet Valve 0SX147 CC HX "0" Outlet Valve 2SX001A 2A SX Pump Suction Valve MOV 2SX001B 2B SX Pump Suction Valve MOV 2SX004Unit2 SX Supply to Unit2 CCW HX MOV 2SX005 2B SX Pump Supply to CCW HX "O" MOV 2SX007 CC HX Outlet Valve 2SX010Unit2 TrainA Return Valve AB 2SX011TrainA TrainB Unit2 Return X-tie Valve AB 2SX033 2A SX Pump Discharge X-tie MOV 2SX034 2B SX Pump Discharge X-tie MOV 2SX136Unit2 TrainB Return Valve AB 2SX150ASX Strainer 2A Backwashto Waste Treatment Building MOV 2SX150B SX Strainer 2B Backwash to Waste Treatment Building MOV 2W0006A Chilled Water Coils 2A & 2C Supply Isolation Valve 2W0006B Chilled Water Coils 2B & 2D Supply Isolation Valve 2W0020A Chilled Water Coils 2A & 2C Return Isolation Valve 2W0020B Chilled Water Coils 2B & 2D Return Isolation Valve 2W0056A Chilled Water Containment Isolation Valve 2W0056B Chilled Water Containment Isolation Valve TRM Battery Monitoring and Maintenance 3.8.c BRAIDWOOD - UNITS 1 & 2 3.8.c - 1 Revision 26 Technical Requirements Manual 3.8 ELECTRICAL POWER SYSTEMS 3.8.c Battery Monitoring and Maintenance

TLCO 3.8.c Battery cell parameters for Division 11(21) and Division 12(22) batteries shall be within limits of Table T3.8.c-1.

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 battery with one or more battery cell

parameters not within Category A or B limits.

A.1 Verify pilot cell electrolyte level and

float voltage meet Table T3.8.c-1 Category C limits.

AND A.2 Verify battery cell parameters meet Table

T3.8.c-1 Category C limits. AND A.3 Restore battery cell parameters to

Category A and B

limits of Table T3.8.c-1.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 24 hours AND Once per 7 days

thereafter 31 days (continued)

TRM Battery Monitoring and Maintenance 3.8.c BRAIDWOOD - UNITS 1 & 2 3.8.c - 2 Revision 26 Technical Requirements Manual ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. ---------NOTE--------- Required Actions B.1 and B.2 must be

completed after LCO 3.8.6, "Battery Parameters," Required Action C.3 is

completed. ----------------------

One battery with one or more cells with

electrolyte level less than the minimum

established design limit. B.1 Conduct an equalizing charge of the

affected battery cell(s).

AND B.2 Verify successful completion of

appropriate testing for the affected cell(s).

31 days 31 days

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

TSR 3.8.c.1 Verify battery cell parameters meet Table T3.8.c-1 Category A limits.

7 days (continued)

TRM Battery Monitoring and Maintenance 3.8.c BRAIDWOOD - UNITS 1 & 2 3.8.c - 3 Revision 63 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.8.c.2 Verify battery cell parameters meet Table T3.8.c-1 Category B limits.

92 days AND Once within 7 days after a battery discharge

< 110 V AND Once within 7 days after a

battery overcharge

> 145 V TSR 3.8.c.3 Verify no visible corrosion at battery terminals and connectors.

OR Verify battery connection resistance is 150 micro-ohms for inter-cell connections, 150 micro-ohms for inter-rack connections, 150 micro-ohms for inter-tier connections, and 150 micro-ohms for terminal connections.

AND Verify total battery connection resistance is < 3245 micro-ohms.

92 days TSR 3.8.c.4 Verify battery cells, cell plates, and racks show no visual indication of physical

damage or abnormal deterioration that could degrade battery performance.

18 months (continued)

TRM Battery Monitoring and Maintenance 3.8.c BRAIDWOOD - UNITS 1 & 2 3.8.c - 4 Revision 63 Technical Requirements Manual SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.8.c.5 Remove visible terminal corrosion, verify battery cell to cell and terminal

connections are clean and tight, and are coated with anti-corrosion material.

18 months

TSR 3.8.c.6 Verify battery connection resistance is 150 micro-ohms for inter-cell connections, 150 micro-ohms for inter-rack connections, 150 micro-ohms for inter-tier connections, and 150 micro-ohms for terminal connections.

AND Verify total battery connection resistance is < 3245 micro-ohms.

18 months TRM Battery Monitoring and Maintenance 3.8.c BRAIDWOOD - UNITS 1 & 2 3.8.c-5 Revision 26 Technical Requirements Manual Table T3.8.c-1 (page 1 of 1) Battery Cell Parameters Requirements

PARAMETER CATEGORY A: LIMITS FOR EACH DESIGNATED PILOT CELL CATEGORY B: LIMITS FOR EACH CONNECTED CELL CATEGORY C: ALLOWABLE LIMITS FOR EACH CONNECTED CELL

Electrolyte Level

Minimum level indication mark, and 1/4 inch above maximum level indication mark (a) Minimum level indication mark, and 1/4 inch above maximum level indication mark (a) Above top of plates, and not overflowing Float Voltage

2.13 V 2.13 V (b) > 2.07 V Specific Gravity(c)(d) 1.200 1.195 AND Average of all connected cells > 1.205

Not more than 0.020 below average of all connected cells AND Average of all connected cells 1.195 (a) It is acceptable for the electrolyte level to temporarily increase above the specified maximum during equalizing charges provided it is not overflowing. (b) Corrected for average electrolyte temperature.

(c) Corrected for electrolyte temperature. (d) A battery charging current of < 3 amps when on float charge is acceptable for meeting specific gravity limits following a battery recharge, for a maximum of 7 days. When charging current is used to satisfy specific gravity requirements, specific gravity of each connected cell shall be measured prior to expiration of the 7 day allowance.

TRM Decay Time 3.9.aBRAIDWOOD -UNITS 1 & 23.9.a -1Revision89 Technical Requirements Manual 3.9 REFUELING OPERATIONS 3.9.a Decay TimeTLCO 3.9.aThe reactor shall be subcritical for

!113hours OR The reactor shall be subcritical for 65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months ANDthe core offload shall be within the limits of the appropriate figure (Figure 3.9.a-1 through 3.9.a-9, as applicable).APPLICABILITY:During movement of irradiated fuel in the reactor vessel.

ACTIONSCONDITIONREQUIRED ACTIONCOMPLETION TIMEA.Reactor subcritical for 65hours.OR Reactor subcritical for < 113hours AND the core offload not within the limits of the appropriate figure (Figure 3.9.a-1 through 3.9.a-9, as applicable).A.1Suspend movement of irradiated fuel in the reactor vessel.

Immediately TRM Decay Time 3.9.aBRAIDWOOD -UNITS 1 & 23.9.a -2Revision89 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCEFREQUENCYTSR3.9.a.1-------------------NOTE--------------------

Not required to be performed once Acceptable Region II in Figure 3.9.a-1 through 3.9.a-9 is entered.

Verify the reactor subcritical

!113hours by confirming the date and time of subcriticality.

OR Verify the reactor subcritical 65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months by confirming the date and time of subcriticality ANDverify the core offload remains within the limits of the appropriate figure (Figure 3.9.a-1 through 3.9.a-9, as applicable) determined by TSR 3.9.a.2 during movement of irradiated fuel.

Prior to initial movement of

irradiated fuel in the reactor vessel each

outageTSR 3.9.a.2-------------------NOTE--------------------

Only required to be performed if cycle-specific Spent Fuel Pool (SFP) Heat Load Margin figures are used in TSR 3.9.a.1.

Determine the SFP Heat Load Margin for the specific cycle for use in TSR 3.9.a.1.

Round the margin down to the next MBTU/hr value to determine the applicable SFP Heat Load Margin Figure (Figure 3.9.a-1 through 3.9.a-9).Prior to initial movement of irradiated fuel in the reactor

vessel each

outage.

TRM Decay Time 3.9.aBRAIDWOOD -UNITS 1 & 23.9.a -3Revision89 Technical Requirements Manual 0 20 40 60 80 100 120 140 160 180 200405060708090100110120130140Total Number of Assys OffloadedTime After Shutdown (Hrs) 41 MBTU/hr SFP Heat Load Margin ICDT Unacceptable Region Acceptable Region I Acceptable Region IIFigure 3.9.a-1, "41 MBTU/hr SFP Heat LoadMargin"

"'C Cl) "'C ns 0 E 0 U) U) U) <C .... 0 I.. (I) .c E ::s z -ftJ ..., 0 I-200 180 160 140 120 100 80 60 40 20 42 MBTU/hr SFP Heat Load Margin TRM Decay Time 3.9.a I i I : . : !

__ _.__ . ----*--_,___ ,____ -----i i ! ,----*------*.-:---------=..:........,....,.-r

' ' . . /, ' -------l ---+--, ---;-----__ , ___ Unacceptable

_ .... ,,....---.....

1 i ! / : -' Region .._:..-..... ; 1 i *----......

-->----i : * ----J l--1---*--<------*--___ _J___ 1 : ---. r--*--**** I _, ----.... --'-----: -,--*-----e-

*------

.---* i i ! ; * : -... ,.....

.. **<-*****--** *-*** I I ! i : I ' i . . **---. ---,__ ,_____ *---' I i ' _ .... _ .... ___ .._. __ ,__ ___ Acceptable

__ ,__ * ':/, 1 * : Re!i I , , . i * . -*-,____ t-->-... ...i----* -! I . : i : ! ' i , '

-, __ *-*---*-*-*---Ii' ---*--*-*---*----*---/i : [ Acceptable

* ------* *------*---*---*-----*--1 1 i ,

Region II --*---******* .... *-*-** *-**** ....... -**-*** . . .. 1-----**-* --. -***** . **-***** ***----------I.. : I ----:---+* . : . -! ! i I -,__ --*--* ---____ ,. ____ ,__ -I------**--*-**--

-----**----! I i -*-' ' : i : ! --*----'--*-* -*-------:-----, i l : ! I l J i ; ' ' ' : ------i-... _.___ I *-_.___ ---------I ' , i 0 40 -,_ --------i ---+ ------i I . I ' ' ' ' : I I 50 60 70 80 90 100 110 120 130 140 Time After Shutdown (Hrs) Figure 3.9.a-2, "42 MBTU/hr SFP Heat Load Margin" BRAIDWOOD

-UNITS 1 & 2 Technical Requirements Manual 3.9.a -4 Revision 89

'"O CD '"O ns 0 "' "' ... 0 .... CD .c E 200 180 160 140 120 100 43 MBTU/hr SFP Heat Load Margin I *---*-**-*--***---* I **** *---i -*-* , ... ,__ __. l..-----..-r-----I -, ...*.. Unacceptable J i I !!Ii -r---*--*--r--C--* I f j , J *--* . ----.-. **--,_ .... _ **----* ---* *--, ___ *--***----* **--------* -----*--!*-*-*** ---* i i -*----***-* *---*-Acceptable

-.... --. .... --I* ,_ -----* -Region I ! ! \ --,__. .. ;-,_,_ -I*** ----!---*----,_ --.... ,. ' .. -* i i -----------' i ' : : : ! i -' ,,j ' I :::J z 80 60 40 20 -1*-*--, __ *-/ ! : :-*--t """

Ci ... -, .. -*--.. .........

0 i i 40 50 BRAIDWOOD

-UNITS l & 2 Technical Requirements Manual -* -* ---*----*---I *----' , __ *--J i , i J **'--1-f-*--,---* -"-*--! *---* -60 70 80 90 100 Time After Shutdown (Hrs) Figure 3.9.a-3, "43 MBTU/hr SFP Heat Load Margin" 3.9.a -5 ' i i i ! i : J J :/ l /: , : : i i ' TRM Decay Time 3.9.a .-J-i : -*7 l : I ' ' ' : ' ,,j ' I i I i : ' ' ! ! :; ' i ' /: i ,/ ' I I ! I ... I ! ' r i i : l ; ' i ' ! ! t I ! i .... Acceptable

! Region II ! i : ' ' : l -

' -i ! ' i i l : i I 110 120 130 Revision 89 "C Cl) ,, cu 0 E 0 tn >. tn .... 0 s.. Cl) .Q E 200 180 160 140 120 100 44 MBTU/hr SFP Heat Load Margin i ' I _,_ ,, ;, ' ---------------...... --_ __. --**-,,_,, ____ ------------------*-.r I -----------_ Unacceptable

!Qi f I ,_, " ----**-, ------------p-.. ---* , ____ : i -,, _____ ' -------------1----------' i ! ____ ,_ _, -----------------*--*----' --------Acceptable

__ ,.,,., *Y I ---------"'" ,_,,, -'" --------------------______ , ____ -,,, ____ , *--i ! -------r-'

! : ' . i -------' l i i ; j i i : ' i i l j ! l '

-! ! ! i ' J-,. -!f ' I ' ),' TRM Deca y Time 3.9.a -! /: : ! I ' : ----i ' I I ' f : i ' 'I ' ./. ! ! : / ! i I; : ' ' ; ' ; ' I i ! ' --I. I i ! I Acceptable z ca 80 60 40 20 " ----, _____ ---' -----: ! I ' II ----, __ ' ----i ! ...... - ' ' 1---0 40 BRAIDWOOD

-UNITS 1 & 2 Technical Requirements Manual 50 , , ----i /i -*>-* ***-*-------! ' ' ' 60 70 80 90 Time After Shutdown (Hrs) Figure 3.9.a-4, "44 MBTU/hr SFP Heat Load M argin" 3.9.a -6 ' ' i : i ' ' ' ' t I i ' i ' ; ; ; ' ' I 100 110 120 Revision 89

"'C (I.) "'C C'G 0 E 0 en en en <( ..... 0 .... (I.) .c E = z Ci ....., 45 MBTU/hr SFP Heat Load Margin 200 180 -1*.0*o**,******

<>M*'**'o*o**.***

I* 160 -140 -120 _, --100 -,_ 80 ------40 _, 20 -0 40 ------------------------------------------------------------------, ______ --------_, ________ ---------------!---! --...-..........,...-

i ----------------...---i --,,,.,,.,,.

--,__ __ -------------------------------l ----.,,... *****'-******-**--, ___ J .* .*****************

i------Unacceptable

' .egio ------------

i---------_, ____ --------------------------------------------------------------------------------------------------Acceptable I --------------------, _____ I -----------------------_________ , ___ i I / I I -------------------i / ----------I ------------------____ ,_ ----r------------------c-------I ------------, ---, _____ J ----r i I 50 60 70 80 90 Time After Shutdown (Hrs) igure 3.9.a-5, "45 MBTU/hr SFP Heat Load Margin" BRAIDWOOD

-UNITS 1 & 2 Technical Requirements Manual 3.9.a -7 f -----_..... i ! i J ! j I I / I ! ----1 i i i i I 100 ---__,....--I ! i / / i I i /: j I i -------------i i -1 Acceptable II +----i I ! I i i i : i I 110 i i i I ! t t i I ----i I i Decay 3.9.a t*----------------120 Revision 89 46 MBTU/hr SFP Heat Load Margin 200 "CS 180 Q) "CS 160 ca 0 -t: 140 0 fl) 120 en en 100 <( 'O 80 '-Q) ..Q 60 E :::s z 40 -ca ...., 20 0 40 BRAIDWOOD

-UNITS 1 & 2 Technical Requirements Manual 50 60 70 80 Time After Shutdown (Hrs) Figure 3.9.a-6, "46 MBTU/hr SFP Heat Load Margin" 3.9.a -8 90 100 TRM Decay Time 3.9.a 110 Revision 89 TRM Deca y Time 3.9.a 47 MBTU/hr SFP Heat Load Margin "" Cl> "" ('CS 0 5 0 0 'lo-0 a.. Cl> ..c E ::s z -('CS ..... 0 I-200 180 -160 -140 -120 -100 ---80 -----*---60 _,_ _______ 40 -* -0 40 ,,. '***** ,_ ,*, --*-' -*-"" *-----* - ----- --*----*--------------------------;-----' -------I ----BRAIDWOOD

-UNITS 1 & 2 Technical Requirements Manual I I i ---------i ' ------, __ --L..J::---/ --*--** **-**-**-i --_,.. i ; : I *-----------------------------I/ / ------***----------i -*--..

___ .. ______ ,,_ ________ ----*--J i : 7 ' ----

/ i /, I ---* *------------__ ._ ___ ' i ----, i i / ---*---Unacceptable i I -----*-'"" I --*-----------------------/, ;

' I -; ' ; ----I i : f I ' I -----------i / ; ; ' ; ' ----*>-----/ f ; *-----------,__ .. -------------------' --/ ' i *-*--' I ' Acceptable

/ i i--' -----

---*-i --*--------Region II " ---*--**-*-*

J i ------i-----,_ ,' ' I : ----/1 i------i 1 I r i i I 50 60 70 80 90 100 110 Time After Shutdown (Hrs) Figure 3.9.a-7, "47 MBTU/hr SFP Heat Load Margin" 3.9.a -9 Revision 89 48 MBTU/hr SFP Heat Load Margin 200 "C 180 G> "C 160 ca 0 5 140 ti) 120 >a ti> ti> 100 <( .... 0 80 s.. G> ..c E 60 ::s z 40 c;; ...... 20 0 40 BRAIDWOOD

-UNITS 1 & 2 Technical Requirements Manual 50 60 70 80 Time After Shutdown (Hrs) Figure 3.9.a-8, "48 MBTU/hr SFP Heat Load Margin" 3.9.a -10 Acceptable Region II 90 TRM Decay 3.9.a 100 Revision 89 49 MBTU/hr SFP Heat Load Margin 200 "'C 180 Q) "'C 160 0 5 140 fl) 120 >. fl) .:( 100 ..... 0 ... 80 Q) .c E 60 ::s z <<; 40 ...... {!. 20 0 40 BRAIDWOOD

-UNITS 1 & 2 Technical Requirements Manual Unacceptable Region 50 60 70 Time After Shutdown (Hrs) 80 igure 3.9.a-9, "49 MBTU7ffr--SFP Heat Load Margin" 3.9.a -90 TRM Decay Time 3.9.a 100 Revision 89 TRM Communications 3.9.b BRAIDWOOD - UNITS 1 & 2 3.9.b - 1 Revision 1 Technical Requirements Manual 3.9 REFUELING OPERATIONS 3.9.b Communications

TLCO 3.9.b Direct communications shall be maintained between the control room and personnel at the containment refueling

station. APPLICABILITY: During CORE ALTERATIONS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

A. Direct communications not maintained.

A.1 Suspend CORE ALTERATIONS.

Immediately

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

TSR 3.9.b.1 Demonstrate direct communications between the control room and personnel at the

containment refueling station.

Once within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to the start of CORE ALTERATIONS AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter

TRM Refueling Equipment 3.9.c BRAIDWOOD - UNITS 1 & 2 3.9.c - 1 Revision 17 Technical Requirements Manual 3.9 REFUELING OPERATIONS 3.9.c Refueling Equipment TLCO 3.9.c The following refueling equipment shall be OPERABLE:

1. The refueling machine used for movement of fuel assemblies, and

2. The auxiliary hoist or reactor cavity maintenance crane used for latching and unlatching drive rods.

APPLICABILITY: During movement of drive rods or fuel assemblies within the reactor vessel.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling machine inoperable.

A.1 Suspend use of the inoperable refueling

machine from operations involving

the movement of fuel assemblies within the

reactor vessel.

Immediately B. Required auxiliary hoist inoperable.

OR Required reactor cavity maintenance crane inoperable.

B.1 Suspend use of the inoperable required auxiliary hoist or inoperable required reactor cavity maintenance crane from operations involving the movement of drive rods within the reactor vessel.

Immediately

TRM Refueling Equipment 3.9.c BRAIDWOOD - UNITS 1 & 2 3.9.c - 2 Revision 17 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.9.c.1 Verify refueling machine operability by:

a. Performing a load test of 3563 pounds; and

b. Demonstrating an automatic load cutoff when the crane load

> 2850 pounds.

Once within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of movement of fuel assemblies within the reactor vessel

TSR 3.9.c.2 Verify required auxiliary hoist or required reactor cavity maintenance crane and associated load indicator operability by performing a load test 2500 pounds.

Once within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of movement of

drive rods within the reactor vessel

TRM Crane Travel - Spent Fuel Pool 3.9.dBRAIDWOOD - UNITS 1 & 23.9.d -1Revision75 Technical Requirements Manual 3.9 REFUELING OPERATIONS 3.9.d Crane Travel - Spent Fuel PoolTLCO 3.9.dLoads shall be limited to 2000 pounds when traveling over fuel assemblies in the spent fuel pool.

NOTES---------------------------1.Based on the design of the load block, the main hoist/load block is allowed to travel over the spent fuel pool.2.Loads > 2000 pounds may be carried over the cask loading area provided they are carried by a SINGLE-FAILURE PROOF LOAD HANDLING SYSTEM.3.Deviations from defined safe load paths for heavy loads require Plant Operations Review Committee approval.

APPLICABILITY:With fuel assemblies in the spent fuel pool.

ACTIONS-------------------------------------NOTE-------------------------------------TLCO3.0.c is not applicable.

CONDITIONREQUIRED ACTION COMPLETION TIMEA.Load not within limit.A.1Place the crane load in a safe condition.

Immediately TRM Crane Travel - Spent Fuel Pool 3.9.dBRAIDWOOD - UNITS 1 & 23.9.d -2Revision75 Technical Requirements Manual SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCYTSR3.9.d.1Verify crane interlocks preventcrane travel with loads> 2000 pounds over fuel assembliesin the spent fuel pool, with the exception of the cask loading area.

Once within 7days prior to

crane use AND Once per 7 days thereafter

during crane operation TRM Refueling Cavity Water Level 3.9.e BRAIDWOOD - UNITS 1 & 2 3.9.e - 1 Revision 1 Technical Requirements Manual 3.9 REFUELING OPERATIONS 3.9.e Refueling Cavity Water Level

TLCO 3.9.e Refueling cavity water level shall be maintained 23 ft above the top of the reactor vessel flange.

APPLICABILITY: During movement of new fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling cavity water level not within

limit.

A.1 Suspend movement of new fuel assemblies

within containment.

Immediately

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

TSR 3.9.e.1 Verify refueling cavity water level is 23 ft above the top of reactor vessel flange.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

TRM Safety Limit Violation 5.1 BRAIDWOOD - UNITS 1 & 2 5.1 - 1 Revision 1 Technical Requirements Manual 5.0 ADMINISTRATIVE CONTROLS 5.1 Safety Limit Violation 5.1 The following actions shall be taken in the event a Safety Limit (Technical Specification 2.1.1 or 2.1.2) is violated:

a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , b. The Site Vice President and the Offsite Review and Investigative Function shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the Onsite Review and Investigative Function. This report shall describe: (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action to prevent recurrence, d. The Safety Limit Violation Report shall be submitted to the Commission, the Offsite Review and Investigative Function and the Site Vice President within 14 days of the violation, and e. Critical operation of the Unit shall not be resumed until authorized by the Commission.

TRM Procedures and Programs 5.2 BRAIDWOOD - UNITS 1 & 2 5.2 - 1 Revision 1 Technical Requirements Manual 5.0 ADMINISTRATIVE CONTROLS 5.2 Procedures and Programs 5.2.a Process Control Program (PCP)

Written procedures shall be established, implemented, and maintained covering the activities of the PCP implementation.

The PCP shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground

requirements, and other requirements governing the disposal of solid radioactive waste.

Changes to the PCP:

1. Shall be documented and records of reviews performed shall be retained for the duration of the unit Operating License.

This documentation shall contain:

a. Sufficient information to support the change together with the appropriate analyses or evaluations

justifying the change(s) and, b. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, and other applicable regulations.

2. Shall become effective after review and acceptance by the Onsite Review and Investigative Function (Onsite Review) and the approval of the Station Manager.

TRM Procedures and Programs 5.2 BRAIDWOOD - UNITS 1 & 2 5.2 - 2 Revision 1 Technical Requirements Manual 5.2 Procedures and Programs 5.2.b In-Plant Radiation Monitoring A program shall be established, implemented and maintained which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.

This program shall include the following:

1. Training of personnel,

2. Procedures for monitoring, and

3. Provisions for maintenance of sampling and analysis equipment.

5.2.c Radiological Environmental Monitoring Program A program shall be established, implemented and maintained which will monitor the radiation and radionuclides in the environs of

the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the Offsite Dose Calculation Manual (ODCM), (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1. Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,

2. A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and

3. Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the Quality Assurance Program for environmental monitoring.

TRM Procedures and Programs 5.2 BRAIDWOOD - UNITS 1 & 2 5.2 - 3 Revision 1 Technical Requirements Manual 5.2 Procedures and Programs 5.2.d Radiation Protection Program Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

5.2.e Offsite Dose Calculation Manual (ODCM)

The requirement for an ODCM program is contained in Technical Specification 5.5.1.

Changes to the ODCM shall become effective after review and

acceptance by the Onsite Review and Investigative Function and the approval of the Station Manager on the date specified by the Onsite Review and Investigative Function.

TRM Reporting Requirements 5.3 BRAIDWOOD - UNITS 1 & 2 5.3 - 1 Revision 1 Technical Requirements Manual 5.0 ADMINISTRATIVE CONTROLS 5.3 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.3.a Startup Report

1. A summary report of plant startup and power escalation testing shall be submitted to the Commission following:

(1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

2. The Startup Report shall address each of the tests identified in the Updated Final Safety Analysis Report (UFSAR) and shall include a description of the measured values of the operating conditions or characteristics

obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

3. Startup Reports shall be submitted within: (1) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and

resumption or commencement of commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed.

TRM Reporting Requirements 5.3 BRAIDWOOD - UNITS 1 & 2 5.3 - 2 Revision 1 Technical Requirements Manual 5.3 Reporting Requirements 5.3.b Annual Specific Activity Report An Annual Report covering the activity of the facility for the previous calendar year shall be submitted to the Commission prior to March 1 of each year.

The results of specific activity analysis in which the primary

coolant exceeded the limits of Specification 3.4.16. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after radioiodine activity was reduced to less than limit. Each

result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a

function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit. 5.3.c Special Reports

1. In the event the unit is in MODE 1 or 2 with K eff 1 and with the Moderator Temperature Coefficient (MTC) more positive than the beginning of life limit specified in the COLR, a Special Report shall be prepared and submitted to the Commission within 10 days. The Special Report shall describe the value of the measured MTC, the interim control rod withdrawal limits, and the predicted average core burnup necessary for restoring the positive MTC to within its limit

for the all rods withdrawn condition.

2. In the event an inoperable Main Control Room Radiation Outside Air Intake Monitor (ORE-PR031B/32B or

ORE-PR033B/34B) is not restored to OPERABLE within 30 days, a Special Report shall be prepared and submitted to the Commission within the following 30 days. The Special Report shall describe the cause of the inoperability and the plans for restoration.

TRM Reporting Requirements 5.3 BRAIDWOOD - UNITS 1 & 2 5.3 - 3 Revision 1 Technical Requirements Manual 5.3 Reporting Requirements 5.3.c Special Reports (continued)

3. In the event the unit is in MODE 4, 5, or 6 with the reactor head on and either the PORVs, RHR suction relief valves, or the RCS vents are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission within 30 days. The Special Report shall

describe the circumstances initiating the transient, the effect of the PORVs, RHR suction relief valves, or RCS vents on the transient, and any corrective action necessary to prevent recurrence.

4. In the event the unit is in MODE 1, 2, 3, or 4 and the ECCS is actuated and injects water into the RCS, a Special Report shall be prepared and submitted to the Commission within 90 days. The Special Report shall describe the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected Safety Injection nozzle shall be provided in this

Special Report whenever its value exceeds 0.70.

(NOTE: If a Licensee Event Report (LER) has been provided to the NRC documenting the event and that report includes all of the requirements of the Special Report, no additional actions are required.)

TRM ODCM and Radiological Controls Reports and Program Appendix A

BRAIDWOOD UNITS 1 & 2 1 of 5 Revision 33 Technical Requirements Manual ODCM AND RADIOLOGICAL CONTROLS REPORTS AND PROGRAM BRAIDWOOD

TABLE OF CONTENTS SECTIONS TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS

1.4 PROGRAM DESCRIPTION 1.5 PROGRAM IMPLEMENTATION 1.6 ACCEPTANCE CRITERIA

1.7 LCOARS/COMPENSATORY MEASURES 1.8 REPORTING REQUIREMENTS 1.9 CHANGE CONTROL

TRM ODCM and Radiological Controls Reports and Program Appendix A

BRAIDWOOD UNITS 1 & 2 2 of 5 Revision 33 Technical Requirements Manual

1.1 PURPOSE

This Program provides guidance for the implementation of Technical Specification (TS) 5.5.1, "Offsite Dose Calculation Manual (ODCM)", 5.6.2, "Annual Radiological Environmental Operating Report", and 5.6.3, "Radioactive Effluent Release Report."

The ODCM contains the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and the conduct of the Radiological Environmental Monitoring Program. In addition, the ODCM contains the radioactive effluent controls, radiological environmental monitoring activities, and descriptions of the

information that is included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports.

1.2 REFERENCES

1. Technical Specifications:

a. 5.5.1, "Offsite Dose Calculation Manual (ODCM)"

b. 5.6.2, "Annual Radiological Environmental Operating Report"

c. 5.6.3, "Radioactive Effluent Release Report" 2. US NRC 10CFR20.1302

3. US NRC 40CFR190

4. US NRC 10CFR50, Appendix I 1.3 DEFINITIONS AND/OR ACRONYMS

Offsite Dose Calculation Manual - ODCM 1.4 PROGRAM DESCRIPTION The purpose of this Program is to ensure that methodologies, parameters, effluent controls, radiological monitoring, and reporting requirements are properly implemented by the ODCM or other approved plant procedures.

TRM ODCM and Radiological Controls Reports and Program Appendix A

BRAIDWOOD UNITS 1 & 2 3 of 5 Revision 33 Technical Requirements Manual 1.5 PROGRAM IMPLEMENTATION

1. 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.

2. 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

in Reference 1.

The Chemistry Department shall have responsibility for the implementation, performance, completion and reporting of this

Program.

1.6 ACCEPTANCE CRITERIA Acceptance criteria is contained in the ODCM, plant implementing

or surveillance procedures.

1.7 LCOARS/COMPENSATORY MEASURES No LCOARs will be entered as a result of exceeding any acceptance

criteria. Any corrective measures are contained in the ODCM or plant procedures. In addition, an Issue Report (IR) may need to be generated to provide proper tracking and resolution of noted

problems associated with the implementation of this Program.

1.8 REPORTING REQUIREMENTS

1. Annual Radiological Environmental Operating Report covering the operation of the facility 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 ODCM, and Reference 4.

TRM ODCM and Radiological Controls Reports and Program Appendix A

BRAIDWOOD UNITS 1 & 2 4 of 5 Revision 33 Technical Requirements Manual 2. The Radioactive Effluent Release Report covering the operation of the facility during the previous year shall be submitted prior to May 1 of each year in accordance with 10CFR50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility. The material provided shall be consistent with the objectives outlined in

the ODCM and Process Control Program and in conformance with 10CFR50.36a and Reference 4.

A single submittal may be made for the facility. The submittal should combine sections common to both units.

The Chemistry Department is responsible for preparing and submitting the subject reports.

1.9 CHANGE CONTROL Changes to the ODCM shall be documented and records of reviews performed shall be retained. As a minimum, the 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 References 2, 3, 4,

and 10CFR50.36a and do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

Changes to the ODCM are effective upon approval of the Plant Manager or designee.

Changes to the ODCM 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.

TRM ODCM and Radiological Controls Reports and Program Appendix A

BRAIDWOOD UNITS 1 & 2 5 of 5 Revision 33 Technical Requirements Manual Changes to this Program, other than editorial changes, shall include a 10CFR50.59 Review and a Station Qualified Review (SQR).

The SQR composition shall include Regulatory Assurance Department in all cases. As a part of the SQR, Byron and Braidwood Plant Operations Review Committee (PORC) approval is required as determined by the Regulatory Assurance Manager. Byron and Braidwood shall implement the same change unless the change being implemented at Braidwood has been reviewed and was determined not to be applicable to Byron.

TRM Primary Coolant Sources Outside Containment Program Appendix B BRAIDWOOD UNITS 1 & 2 1 of 4 Revision 58 Technical Requirements Manual

PRIMARY COOLANT SOURCES OUTSIDE CONTAINMENT BRAIDWOOD TABLE OF CONTENTS

SECTION TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS 1.4 PROGRAM DESCRIPTION 1.5 PROGRAM IMPLEMENTATION

1.6 ACCEPTANCE CRITERIA 1.7 LCOARS/COMPENSATORY MEASURES 1.8 REPORTING REQUIREMENTS

1.9 CHANGE CONTROL TRM Primary Coolant Sources Outside Containment Program Appendix B BRAIDWOOD UNITS 1 & 2 2 of 4 Revision 58 Technical Requirements Manual

1.1 PURPOSE

The purpose of this Program is to verify leakage tests are performed on each system or portion of systems outside containment that could potentially contain highly radioactive fluids or gases, pursuant to Technical Specification (TS) 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 level as low as practicable.

1.2 References

1. Technical Specifications 5.5.2, "Primary Coolant Sources Outside Containment"

2. UFSAR Appendix E.77 (UFSAR), "Primary Coolant Sources Outside Containment (III.D.1.1)" 3. NUREG 0737.III.D.1.1, "Integrity of Systems Outside Containment Likely to Contain Radioactive Material for

Pressurized-Water Reactors and Boiling-Water Reactors" 4. NRC Generic Letter 88-05, "Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants" 1.3 DEFINITIONS AND ACRONYMS

1. INDICATION - The response from the application of a visual examination (VT-2).

2. VT-2 (Visual Examination) - An inspection of an ASME/NUREG System component at normal system operating pressure.

1.4 PROGRAM DESCRIPTION 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 the recirculation portions of the Containment Spray, Safety Injection, Chemical and Volume Control, and Residual Heat Removal.

TRM Primary Coolant Sources Outside Containment Program Appendix B BRAIDWOOD UNITS 1 & 2 3 of 4 Revision 58 Technical Requirements Manual 1.5 PROGRAM IMPLEMENTATION This Program determines, through the associated implementing

procedures, that leakage sources outside containment will be accounted for to insure the total amount will not exceed the UFSAR acceptable limits for Braidwood Station. The bases for this Program were established per References 2 and 3 that provide for

the following:

1. Monitor the leak testing of piping so that the appropriate lines are examined at least once per 18 months on each System or portions of Systems;

2. Direct leak test examinations such that systems are tested at approximate operating pressure or higher;

3. Align systems such that all piping tested is properly pressurized;

4. Identify lines that contain gases that require pressure decay and/or metered makeup testing;

5. Quantify results of leakage examinations;

6. Initiate corrective action; and

7. Preventive maintenance in accordance with approved plant procedures consistent with the Braidwood Maintenance Rule.

The Engineering Programs Group shall have responsibility for the completion of this Program.

1.6 ACCEPTANCE CRITERIA

1. All examinations required by this Program are completed at least once per 18 months. The provisions of SR 3.0.2 are applicable.

2. Cumulative leakage shall be within the acceptable range specified per UFSAR Table 15.6-13.

TRM Primary Coolant Sources Outside Containment Program Appendix B BRAIDWOOD UNITS 1 & 2 4 of 4 Revision 58 Technical Requirements Manual 1.7 LCOARS/COMPENSATORY MEASURES Any examinations exceeding acceptance criteria shall be immediately conveyed to the Shift Manager. The Shift Manager shall determine the OPERABILITY status and implement a LCOAR if applicable. In addition, an Issue Report may need to be generated to provide proper tracking and resolution of noted problems associated with the implementation of this Program.

1.8 REPORTING REQUIREMENTS Any examinations exceeding acceptance criteria will be coordinated/reported in accordance with the requirements of the Maintenance Rule Program.

1.9 CHANGE CONTROL Changes to this Program, other than editorial changes, shall include a 10CFR50.59 Review and a Station Qualified Review (SQR).

The SQR composition shall include the Regulatory Assurance Department in all cases. As a part of the SQR, Byron and Braidwood Plant Operations Review Committee (PORC) approval is required as determined by the Regulatory Assurance Manager. Byron and Braidwood shall implement the same change unless the change being implemented at Braidwood has been reviewed and determined not to be applicable to Byron.

TRM Radioactive Effluent Controls Program Appendix D BRAIDWOOD UNITS 1 & 2 1 of 5 Revision 33 Technical Requirements Manual RADIOACTIVE EFFLUENT CONTROLS PROGRAM BRAIDWOOD TABLE OF CONTENTS SECTION TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITION AND/OR ACRONYMS

1.4 PROGRAM DESCRIPTION 1.5 PROGRAM IMPLEMENTATION 1.6 ACCEPTANCE CRITERIA 1.7 LCOARS/COMPENSATORY MEASURES

1.8 REPORTING REQUIREMENTS 1.9 CHANGE CONTROL

TRM Radioactive Effluent Controls Program Appendix D BRAIDWOOD UNITS 1 & 2 2 of 5 Revision 33 Technical Requirements Manual

1.1 PURPOSE

This Program is in compliance with Technical Specification (TS)

5.5.4, "Radioactive Effluent Controls Program." This Program provides controls for 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 Offsite Dose Calculation Manual (ODCM) which is implemented by plant procedures which also include remedial actions taken whenever the acceptance criteria is exceeded.

1.2 REFERENCES

1. Technical Specifications 5.5.4, "Radioactive Effluent Controls Program" 2. Offsite Dose Calculation Manual (ODCM)

3. US NRC 10CFR20, Appendix B, Table 2, Column 2

4. US NRC 10CFR20.1302

5. US NRC 10CFR50, Appendix I

6. US NRC 40CFR190 1.3 DEFINITIONS AND/OR ACRONYMS Offsite Dose Calculation Manual - ODCM

1.4 PROGRAM DESCRIPTION This Program ensures that appropriate plant procedures, along with

the ODCM are implemented for radioactive effluent controls. These controls are to be maintained in accordance with the guidance provided by referenced NRC requirements. This Program provides the general guidance for surveillance testing, monitoring, setpoint determination, exposure limits, and reporting requirements.

TRM Radioactive Effluent Controls Program Appendix D BRAIDWOOD UNITS 1 & 2 3 of 5 Revision 33 Technical Requirements Manual 1.5 PROGRAM IMPLEMENTATION This Program shall be implemented by plant procedures or the ODCM which will include at least the following:

1. Limitations on the functional capability of radioactive liquid and gaseous monitoring

instrumentation including surveillance tests and

setpoint determination in accordance with the methodology in Reference 2;

2. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentrations stated in Reference 3;

3. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with Reference 4 and with

the methodology and parameters per Reference 2;

4. Limitations on the quarterly and annual 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 Reference 5;

5. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in Reference 2, Section 12 at least every 31 days;

6. 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 Reference 5;

7. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the

site boundary conforming to the acceptance criteria.

TRM Radioactive Effluent Controls Program Appendix D BRAIDWOOD UNITS 1 & 2 4 of 5 Revision 33 Technical Requirements Manual

8. Limitations on the quarterly and annual air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to Reference 5.

9. Limitations on the quarterly and annual 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 Reference 5; and

10. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to

radiation from uranium fuel cycle sources, conforming to

Reference 6.

The Chemistry Department shall have responsibility for the implementation, performance, completion, and reporting of this

Program.

1.6 ACCEPTANCE CRITERIA All acceptance criteria pertaining to this Program is located in

the ODCM, implementing, or surveillance procedures.

1.7 LCOARS/COMPENSATORY MEASURES An Issue Report (IR) may need to be generated to provide proper tracking and resolution of noted problems associated with the implementation of this Program..

1.8 REPORTING REQUIREMENTS Any reporting requirements are listed in the ODCM and implementing

procedures.

TRM Radioactive Effluent Controls Program Appendix D BRAIDWOOD UNITS 1 & 2 5 of 5 Revision 33 Technical Requirements Manual 1.9 CHANGE CONTROL Changes to this Program, other than editorial changes, shall

include a 10CFR50.59 Review and a Station Qualified Review (SQR).

The SQR composition shall include Regulatory Assurance Department in all cases. As a part of the SQR, Byron and Braidwood Plant Operations Review Committee (PORC) approval is required as determined by the Regulatory Assurance Manager. Byron and Braidwood shall implement the same change unless the change being implemented at Braidwood has been reviewed and was determined not to be applicable to Byron.

TRM Transient Monitoring Program Appendix E BRAIDWOOD UNITS 1 & 2 1 of 6 Revision 1 Technical Requirements Manual TRANSIENT MONITORING PROGRAM BRAIDWOOD TABLE OF CONTENTS

SECTION TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS 1.4 PROGRAM DESCRIPTION 1.5 PROGRAM IMPLEMENTATION 1.6 ACCEPTANCE CRITERIA

1.7 LCOARS/COMPENSATORY MEASURES 1.8 REPORTING REQUIREMENTS

1.9 CHANGE CONTROL

TRM Transient Monitoring Program Appendix E BRAIDWOOD UNITS 1 & 2 2 of 6 Revision 1 Technical Requirements Manual

1.1 PURPOSE

The purpose of this Program is to provide guidance for tracking

the number of cycles of specific transients and to ensure operation within the Braidwood Plant Design Basis is in accordance with Technical Specifications (TS) 5.5.5, "Component Cyclic or Transient Limit."

The minimum requirements for cyclic or transient tracking are those transients listed in Attachment 1 of this Program. These items, in addition to various other monitored parameters or transients, will be tracked periodically in accordance with appropriate Plant Procedures.

Components affected by the transients monitored are typically ASME

Section III Code Class 1 vessels. The design of such components includes cyclic/fatigue assumptions which must be tracked to ensure that the unit is operating within its design basis. Piping and components designed to ANSI B31.1, Power piping does not generally require fatigue monitoring as those considerations are inherent to the safety margins applied by that Code.

1.2 REFERENCES

1. TS Specification 5.5.5, "Component Cyclic or Transient Limit" 2. Updated Final Safety Analysis Report, (UFSAR), Section 3.9 and 5.2 3. 10CFR50, Appendix A

4. "WCAP-12235, General Guidelines for Nuclear Power Plant Transient and Fatigue Monitoring", March, 1989

1.3 DEFINITION AND/OR ACRONYMS Not applicable.

TRM Transient Monitoring Program Appendix E BRAIDWOOD UNITS 1 & 2 3 of 6 Revision 1 Technical Requirements Manual 1.4 PROGRAM DESCRIPTION This Program ensures that appropriate plant procedures are

implemented to monitor transients that may have an affect on ASME Section III Code Class 1 vessels/components as specified in Reference 2.

provides component cyclic or transient limits as well as design cycle or transient parameters for specific plant components. Monitoring of additional equipment/parameters not listed in Attachment 1 may be performed as a good practice on an as needed basis, and are not considered within the scope of this Program though they may be tracked using appropriate Plant Procedures, Implementing procedures shall have adequate measures

to identify cumulative cyclic/transient conditions requiring further analysis prior to the design basis limits being reached.

In the event any of the limits are approached or exceeded, required actions or reporting requirements are specified in this Program or appropriate Plant Procedures.

1.5 PROGRAM IMPLEMENTATION Specific plant procedures have been developed and implemented in

order to perform the following:

1. Provide a tracking program for the relevant transient cycles/trips for those ASME Section III Code Class 1 components specified in Reference 2.

2. Periodically monitor components identified in Attachment 1 for code compliance relative to parameters such as, transient limits and usage factors.

System Engineering Department shall have responsibility for the implementation, performance, completion, and reporting of this Program.

1.6 ACCEPTANCE CRITERIA

1. Attachment 1 provides cyclic or transient limit acceptance criteria for each component within the scope of this Program.

TRM Transient Monitoring Program Appendix E BRAIDWOOD UNITS 1 & 2 4 of 6 Revision 1 Technical Requirements Manual

2. Should the design basis limits be approached or exceeded, an evaluation and recommended operating restrictions (if any) will be provided by Site Engineering - Mechanical. Any recommendations to modify design limits shall be accompanied by a safety evaluation.

1.7 LCOARS/COMPENSATORY MEASURES In the event that a component has reached its administrative

cyclic or transient limit, the Shift Manager shall be notified immediately. The Shift Manager shall determine OPERABILITY status and implement a LCOAR if applicable. In addition, a Problem Identification Form (PIF) may need to be generated to provide proper tracking and resolution of noted problems associated with

the implementation of this Program.

1.8 REPORTING REQUIREMENTS

1. A special report will be generated whenever cyclic or transient limits are being approached or exceeded. This

report shall be generated and distributed, as a minimum to

the following:

PORC (Plant Operations Review Committee)

Site V.P. - Braidwood Plant Manager

Operations Manager Engineering Manager

2. Any violations of the cyclic or transient limits shall be reported to the NRC in accordance with 10CFR50.71 and

10CFR50.72.

TRM Transient Monitoring Program Appendix E BRAIDWOOD UNITS 1 & 2 5 of 6 Revision 1 Technical Requirements Manual 1.9 CHANGE CONTROL Changes to this Program, other than editorial, shall include a

10CFR50.59 evaluation and an Independent Technical Review (ITR).

The ITR composition shall include Regulatory Assurance Department in all cases. As a part of the ITR, for a change to this Program,

concurrence from Byron Station and Braidwood Plant Operations Review Committee (PORC) approval is required. The concurrence shall be that Byron Station is implementing the same change or that the change has been reviewed and determined not to be applicable to Byron Station.

TRM Transient Monitoring Program Appendix E BRAIDWOOD UNITS 1 & 2 6 of 6 Revision 1 Technical Requirements Manual ATTACHMENT 1 COMPONENT CYCLIC OR TRANSIENT LIMITS COMPONENT CYCLIC OR TRANSIENT LIMIT DESIGN CYCLE

OR TRANSIENT Reactor Coolant System 200 heatup cycles at 100°F/h and 200 cool-down cycles at

< 100 °F/h. Heatup cycle - T avg from 200°F to 550°F. Cooldown cycle - T avg from 550°F to 200°F. 200 pressurizer cooldown cycles at 200°F/h. Pressurizer cooldown cycle temperature from 650°F to 100°F. 80 loss of load cycles, without immediate Turbine or Reactor Trip. 15% of RATED THERMAL POWER to 0% of RATED

THERMAL POWER.

40 cycles of loss-of-offsite A.C. electrical power.

Loss-of-Offsite A.C.

electrical ESF Electrical System.

80 cycles of loss of flow in one reactor coolant loop.

Loss of only one reactor coolant pump.

400 Reactor trip cycles. 100% to 0% of RATED THERMAL POWER.

10 auxiliary spray actuation cycles. Spray water temperature

differential

> 320°F. 200 leak tests. Pressurized to 2485 psig. 10 hydrostatic pressure tests. Pressurized to 3107 psig. Secondary Coolant

System 1 large steam line break. Break in a > 6 inch steam line.

10 hydrostatic pressure tests. Pressurized to 1481 psig.

TRM Pre-stressed Concrete Containment Tendon Surveillance Program Appendix F

BRAIDWOOD UNITS 1 & 2 1 of 5 Revision 61 Technical Requirements Manual PRE-STRESSED CONCRETE CONTAINMENT TENDON SURVEILLANCE PROGRAM BRAIDWOOD TABLE OF CONTENTS SECTION TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS

1.4 PROGRAM DESCRIPTION 1.5 PROGRAM IMPLEMENTATION 1.6 ACCEPTANCE CRITERIA

1.7 LCOAR/COMPENSATORY MEASURES 1.8 REPORTING REQUIREMENTS 1.9 CHANGE CONTROL

TRM Pre-stressed Concrete Containment Tendon Surveillance Program Appendix F

BRAIDWOOD UNITS 1 & 2 2 of 5 Revision 61 Technical Requirements Manual

1.1 PURPOSE

This Program provides controls for monitoring any tendon degradation in the pre-stressed concrete containments and is pursuant to Technical Specifications (TS) 5.5.6 and 5.6.8.

1.2 REFERENCES

1. Technical Specifications:

a. 5.5.6, "Pre-Stressed Concrete Containment Tendon Surveillance Program"

b. 5.6.8, "Tendon Surveillance Report"

2. USFAR Section 3.8.1.7.3.2, "Inservice Tendon Surveillance Program"

3. U.S. NRC 10 CFR 50.55a

4. U.S. NRC Regulatory Guide 1.35.1, "Determining Pre-Stressing Forces For Inspection of Pre-Stressed Concrete Containments," dated July 1990

5. ASME Boiler and Pressure Vessel Code,Section XI, Sub Section IWL

6. Drawings:

a. S884: Containment Building Tendon Location Plans and Sections

b. Inland Ryerson Company Drawings 781 / 782 through 781 / 782-23

c. Braidwood Station In Service Inspection Drawings for Containment Tendons

7. Braidwood SER Section 3.8.1

8. Braidwood Maintenance Rule 10 CFR 50.65 TRM Pre-stressed Concrete Containment Tendon Surveillance Program Appendix F

BRAIDWOOD UNITS 1 & 2 3 of 5 Revision 61 Technical Requirements Manual 1.3 DEFINITIONS AND/OR ACRONYMS

1. TENDON - The bundle of wire assemblies and anchorages that maintain pre-stressed forces within the containment structure.

2. ANCHORAGE - The components at each end of the wire bundle that are used to maintain the required pre-

stressed forces and distribute the forces within the tendon.

3. LIFT OFF FORCE - The force required to lift the containment tendon anchorage from the shim stack or structure.

4. SHEATHING FILLER GREASE - The corrosion protection medium that encases the tendon and anchorage.

1.4 PROGRAM

DESCRIPTION The Pre-Stressed Concrete Containment Tendon Surveillance

Program provides a standardized methodology to ensure that aging and degradation issues are identified early and monitored through the following activities:

1. Measuring, recording, and evaluating the lift off force for tendons included in the test sample population;

2. Ensuring the containment vessel, tendon anchorages, and tendon wires do not exhibit signs of abnormal

degradation;

3. Ensuring the tendon wires continue to maintain the required integrity through physical testing; and

4. Ensuring the sheathing filler grease continues to protect the tendon components from corrosion by

identification of free water and chemical analysis of

the sheathing filler grease.

TRM Pre-stressed Concrete Containment Tendon Surveillance Program Appendix F

BRAIDWOOD UNITS 1 & 2 4 of 5 Revision 61 Technical Requirements Manual

1.5 PROGRAM

IMPLEMENTATION Inspection schedules, examination and testing methods, personnel qualification requirements, and reporting requirements shall be established, implemented, and maintained in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55(a) except where alternative, exemption or relief has been authorized by the NRC. The Engineering Programs Group shall have the responsibility for all aspects of

the Program.

The detection of degradation of the containment structure or trending shall be coordinated with the requirements of the Maintenance Rule.

1.6 ACCEPTANCE

CRITERIA Acceptance criteria for the Braidwood Pre-Stressed Concrete

Containment Tendon Surveillance Program is contained in appropriate Plant Procedures as described in the Braidwood Containment Inservice Inspection (CISI) Program Plan.

1.7 LCOARS

/ COMPENSATORY MEASURES In the event the acceptance criteria is exceeded, immediately notify the Shift Manager. In addition, the issue shall be entered into the Corrective Action Program to provide proper tracking and resolution of noted problems associated with the implementation of this Program. Engineering shall determine if the condition that exceeded the acceptance criteria renders the containment inoperable. In the event the containment is found to be inoperable, the Shift Manager shall be immediately notified

and the Shift Manager shall implement the applicable LCOAR.

1.8 REPORTING

REQUIREMENTS

1. Items which do not meet the acceptance criteria shall be evaluated by Engineering and an Engineering Evaluation

Report shall be prepared. The Engineering Evaluation

Report(s) shall be maintained at the site and are subject to review by the regulatory and enforcement authorities.

a. The Engineering Evaluation Report shall be in accordance with the ASME Code Section XI, IWL Subsection.

TRM Pre-stressed Concrete Containment Tendon Surveillance Program Appendix F

BRAIDWOOD UNITS 1 & 2 5 of 5 Revision 61 Technical Requirements Manual 2. The following conditions shall also be reported in the ISI Summary Report required by ASME Section XI, IWA6000 when: a. The elongation corresponding to a specific load ( adjusted for effective wires or strands )

during re-tensioning of the tendons differs by

more than 10 percent from that recorded during the last measurement;

b. The Sheathing Filler Grease Analysis contains chemically combined water exceeding 10 percent by weight;

c. The presence of free water is identified in the sheathing filler grease;

d. The absolute difference between the amount of sheathing filler grease removed during inspection and testing and the amount replaced thereafter exceeds 10 percent of the tendon duct

volume; or

e. Grease leakage is detected during general visual examination of the containment surface.

1.9 CHANGE

CONTROL Changes to this Program, other than editorial changes, shall

include a 10 CFR 50.59 Review and a Station Qualified Review (SQR). The SQR composition shall include the Regulatory Assurance Department in all cases. As part of the SQR, Byron and Braidwood Plant Operations Review Committee (PORC) approval is required as determined by the Regulatory Assurance Manager. Byron and Braidwood shall implement the same change unless the change being implemented at Braidwood has been reviewed and was determined not to be applicable to Byron.

TRM Reactor Coolant Pump Flywheel Inspection Program Appendix GBRAIDWOOD UNITS 1 & 21 of 5Revision 71 Technical Requirements Manual REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM BRAIDWOOD TABLE OF CONTENTS SECTION TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS 1.4 PROGRAM DESCRIPTION 1.5 PROGRAM IMPLEMENTATION 1.6 ACCEPTANCE CRITERIA 1.7 LCOARS/COMPENSATORY MEASURES 1.8 REPORTING REQUIREMENTS 1.9 CHANGE CONTROL TRM Reactor Coolant Pump Flywheel Inspection Program Appendix GBRAIDWOOD UNITS 1 & 22 of 5Revision 71 Technical Requirements Manual1.1PURPOSE The purpose of this Program is to verify the structural integrity of each Reactor Coolant Pump Flywheel pursuant to Technical Specification (TS) 5.5.7, "Reactor Coolant Pump Flywheel

Inspection Program." This Program provides for the inspection of

each reactor coolant pump flywheel in general conformance with Reference 5 as modified by References 12 and 13.

1.2REFERENCES

1.Technical Specification 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program"2.UFSAR:a.Section 5.4.1.5.2b.Appendix A3.10CFR50 Appendix A and B 4.NUREG-0800, Section 5.4.1.1, "Pump Flywheel Integrity"5.Regulatory Guide 1.14, "Reactor Coolant Pump Flywheel Integrity"6.Braidwood Station Units 1 and 2 Inservice Inspection Program Plan7.Westinghouse WCAP-8163, "Topical Report on Reactor Coolant Pump Integrity in LOCA"8.Westinghouse Vendor Manual F-198, "Reactor Coolant Pump" TRM Reactor Coolant Pump Flywheel Inspection Program Appendix GBRAIDWOOD UNITS 1 & 23 of 5Revision 71 Technical Requirements Manual9.Braidwood SER Sections:a.2.2.4b.3.5.1.2c.5.4.110.Braidwood Station Maintenance Rule Program 11.Westinghouse WCAP-14535A, "Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination"12.Mahesh Chawla to O.D. Kingsley, "Issuance of Amendments -

Byron Station, Units 1 and 2 and Braidwood Station, Units 1 and 2 - Request for Technical Specifications Change -

Revision to the Reactor Coolant Pump Flywheel Inspection Program," dated September 21, 2001.13.Marshall David to M.J. Pacilio, "Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2 - Issuance of Amendments RE: Extension of Inspection Interval for Reactor Coolant Flywheels (TAC Nos. ME3640, ME3641, ME3642, and ME3643), dated September 16, 2010.1.3DEFINITIONS AND/OR ACRONYMS1.UT - Ultrasonic Testing2.SURFACE EXAMINATION - Examination method using liquid penetrant (PT) or magnetic particle (MT) techniques.3.INDICATION - The response from the application of a nondestructive examination (NDE).4.RELEVANT INDICATION OR FLAW - An imperfection or unintentional discontinuity that is detectable by NDE.5.DEFECT - A flaw of such size, shape, orientation, location, or properties as to be rejectable. 1.4PROGRAM DESCRIPTIONS One of the following examinations shall be performed on each reactor coolant pump flywheel at the specified frequency:

TRM Reactor Coolant Pump Flywheel Inspection Program Appendix GBRAIDWOOD UNITS 1 & 24 of 5Revision 71 Technical Requirements Manual1.A qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of half the outer

radius or2.A surface examination (MT or PT) of the bore and keyway area whenever the flywheels are removed for maintenance purposes.

Since the exposed surfaces, other than the bore and keyway areas, of the flywheels are coated with corrosion preventative primer paint, a surface examination of these

surfaces is not practicable.3.For reactor coolant pump motor serial numbers 4S88P961 and 1S88P961, in lieu of Regulatory Position c.4.b(1) and c.4.b(2), a qualified in-place UT examination over the volume from theinner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI.

For all other reactor coolant pump motors, in lieu of Regulatory 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 of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at an interval not to exceed 20 years.1.5PROGRAM IMPLEMENTATION Inspection schedules, personnel, equipment and material

certifications, applicable examination methods, and examination

reports shall be initiated and maintained in accordance with

Braidwood Unit 1 and 2 Inservice Inspection Program Plan and associated procedures.

The Engineering Programs Group shall have responsibility for the implementation, performance, completion, and reporting of this

Program.1.6ACCEPTANCE CRITERIA1.All relevant indications shall be recorded on the appropriate examination form.

TRM Reactor Coolant Pump Flywheel Inspection Program Appendix GBRAIDWOOD UNITS 1 & 25 of 5Revision 71 Technical Requirements Manual2.Final disposition of flaws shall be based on engineering analysis.1.7LCOARS/COMPENSATORY MEASURES In the event indication(s) exceed allowable length, the Shift Manager shall be notified immediately. The Shift Manager shall determine OPERABILITY status and implement a LCOAR if applicable.

In addition, an Issue Report (IR) may need to be generatedto

provide proper tracking and resolution of noted problems associatedwith the implementation of this Program.1.8REPORTING REQUIREMENTS1.If the examination and evaluation indicate an increase in flaw size or growth rate greater than predicted for the service life of the flywheel, the results of the examination and evaluation should be submitted to the NRC for

evaluation.2.The detection of flaws that exceed the acceptance criteria standards shall be coordinated with the requirements of the

Maintenance Rule Program.1.9CHANGE CONTROL Changes to this Program, other than editorial changes, shall

include a 10 CFR 50.59 Review and a Station Qualified Review (SQR).

The SQR composition shall include Regulatory Assurance Department

in all cases. As a part of the SQR, Byron and Braidwood Plant Operations Review Committee (PORC) approval is required as determined by the Regulatory Assurance Manager. Byron and

Braidwood shall implement the same change unless the change being

implemented at Braidwood has been reviewed and was determined not

to be applicable to Byron.

TRM Inservice Testing Program Appendix H BRAIDWOOD UNITS 1 & 2 1 of 4 Revision 59 Technical Requirements Manual INSERVICE TESTING PROGRAM BRAIDWOOD TABLE OF CONTENTS

SECTION TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS

1.4 PROGRAM DESCRIPTION 1.5 PROGRAM IMPLEMENTATION 1.6 ACCEPTANCE CRITERIA

1.7 LCOARS/COMPENSATORY MEASURES 1.8 REPORTING REQUIREMENTS 1.9 CHANGE CONTROL TRM Inservice Testing Program Appendix H BRAIDWOOD UNITS 1 & 2 2 of 4 Revision 59 Technical Requirements Manual

1.1 PURPOSE

The purpose of this Program is to perform Inservice Testing of

ASME Code Class 1, 2, and 3 pumps and valves, pursuant to Technical Specifications 5.5.8, "Inservice Testing Program."

1.2 REFERENCES

1. Technical Specifications Section 5.5.8, "Inservice Testing Program" 2. Updated Final Analysis Report (UFSAR) Section, 3.9.6, "Inservice Testing of Pumps and Valves" 3. USNRC Generic Letter GL 89-04, "Guidance on Developing Acceptable IST Programs" 4. USNRC Regulatory Guides

5. USNRC Bulletins (IEB)

6. 10CFR Part 50.55a Codes and Standards

7. ASME OM Code

8. Braidwood Inservice Testing Program Plan Pumps and Valves Additional references and descriptions of the Codes along with the Addenda applicable to the Inservice Testing Program for pumps and valves are provided in the Braidwood Inservice Testing Program Plan Pumps and Valves.

1.3 DEFINITIONS AND/OR ACRONYMS American Society of Mechanical Engineers - ASME TRM Inservice Testing Program Appendix H BRAIDWOOD UNITS 1 & 2 3 of 4 Revision 59 Technical Requirements Manual

1.4 PROGRAM DESCRIPTION Inservice Testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with the ASME OM Code and applicable addenda as required by 10CFR Part 50, Section 50.55a(f), except where specific written relief has been granted by the Commission pursuant to 10CFR Part 50, Section 55a(f)(6)(i) or Section 55a(a)(3).

The Braidwood Inservice Testing Program Plan Pumps and Valves

contains the list of pumps and valves in the Program and the tests and test frequencies associated with each pump and valve. The

Program Plan also contains justifications for testing at frequencies other than the ASME Code required frequencies, technical positions, and relief requests from ASME Code requirements which are determined to be impractical. The Program Plan also describes the Codes and Addenda applicable to the Braidwood Inservice Testing Program. The Program Plan is submitted to the NRC.

Surveillance intervals for Inservice Testing activities shall be

as applicable as identified in Reference 1.

1.5 PROGRAM IMPLEMENTATION The pump and valve testing described in the Inservice Testing

Program Plan are implemented through station surveillance procedures. Administrative procedures are also used to implement Program requirements. The Engineering Department is responsible for the Inservice Testing Program Plan Pumps and Valves. The Departments who own the specific station surveillance procedures

are responsible for scheduling and implementing those surveillances.

1.6 ACCEPTANCE CRITERIA The acceptance criteria for the Inservice Testing pump and valve tests is contained in the implementing surveillance procedures.

TRM Inservice Testing Program Appendix H BRAIDWOOD UNITS 1 & 2 4 of 4 Revision 59 Technical Requirements Manual

1.7 LCOARS/COMPENSATORY MEASURES In the event a surveillance is failed, the Shift Manager shall be notified immediately. The Shift Manager shall determine the OPERABILITY status and implement a LCOAR if applicable. In

addition, an Issue Report (IR) may need to be generated to provide proper tracking and resolution of noted problems

associated with the implementation of this Program.

1.8 REPORTING REQUIREMENTS Pump and valve test records shall be maintained at the plant.

1.9 CHANGE CONTROL Changes to this Program, other than editorial changes, shall include a 10CFR50.59 Review and Station Qualified Review (SQR).

The SQR composition shall include Regulatory Assurance Department in all cases. As a part of the SQR, Byron and Braidwood Plant Operations Review Committee (PORC) approval is required as determined by the Regulatory Assurance Manager. Byron and Braidwood shall implement the same changes to Appendix H unless the change being implemented at Braidwood has been reviewed and determined no to be applicable to Byron.

TRM Steam Generator Program Appendix IBRAIDWOOD UNITS 1 & 21of 9Revision 89 Technical Requirements Manual STEAM GENERATOR PROGRAM BRAIDWOOD TABLE OF CONTENTS SECTION TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS 1.4 PROGRAM DESCRIPTION 1.5 PROGRAM IMPLEMENTATION 1.6 ACCEPTANCE CRITERIA 1.7 LCOARS/COMPENSATORY MEASURES 1.8 REPORTING REQUIREMENTS 1.9 CHANGE CONTROL TRM Steam Generator Program Appendix IBRAIDWOOD UNITS 1 & 22of 9Revision 89 Technical Requirements Manual1.1PURPOSE This Program verifies the tube integrity of the Steam Generators (SGs) by performing inspections and tube plugging in accordance with Technical Specification (TS) 3.4.19, "Steam Generator (SG)

Tube Integrity," and the Steam Generator Program. The Steam

Generator Program is defined by TS 5.5.9, NEI 97-06 and its associated EPRI Steam Generator Management Program Guidelines.

TS 5.6.9, "Steam Generator (SG) Tube Inspection Reports,"

provides the SG reporting requirements.

1.2REFERENCES

1.Technical Specifications:a.5.5.9, "Steam Generator (SG) Program"b.5.6.9, "Steam Generator (SG) Tube Inspection Reports"c.3.4.13, "RCS Operational LEAKAGE" d.3.4.19, "Steam Generator (SG) Tube Integrity"2.Update Final Safety Analysis Report Sections:a.5.4.2, "Steam Generators"b.15.1.5, "Steam System Piping Failure"c.15.6.3, "Steam Generator Tube Rupture"3.Exelon Generation Company, LLC, Quality Assurance Topical Report4.ASME Boiler and Pressure Vessel Code:a.Section V, Nondestructive Examination, 2001 Edition through 2003 Addendab.Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 2001 Edition through 2003 Addenda5.American Society for Nondestructive Testing (ASNT): "Standard for Qualification and Certification of

Nondestructive Testing Personnel, CP-189, 1995 Edition" TRM Steam Generator Program Appendix IBRAIDWOOD UNITS 1 & 23of 9Revision 89 Technical Requirements Manual6.General Design Criteria (GDC) of Appendix A to 10CFR50:a.GDC-14b.GDC-15c.GDC-30d.GDC-31e.GDC-327.Nuclear Energy Institute (NEI) Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler:a.TSTF-449, Revision 4b.TSTF-510, Revision 28.Draft Regulatory Guide 1.121, "Bases for Plugging Degraded PWR Steam Generator Tubes"9.Maintenance Rule Performance Criteria RC-2, "Remove Heat from Reactor to Steam Generators Including Steam Generator

Integrity"10.NEI 97-06 Steam Generator Program Guidelines11.EPRI PWR Steam Generator Examination Guidelines12.EPRI Primary to Secondary Leak Guidelines13.EPRI Steam Generator Integrity Guidelines14.EPRI Steam Generator In Situ Pressure Test Guidelines 15.EPRI Steam Generator Secondary Water Chemistry Guidelines16.EPRI Steam Generator Primary Water Chemistry Guidelines1.3DEFINITIONS AND/OR ACRONYMS1.IMPERFECTION -An exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy current testing

indications

!20% of the nominal wall thickness, if detectable, may be considered as imperfections.

TRM Steam Generator Program Appendix IBRAIDWOOD UNITS 1 & 24of 9Revision 89 Technical Requirements Manual2.DEGRADATION -A service induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a

tube.3.DEGRADED TUBE -A tube containing imperfections 20% of the nominal tube wall thickness caused by degradation.4.DEFECT -An imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.5.PLUGGING LIMIT-The imperfection depth at or beyond which the tube shall be removed from service by plugging. The plugging limit imperfection depth for the tubing isequal

to 40% of the nominal wall thickness.

For Unit 2 only, this definition does not apply to service-induced flaws identified in the portion of the tube below 14.01inches from the top of the tubesheet. Service-induced flaws found in the portion of the tube below 14.01inches

from the top of the tubesheet do not require plugging.

For Unit 2 only, service-induced flaws identified in the portion of the tube from the top of the tubesheet to 14.01 inches below thetop of the tubesheet shall be plugged upon detection.6.Deleted.

TRM Steam Generator Program Appendix IBRAIDWOOD UNITS 1 & 25of 9Revision 89 Technical Requirements Manual7.DEGRADATION ASSESSMENT -An assessment of degradation performed prior to an upcoming outage to determine the type and location of flaws to which the tubes may be susceptible

and to determine which inspection methods need to be employed and at what locations. The assessment includes appropriate inspection plans, inspection methods and

inspection intervals for the applicable degradation

mechanisms identified.8.CONDITION MONITORING -An evaluation of the "as found" condition of the tubing during a SG inspection outage with

respect to the performance criteria for structural integrity

and accident induced leakage prior to the plugging of tubes.9.OPERATIONAL ASSESSMENT -An evaluationthat projects the condition of the tubes from the "as-left" condition exiting

a SG inspection outage to the next SG inspection with

respect to the performance criteria for structural integrity and accident induced leakage following plugging of tubes.1.4PROGRAM DESCRIPTION This Program verifies the tube integrity of the SGs through

periodic eddy current inspections. The Bases for this Program and TS Section were established by NEI TSTF-449& TSTF-510(References

7.a & 7.b) and NEI 97-06 (Reference 10) and its referenced EPRI Guidelines (References 11 through 16). The SG Program provides a means to detect and plug degradation of SG tubes in order to

maintain the steam generator performance criteria for tube

structural integrity, accident induced leakage, and operational

leakage as delineated in TS 5.5.9 and NEI 97-06.1.5PROGRAM IMPLEMENTATION A SG Program has been established and implemented to ensure that

SG tube integrity is maintained. The SG Program is implemented through Exelon SG Program administrative and surveillance procedures to ensure compliance with the requirements of TS

3.4.19, TS 5.5.9, NEI 97-06 and its associated EPRI Guidelines.

The SG Program includes the following provisions:

TRM Steam Generator Program Appendix IBRAIDWOOD UNITS 1 & 26of 9Revision 89 Technical Requirements Manual1.Condition monitoring assessments are performed during each SG inspection to evaluate the "as-found" condition of the tubes with respect to the SG performance criteria for

structural integrity and accident induced leakage as determined from the inservice inspection results.2.SG integrity is maintained by meeting the performance criteria for tube structural integrity, accident induced leakage and operational leakage. The SG Program procedures implement the performance criteria that are delineated in TS 5.5.9.b and NEI 97-06. Meeting the SG performance

criteria provides reasonable assurance of maintaining tube

integrity at normal and accident conditions.3.Tubes found by inservice inspection that contain flaws that are equal to or greater than 40% of the nominal tube wall

thickness are plugged. For Unit 2 only, service-induced

flaws identified in the portion of the tube from the top of the tubesheet to 14.01inches below the top of the

tubesheet are plugged upon detection. For Unit 2 only, service-induced flaws found in the portion of the tube below 14.01inches fromthe top of the tubesheet do not

require plugging. 4.Periodic SG tube inspections are performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial and circumferential cracks) that may be present along the length of the tube, from the tube-to-

tubesheet weld at the tube inlet to the tube-to-tubesheet

weld at the tube outlet, and that may satisfy the applicable tube plugging criteria. For Unit 2 only, the portion of the tube below 14.01inches from the top of

tubesheet is excluded. The tube-to-tubesheet weld is not

part of the tube. The inspection scope, inspection methods

and inspection intervals are determined by a degradation assessment that is performed in accordance with TS 5.5.9.d and NEI 97-06 to ensure that SG integrityis maintained

until the next SG inspection.

TRM Steam Generator Program Appendix IBRAIDWOOD UNITS 1 & 27of 9Revision 89 Technical Requirements Manual5.Operational primary-to-secondary leakage monitoring is performed in accordance with TS 3.4.13, NEI 97-06 and EPRI Primary to Secondary Leak Guidelines (Reference 12).6.There are no approved tube repair methods for the Units1 and 2 SGs.

The Engineering Programs Department is the owner of the SG

Program. The site Chemistry and Operations Departments are

responsible for monitoring and responding to operational primary to secondary leakage. The site Chemistry Department is responsible for implementing the primary water and secondary

water chemistry programs as described in References 15 and 16.1.6ACCEPTANCE CRITERIA1.A tube with an imperfection depth greater than or equal to 40% of the nominal tube wall thickness shall be plugged.

For Unit 2 only, service-induced flaws found in the portion of the tube below 14.01inches from the top of the tubesheet do not require plugging.

For Unit 2 only, service induced flaws identified in the portion of the tube from thetop of the tubesheet to 14.01

inches below the top of the tubesheet shall be plugged upon detection.2.Deleted.3.SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage and operational leakage as delineated in TS

5.5.9.b.4.For Unit 1, the maximum equivalent plugging level is 5% per SG.5.For Unit 2, the maximum equivalent plugging level is 5% per SG.

TRM Steam Generator Program Appendix IBRAIDWOOD UNITS 1 & 28of 9Revision 89 Technical Requirements Manual1.7LCOARS/COMPENSATORY MEASURES1.If a SG performance criterion is exceeded, reports shall be submitted to the NRC as required by 10 CFR 50.72 and 50.73, including a root cause evaluation identifying the performance criterion exceeded and an Operational Assessment establishing

the basis for the next operating cycle.2.The Shift Manager shall be notified immediately for any of the conditions identified below. The Shift Manager shall

determine OPERABILITY status and implement a LCOAR as

applicable. In addition, an Issue Report (IR) may need to be

generated to provide proper tracking and resolution of noted problems associated with the implementation of this Program.a.Primary-to-secondary leakage not within limit.

b.One or more SG tubes satisfying the tube plugging criteria and not plugged in accordance with the SG Program.c.A SG performance criterion is exceeded.d.SG Tube integrity is not maintained.1.8REPORTING REQUIREMENTS1.Following each inservice inspection of SG tubes performed in accordance with TS 5.5.9, a report of inspection results shall be submitted to the NRC within 180 days after initial

entry into MODE 4 in accordance with TS 5.6.9.2.An inservice summary report shall be submitted to the NRC and IEMA within 90 days of the completion of each refueling

outage when SG inspections are performed, as required by ASME

Section XI IWA-6000.3.The Steam Generator Surveillance Program effectiveness is monitored by Maintenance Rule Criteria RC-2.

The Engineering Programs Department is responsible for preparing

and submitting the above reports.

TRM Steam Generator Program Appendix IBRAIDWOOD UNITS 1 & 29of 9Revision 89 Technical Requirements Manual1.9CHANGE CONTROL Changes to this Program, other than editorial changes, shall include a 10CFR50.59 Review and a Station Qualified Review (SQR).

The SQR composition shall include Regulatory Assurance Department in all cases. As a part of the SQR, Byron and Braidwood Plant

Operations Review Committee (PORC) approval is required as

determined by the Regulatory Assurance Manager. Byron and Braidwood shall implement the same change unless the change being implemented at Braidwood has been reviewed and was determined not tobe applicable to Byron.

TRM Secondary Water Chemistry Program Appendix J BRAIDWOOD UNITS 1 & 2 1 of 5 Revision 1 Technical Requirements Manual SECONDARY WATER CHEMISTRY PROGRAM BRAIDWOOD TABLE OF CONTENTS SECTION TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS 1.4 PROGRAM DESCRIPTION

1.5 PROGRAM IMPLEMENTATION 1.6 ACCEPTANCE CRITERIA 1.7 LCOARS/COMPENSATORY MEASURES

1.8 REPORTING REQUIREMENTS 1.9 CHANGE CONTROL

TRM Secondary Water Chemistry Program Appendix J BRAIDWOOD UNITS 1 & 2 2 of 5 Revision 1 Technical Requirements Manual

1.1 PURPOSE

In accordance with Technical Specification (TS) 5.5.10, "Secondary Water Chemistry Program." This Program provides controls for monitoring secondary water chemistry in order to inhibit steam generator tube degradation.

1.2 REFERENCES

1. Technical Specification 5.5.10, "Secondary Water Chemistry Program"

2. UFSAR Section 5.4.2.1.3, and 10.3.3

3. Electric Power Research Institute, PWR Secondary Water Chemistry Guidelines

4. Westinghouse Guidelines for Secondary Water Chemistry, February, 1985

1.3 DEFINITIONS AND/OR ACRONYMS

1. SECONDARY SYSTEM CHEMISTRY PARAMETERS - Chemical impurities in the secondary system have the potential to create

conditions harmful to steam generator materials. Carefully

controlling steam generator chemistry parameters minimizes material degradation.

Parameters that cause rapid corrosion cannot be exceeded for more than brief periods at power. Power reductions or shutdown is required within set times of exceeding limits on these critical parameters.

2. Pressurized Water Reactor - PWR 3, Electric Power Research Institute - EPRI

4. Institute of Nuclear Power Operations - INPO TRM Secondary Water Chemistry Program Appendix J BRAIDWOOD UNITS 1 & 2 3 of 5 Revision 1 Technical Requirements Manual 1.4 PROGRAM DESCRIPTION The Secondary Chemistry Monitoring Program states chemical parameters which can indicate corrosive conditions and provides concentration limits for each parameter. These secondary chemistry guidelines were derived from Reference 3. Station procedures outline who is responsible for what actions and describes how other documents interact with this Program.

This Program provides controls for monitoring secondary water

chemistry to inhibit Steam Generator tube degradation. The Program includes:

1. identification of a sampling schedule for critical variables and control points for these variables;

2. identification of the procedures used to measure the values of the critical variables;

3. identification of process sampling points which shall include monitoring the discharge of the condensate pumps for

evidence of condenser inleakage;

4. procedures for the recording and management of data;

5. procedures defining corrective actions for all out of specification chemistry conditions; and

6. procedures identifying the authority responsible for the interpretation of the data and the sequence and timing of

corrective actions.

1.5 PROGRAM IMPLEMENTATION The requirements of the Program apply at all times.

1. The sampling schedule for the critical variables and control points for these variables is located in appropriate station procedures. The department responsible for this action is the Chemistry Department.

2. A means to measure the values of the critical variables will be located in appropriate station procedures. The

Chemistry Department is responsible for revising and implementing these procedures.

TRM Secondary Water Chemistry Program Appendix J BRAIDWOOD UNITS 1 & 2 4 of 5 Revision 1 Technical Requirements Manual 3. Process sampling points are identified in appropriate station procedures and include the condensate pump discharge for evidence of a condenser leak. The Chemistry Department

maintains a sample point book which contains additional sampling points. The Chemistry Department is responsible for this action.

4. The recording and management of the data is controlled by appropriate station procedures and is the responsibility of the Chemistry Department.

5. The definitions for corrective actions for all out of specification chemistry conditions are in appropriate

station procedures and are the responsibility of the Chemistry Department with support from the Operations and

Radiation Protection Departments.

6. The Chemistry Department shall be responsible for the interpretation of the data and the sequence and timing of

corrective actions. This shall be performed with required support from the Operating, Radiation Protection, and System Engineering Departments.

1.6 ACCEPTANCE CRITERIA This Program is based on Reference 3 and acceptance criteria are incorporated into appropriate station procedures.

1.7 LCOARS/COMPENSATORY MEASURES The compensatory measures for exceeding secondary water chemistry parameters can be identified in appropriate station procedures.

In addition, a Problem Identification Form (PIF) may need to be generated to provide proper tracking and resolution of noted

problems associated with the implementation of this Program.

TRM Secondary Water Chemistry Program Appendix J BRAIDWOOD UNITS 1 & 2 5 of 5 Revision 1 Technical Requirements Manual 1.8 REPORTING REQUIREMENTS To assure corporate and station steam generator chemistry objectives are met, an ongoing review of secondary water chemistry will be conducted by the Chemistry Department. The Chemistry Supervisor and/or their designee is responsible for a monthly review of key program parameters, chosen by the Chemistry Supervisor and /or their designee. The Program's effectiveness

will be measured against recognized industry standards, such as INPO standards (or other comparable standards).

The Chemistry Department is additionally responsible for reporting and reviewing programmatic failures through an approved station problem identification process.

1.9 CHANGE CONTROL

Changes to this Program, other than editorial changes, shall require a 10CFR50.59 evaluation and an Independent Technical Review (ITR). The ITR composition shall include Regulatory Assurance in all cases. As a part of the ITR, for a change to this Program, concurrence from Byron and Braidwood Plant

Operations Review Committee (PORC) approval is required. The concurrence shall be that Byron is implementing the same change or that the change has been reviewed and determined not to be applicable to Byron.

SECTION 1.1 1.2 1.3 1.4 1.5 1.6 1. 7 1.8 1.9 TRM Ventilation Filter Testing Program Appendix K VENTILATION FILTER TESTING PROGRAM BRAIDWOOD TABLE OF CONTENTS TITLE PURPOSE REFERENCES DEFINITIONS AND/OR ACRONYMS PROGRAM DESCRIPTION PROGRAM IMPLEMENTATION ACCEPTANCE CRITERIA LCOARS/COMPENSATORY MEASURES REPORTING REQUIREMENTS CHANGE CONTROL BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 1 of 15 Revision 65 1.1 PURPOSE TRM Ventilation Filter Testing Program Appendix K The purpose of this Program is to provide guidelines for performing surveillance testing of Technical Specification (TS) 5.5.11, "Ventilation Filter Testing Program (VFTP)" HVAC System Filters at Braidwood Station.

1.2 REFERENCES

1. Technical Specification Section 5.5.11, "Ventilation Filter Testing Program (VFTP)" 2. USNRC Regulatory Guide 1.52, Rev. 2, March 1978 3. ANSI N510 1980 4. ASTM D 3803-1989, "Standard Test Method for Nuclear Grade Activated Carbon" 5. UFSAR Appendix A 1.3 DEFINITIONS AND/OR ACRONYMS 1. Ventilation Filter Testing Program -VFTP 2. High Efficiency Particulate Air -HEPA 1.4 PROGRAM DESCRIPTION This Program implements the following required testing of Engineered Safety Feature (ESE) ventilation filter systems at the frequencies specified in accordance with References 2 and 3. 1. Demonstrate for each of the ESF filter systems that an in-place test of the High Efficiency Particulate Air (HEPA) filters shows a penetration when tested in accordance with References 2 and 3 at the system flow rate, specified in Table l, Part 1. 2. Demonstrate for each of the ESE filter systems that an in place test of the charcoal absorber shows a bypass leakage within limits when tested in accordance with References 2 and 3 at the system flow rated specified in Table l, Part 2. BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 2 of 15 Revision 65 Ventilation Filter Testing Program Appendix K 3. Demonstrate for each of the ESF filter systems that a laboratory test of a sample of the charcoal absorber, when obtained as described in Reference 2, shows the methyl iodide penetration less than the value specified in Table 1, Part 3, when tested in accordance with References 2, 3 and 4 at a temperature of 30°C and Relative Humidity CRH) specified in Table 1, Part 3. 4. Demonstrate for each of the ESF filter systems that the pressure drop across the combined HEPA filters and the charcoal adsorbers is < 6 inches of water gauge when tested in accordance with References 2 and 3 at the system flow rate, specified in Table 1, Part 4. 5. Demonstrate for each of the ESF filter systems that a bypass leakage test of the 1) combined HEPA filters and damper or 2) combined charcoal filter and damper leakage shows a total bypass leakage within acceptable limits at the system flow rate specified in Table 1, Part 5. 6. Demonstrate that the heaters for each of the ESF filter systems dissipate the value specified in Table l, Part 6, when tested in accordance with References 3 and 5. 1.5 PROGRAM IMPLEMENTATION Technical Section Filter Testing. Inspection and Repair 1. Control Room Ventilation (VC) System: a. At least once per 18 months (+ 25% tolerance) or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housing, or (2) following painting, fire or chemical release in any ventilation zone co111T1Unicating with the Emergency Makeup System filter plenum shall meet the following requirements:

1. Verify that each HEPA and charcoal bank BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual satisfies the inplace penetration testing acceptance criteria of less than 0.05% and less than 1.0%, respectively; and that the system flow rate is 5400 cfm and 6600 cfm for the Emergency Makeup System using test procedure guidance in accordance with References 2 and 3; 3 of 15 Revision 65 Ventilation Filter Testing Program Appendix K 2. Verify, within 31 days (+ 25% tolerance) after removal, that a laboratory analysis of a representative carbon sample from the Emergency Makeup System obtained in accordance with Reference 2 meets the laboratory testing criteria for a methyl iodide penetration of less than 2.0% when tested according to Reference 4 at a temperature of 30 °C and a RH of 70%; and 3. Verify a system flow rate 5400 cfm and 6600cfm for the Emergency Makeup System and 44,550 cfm and 54,450 cfm for the Recirculation System when tested in accordance with Reference

3. b. After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months (+ 25% tolerance) of Emergency Makeup System operation, verify, within 31 days (+ 25% tolerance) after removal, that a laboratory analysis of a representative carbon sample from the Emergency Makeup System obtained in accordance with Reference 2, meets the laboratory testing criteria for a methyl iodide penetration of less than 2.0% when tested according to Reference 4 at a temperature of 3Q<>C and a RH of 70%. c. At least once per 18 months (+ 25% tolerance) by: 1. verifying the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6.0 inches Water Gauge while operating the Emergency Makeup System at a flow rate 5400 cfm and 6600 cfm when tested in accordance with References 2 and 3. 2. verifying that the heaters 24.5 kW and 29.9 kW when tested in accordance with Reference 3 and the exceptions noted in Reference

5. BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 4 of 15 Revision 65

d. e. f. TRM Ventilation Filter Testing Program Appendix K After each complete or partial replacement of a HEPA filter bank in the Emergency Makeup System, verify that the affected HEPA filter bank satisfies the inplace penetration testing acceptance criteria of less than 0.05% in accordance with Reference 3 while operating the Emergency Makeup System at a flow rate of 5400 cfm and 6600 cfm. After each complete or partial replacement of a charcoal adsorber bank in the Emergency Makeup System, verify that the affected charcoal adsorber bank satisfies the inplace penetration testing acceptance criteria of less than 1% in accordance with Reference 3 while operating the system at a flow rate 5400 cfm and 6600 cfm. At least once per 18 months (+ 25% tolerance) or (1) after any structural maintenance on the charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone corrmunicating with the recirculation charcoal adsorber by: BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 5 of 15 Revision 65 Ventilation Filter Testing Program Appendix K 1. verifying that the recirculation charcoal adsorber plenum satisfies the inplace penetration testing acceptance criteria of less than 2% total bypass, using the test procedure guidance in accordance with References 2 and 3, while the system flow rate is 44,550 cfm and 54,450 cfm for the recirculation charcoal adsorber;

2. verifying, within 31 days (+ 25% tolerance) after removal, that a laboratory analysis of a representative carbon sample from the recirculation charcoal adsorber obtained in accordance with Reference 2 meets the laboratory testing criteria for a methyl iodide penetration of less than 4% when tested according to Reference 4 at a temperature of 30 °C and a RH of 70%; and 3. verifying a system flow rate of 44,550 cfm and 54,450 cfm for the Recirculation Charcoal Adsorber when tested in accordance with Reference

3. g. After each complete or partial replacement of a charcoal adsorber bank in the Recirculation Charcoal Absorber System by verifying that the charcoal adsorber bank satisfies the inplace penetration testing acceptance criteria of less than 0.1% in accordance with Reference 3 while operating at a system flow rate of 44,550 cfm and 54,450 cfm. h. After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months (+ 25% tolerance) of Recirculation Charcoal Adsorber System operation by verifying, within 31 days (+ 25% tolerance) after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Reference 2, meets the laboratory testing criteria for a methyl iodide penetration of less than 4% when tested according to Reference 4 at a temperature of 300C and a RH of 70%. BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 6 of 15 Revision 65 Ventilation Filter Testing Program Appendix K 2. Non-Accessible Area Exhaust Filter Plenum Ventilation System: a. At least once per 18 months (+ 25% tolerance) or Cl) after any structural maintenance on the HEPA filter or charcoal adsorber housing, or (2) following painting, fire or chemical release in any ventilation zone co11111unicating with the exhaust filter plenum by: BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 1. verifying that each HEPA and charcoal bank satisfies the inplace penetration and bypass leakage testing acceptance criteria of less than 1%, using the test procedure guidance in accordance with References 2 and 3. while the flow rate 60,210 cfm and 73,590 cfm for the train; 2. verifying, within 31 days (+ 25% tolerance) after removal, that a laboratory analysis of a representative carbon sample from each bank of adsorbers of the train obtained in accordance with Reference 2 meets the laboratory testing criteria for a methyl iodide penetration of less than 4.5% (and administratively controlled to less than 3% to accorrmodate total bypass leakage margin) when tested according to Reference 4 at a temperature of 30 °c and a RH of 70%; and 3. verifying a system flow rate of 60,210 cfm and 73,590 cfm through the train through the exhaust filter plenum when tested in accordance with Reference

3. 4. verifying that with 2 of 3 trains operatin at a flow rate 60,210 cfm and 73,590 cfm for each train and exhausting through the HEPA filters and charcoal adsorbers, with 2 main VA supply and 2 main VA exhaust fans operating, the total charcoal bypass flow of the system including damper bypass leakage at an additional 0.5 inches water gauge differential pressure above actual differential pressure for all three train (two on-line and one in standby) is less than or equal to 4%. 7 of 15 Revision 65 TRM Ventilation Filter Testing Program Appendix K 5. verifying that with 2 of 3 trains operatin at a flow rate of 60,210 cfm and 73,590 cfm for each train and exhausting through the HEPA filters and charcoal adsorbers, with 2 main VA supply and 2 main VA exhaust fans operating, the total HEPA bypass flow of the system including damper bypass leakage at an additional 0.5 inches wter gauge differential pressure above actual differential pressure for all three train (two on-line and one in standby) is less than or equal to 1%. 6. verifying, with a system flow 60,210 cfm and 73,590 cfm through the train and exhaust filter plenum, that the flow rate in each filter bank 20,070 cfm and 24,530 cfm. b. After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months (+25% tolerance) of charcoal adsorber operation by verifying, within 31 days (+ 25% tolerance) after removal, that a laboratory analysis of a representative carbon sample obtained from each bank of adsorbers of the train in accordance with Reference 2, meets the laboratory testing criteria for a methyl iodide penetration of less than an average of 4.5% (and administratively controlled to less than 3% I to accorrrnodate total bypass leakage margin) when tested according to Reference 4 at a temperature of 3D°C and a RH 70%. c. At least once per 18 months (+25% tolerance) by verifying for each filter bank of the train that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6.0 inches Water Gauge while operating the exhaust filter plenum at a flow rate 60,210 cfm and 73,590 cfm when tested in accordance with References 2 and 3. d. After each complete or partial replacement of a HEPA filter bank by verifying that the exhaust filter plenum satisfies the inplace penetration testing acceptance criteria of less than 1% in accordance with Reference 3 while operating at a flow rate 60,210 cfm and 73,590 cfm through the train. BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 8 of 15 Revision 65

e. TRM Ventilation Filter Testing Program Appendix K After each complete or partial replacement of a charcoal adsorber bank by verifying that the exhaust filter plenum satisfies the inplace penetration testing acceptance criteria of less than 1% in accordance with Reference 3 while operating at a system flow rate of 60,210 cfm and 73,590 cfm through the train. 3. Fuel Handling Building Exhaust Filter Plenums: a. At least once per 18 months (+ 25% tolerance) or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housing, or (2) following painting, fire or chemical release in any ventilation zone corrmunicating with the system by: BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 1. verifying that the Fuel Handling Building Exhaust Filter Plenum satisfies the inplace penetration testing acceptance criteria of less than 1% when using the test procedure guidance in accordance with References 2 and 3 while the system flow rate 18,900 cfm 23,100 cfm; 2. verifying, within 31 days (+ 25% tolerance) after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Reference 2 meets the laboratory testing criteria for a methyl iodide penetration of less than 10% when tested according to Reference 4 at a temperature of 30 °C and a RH of 95%; 3. verifying a flow rate 18,900 cfm and 23,100 cfm through the Fuel Handling Building Exhaust Filter Plenum during operation when tested in accordance with Reference 3; and 9 of 15 Revision 65

b. c. d. e. TRM Ventilation Filter Testing Program Appendix K 4. verifying that with the system operating at a flow rate 18,900 cfm and 23,100 cfm and exhausting through the HEPA filters and charcoal adsorbers, with 2 main VA supply and 2 main VA exhaust fans operating, the total HEPA bypass flow of the system including damper bypass leakage at an additional 0.5 inches water gauge differential pressure above actual differential pressure is less than or equa to 1% and the total charcoal bypass flow o the system including damper bypass leakage is less than or equal to 1%. After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months (+25% tolerance) of charcoal adsorber operation by verifying, within 31 days (+ 25% tolerance) after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Reference 2, meets the laboratory testing criteria for a methyl iodide penetration of less than 10% when tested according to Reference 4 at a temperature of 30°C and a RH of 95%. At least once per 18 months (+25% tolerance) by verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6.0 inches Water Gauge while operating the exhaust filter plenum at a flow rate of 18,900 cfm and 23,100 cfm when tested in accordance with References 2 and 3. After each complete or partial replacement of a HEPA filter bank by verifying that the Fuel Handling Building Exhaust Filter Plenum satisfies the inplace penetration testing acceptance criteria of less than 1% in accordance with Reference 3 while operating at a system flow rate 18,900 cfm 23,100 cfm; and After each complete or partial replacement of a charcoal adsorber bank by verifying that the Fuel Handling Building Exhaust Filter Plenum satisfies the inplace penetration testing acceptance criteria of less than 1% in accordance with Reference 3 while operating at a system flow rate of 18,900 cfm and 23,100 cfm. BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 10 of 15 Revision 65 1.6 ACCEPTANCE CRITERIA TRM Ventilation Filter Testing Program Appendix K Acceptance criteria is listed in Table 1. 1.7 LCOARS/COMPENSATORY MEASURES In the event any of the acceptance criteria is not met, the Shift Manager will irrmediately be notified.

The Shift Manger shall determine OPERABILITY status and implement a LCOAR as applicable.

In addition, an Issue Report may be generated to provide proper tracking and resolution of noted problems associated with the implementation of this Program. 1.8 REPORTING REQUIREMENTS Not applicable.

1.9 CHANGE CONTROL Changes to this Program, other than editorial changes, shall require a 10 CFR 50.59 Review and a Station Qualified Review CSOR). The SOR composition shall include Regulatory Assurance Department in all cases. As a part of the SOR, Byron and Braidwood Plant Operations Review Corrmittee (PORC) approval is required as determined by the Regulatory Assurance Manager. Byron and Braidwood shall implement the same change unless the change being implemented at Braidwood has been reviewed and was determined not to be applicable to Byron. BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 11 of 15 Revision 65 TABLE 1 TRM Ventilation Filter Testing Appendix K VENTILATION FILTER TESTING PROGRAM (VFTP) Part 1 ESF Ventilation System Control Room Ventilation CVC) Filtration System (makeup) Nonaccessable Area Exhaust Filter Plenum Ventilation System (after structural maintenance of the HEPA filter housings)

Nonaccessible Area Exhaust Filter Plenum Ventilation System (for reasons other than structural maintenance of the EPA filter housings)

Fuel Handling Building Exhaust Filter Plenum (FHB) Ventilation System BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual Flow Rate PenetratiQD 5400 cfm and <0.05% :5 6600 cf m 60,210 cfm and < 1% :5 73,590 cfm per train, and 20,070 cfm and 24,530 cfm per bank 60,210 cfm and < 1% 73,590 cfm per train 18,900 cfm and < 1% 23,100 cfm 12 of 15 Revision 65 Part 2 ESF Ventilat]Qn VC Filtration System (makeup) VC Filtration System (recirculation, charcoal bed after complete or partial replacement)

Nonaccessible Area Exhaust Filter Plenum Ventilation System (after structural maintenance of the charcoal adsorber housings)

Nonaccessible Area Exhaust Filter Plenum Ventilation System (for reasons other than structural maintenance of the charcoal adsorber housings)

FHB Ventilation System BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual Flow Rate TRM Ventilation Filter Testing Program Appendix K 5400 cfm and < 1% 6600 cf m 44,550 cfm < 0.1% and 54,450 cfm 60,210 cfm < 1% and 73,590 cfm per train, and 20,070 cfm and 24,530 cfm per bank 60,210 cfm < 1% and 73,590 cfm per train 18,900 cfm < 1% and 23,100 cfm per train 13 of 15 Revision 65 Part 3 ESE Ventilation VC Filtration System (makeup) VC Filtration System (recirculation)

Nonaccessible Area Exhaust Filter Plenum Ventilation System FHB Ventilation System Part 4 EFS VC Filtration System (makeup) Nonaccessible Area Exhaust Filter Plenum Ventilation System FHB Ventilation System BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual TRM Ventilation Filter Testing Program Appendix K Penetration .Bti 2.0% 70% 4% 70% 4.5% 70% 10% 95% Flow Rate 5400 cfm and 6600 cf m 60,210 cfm and 73,590 cfm per train 18,900 cfm and 23,100 cfm 14 of 15 Revision 65 Part 5 ESF Ventilation System Nonaccessible Area Exhaust Filter Plenum Ventilation System FHB Ventilation System VC Filteration System (recirculation for reasons other than complete or partial charcoal bed replacement)

Part 6 ESF Ventilation System VC Filtration System BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual TRM Ventilation Filter Testing Program Appendix K Flow Rate 60,210 cfm and 73,590 cfm per on-line train 18,900 cfm and :::; 23,100 cfm 44,550 cfm and :::; 54,450 Wattage 24.5 kW and 29.9 kW 15 of 15 Bypass 1% CHEPA) 4% C Cha rcoa 1) :::; 1% < 2% Revision 65 TRM Explosive Gas & Storage Tank Radioactivity Monitoring Program Appendix L BRAIDWOOD UNITS 1 & 2 1 of 7 Revision 44 Technical Requirements Manual EXPLOSIVE GAS AND STORAGE TANK RADIOACTIVITY MONITORING PROGRAM BRAIDWOOD

TABLE OF CONTENTS

SECTION TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS

1.4 PROGRAM DESCRIPTION 1.5 PROGRAM IMPLEMENTATION 1.6 ACCEPTANCE CRITERIA

1.7 LCOARS/COMPENSATORY MEASURES 1.8 REPORTING REQUIREMENTS 1.9 CHANGE CONTROL TRM Explosive Gas & Storage Tank Radioactivity Monitoring Program Appendix L BRAIDWOOD UNITS 1 & 2 2 of 7 Revision 44 Technical Requirements Manual

1.1. PURPOSE

In accordance with Technical Specification (TS) Specification 5.5.12, "Explosive Gas and Storage Tank Radioactive Monitoring Program". This Program provides controls for:

1. potentially explosive gas mixtures contained in the Waste Gas System;

2. the quantity of radioactivity contained in gas decay tanks; and 3. the quantity of radioactivity contained in unprotected outdoor liquid radwaste storage tanks.

The requirements of this Program dictate the contents of the implementing procedures.

1.2 REFERENCES

1. TS Specification 5.5.12, "Explosive Gas and Storage Tank Radioactivity Monitoring Program"

2. UFSAR Section 11.3.2.6

3. ODCM

4. Standard Review Plan 11.3, Branch Technical Position (BTP)

ETSB 11-5, "Postulated Radioactive Release due to Waste Gas

System Leak or Failure," in NUREG-0800, July 1981

5. 10CFR20, Appendix B, Table 2, Column 2

6. General Design Criterion 60 of Appendix A to 10CFR50

TRM Explosive Gas & Storage Tank Radioactivity Monitoring Program Appendix L BRAIDWOOD UNITS 1 & 2 3 of 7 Revision 44 Technical Requirements Manual 1.3 DEFINITIONS AND/OR ACRONYMS A WASTE GAS HOLDUP SYSTEM - Any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off-gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

PRIMARY COOLANT DEGASSING OPERATION - When preparing the plant for

MODE 5 prior to MODE 6, the Reactor Coolant is degassed to reduce the hydrogen concentrations. At the start of the degassing operation, the Volume Control Tank (VCT) gas space contains hydrogen and traces of fission gases. The operation involves opening the VCT vent, raising VCT water level to force gasses out of the tank, and closing the VCT vent.

MEMBER(S) OF THE PUBLIC - Include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors or vendors and persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

The SITE BOUNDARY - Be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

IMMEDIATELY - That the Required Actions should be pursued without

delay and in a controlled manner.

1.4 PROGRAM DESCRIPTION This Program ensures that the concentration of potentially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM is maintained below the flammability limits for hydrogen and oxygen.

Sample instruments with alarms are provided to alert operators to take compensatory measures to prevent the hydrogen and oxygen concentrations from reaching flammability limits. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of Reference 6.

TRM Explosive Gas & Storage Tank Radioactivity Monitoring Program Appendix L BRAIDWOOD UNITS 1 & 2 4 of 7 Revision 44 Technical Requirements Manual Restricting the quantity of radioactivity contained in each gas

decay tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting whole body exposure

to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem. This is consistent with Reference 4.

The quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tank's contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system is an amount that would result in concentrations less than the limits of Reference 5, 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 tank's contents.

The Radiation Protection Department shall be the Program owner with required support from the Operating, Chemistry, and System Engineering Departments.

1.5 PROGRAM IMPLEMENTATION The requirements of this Program apply at all times.

1. The concentration of hydrogen and oxygen in the WASTE GAS HOLDUP SYSTEM shall be determined to be within the acceptance criteria by continuously monitoring the waste

gases in the WASTE GAS HOLDUP SYSTEM with the hydrogen and oxygen monitors required by TRM LCO 3.3.e.

2. The quantity of radioactivity contained in each gas decay tank shall be determined, in accordance with the guidance

provided in Reference 4, to be within the acceptance criteria at least once per 7 days when radioactive materials

are being added to the tank, and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during PRIMARY COOLANT DEGASSING OPERATION.

3. The quantity of radioactive material contained in the Primary Water Storage Tank and any Outside Temporary Tanks

shall be determined to be within the acceptance criteria by analyzing a representative sample of the tank's contents at

least once per 7 days when radioactive materials are being added to the tank.

TRM Explosive Gas & Storage Tank Radioactivity Monitoring Program Appendix L BRAIDWOOD UNITS 1 & 2 5 of 7 Revision 44 Technical Requirements Manual If the supply and discharge piping to the Primary Water Storage Tanks are crosstied with flow for a sufficient duration, one sample of the Primary Water Makeup System may be used to represent the contents of each tank.

1.6 ACCEPTANCE CRITERIA

1. Explosive Gas Mixtures The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM

shall be 2% by volume whenever the hydrogen concentration is > 4% by volume.

2. Radioactivity Contained in Gas Decay Tanks The quantity of radioactivity contained in each gas decay tank shall be limited to 5 E+04 Curies of noble gases (considered as Xe-133 equivalent).

3. Radioactivity Contained in Unprotected Outdoor Liquid Radwaste Storage Tanks.

The quantity of radioactive material, excluding tritium and dissolved or entrained noble gases, shall be limited to the following:

a. Primary Water Storage Tank 2000 Curies when sampling 0A and 0B Primary Water Storage Tanks individually OR Primary Water Storage Tank 1000 Curies when obtaining one sample representing both tanks with 0A and 0B Primary Water Storage Tanks crosstied

b. Outside Temporary Tank 10 Curies

1.7 LCOARS/COMPENSATORY MEASURES

1. Explosive Gas Mixtures

a. With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM > 2% by volume but 4% by volume, when hydrogen is > 4% by volume, restore the oxygen concentration to 2% within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

TRM Explosive Gas & Storage Tank Radioactivity Monitoring Program Appendix L BRAIDWOOD UNITS 1 & 2 6 of 7 Revision 44 Technical Requirements Manual b. With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM > 4% by volume and the hydrogen concentration > 4% by volume, IMMEDIATELY suspend all

additions of waste gases to the system and reduce the concentration of oxygen to 4% by volume, then restore the oxygen concentration to 2% within the following 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

The department responsible for the above actions is the

Operating Department.

2. Radioactivity Contained in Gas Decay Tanks

With the quantity of radioactive material in any gas decay tank exceeding the acceptance criteria:

a. IMMEDIATELY suspend all additions of radioactive material to the tank, and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , reduce the

tank contents to within the limit; and

b. describe the events leading to this condition in the next Radioactive Effluent Release Report.

The department responsible for action a is the Operating Department, action b is the responsibility of the Radiation Protection Department.

3. Radioactivity Contained in Unprotected Outdoor Liquid Radwaste Storage Tanks

With the quantity of radioactive material in the Primary Water Storage Tank or any Outside Temporary Tank exceeding the acceptance criteria:

a. IMMEDIATELY suspend all additions of radioactive material to the tank;

b. within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the acceptance criteria; and

c. describe the events leading to this condition in the next Radioactive Effluent Release Report The Operations Department is responsible for actions a and b, and the Radiation Protection Department is responsible for action c.

TRM Explosive Gas & Storage Tank Radioactivity Monitoring Program Appendix L BRAIDWOOD UNITS 1 & 2 7 of 7 Revision 44 Technical Requirements Manual The Shift Manager shall determine OPERABILITY status and

implement a LCOAR as applicable. A Problem Identification Form (PIF) may need to be generated to provide proper

tracking and resolution of noted problems associated with the implementation of this Program.

1.8 REPORTING REQUIREMENTS This Program shall be reviewed every two years for technical accuracy and revision. The review shall be done by the Radiation Protection Department with input from the Operating, Chemistry, and System Engineering Departments.

Program failures shall be reported through an approved station problem identification process. The Operations Department will be

responsible for ensuring that Program failures have been reported.

1.9 CHANGE CONTROL Changes to this Program, other than editorial changes, shall include a 10CFR50.59 evaluation and an Independent Technical Review (ITR). The ITR composition shall include Regulatory

Assurance Department in all cases. As a part of the ITR, for a change to this Program, concurrence from Byron and Braidwood Plant Operations Review Committee (PORC) approval is required. The concurrence shall be that Byron is implementing the same change or that the change has been reviewed and determined not to be

applicable to Byron.

TRM Diesel Fuel Oil Testing Program Appendix M BRAIDWOOD UNITS 1 & 2 1 of 9 Revision 48 Technical Requirements Manual DIESEL FUEL OIL TESTING PROGRAM BRAIDWOOD TABLE OF CONTENTS

SECTION TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS

1.4 PROGRAM DESCRIPTION 1.5 PROGRAM IMPLEMENTATION 1.6 ACCEPTANCE CRITERIA

1.7 LCOARS/COMPENSATORY MEASURES 1.8 REPORTING REQUIREMENTS 1.9 CHANGE CONTROL TRM Diesel Fuel Oil Testing Program Appendix M BRAIDWOOD UNITS 1 & 2 2 of 9 Revision 48 Technical Requirements Manual

1.1 PURPOSE

The purpose of this Program is to provide guidance for implementation of Diesel Fuel Oil Testing at the Braidwood Station

as required by Technical Specification (TS) 5.5.13. This Program, through approved Exelon Nuclear, Braidwood Station, or Vendor procedures, ensures that delivered, new and stored diesel fuel oil meet the appropriate standards.

1.2 REFERENCES

1. Technical Specification 5.5.13, "Diesel Fuel Oil Testing Program" 2. ASTM Standards

a. D5452-98, "Particulate Contamination in Aviation Fuels by Laboratory Filtration," b. D1552-95, "Standard Test Method for Sulfur in Petroleum Products (High Temperature Method)" c. D975-98b, "Standard Specifications for Diesel Fuel Oils" d. D2622-98, "Standard Test Method for Sulfur in Petroleum Products by Wavelength Dispersive X-Ray Fluorescent Spectrometry" e. D4176-93, "Standard Test Method for Free Water and Particulate Contamination in Distillate Fuels (Visual Inspection Procedures)" f. D4057-95, "Standard Practice for Manual Sampling of Petroleum and Petroleum Products" g. D1298-99, "Standard Practice for Density, Relative density (Specific Gravity), or API Gravity of Crude

Petroleum and Liquid Petroleum Products by Hydrometer Method" h. D4294-98, "Standard Test Method for Sulfur in Petroleum Products by Energy-Dispersive X-Ray

Fluorescence Spectroscopy" i. D2709-96e, "Test Method for Water and Sediment in Distillate Fuels by Centrifuge" j. D1500-98, "Standard Test Method for ASTM Color of Petroleum Products (ASTM Color Scale)"

TRM Diesel Fuel Oil Testing Program Appendix M BRAIDWOOD UNITS 1 & 2 3 of 9 Revision 48 Technical Requirements Manual 1.3 DEFINITIONS AND/OR ACRONYMS

1. DELIVERED DIESEL FUEL - Any diesel fuel being delivered to Braidwood Station which is intended to be used by INSTALLED PLANT EQUIPMENT. Fuel is typically delivered by truck and is either blended at approximately 25% #1 grade and 75% #2 grade, or purchased such that the resultant fuel has an approximate 25% #1 to 75% #2 ratio (i.e. one truck load #1 to three truck loads #2). This blend can be used year-

around, but is intended to prevent winter gelling concerns.

Braidwood Station may also specify straight #2 fuel if desired, with optional anti-gel additives utilized for winter considerations. Delivered diesel fuel oil receives a cursory analysis of properties to give confidence that the truck indeed contains diesel fuel oil prior to adding it to any OUTDOOR BULK DIESEL FUEL OIL TANK. If fuel is being

delivered using the one truck load #1 to three truck loads #2 method to achieve the blend, it is recognized that the straight #1 fuel parameters may not meet the blend's specification. In this case, the fuel is still accepted since it is known that it will eventually be blended with #2 and the resultant further analyzed before use as described in the definition of "UNCERTIFIED" DIESEL FUEL OIL.

2. "UNCERTIFIED" DIESEL FUEL OIL - Any diesel fuel oil that has not been tested and found to meet the applicable acceptance

criteria for grade #2 diesel fuel oil and is to be added, or already is in, the INSTALLED PLANT EQUIPMENT's TANKS or the

OUTDOOR BULK DIESEL FUEL OIL TANKS. Fuel in the INSTALLED PLANT EQUIPMENT's TANKS or the OUTDOOR BULK DIESEL OIL TANKS can become "UNCERTIFIED" when samples are not found to meet fuel specification (following analysis of an optional confirmatory sample) or by adding DELIVERED or "UNCERTIFIED" FUEL to the tanks. In the event fuel is "UNCERTIFIED", actions are taken to either bring the fuel back into

specifications and/or prevent the fuel from being used until it is deemed "CERTIFIED".

3. "CERTIFIED" DIESEL FUEL OIL - Diesel fuel oil in any station diesel fuel oil tank which has previously been sampled, analyzed, and found to meet the applicable acceptance criteria for grade #2 diesel fuel oil. This fuel can be

stored in either the OUTDOOR BULK DIESEL FUEL OIL TANKS or tanks associated with the INSTALLED PLANT EQUIPMENT. This fuel is periodically sampled and analyzed. See Attachment A for test and test frequency.

TRM Diesel Fuel Oil Testing Program Appendix M BRAIDWOOD UNITS 1 & 2 4 of 9 Revision 48 Technical Requirements Manual

4. NEW FUEL OIL - Diesel fuel oil that has been sampled and tested in accordance with the requirements of TS 5.5.13 for

NEW FUEL OIL. TS 5.5.13 requires specific tests of fuel

oil prior to addition to storage tanks, e.g., 1) an API gravity or an absolute specific gravity, 2) a flash point and kinematic viscosity, and 3) a clear and bright appearance with proper color or a water and sediment content. Additional tests are required to verify other

properties of NEW FUEL OIL within 30 days following sampling and addition to storage tanks.

For the Emergency Diesel Generators (EDGs), the OUTDOOR BULK DIESEL FUEL OIL TANKS (one 50,000 gal. and one 125,000 gal.) are normally the source of "NEW" FUEL OIL

5. STORED FUEL OIL - Diesel fuel oil that has been sampled and tested in accordance with the requirements of TS 5.5.13 for

STORED FUEL OIL. Fuel oil degradation during long term storage shows up as an increase in particulate, due mostly to oxidation. Consequently, TS 5.5.13 requires STORED FUEL OIL to be tested for total particulate concentration every 31 days. For the EDGs, the inside storage tanks (each Unit 1 EDG is

provided with two 25,000 gal. inside storage tanks and each Unit 2 EDG is provided with one 50,000 gal. inside storage tank) are the source of the required "STORED" FUEL OIL.

6. INSTALLED PLANT EQUIPMENT - EDGs, Diesel-driven fire pump, Security diesel generator, Diesel-driven Auxiliary

Feedwater pump, Auxiliary boilers (note: Auxiliary boilers burn "CERTIFIED" or "UNCERTIFIED" fuel directly from the OUTDOOR BULK DIESEL FUEL OIL TANKS).

7. OUTDOOR BULK DIESEL FUEL OIL TANKS - Typically called 125K and 50K tanks (OD003T and OD012T respectively). These

tanks receive the delivered fuel and store it "UNCERTIFIED" until being "CERTIFIED" through analysis. Once "CERTIFIED" the fuel stored in these tanks is normally used to fill the tanks of the INSTALLED PLANT EQUIPMENT.

TRM Diesel Fuel Oil Testing Program Appendix M BRAIDWOOD UNITS 1 & 2 5 of 9 Revision 48 Technical Requirements Manual 1.4 PROGRAM DESCRIPTION The Diesel Fuel Oil Testing Program provides guidance for testing DELIVERED, NEW, and STORED DIESEL FUEL OIL. This Program includes

sampling and testing requirements as outlined in Attachment A which also may be contained in appropriate procedures, as well as acceptance criteria in accordance with the applicable standards.

This Program also describes preventative maintenance activities that are performed to ensure good fuel quality and tank condition

for certain INSTALLED PLANT EQUIPMENT TANKS.

1.5 PROGRAM IMPLEMENTATION This Diesel Fuel Oil Testing Program implements required sampling and analysis of DELIVERED, NEW, and STORED DIESEL FUEL OIL. The Program includes sampling and testing requirements as outlined in

Attachment A which also may be contained in appropriate procedures, as well as acceptance criteria, in accordance with applicable standards. This Program also describes preventative maintenance activities that are performed to ensure good fuel quality and tank condition for certain INSTALLED PLANT EQUIPMENT'S TANKS. This Program establishes the following:

1. Other properties of NEW FUEL OIL are within limits within 30 days following sampling in accordance with ASTM D4057-95 and

addition to storage tanks;

2. Total particulate concentration of the fuel oil is 10 mg/l when tested every 31 days in accordance with ASTM D5452-98.

3. Acceptability (certification) of "UNCERTIFIED" fuel oil and continued certification on a periodic basis in the fuel oil

storage tanks by determining that the fuel oil:

a. meets ASTM D975-98b specifications;

b. meets ASTM D5452-98 specification for particulate contamination;

c. meets Illinois EPA sulfur requirements and may be tested in accordance with ASTM D1552-95, ASTM D2622-

98, or ASTM D4294-98;

d. a flash point and kinematic viscosity is within limits:

TRM Diesel Fuel Oil Testing Program Appendix M BRAIDWOOD UNITS 1 & 2 6 of 9 Revision 48 Technical Requirements Manual e. API specific gravity or an absolute specific gravity within limits when tested in accoradance with ASTM

D1298-99;

f. water and sediment when tested in accordance with ASTM D2709-96e is within limits; and

g. a clear and bright appearance with when tested in accordance with ASTM D4176-93, and proper color when tested in accordance with ASTM D1500-98.

Actual testing for each individual tank may vary. The minimum testing schedule is shown in Attachment A. Actual fuel analysis performed is determined within specific Exelon Nuclear, Braidwood Station, or approved Vendor procedures.

4. 10 year OUTDOOR BULK DIESEL FUEL OIL TANK (0DO03T - 125K gallon tank and 0DO12T - 50K gallon tank) cleaning using a

Sodium hypochlorite (household bleach) solution or evaluated equivalent; and

5. 10 year EDG tank cleaning using a Sodium Hypochlorite (household bleach) solution or evaluated equivalent (Unit 1 has four 25,000 gallon (1DO01TA/B/C/D) and Unit 2 has two

50,000 gallon (2DO01TA/B) tanks); and

6. Periodic check for and removal of accumulated water from the EDG day tanks.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program frequencies.

The Braidwood Operating Department, Chemistry Departments, and Vendors are responsible for the implementation, performance, completion, and reporting of this Program.

1.6 ACCEPTANCE CRITERIA Acceptance criteria for the fuel used in the INSTALLED PLANT EQUIPMENT at Braidwood is specified in the applicable Exelon Nuclear, Braidwood Station, and Vendor procedures implemented by this Program.

TRM Diesel Fuel Oil Testing Program Appendix M BRAIDWOOD UNITS 1 & 2 7 of 9 Revision 48 Technical Requirements Manual 1.7 LCOARS/COMPENSATORY MEASURES In the event the diesel fuel oil does not meet the acceptance

criteria, the Shift Manager or designee shall be immediately notified. The Shift Manager or designee shall determine OPERABILITY status and implement a LCOAR(s) as applicable.

Typically, fuel stored in the 125K and 50K OUTDOOR BULK DIESEL FUEL OIL TANKS which does not meet acceptance criteria is declared "UNCERTIFIED" since there is not any LOCAR(s) associated with these tanks. Actions are taken to prevent "UNCERTIFIED" fuel from being used. A confirmatory sample should be analyzed in the event a sample is found to not meet the acceptance criteria. In addition, a Condition Report (CR) may need to be generated to provide proper tracking and resolution of noted problems associated with the implementation of this Program.

1.8 REPORTING REQUIREMENTS Analysis results are reported to Braidwood by Vendor.

1.9 CHANGE CONTROL Changes to this Program, other than editorial changes, shall

include a 10 CFR 50.59 Review and a Station Qualified Review (SQR).

The SQR composition shall include Regulatory Assurance Department in all cases. As a part of the SQR, concurrence from Byron and Braidwood Plant Operations Review Committee (PORC) approval is

required as determined by the Regulatory Assurance Manager. Byron and Braidwood shall implement the same change unless the change has been reviewed and determined not to be applicable to Braidwood.

TRM Diesel Fuel Oil Testing Program Appendix M BRAIDWOOD UNITS 1 & 2 8 of 9 Revision 48 Technical Requirements Manual ATTACHMENT A Diesel Fuel Oil Testing Matrix Outdoor Bulk Diesel Fuel Oil Tanks:

0DO03T (125K gal.)

0DO012T (50K gal.)

EDG Tanks:

1DO01TA/B/C/D (25K gal.)

2DO01TA/B (50K gal.)

EDG Tanks:

1DO02TA/B (500 gal.)

2DO02TA/B (500 gal.)

_B AF Pump Diesel Day Tanks:

1DO10T (500 gal.)

2DO10T (500 gal.)

Diesel-Driven Fire Pump Diesel Fuel Oil Tank:

0DO05T (650 gal.)

Security Diesel Generator Day Tank: 0DO06T (500 gal.)

Frequency Monthly Monthly Monthly Monthly (5) Monthly (5) Monthly Parameter:

Flash Point XX (2) Cloud Point XX (3) Water & Sediment XX (1)(2) X X X X X Ramsbottom Carbon Residue XX (3) Ash XX (3) Kinematic Viscosity XX (2) X X X X X Copper Strip Corrosion XX (3) Cetane Index XX (3) Sulfur XX (3) API Gravity XX (2) X X X X X Distillation

Temperature XX (3) Bacteria X Clear & Bright XX (1)(2) X X X X X Color XX (1)(2) X X X X X Heat Value X Total Particulate Contamination XX (4) XX X X X X Removal of accumulated water XX XX XX XX = Technical Specification required testing performed X = Testing performed

TRM Diesel Fuel Oil Testing Program Appendix M BRAIDWOOD UNITS 1 & 2 9 of 9 Revision 48 Technical Requirements Manual NOTES: (1) Water & Sediment OR Clear & Bright with Color is required. (2) Technical Specifications require verifying within limits within 30 days prior to adding new fuel oil to storage tanks.

(3) Technical Specifications require verifying within 30 days following sampling and addition to storage tanks. (4) Required since the Outdoor Bulk Diesel Fuel Oil Tanks are considered the source of stored fuel for the _B AF Pump Diesel Day Tanks. (5) Testing performed on a monthly basis, however, results are only required to be verified on a quarterly basis.

SECTION 1.1 1.2 1.3 1.4 1.5 1.6 1. 7 1.8 1.9 TRM TS Bases Control Program Appendix N TECHNICAL SPECIFICATIONS BASES CONTROL PROGRAM TABLE OF CONTENTS TITLE PURPOSE REFERENCES DEFINITIONS AND/OR ACRONYMS PROGRAM DESCRIPTION PROGRAM IMPLEMENTATION ACCEPTANCE CRITERIA LCOARS/COMPENSATORY MEASURES REPORTING REQUIREMENTS CHANGE CONTROL BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 1 of 13 Revision 64 1.1 PURPOSE TRM TS Bases Control Program Appendix N The purpose of this Program is to provide guidance for identifying, processing, and implementing changes to the Technical Specifications (TS) Bases. This Program implements and satisfies the requirements of TS 5.5.14, "Technical Specifications (TS) Bases Control Program." This Program is applicable to the preparation, review, implementation, and distribution of changes to the TS Bases. This Program also provides guidance for preparing TS Bases Change Packages for distribution.

1.2 REFERENCES

1. TS 5.5.14, "Technical Specifications (TS) Bases Control Program" 2. 10 CFR 50.4, "Written Corrmunications" 3. 10 CFR 50.59, "Changes, Tests and Experiments" 4. 10 CFR 50.71, "Maintenance of Records, Making of Reports" 5. 10 CFR 50.90, "Application for Amendment of License or Construction Permit" 1.3 DEFINITIONS AND/OR ACRONYMS 1. 10 CFR 50.59 REVIEW -A written regulatory evaluation which provides the basis for the determination that a change does, or does not, require NRC approval pursuant to 10 CFR 50.59. The scope of the evaluation should be corrmensurate with the potential safety significance of the change, but must address the relevant safety concerns included in the Safety Analysis Report and other owner controlled documents.

The depth of the evaluation must be sufficient to determine whether or not NRC approval is required prior to implementation.

Depending upon the significance of the change, the evaluation may be brief; however, a simple statement of conclusion is not sufficient.

BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 2 of 13 Revision 64 TS Bases Control Program Appendix N 2. EDITORIAL CHANGE -Editorial changes include correction of punctuation, insignificant word or title changes, style or format changes, typographical errors, or correction of reference errors that do not change the intent, outcome, results, functions, processes, responsibilities, or performance requirements of the item being changed. Changes in numerical values shall .Il.Qt be considered as editorial changes. Editorial changes do not constitute a change to the TRM and therefore do not require further 10 CFR 50.59 Reviews. If the full scope of this proposed change is encompassed by one or more of the below, then the change is considered editorial.

Rewording or format changes that do not result in changing actions to be accomplished.

Deletion of cycle-specific information that is no longer applicable.

Addition of clarifying information, such as: Spelling, grarrrnar, or punctuation changes Changes to references Name or title references 1.4 PROGRAM DESCRIPTION

1. A Licensee may make changes to the TS Bases without prior NRC approval provided the changes do not require either of the following:

a. A change in the TS as currently incorporated in the license; or b. A change to the Updated Final Safety Analysis Report CUFSAR) or TS Bases that requires NRC approval pursuant to 10 CFR 50.59. 2. Changes that meet the above criteria (i.e., 1.4.1.a or 1.4.1.b) shall be submitted to the NRC pursuant to 10 CFR 50.90 and reviewed and approved by the NRC prior to implementation.

3. The TS Bases shall be maintained consistent with the UFSAR. BRAIDWOOD UNITS 1 & 2 Technical Requirerrents Manual 3 of 13 Revision 64 TS Bases Control Appendix N 4. If a change to the TS Bases is not consistent with the UFSAR, then the cognizant Engineer shall prepare and submit a UFSAR Change Package when the TS Bases Change Request is submitted to Regulatory Assurance (RA) for processing.

5. Changes to the TS Bases that do not require prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e), as modified by approved exemptions.

6. TS Bases changes associated with a TS Amendment shall be implemented consistent with the implementation requirements of the TS Amendment.

7. Cantera Licensing CCL) is responsible for the control and distribution of the TS Bases. In order to prevent distribution errors (i.e., omissions or duplications), CL shall maintain the master TS Bases distribution list. 1.5 PROGRAM IMPLEMENTATION

1. 2. 3. TS Bases Change Requester identifies the need for a revision to the TS Bases and notifies the RA Licensing Engineer (i.e., hereafter referred to as RA LE). A TS Bases change can be initiated through any Stations' RA. TS Bases Change Requester notifies their counterparts on the need for a change. RA LE notifies their counterparts of identified need for revision to the TS Bases. RA LE obtains concurrence from CL on the need for a change. BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 4 of 13 Revision 64 TRM TS Bases Control Program Appendix N 4. RA LE drafts TS Bases changes considering format, rules of usage, and technical adequacy.

5. CL Engineer (i.e., hereafter referred to as CLE) reviews the agreed upon TS Bases wording changes for consistency with fonnat, rules of usage, and technical adequacy and provides final concurrence.

6. After concurrence of the TS Bases wording changes is obtained, CLE makes an electronic version available in a working directory for use in the preparation of the 10 CFR 50.59 REVIEW and Station Qualified Review (SQR) process. The CLE shall ensure that the master electronic TS Bases files are revised per step 14 below upon receiving SOR I approval.

The Revision number in the footer should be a sequential number (i.e., 1, 2, etc.). *************************************************************

NOTE * * *

If the TS Bases changes a re app 1 i cab 1 e to more than one *

Station, the following steps should be performed

concurrently for each Station. * *************************************************************

7. TS Bases Change Requestor provides a 10 CFR 50.59 REVIEW for the TS Bases changes in accordance with appropriate plant procedures.

An exception to this requirement applies when the changes are being requested in order to reflect an approved NRC Safety Evaluation CSE) associated with a site specific Operating License or TS change. The NRC SE is sufficient to support the changes provided it has been determined that the changes are consistent with and entirely bounded by the NRC SE. A 10 CFR 50.59 REVIEW shall be performed for TS Bases changes that reflect generic industry approval by an NRC SE to detennine site specific agplicability.

A 10 CFR 50.59 REVIEW is not required for an E ITORIAL CHANGE. 8. TS Bases Change Requestor COf11Pletes Attachment A, "Technical Specifications Bases Change Request Form," as follows: BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 5 of 13 Revision 64

a. b. c. d. e. f. g. h .. i. j. k. TRM TS Bases Control Program Appendix N Identifies the affected sections, and includes a copy of the proposed TS Bases changes; Briefly sunmarizes the changes including the LCO, Action, or Surveillance Requirement to which the changes apply; Briefly surnnarizes the reason for the changes and attaches all supporting documentation; Identifies any schedule requirements and proposed implementation date that apply (i.e., describe any time limitations that might apply which would require expedited processing).

If the changes are outage related, then checks "yes" and lists the applicable outage identifier; Identifies any known implementation requirements such as procedure UFSAR changes, Passport changes, Reportab1lity Manual revisions, implementation training requirements, etc.; If a 10 CFR 50.59 REVIEW was prepared to support the TS Bases changes, the Requestor then checks the appropriate box, lists the associated 10 CFR 50.59 REVIEW Number, and attaches the original; If the changes to the TS Bases are the result of an approved NRC SE associated with a site specific Operating License or TS change and the scope of the changes determined to be consistent with and entirely bounded by the NRC SEt then the Requestor checks the appropriate box and attaches a copy; If the changes to the TS Bases are EDITORIAL CHANGES, the the Requestor checks the appropriate box and no 10 CFR 50.59 REVIEW is required; Signs and dates as Requestor and identifies the originating department; Obtains approval to proceed from Department Supervisor Cor designee);

and Returns Attachment A to the RA LE. BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 6 of 13 Revision 64 TS Bases Control Program Appendix N 9. RA LE reviews the TS Bases Change Request Form, including supporting documentation, and documents the review by signing Attachment A. The review verifies that the following information or documentation is included:

a. Completed 10 CFR 50.59 REVIEW. If the changes are related to an approved NRC SE associated with a site specific Operating License or TS change and determined to be entirely bounded by the NRC SE, then only a copy of the SE is required to be attached and no 10 CFR 50.59 REVIEW is required.

A 10 CFR 50.59 REVIEW is not required for an EDITORIAL CHANGE; b. Identification of known documents requiring revisions; and c. Completed UFSAR Change Request with supporting documentation, in accordance with appropriate plant procedures, if applicable.

10. If the TS Bases change is not an EDITORIAL CHANGE, the RA LE/TS Bases Change Requester obtains SOR approval of the TS Bases changes by performing the following:

a. RA LE prepares the TS Bases Change SOR package. The SOR package shall include Attachment A (including completed 10 CFR 50.59 REVIEW or NRC SE) and the revised TS Bases pages. Attachment A is provided for the purpose of reviewing and finalizing the imple11Entation requirements and ensuring the necessary actions have been initiated.

RA LE shall assign Action Tracking CAT) items, as necessary, to track implementation requirements;

b. TS Bases Change Requester submits the TS Bases Change SOR package to the SOR Corrmittee 11Embers for a preliminary review. The SOR composition shall include RA and Operating Departments in all cases; and c. TS Bases Change Requester resolves preliminary review c01T1T1ents and finalizes the TS Bases Change SOR package. 11. The RAM shall determine the need for Plant Operations Review I Corrmittee CPORC) approval.

The need for PORC approval shall be documented on Attachment A. . BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 7 of 13 Revision 64 TRM TS Bases Control Program Appendix N 12. RA LE/TS Bases Change Requestor obtains PORC approval, if necessary.

13. RA LE notifies CLE of approval of the TS Bases changes by I forwarding a copy of the approved SQR/PORC Change package to CLE. 14. After approval of the TS Bases changes by SQR/PORC, CLE ensures that the controlled master electronic files are updated. 15. RS/RA completes Attachment B, "Technical Specifications Bases Change Instruction Form," as follows: a. b. c. CLE indicates the effective date of the TS Bases changes consistent with the SQR/PORC approval or TS amendment required implementation date. If the TS Bases change is a result of a TS Amendment, the update shall be implemented coincident with implementation requirements of the TS Amendment.

Otherwise, the update must be implemented by the date indicated on Attachment B; CLE lists each page to be removed and inserted, including the Affected Page List; and RA LE provides the updated master file directory for updating Electronic Document Management System CEDMS), if applicable.

16. CLE creates a TS Bases Change Package. The TS Bases Change Package shall consist of: a. TS Bases Change Instruction Form (Attachment B); b. Revised Affected Page List; and c. Revised TS Bases pages. One CLE shall assemble and approve the TS Bases Change Package for distribution and a second CLE shall perform a peer check to verify completeness of the TS Bases Change Package. BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 8 of 13 Revision 64

17. 18. 19. 20. 21. TS Bases Control Program Appendix N After the RA LE notifies the CLE that SQR/PORC approval of the TS Bases changes has been obtained and that all AT items assigned to track implementation requirements have been completed, CLE forwards the TS Bases Change Package to the RA LE as notification of the need to update the onsite TS Bases controlled copies and EDMS, if applicable.

CLE also forwards the TS Bases Change Package to CL Records Management as notification of the need to update the offsite (CL) TS Bases controlled copies and to transmit updates to the offsite (non-CL) TS Bases controlled copies. RA LE forwards the TS Bases Change Package to Station Records Management as notification of the need to update the onsite TS Bases controlled copies and EDMS, if applicable.

Upon completion of updating the onsite TS Bases controlled copies and EDMS (if applicable), Station Records Management Supervisor signs and dates Attachment B and returns Attachment B to the appropriate CLE. Upon completion of updating the offsite (CL) TS Bases controlled copies and transmitting updates to the offsite (non-CL) TS Bases controlled copies, CL Records Management signs and dates Attachment B and returns Attachment B to the appropriate CLE. RA LE ensures that the documentation required to be maintained as a quality record is provided to Station Records Management for the purpose of record retention.

BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 9 of 13 Revision 64 1.6 ACCEPTANCE CRITERIA Not applicable.

1.7 LCOARS/COMPENSATORY MEASURES TS Bases Control Program Appendix N An Issue Report may need to be generated to provide proper tracking and resolution of noted problems associated with the implementation of this Program. The RAM will be responsible for ensuring that Program failures have been resolved.

1.8 REPORTING REQUIREMENTS

NOTE * *

TS Bases changes requiring prior NRC approval shall be

submitted in accordance with Reference

5. * * * * * *************************************************************

TS Bases changes not requiring prior NRC approval, as described in Section 1.4 of this Program, shall be submitted to the NRC in accordance with 10 CFR 50.?l(e).

1.9 CHANGE CONTROL Changes to this Program, other than EDITORIAL CHANGES, shall include a 10 CFR 50.59 REVIEW and a SOR. The SOR composition shall include RA Department in all cases. For a change to this Program, PORC approval from all Stations is required.

The concurrence shall be that the other Stations are implementing the same changes or that the changes have been reviewed and determined not to be applicable to the other Stations.

BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 10 of 13 Revision 64

1. ATTACHMENT A TRM TS Bases Control Program Appendix N TECHNICAL SPECIFICATIONS BASES CHANGE REQUEST FORM Change Request #: Affected Bases Section(s):

________ _ 2. Description of changes: 3. Reason for changes (attach all supporting documentation):

4. 5. 6. 7. Schedule Requirements:

D No 0 Yes, Outage # ___ _ Outage Related (check one) Other (explain)

Implementation Requirements (attach additional pages, as necessary):

Identify the impact of the changes on the following:

Affected N/A 0 0 D D D D D D D D D D D 0 D D D 0 D D D D D 0 D 0 D D D 0 D 0 D D 0 0 D 0 D 0 D 0 D 0 Check one: UFSAR _________________

_

Technical Manual -----------

NRC Safety Evaluation Fire Protection NRC Comni tnents Vendor OoclllleJlta..,...,ti,....on--------------

Special Pennits/Licenses Procedures Enviroment.....,al.-Qu=--=a1

..... ;f"""ic_a.,...,ti,.....on------------

Design Basis Docurrentation Engineering PRA Infonnation

Programs.,,..,..,...__,..,,..

_______________

_ RePQrtability Manual QA Topical Report---------------

Passport,___---------------

Training Maintenance Rule Off site Dose cal c.....,ul..-at:-:-i-on-=Ma-:--n-u-=a1:-------------

_________________ 0 10 CFR 50.59 REVIEW Attached, 10 CFR 50.59 REVIEW#: ___ ....,...____,,...-.,,-,,.,...----

0 NRC SE Attached, Changes consistent with and entirely bounded by NRC SE 0 EDITORIAL CHANGE, No 10 CFR 50.59 REVIEW required Requester:

I /.,..,,._---..,.------(Signature) (Date) (Department)

8. Requesting Supervisor Approval:

_________

_ 9. PORC Approval Required:

10. Licensing Engineer Review: BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual (Signature) 0 Yes (Date) D No ________ __,! _________ (Signature) mate) 11 of 13 Revision 64 TRM TS Bases Control Program Appendix N ATTACHMENT B TECHNICAL SPECIFICATIONS BASES CHANGE INSTRUCTION FORM FOR ONSITE/OFFSITE DISTRIBUTION AND FOR UPDATING EOMS Braidwood/Byron/Dresden/LaSalle/QC (circle one) TS Bases NOTE: This change is effective as of and shall be implemented by (SQR/PORC or Amendment Implementation Date) (Date) Approved for distribution: (CLE Signature) (Date) Verified: ( CLE Signature) (Date) REMOVE REMOVE INSERT INSERT UPDATE EDMS Section Paqe Section Paqe Section Affected All Affected Page All N/A Page List List BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 12 of 13 UPDATE EDMS Paqe N/A Revision 64 TRM TS Bases Control Program Appendix N ATTACHMENT B TECHNICAL SPECIFICATIONS BASES CHANGE INSTRUCTION FORM FOR ONSITE/OFFSITE DISTRIBUTION AND FOR UPDATING EDMS Braidwood/Byron/Dresden/LaSalle/QC (circle one) TS Bases Station Records Management:

Onsite Distribution Completed: ( St at ion Records Mgmt. Supr.) CDate) EDMS Update Completed: (St at ion Records Mgmt. Supr.) (Date) ** Return this sheet to: Cantera Licensing Braidwood/Byron/Dresden/LaSalle/QC (circle one) CLE CANTE RA CL Records Management:

Offsite (CL) Distribution Completed: (CL Records Mgmt.) Offsite (non-CL) Distribution Transmitted:

_________

__,/ ______ _ (CL Records Mgmt.) (Date) ** Return this sheet to Braidwood/Byron/Dresden/LaSalle/QC (circle one) CL Offsite (non-CL) Controlled Copy Holders: Offsite (non-CL) Distribution Completed:

______ _ (Signature) (Date) ** Return this sheet to: EXELON GENERATION COMPANY, LLC LICENSING AND REGULATORY AFFAIRS DEPARTMENT 4300 WINFIELD ROAD WARRENVILLE, IL 60555 BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 13 of 13 Revision 64 TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 21of 43Revision 87 Technical Requirements Manual SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)

BRAIDWOOD TABLE OF CONTENTSSECTIONTITLE1.1PURPOSE

1.2REFERENCES

1.3DEFINITIONS AND/OR ACRONYMS1.4PROGRAM DESCRIPTION1.5PROGRAM IMPLEMENTATION1.6ACCEPTANCE CRITERIA 1.7LCOARS/COMPENSATORYMEASURES1.8REPORTING REQUIREMENTS1.9CHANGE CONTROL TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 22of 43Revision 87 Technical Requirements Manual1.1PURPOSE The purpose of the SFDP is to ensure that the proper Actions are taken uponfailure to concurrently meet two or more Technical Specifications (TS)Limiting Conditions for Operation (LCOs) such that multiple

inoperabilities of Systems, Structures, or Components (SSCs) do not result inan undetected LOSS OF SAFETY FUNCTION (LOSF).

1.2REFERENCES

1.Technical Specification LCO 3.0.62.TS Specification 5.5.15, "Safety Function Determination Program (SFDP)"3.Maintenance Rule Scoping Manual1.3DEFINITIONS AND/OR ACRONYMS1.ACTIONS -In the LCO Actions section, it describes the Required Actions to be taken under designated Conditions within specified COMPLETION TIMES. 2.LOSS OFSAFETY FUNCTION (LOSF) -A LOSF exists when, assuming no concurrent single failure and assuming no concurrent loss of offsite

power or loss of emergency diesel generator(s), a safety function assumed in the accident analysis cannot be performed. 3.COMPLETION TIME -In the LCO Actions section, it states the amount of time allowed to complete a Required Action.4.COMPLETION TIME EXTENSION -The additional amount of time a SUPPORTED SYSTEM may be inoperable due to its associated SUPPORT SYSTEM being inoperable. NOTE -the inoperability of the SUPPORTED

SYSTEM must only be directly attributed to its associated SUPPORT

SYSTEM being inoperable and the SUPPORT SYSTEM Required Actions not specifically requiring entry into the SUPPORTED SYSTEMS Required Actions and associated COMPLETION TIMES.5.CONDITION -In the LCO Actions section, it describes the ways in which the requirements of an LCO can fail to be met.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 23of 43Revision 87 Technical Requirements Manual1.3.6.OPERABLE/OPERABILITY -A system, subsystem, train, component, or device shall be OPERABLE 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).7.SAFETY FUNCTION -An accident mitigation feature required by NRC regulation, plant design or Technical Specifications normally composed of two trains of SUPPORTED and SUPPORT equipment.8.SUPPORTED SYSTEM -A SSC, required by the TS, which requires a SUPPORT SYSTEM to ensure its safety function can be performed.

Process parameters or operatinglimits do not comprise SUPPORTED

SYSTEMS for the purposes of implementing LCO 3.0.6.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 24of 43Revision 87 Technical Requirements Manual1.3.9.SUPPORT SYSTEM -A SSC which is needed by another TS LCO required SSC to perform a safety function.

An example would be the Component Cooling Water (CC) System (SUPPORT SYSTEM) which is required by the Residual Heat Removal System (SUPPORTED SYSTEM) to fulfill the RH safety function. A SUPPORT

SYSTEM may also be a SUPPORTED SYSTEM. An example is the Component Cooling Water (CC) System which needs the Essential Service Water (SX) System to fulfill its safety function.

- NOTE A SSC which monitors or maintains a process parameter or operating limit is not a

SUPPORT SYSTEM for the purposes of implementing

LCO 3.0.6. An example is Rod Position Indication

which is used to monitor control rod insertion limits. Inoperability of the Rod Position Indication System does not automatically suggest

that the control rods are no longer within

insertion limits. Control rod insertion limits

are monitored separately and Actions are taken as appropriate when insertion limits are not met or if Surveillance Requirements can not be

performed when required.

Likewise, parameter limits that could affect other parameter limits if exceeded are also not considered SUPPORT SYSTEM for the purposes

of implementing LCO 3.0.6. An example is that

exceeding control rod insertion limits could

affect hot channel factors.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 25of 43Revision 87 Technical Requirements Manual1.4PROGRAM DESCRIPTION1.TS LCO 3.0.2 states that 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. LCO 3.0.6 provides

an exception to LCO 3.0.2 for SUPPORTED SYSTEMS by not requiring the

Required Actions for the SUPPORTED SYSTEMS to be performed when the failure to meet an LCO is solely due to a SUPPORT SYSTEM LCO not being met. In this situation, although the SUPPORTED SYSTEM is

declared inoperable, LCO 3.0.6 requires only the Conditions and

Required Actions of the SUPPORT SYSTEM to be performed. The

Conditions and Required Actions for the SUPPORTED SYSTEM are not required to be performed (i.e., cascading to the SUPPORTED SYSTEM) per LCO 3.0.6.

There are two types of SUPPORT SYSTEMS which must be considered when implementing LCO 3.0.6: (1) those addressed in Technical Specifications, and (2) those which are not. If the required SUPPORT SYSTEM is not addressed in the Technical Specifications, the

impact of the SUPPORT SYSTEM inoperability must be evaluated with

respect to any SUPPORTED SYSTEM which is addressed in Technical

Specifications. An example of this is the loss of a ventilation system for which there is no LCO. If the equipment supported by the ventilation system were subsequently exposed to freezing conditions, then all affected systems which have an LCO must be evaluated to

ensure that they remain OPERABLE and that there is no LOSF.

If the SUPPORT SYSTEM is addressed in the Technical Specifications, only the SUPPORT SYSTEM LCO must be entered per LCO 3.0.6 (i.e.,

"cascading" to the SUPPORTED SYSTEM is not required). However, the

SUPPORT SYSTEM inoperability must still be evaluated with respect to the existing plant conditions to ensure that a LOSF does not exist.

An example of this is the loss of component cooling water to one

residual heat removal (RHR) heat exchanger. If the electrical bus supplying the second RHR pump were also removed from service,a LOSF

may exist following a loss-of-coolant-accident and this plant configuration must be evaluated. It should be noted that for cases in which the inoperable SUPPORT SYSTEM is addressed in Technical

Specifications, "cascading" can still be performed. LCO 3.0.6 only

provides an option for not cascading at the discretion of

operations.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 26of 43Revision 87 Technical Requirements Manual1.4.2.If the exception of 3.0.6 is utilized, additional evaluations and limitations may be required in accordance with Specification 5.5.15, "Safety Function Determination Program (SFDP)" (Reference Figure 1).

If a LOSF is determined to exist by this Program, the appropriate Conditions and Required Actions of the LCO in which the LOSF 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 3.0.2.3.Since "cascading" is not required when applying 3.0.6, a possibility exists that unrelated concurrent failures of more than one system

could result in the complete loss of both trains of a SUPPORTED

SYSTEM. Therefore, upon a failure to meet two or more LCOs during

the same time period, an evaluation shall be conducted to determine if a LOSF exists. Generally, this is done by confirming that the remaining required redundant SSCs are OPERABLE. If a LOSF does

exist, the SFDP directs that the appropriate actions be taken.

NOTE If the failure of an TS required SUPPORT SYSTEM results

in the inoperability of a system outside of the TS, and

that system is subsequently relied upon by a SUPPORTED SYSTEM to remain OPERABLE, then LCO 3.0.6 could apply and only the SUPPORT SYSTEM'S Required Actions would be

entered.*

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 27of 43Revision 87 Technical Requirements Manual1.4.4.A single component inoperability may result in multiple inoperabilities within a single train and affect multiple TS LCOs.

LCO 3.0.6 limits the amount of "cascading" Actions that are required when an inoperable SSC renders a SUPPORT SYSTEM inoperable.

A LOSF evaluation must only be performed when equipment is inoperable in more than one train. For multiple inoperabilities within a single train, whether separate inoperabilities or inoperabilities of SUPPORTED SYSTEM(S) due to the inoperability of

a SUPPORT SYSTEM, compliance with the Required Actions within the

LCOs as directed by LCO 3.0.2 and LCO 3.0.6 is sufficient to ensure

safe operation.

If the inoperable system is a SUPPORT SYSTEM and its Required Actions have not been pre-evaluated in combination with other

inoperabilities as noted in Table 1, then perform a LOSF evaluation

in accordance with Section 1.5. LCO's which are not SUPPORT SYSTEMS may also result in a LOSF when taken in combination with additional inoperabilities. Therefore, a LOSF evaluation is required and the

Required Actions of the applicable LCOs shall be met in accordance

with LCO 3.0.2.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 28of 43Revision 87 Technical Requirements Manual1.4.4.(CONTINUED)

If more than one LCO's Required Actions have been entered, then determine if all the LCOs have been entered for the same train.a.If the LCOs have been entered for the same train, then no LOSF exists provided the redundant equipment on the opposite train is not inoperable for other reasons. No further evaluation is required.b.If the LCOs have been entered for different trains, then a LOSF evaluation shall be performed to determine if the initial inoperability(ies), in conjunction with subsequent inoperability(ies) in the required redundant train, results in

the loss of a safety function. This evaluation shall address

the following examples:1)A required system redundant to the system(s) supported by the inoperable SUPPORT SYSTEM is

also inoperable (see Figure 2, Example 1); or2)A required system redundant to the system(s)in turn supported by the inoperable SUPPORTED SYSTEM

is also inoperable (see Figure 2, Example 2); or3)A required system redundant to the SUPPORT SYSTEM(s) for the SUPPORTED SYSTEMs (a) and (b)

above is also inoperable (see Figure 2, Example

3).For a TS related SUPPORT SYSTEM, Table 1 may be used as a guide for evaluating SUPPORT/SUPPORTED SYSTEM(s) relationships between TS systems.

Inoperable SSC(s) should be evaluated if the inoperability impacts the ability of the SSC(s) to perform its required safety function.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 29of 43Revision 87 Technical Requirements Manual1.5PROGRAM IMPLEMENTATION-LOSS OF SAFETY FUNCTION (LOSF) EVALUATION

- - NOTE1.If an LCO is not met for a SUPPORT SYSTEM, and the SUPPORT SYSTEM Actions direct the Actions for the SUPPORTED SYSTEMS be entered, enter the appropriate Actions for the SUPPORTED SYSTEMS.2.If a SUPPORTED SYSTEM LCO is not met solely due to a SUPPORT SYSTEM inoperability, and the SUPPORT SYSTEM Actions do not direct that Actions for the SUPPORTED SYSTEMS be entered, then do not enter the

Actions for the SUPPORTED SYSTEMS per LCO 3.0.6.

- - - - 1.Identify if the degraded SSC renders a TS required SSC inoperable.

If NO, then no further evaluation is necessary.2.If YES, then enter the LCOAR for the inoperable SSC.3.Determine ifthe inoperable SSC is also a SUPPORT SYSTEM SSC.4.If YES, then identify all TS required SUPPORTED SYSTEM SSC's that are rendered inoperable as a result of this LCOAR entry.5.If the SUPPORT SYSTEM SSC Required Actions direct performance of any SUPPORTED SYSTEM SSC Required Action(s), then enter the LCOAR for the SUPPORTED SYSTEM SSC as directed and perform the Required

Actions.6.For ALL inoperable SUPPORT and SUPPORTED SYSTEM SSC's, perform an evaluation to ensure a LOSF does not exist for current plant

conditions. Perform cross-train checks to ensure redundant trains

are fully operational.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 210of 43Revision 87 Technical Requirements Manual1.5.7.If anyredundant train SSC is NOT fully Operational, then one of the following conditions will apply:a.The SSC is part of a single LCO with multiple subsystems and the LCO specified function is intact. NO LOSF exists for this specific SSC.b.The SSC will still perform it's required Safety Function as defined in the Safety Analysis Report (SAR). NO LOSF exists

for this specific SSC.c.A LOSF exists. Enter the LCOAR and perform the Required Actions of the SSC in which the LOSF exists for the specific

Condition(s) that apply.8.If No LOSF exists, for all SUPPORTED SYSTEM SSC's which are rendered inoperable, perform one of the following actions:a.Enter the LCOAR(s) for each inoperable SSC and perform the Conditions and Required Actions as directed (Cascading), ORb.Declare the SUPPORTED SYSTEM SSC(s) inoperable and apply LCO 3.0.6 to preclude entry into the Conditions and Required Actions associated with the inoperable SUPPORTED SYSTEM

SSC(s). Track the inoperable SSC(s) on the Delayed LCOAR

Entry Table of the inoperable SUPPORT SYSTEM SSC LCOAR.NOTE:Examples of LOSF evaluations may be found in Figures 1 and 2, and .1.6ACCEPTANCE CRITERIA Not Applicable.1.7LCOARS/COMPENSATORY MEASURES The Shift Manager is responsible for initiating any LCOARs or Compensatory

Measures resulting from the LOSF evaluation. In addition, an Issue Report (IR) may be generated to provide proper tracking and resolution of noted problems associated with the implementation of this program.1.8REPORTING REQUIREMENTS This will be evaluated on a case-by-case situation.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 211of 43Revision 87 Technical Requirements Manual1.9CHANGE CONTROL Changes to this Program, other than editorial changes, shall include a 10CFR50.59 Review and a Station Qualified Review (SQR). The SQR

composition shall include the Regulatory Assurance Department in all

cases. As a part of the SQR, Byron and Braidwood Plant Operations Review Committee (PORC) is required as determined by the Regulatory Assurance Manager. Byron and Braidwood shall implement the same change unless the

change being implemented at Braidwood has been reviewed and was determined

not to be applicable to Byron.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 212of 43Revision 87 Technical Requirements Manual FIGURES 1 and 2 SFDP FLOWCHART SUPPORT/SUPPORTED SYSTEM DIAGRAM TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 213of 43Revision 87 Technical Requirements Manual SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)

Is an ITS Required SSC rendered INOP Finished Is INOP SSC a SUPPORT SSC?

Perform the LCO Required Actions for the Inoperable SSC Identify all inoperable SUPPORTED SSCs (use Table 1 as a guide)

Do INOP SUPPORT SSC Required Actions directly address SUPPORTED SSCs?

For each SSC that is determined tobe inoperable -Perform a Safety Function Determination Evaluation Page 2 SFD (continue on page 2)

Perform SUPPORT SSC Required Actions and SUPPORTED SSC LCO Required Actions as directed Yes No No No Yes Yes TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 214of 43Revision 87 Technical Requirements Manual SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)

SFD (continued from page 1)

Does this ITS Required SSC have any redundant SSC's that are also inoperable?

note---------------

Consider all active LCOAR's and SSC's which are inoperable but not in LCOAR under the allowances of LCO 3.0.6 Is the SSC part of a single LCO with multiple subsystems with the LCO specified function intact?

Can the SSC still perform its required safety function as defined in the Safety Analysis Report (UFSAR)?

A Loss of Safety Function Exits Enter the LCOAR and perform the Required Actions of the LCO in which the LOSF exists for the specific Condition(s) which apply.

No Loss of Safety Function Exists for this specific SSC.

Either: Perform both SUPPORT and SUPPORTEDSSC RequiredActions (Cascade)

OR Perform SUPPORT SSC Required Actions and enter LCO 3.0.6 for SUPPORTED SSC's Yes Yes Yes No No No TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 215of 43Revision 87 Technical Requirements Manual FIGURE 2 SUPPORT/SUPPORTED SYSTEM DIAGRAM EXAMPLE 1 A LOSF may exist when a SUPPORT SYSTEM is inoperable, and:

A required system redundant to the system(s) supported by the inoperable SUPPORT SYSTEM is also inoperable.

If System 2 of Train A is inoperable, and System 5 of Train B is inoperable, a LOSF exists in SUPPORTED SYSTEM 5, 10, 11.

EXAMPLESTRAIN A TRAIN B System 8 System 8 System 4 System 4 System 9 System 9 System 2 System 2 System 10 System 10 System 5 System 5 System 11 System 11 System 1 System 1 System 12 System 12 System 6 System 6 System 13 System 13 System 3 System 3 System 14 System 14 System 7 System 7 System 15 System 15Note:Chart reads from left to right, i.e., System 1 is a SUPPORT SYSTEM for Systems 2 through 15.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 216of 43Revision 87 Technical Requirements Manual FIGURE 2 SUPPORT/SUPPORTED SYSTEM DIAGRAM EXAMPLE 2 A LOSF may exist when a SUPPORT SYSTEM is inoperable, and:

A required system redundant to the system(s) in turn supported by the

inoperable SUPPORTED SYSTEM is also inoperable.

If System 2 of Train A is inoperable, and System 11 of Train B is inoperable, a LOSF exists in System 11 which is in turn supported by

System 5.EXAMPLESTRAIN A TRAIN B System 8 System 8 System 4 System 4 System 9 System 9 System 2 System 2 System 10 System 10 System 5 System 5 System 11 System 11 System 1 System 1 System 12 System 12 System 6 System 6 System 13 System 13 System 3 System 3 System 14 System 14 System 7 System 7 System 15 System 15Note:Chart reads from left to right, i.e., System 1 is a SUPPORT SYSTEM for Systems 2 through 15.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 217of 43Revision 87 Technical Requirements Manual FIGURE 2 SUPPORT/SUPPORTED SYSTEM DIAGRAM EXAMPLE 3 A LOSF may exist when a SUPPORT SYSTEM is inoperable, and:

A required system redundant to the SUPPORT SYSTEM(S) for the SUPPORTED SYSTEMS (a) and (b) above is also inoperable.

If System 2 of Train A is inoperable, and System 1 of Train B is inoperable, a LOSF Exists in Systems 2, 4, 5, 8, 9, 10 and 11.

EXAMPLESTRAIN A TRAIN B System 8 System 8 System 4 System 4 System 9 System 9 System 2 System 2 System 10 System 10 System 5 System 5 System 11 System 11 System 1 System 1 System 12 System 12 System 6 System 6 System 13 System 13 System 3 System 3 System 14 System 14 System 7 System 7 System 15 System 15Note:Chart reads from left to right, i.e., System 1 is a SUPPORT SYSTEM for Systems 2 through 15.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 218of 43Revision 87 Technical Requirements ManualTABLE 1 -SUPPORT SYSTEM TO SUPPORTED SYSTEM TS REFERENCE TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 219of 43Revision 87 Technical Requirements Manual TABLE 1 (page 1 of 7)

SUPPORT SYSTEM TO SUPPORTED SYSTEM TS CROSS REFERENCE Support System TS Number Support System Supported System TS Number Supported System 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation 3.3.1 3.3.6 3.3.7 3.3.8 3.5.2 3.5.3 3.6.3 3.6.6 3.6.7 3.7.2 3.7.5 3.7.7 3.7.8 3.7.10 3.7.11 3.7.12 3.7.13 3.8.1 Reactor Trip System (RTS)

Instrumentation Containment Ventilation

isolation Instrumentation

Control Room Ventilation (VC) Filtration System Actuation Instrumentation

Fuel Handling Building

Exhaust Filter Plenum (FHB)System Actuation InstrumentationECCS -Operating ECCS -Shutdown

Containment Isolation Valves

Containment Spray and Cooling Systems Spray Additive System

Main Steam Isolation Valves (MSIVs)

Auxiliary Feedwater (AF)

System Component Cooling Water (CC)

Essential Service Water (SX)

System Control Room Ventilation (VC) Filtration System

Control Room Ventilation (VC) Temp Control System

Nonaccessible Area Exhaust Filter Plenum Ventilation System Fuel Handling Exhaust Filter

Plenum (FHB) Ventilation

SystemAC Sources -Operating 3.3.5 Loss of Power (LOP)

Diesel Generator (DG)

Start Instrumentation 3.8.1 3.8.2AC Sources -Operating AC Sources -Shutdown TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 220of 43Revision 87 Technical Requirements Manual TABLE 1 (page 2 of 7)

SUPPORT SYSTEM TO SUPPORTED SYSTEM TS CROSS REFERENCE Support System TS Number Support System Supported

System TS Number Supported System 3.3.6 Containment

Ventilation Isolation Instrumentation 3.6.3 Containment Isolation Valves 3.3.7 Control Room

Ventilation (VC)

Filtration System Actuation

Instrumentation 3.7.10 Control Room Ventilation (VC) Filtration System 3.3.8 Fuel Handling Building

Exhaust Filter Plenum (FHB) Ventilation System Actuation

Instrumentation3.7.13FHB Ventilation System 3.4.14 RCS Pressure Isolation

Valve (PIV) Leakage 3.4.6 3.4.13 3.5.2 3.5.3RCS Loops -Mode 4 RCS Operational Leakage ECCS -OperatingECCS -Shutdown 3.4.17 RCS Loop Isolation

Valves 3.3.9 3.4.4 3.4.5 3.4.6 3.4.12 BDPSRCS Loops -MODES 1 and 2RCS Loops -MODE 3 RCS Loops -MODE 4

LTOP System 3.5.4 Refueling Water Storage Tank (RWST) 3.3.9 3.5.2 3.5.3 3.6.6 BDPSECCS -OperatingECCS -Shutdown

Containment Spray and

Cooling Systems3.5.5Seal Injection Flow3.5.2ECCS -Operating

3.6.2 Containment

Airlocks3.6.1Containment TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 221of 43Revision 87 Technical Requirements Manual TABLE 1 (page 3 of 7)

SUPPORT SYSTEM TO SUPPORTED SYSTEM TS CROSS REFERENCE Support System TS Number Support System Supported

System TS Number Supported System 3.6.3 Containment Isolation

Valves 3.5.2 3.5.3 3.6.1 3.6.6 3.7.7 3.7.8ECCS -OperatingECCS -Shutdown Containment

Containment Spray and Cooling Systems Component Cooling System

Essential Service Water (SX)3.6.6Containment Spray3.6.7Spray Additive System 3.7.6 Condensate Storage

Tank 3.7.5AuxiliaryFeedwater (AF)

System 3.7.7 Component Cooling

Water (CC) System 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.5.2 3.5.3 3.9.5 3.9.6RCS Loops -Modes 1 and 2RCS Loops -Mode 3RCS Loops -Mode 4RCS Loops -Mode 5, Loops

Filled RCS Loops -Mode 5, Loops

not FilledECCS -OperatingECCS -Shutdown

Residual Heat Removal (RHR)

Coolant Circulation-High

Water Level Residual Heat Removal (RHR)

Coolant Circulation-Low

Water Level TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 222of 43Revision 87 Technical Requirements Manual TABLE 1 (page 4 of 7)

SUPPORT SYSTEM TO SUPPORTED SYSTEM TS CROSS REFERENCE Support System TS Number Support System Supported

System TS Number Supported System3.7.8Essential Service Water (SX) System 3.4.6 3.5.2 3.5.3 3.6.6 3.7.5 3.7.7 3.7.11 3.8.1 3.8.2RCS Loops -Mode 4ECCS -OperatingECCS -Shutdown

Containment Spray and

Cooling System

Auxiliary Feedwater System Component Cooling Water (CC)

System Control Room Ventilation (VC) Temperature Control

SystemAC Sources -Operating (DG only)

AC Sources -Shutdown (DG

only)3.7.9Ultimate Heat Sink3.7.5 3.7.8"B" AFW System

Essential Service Water (SX)

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 223of 43Revision 87 Technical Requirements Manual TABLE 1 (page 5 of 7)

SUPPORT SYSTEM TO SUPPORTED SYSTEM TS CROSS REFERENCE Support System TS NumberSupport SystemSupported System TS Number Supported System 3.8.1AC Sources -Operating3.8.9Distribution Systems -

Operating (AC portion only)3.8.3Diesel Fuel Oil 3.8.1 3.8.2AC Sources -Operating AC Sources -Shutdown3.8.4DC Sources -Operating 3.8.1 3.8.7 3.8.9 3.4.12AC Sources -OperatingInverters -Operating Distribution Systems -

Operating LTOP System3.8.5DC Sources -Shutdown 3.4.12 3.8.2 3.8.8 3.8.10 LTOP SystemAC Sources -ShutdownInverters -Shutdown Distribution Systems -

Shutdown3.8.6Battery Parameters 3.8.4 3.8.5DC Sources -Operating DC Sources -Shutdown 3.8.7Inverters -Operating3.8.9Distribution Systems -

O p erating3.8.8Inverters -Shutdown 3.4.12 3.8.10 LTOP Distribution Systems -

Shutdown TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 224of 43Revision 87 Technical Requirements Manual TABLE 1 (page 6 of 7)

SUPPORT SYSTEM TO SUPPORTED SYSTEM TS CROSS REFERENCE Support System TS Number Support System Supported

System TS Number Supported System 3.8.9 Distribution Systems -

Operating 3.3.1 3.3.2 3.3.3 3.3.4 3.3.5 3.3.6 3.3.7 3.3.8 3.4.5 3.4.6 3.4.9 3.4.11 3.4.12 3.4.15 3.5.2 3.5.3 3.6.3 3.6.6 3.6.7 3.7.2 3.7.4 3.7.5 3.7.7 3.7.8 3.7.9 3.7.10 3.7.11 3.7.12 3.7.13 3.8.1 3.8.4 3.8.7 Reactor Trip System (RTS) Instrumentation

Engineered Safety Feature ActuationSystem (ESFAS)

Instrumentation Post Accident Monitoring (PAM)

Instrumentation

Remote Shutdown System

Loss of Power (LOP) Diesel

Generator (DG) Start Inst.

Containment Ventilation Isolation

Instrumentation

Control Room Ventilation (VC)

FiltrationSystem Actuation

Instrumentation Fuel Handling Building Exhaust Filter Plenum (FHB) Ventilation SystemActuation Instrumentation RCS Loops -Mode 3 RCS Loops -Mode 4

Pressurizer

Pressurizer Power

Operated Relief Valves (PORVs)

LTOP System

RCS Leakage Detection

InstrumentationECCS -OperatingECCS -Shutdown

Containment Isolation

Valves Containment Spray and Cooling

Systems Spray Additive Tank

Main Steam Isolation Valves (MSIVs)

Steam Generator Power Operated Relief Valves Auxiliary Feedwater (AF) System

Component Cooling Water (CC)

System Essential Service Water (SX)

System Ultimate Heat Sink

Control Room Ventilation (VC)

FiltrationSystem

Control Room Ventilation (VC)

TemperatureControl System Nonessential Area Exhaust Filter PlenumVentilation System

Fuel Handling Building (FHB)

VentilationSystem AC Sources -Operating DC Sources -OperatingInverters -Operating TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 225of 43Revision 87 Technical Requirements Manual TABLE 1 (page 7 of 7)

SUPPORT SYSTEM TO SUPPORTED SYSTEM TS CROSS REFERENCE Support System TS Number Support System Supported System TS Number Supported System 3.8.10 Distribution Systems -Shutdown 3.3.1 3.3.6 3.3.7 3.4.7 3.4.8 3.4.12 3.7.10 3.7.11 3.7.12 3.7.13 3.8.1 3.8.2 3.8.4 3.8.5 3.8.7 3.9.3 3.9.4 3.9.5 3.9.6 Reactor Trip System (RTS)Containment Ventilation

Isolation Instrumentation Control Room Ventilation (VC) Filtration System

Actuation Instrumentation RCS Loops -Mode 5, Loops FilledRCS Loops -Mode 5, Loops Not Filled

LTOP System

Control Room Ventilation (VC) Filtration System Control Room Ventilation (VC) Temperature Control

System Nonaccessible Area Exhaust Filter Plenum Ventilation System Fuel Handling Building

Exhaust Filter Plenum (FHB) Ventilation SystemACSources -Operating AC Sources -Shutdown DC Sources -Operating DC Sources -ShutdownInverters -Operating Nuclear Instrumentation

Containment Penetrations

Residual Heat Removal (RHR) and CoolantCirculation -High Water Level Residual Heat Removal (RHR) and Coolant Circulation -Low Water Level TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 226of 43Revision 87 Technical Requirements Manual ATTACHMENT 1 LCOAR FORMAT TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 227of 43Revision 87 Technical Requirements Manual SAFETY FUNCTION DETERMINATION PROGRAM REQUIREMENTSA.Loss of Safety Function (LOSF) EvaluationIs there anyinoperable or degraded SUPPORT SYSTEM or SUPPORTED SYSTEM equipment on the opposite/redundant train that, when coupled with this

inoperable equipment, might result in a complete loss of a Tech Spec required safety function.1.NO - No LOSF exists. No further evaluation is necessary.

2.YES -A LOSF may exist. Using the SFDP and BwAP 340-1, evaluatewhich of the following conditions apply:a.The SSC is part of an LCO with multiple subsystems and the LCO specified function is intact. No LOSF exists.b.The SSC will still perform its required safety function as defined in the Safety Analysis Report (SAR). No LOSF exists.c.A LOSF exists. Perform the Required Actions of the SSC LCO in which the LOSF exists for the specific Condition(s) that

apply.LCO 3.0.6 -DELAYED LCOAR ENTRY CALCULATION.

Perform this step only if NO LOSF exists and it is desired to delay SUPPORTED SYSTEM LCOAR entry as allowed by LCO 3.0.6. A LOSF does not

exist if the redundant train of the inoperable SUPPORTED SYSTEM(S)

equipment is OPERABLE.1.Rules of Usage:a.With a single SUPPORT SYSTEM inoperable, the affected SUPPORTED SYSTEM(s) LCOAR entry(s) is not required to be entered unless directed by the SUPPORT SYSTEM Required Actions.b.In the event additional SUPPORT SYSTEM(s) become inoperable during the Completion Time for restoration of the first SUPPORT SYSTEM, the LCOAR entry(s) of the SUPPORTED SYSTEM may be delayed by either the maximum allowed Completion Time of the SUPPORT SYSTEMs, OR2 times the Completion Time for restoration of the SUPPORTED SYSTEM (applied at the time the second SUPPORT SYSTEM becomes inoperable), whichever is less.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 228of 43Revision 87 Technical Requirements Manual2.When tracking delayed LCOAR entry times, it is imperative that the INOPERABLE TIME/DATE and required LCOAR entry TIME/DATE reflect

the total time the SUPPORTED SYSTEM has been inoperable. A review of all active LCOARS must be performed to ensure SUPPORTED SYSTEM(s) do not remain inoperable for longer than allowed in 1.b.

above.B.SUPPORT SYSTEM to SUPPORTED SYSTEM Tech Spec cross reference is found in the SFDP. Complete the following table(s) for all inoperable SUPPORTED

SYSTEMS for the purpose of tracking delayed LCOAR entry given subsequent

additional SUPPORT SYSTEM inoperabilities.

Table 1: Supported System delayed LCOAR entry Table: (example)SUPPORT SYSTEM:LCO 3.7.7Component Cooling Water SUPPORTED SYSTEM TS NUMBER SUPPORTED SYSTEM INOPERABLE TIME / DATE Enter LCOAR

TIME / DATE 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.5.2 3.5.3 3.9.5 3.9.6 ______ ______

______RCS Loops -Modes 1 & 2 RCS Loops -Mode 3RCS Loops -Mode 4RCS Loops -Mode 5, Loops filledRCS Loops -Mode 5, Loops not filledECCS -Operating ECCS -Shutdown

RHR Coolant Circulation -

High Water Level RHR Coolant Circulation -

Low Water Level

_________________________

__________________

_________________

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 229of 43Revision 87 Technical Requirements Manual Table 2: ANY/All other SUPPORTED SYSTEMS which are inoperable as a resultofthe SUPPORTED SYSTEM(S) identified in table 1 above.

SUPPORTED

SYSTEM TS NUMBER 2nd / 3rd LEVEL SUPPORTED SYSTEM INOPERABLE TIME / DATE Enter LCOAR

TIME / DATE

______

__________________

______

____________(none pre-identified)

_________________________

__________________

_________________

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 230of 43Revision 87 Technical Requirements Manual ATTACHMENT 2 SFDP EVALUATION EXAMPLES TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 231of 43Revision 87 Technical Requirements Manual ATTACHMENT 2 ITEMS CLEARLY INOPERABLEA.A SSC that is unable to perform its specified function(s) because of obvious failure, damage, or malfunction, or because it is disabled for testing or maintenance is inoperable.B.A SSC that trips (where tripped is not the safety function condition) is inoperable unless it can be restarted promptly, without performing maintenance. If the attempt at restart is unsuccessful, the SSC is inoperable. The time frame for compensatory action begins at the time of the initial trip.CA SUPPORTED SSC is inoperablewhen a SUPPORT SYSTEM is not capable of performing its related support function. However, if it is determined

that the SSC is capable of performing its intended function, even with an inoperable SUPPORT SYSTEM, then the TS SUPPORTED SYSTEM may be

considered OPERABLE.D.Failure of a SSC to meet quantitative acceptance criteria specified in Surveillance Procedures is inoperable unless the Surveillance Procedure

acceptance criteria is more conservative than the existing TS SR

acceptance criteria and the results of the surveillance is clearly

within the acceptance criteria of the TS SR.E.A SSC is inoperable if it fails to meet a safety function requirement identified in a docketed letter to the NRC that specifically describes

its functional capability/requirement.F.A SSC is inoperable if its configuration results in the LOSF or a loss of capability to withstand a single failure, if required.G.If calculation indicates that a SSC will not be able to perform as needed to mitigate the affects of a design basis accident, then the SSC is inoperable.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 232of 43Revision 87 Technical Requirements Manual ATTACHMENT 2 (cont'd)

ITEMS POTENTIALLY INOPERABLEA.A suspected error in any analysis that could affect the functional status of a SSC.B.A lack of documentation that could affect the functional status of a SSC.C.A minor deviation (incorrect bolt size, tolerance/clearance, etc.) found in a SSC. Also included in this category are items such as unevaluated installation of lead shielding on a system or removal of a component from a system without using temporary restraints and without a prior

Engineering evaluation.D.An unfulfilled EQ installation or maintenance requirement for a component or device where the impact is not obvious.EXAMPLE:The EQ Program may require O-rings be replaced with new O-rings every time a cover is removed from a device and at least once every five years. The consequences of failure to replace the O-ring at the end of the five year interval may not be clear, and may or may not cause the device to be

inoperable.EXAMPLE:An unidentified wire is found in an EQ valve operator and there is not sufficient information available to determine

whether the wire is suitable for the application.E.An item found in nonconformance with electrical separation criteria specified in the UFSAR.F.An item found in noncompliance with physical separation or mechanical isolation requirements specified by Plant Drawings,Operating Procedures, Fire Hazards Analysis, etc.G.Equipment found out-of-tolerance in the nonconservative direction.H.When a SSC is found to be outside its design basis, it may be considered operable when it is judged that the SSC is capable of performing its specified functions(s). Further testing calculations, etc. may be required to support this position.I.Discovery of an unanalyzed condition associated with the current design basis (i.e., an unanalyzed condition which should have been analyzed).

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 233of 43Revision 87 Technical Requirements Manual ATTACHMENT 2 (cont'd)SFDP EVALUATION -EXAMPLE 1EXAMPLE 1: At 0100, with Unit 2 in MODE 1, the Unit 2 4160V "242" bus is determined to be inoperable due to degraded voltage. No other TS

SSC inoperabilities exist.

The 4160 V "242" bus is a SUPPORT SSC, addressed by TS LCO

3.8.9. Required Action requires restoring the bus to

OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

The following is the LOSF determination for the SUPPORTED SYSTEM:*LCO 3.3.1 RTS Instrumentation; all channels are capable of performing their design function; no LOSF exists.*LCO 3.3.2 EFSAS Instrumentation; all channels are capable of performing their design function; no LOSF exists.*LCO 3.3.3 PAM Instrumentation; since at least one channel is OPERABLE, no LOSF exists.*LCO 3.3.4 Remote Shutdown System; the functions of the PAM are still OPERABLE since the "241" 4160 V bus is OPERABLE, no LOSF exists.*LCO 3.3.5 LOP Diesel Generator Start Inst; since there is still one bus with two channels of loss of voltage Function and two channels of degraded voltage Function still OPERABLE, no LOSF exists.*LCO 3.3.6 Containment Ventilation Isolation Instrumentation; since one rad monitor is still OPERABLE, no LOSF exists.*LCO 3.3.7 Control Room Ventilation Filtration System Actuation Instrumentation; since the opposite train of the VC Filtration System is OPERABLE and powered by the offsite

train, no LOSF exists.*LCO 3.3.8 Fuel Handling Building Exhaust Filter Plenum (FHB)

Ventilation System Actuation Instrumentation; since the

other channel is OPERABLE, no LOSF exists.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 234of 43Revision 87 Technical Requirements Manual ATTACHMENT 2 (cont'd)*LCO 3.4.9 Pressurizer; the Pressurizer is still OPERABLE since two groups of heaters is still OPERABLE, no LOSF

exists.*LCO 3.4.11 Pressurizer PORVs; since bus 241 is still OPERABLE the PORVs are OPERABLE since power is still being

supplied, no LOSF exists.*LCO 3.4.15 RCS Leakage Detection Instrumentation is not lost, no LOSF exists.*LCO 3.5.2 ECCS -Operating, because Charging, Safety Injection, and RHR are OPERABLE, no LOSF exists.*LCO 3.6.3 Containment Isolation Valves; loss of one bus of the 4160 volt will not render the Containment Isolation

Valves inoperable, no LOSF exists.*LCO 3.6.6 Containment Spray and Containment Cooling Trains, Containment Cooling is not considered inoperable. No LOSF

exists because only one train is required.*LCO 3.6.7 Spray Additive Tank; with a loss of 242v bus, the spray Additive Tank is still OPERABLE, no LOSF exists.*LCO 3.7.2 Main Steam Isolation Valves; there will be no loss of function since the MSIVs will fail in the closed position.*LCO 3.7.4 Steam Generator Power Operated Valves; no LOSF exists since the valves would be placed in a closed position which is their intended position for mitigation of an accident.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 235of 43Revision 87 Technical Requirements Manual ATTACHMENT 2 (cont'd)*LCO 3.7.5 Auxiliary Feedwater is considered OPERABLE. No LOSF exists because only one train is required.*LCO 3.7.7 Component Cooling Water, is considered OPERABLE because the other subsystem is OPERABLE, no LOSF exists.*LCO 3.7.8 Essential Service Water is considered OPERABLE because SX can perform its safety function with one train no

LOSF exists.*LCO3.7.10 Control Room Ventilation Filtration System; the other train of VC Filtration System is still OPERABLE, no

LOSF exists.*LCO 3.7.11 Control Room Ventilation Temperature Control System; the other train of VC Temperature Control is still

OPERABLE, no LOSF exists.*LCO 3.7.12 Nonessential Area Exhaust Filter Plenum Ventilation System; the other 2 trains of Nonessential Area Exhaust Filter Plenum Ventilation System are OPERABLE, no LOSF exists.*LCO 3.7.13 Fuel Handling Building Ventilation System;the other train is still OPERABLE, no LOSF exists.*LCO 3.8.1 AC Sources-Operating; the opposite train is OPERABLE, no LOSF exists.*LCO 3.8.4 DC Sources -Operating; the batteries and chargers are OPERABLE, no LOSF exists.*LCO 3.8.7 Inverters -Operating; the other inverters are OPERABLE, no LOSF exists.

==

Conclusions:==

No LOSF exists. LCO 3.0.6 may be entered with a Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to restore the inoperable bus to

OPERABLE status, beginning at 0100.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 236of 43Revision 87 Technical Requirements Manual ATTACHMENT 2 (cont'd)SFDP EVALUATION -EXAMPLE 2EXAMPLE 2:At 0500, with Unit 2 in MODE 1, both channels of the Containment Radiation-High monitor are determined to be inoperable.

This instrumentation supports the Containment Ventilation Isolation instrumentation by providing input tothe

Automatic Actuation Logic and Actuation relays, and Containment Radiation-High. Since these supported functions require at least 2 channels, for the monitors, entry must be

made into the Required Actions for LCO 3.3.6.These Actions directly specifyto enter applicable Conditions and Required Actions of LCO 3.6.3 for containment valves made inoperable by isolation instrumentation (Required Action B.1). As stated in LCO 3.0.6, when the SUPPORT SYSTEM SSC Required Actions provide direction for

SUPPORTED SYSTEM SSCs, the applicable SUPPORTED SYSTEM SSC Conditions and Required Actions shall be entered. This effectively precludes the use of LCO 3.0.6.

==

Conclusion:==

The LCO 3.3.6 Required Actions should be performed, as well as those for all the inoperable SUPPORTED SYSTEMS. The SFDP will not be entered since LCO 3.0.6 cannotbe used.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 237of 43Revision 87 Technical Requirements Manual ATTACHMENT 2 (cont'd)SFDP EVALUATION -EXAMPLE 3EXAMPLE 3:At 0130, with both Units at 100% power, the Spray Additive Tank is determined to be inoperable.

Per LCO Bases 3.6.7, the Spray Additive Tank provides sodium hydroxide throughthe suction of the Containment Spray Pumps

and into the containment. The purpose of the sodium

hydroxide is to provide iodine scrubbing in the case of a

LOCA.In the event the Spray Additive Tank is inoperable, it will not disable the Containment Spray Pump to perform its

intended safety function which is to spray borated water

from the RWST into containment in order to reduce pressure and temperature. Since this function will still be performed, even with the Spray Additive Tank inoperable, it

is not considered to be a SUPPORT SYSTEM for the Containment

Spray Pump.

The same is not true in the case where the Containment Spray Pump is inoperable. In this case the Containment Spray Pump

is a SUPPORT SYSTEM for the Spray Additive Tank. If the ContainmentSpray Pump is inoperable, the sodium hydroxide, function of the Spray Additive Tank, will not be sprayed intocontainment. In this case the Spray Additive Tank is a

SUPPORTED SYSTEM to the Containment Spray Pump.Conclusion:Since the Spray Additive Tank is not a SUPPORT SYSTEM for the Containment Spray Pumps, both trains of Containment Spray are OPERABLE, and no LOSF exists.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 238of 43Revision 87 Technical Requirements Manual ATTACHMENT 2 (cont'd)SFDP EVALUATION -EXAMPLE 4EXAMPLE 4:At 1300, Unit 1 was at 100% power and Train B Essential Service Water (SX) System became inoperable with the associated LCOAR

implemented. At 1400, the Condensate Storage Tank (CST) becomes inoperable.

Train B SX is a SUPPORT SYSTEM to the Auxiliary Feedwater (AF) Pumps (SUPPORTED SYSTEM). No LOSF exists at this time

(1300 to 1359 hours0.0157 days 0.378 hours 0.00225 weeks 5.170995e-4 months ) since Train A SX is intact and, being a cross-tied system,can supply all the SX needs to both trains of AF, etc. and since no redundant systems are inoperable.

The Actions for SX (LCO 3.7.8, Action A.1) are entered. The

Actions for AF (LCO 3.7.5) are not entered since AF is

operable.At 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months , the CST becomes inoperable. The CST (LCO 3.7.6) is considered to be a SUPPORT SYSTEM to the AF.

However, the CST is not the safety related water supply to

the AF, it is only the preferred supply. At this point the plant is in 2 LCOs and a SFDP evaluation is warranted. In this case, the evaluation should show that no LOSF exists

for the following reason:

The CST does support the AF, however, the CST is not

the safety related water supply to the AF, it is only

the preferred supply. Therefore, the AF is not

inoperable due to the CST being inoperable.

Furthermore, SX remains available to AF.

==

Conclusion:==

A LOSF does not exist and Technical Specification 3.7.6 is entered for the CST inoperability.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 239of 43Revision 87 Technical Requirements Manual COMPLETION TIME EXTENSIONS APPLICABLE TO THE SFDP EXAMPLES RULES OF USAGE FOR COMPLETION TIME EXTENSIONS1.Single SUPPORT SYSTEM inoperable affecting SUPPORTED SYSTEM(s)

With a single SUPPORT SYSTEM inoperable, the affected SUPPORTED SYSTEM(s) LCOARs entry(s) is not required to be entered unless directed

by the SUPPORT SYSTEM Required Actions. Reference Case A.2.Multiple SUPPORT SYSTEMS become inoperable affecting the same SUPPORTED SYSTEM(s)When a SUPPORT SYSTEM becomes inoperable, the Required Action(s) LCOAR

entry is not required to be entered unless directed by the SUPPORT SYSTEM Required Actions. In the event additional SUPPORT SYSTEM(s) become inoperable during the Completion Time of the first SUPPORT

SYSTEM, the LCOAR entry(s) of the SUPPORTED SYSTEM(s) may be delayed by

either: a) The maximum allowed Completion Time of the SUPPORT SYSTEM(S)

OR b) 2 times the Completion Time for restoration of the SUPPORTED SYSTEM (applied at the time the second SUPPORT SYSTEM becomes inoperable), whichever is the shorter duration. Reference Cases B and C.

The SFDP requires declaring SUPPORTED SYSTEM(S) inoperable if a SUPPORT SYSTEM

inoperability renders the SUPPORTED SYSTEM incapable of performing its

required function. However, the Conditions and Required Actions of the

SUPPORTED SYSTEM do not have to be entered (i.e., the LCO Required Actions are

not entered) except as directed by the SUPPORT SYSTEM Required Actions.

Consequently, it is possible to have SUPPORTED SYSTEM(S) inoperable for longer periods of time than their respective Completion Time would allow on their

own. Per Technical Specifications 5.5.15, the SFDP must include measures to

ensure that the SUPPORTED SYSTEM's Completion Times are not inappropriately extended.TheRequired Action may be delayed only if the inoperability is due solely to an inoperability of a SUPPORT SYSTEM. If a SUPPORTED SYSTEM is made directly inoperable, then the LCO and Required Actions are entered at the time of direct inoperability per LCO 3.0.2.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 240of 43Revision 87 Technical Requirements Manual The following criteria apply to Completion Time extension:

CASE A: If only one SUPPORT SYSTEM is inoperable, General Rule 1 applies and the SUPPORTED SYSTEM LCOAR entry need not be entered unless directed by the

SUPPORT SYSTEM Required Actions.

Example:System A (SUPPORTED SYSTEM)Action Completion Time -3 daysSystem B (SUPPORT SYSTEM)Action Completion Time -7 days LCOAR entry on SUPPORTED SYSTEM A is not required to be entered.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 241of 43Revision 87 Technical Requirements Manual Case B:The SUPPORT SYSTEMS become inoperable at differenttimes. The LCOAR entry for the SUPPORTED SYSTEM may be delayed as follows:

Example:System A (SUPPORTED SYSTEM)Action Completion Time -7 daysSystem B (SUPPORT SYSTEM)Action Completion Time -3 daysSystem C (SUPPORT SYSTEM)Action Completion Time -3 days System B and C support System A System B (SUPPORT SYSTEM) is inoperable at T = 0 days Therefore: System A (SUPPORTED SYSTEM) Conditions and Required Action(s) need not be entered unless directed by the System B (SUPPORT SYSTEM)

Required Actions.

System C (SUPPORT SYSTEM) becomes inoperable 2 days after System B (SUPPORT SYSTEM) became inoperable. System B is still not OPERABLE.

Therefore: At T = 0 days until the second SUPPORT SYSTEM becomes inoperable, General Rule 1 is applied. At this point, System B (SUPPORT SYSTEM) Completion Time is 3 days. System A (SUPPORTED SYSTEM) LCOAR is

not entered unless directed by the System B (SUPPORT SYSTEM) Required

Actions.At T = 2 days, System C (SUPPORT SYSTEM) becomes inoperable. System C (SUPPORT SYSTEM) also supports System A (SUPPORTED SYSTEM) initiating

General Rule 2 at T = 2 days. System C (SUPPORT SYSTEM) has a

Completion Time of 3 days. Therefore, the maximum Completion Time for this scenario is from T = 0 days to T = 3 days for System B (SUPPORT SYSTEM), and from T = 2 days to T = 5 days for System C (SUPPORT

SYSTEM). The maximum delay time for System A (SUPPORTED SYSTEM) LCOAR

entry is 5 days because:

System B (SUPPORT SYSTEM) Completion Time is T = 3 days System C (SUPPORT SYSTEM) Completion Time is T = 5 days

T = 5 days is the longer of the two completion times and is compared with the two times the SUPPORTED SYSTEMS's completion time for restoration. System C (SUPPORT SYSTEM) completion time is at T=5days. System A (SUPPORTED SYSTEM) completion time limit is 2X7 = 14 days after T = 2 days. T = 2 + 14 or a total of 16 days.

Since T = 5 days is less than T = 16 days, the maximum allowed delay time to enter the System A (SUPPORTED SYSTEM) LCOAR is the shorter of

the two, 5 days.

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 242of 43Revision 87 Technical Requirements Manual CASE C: Two SUPPORT SYSTEMS become inoperable at different times. The LCOAR entry for the SUPPORTED SYSTEM may be delayed as follows:

Example:System A (SUPPORTED SYSTEM)Action Completion Time -3 days System B (SUPPORT SYSTEM)Action Completion Time -3 daysSystem C (SUPPORT SYSTEM)Action Completion Time -7 days System B and C support System A Case C1-System B (SUPPORT SYSTEM) B becomes inoperable at T = 0 days.

System B (SUPPORT SYSTEM) with a Completion Time of 3 days, renders System A (SUPPORTED SYSTEM) inoperable. General Rule 1 is

applied, which allows an overall Completion Time of 3 days for the System B (SUPPORT SYSTEM). The LCOAR for System A (SUPPORTED SYSTEM) is not required to be entered unless directed by the

System B (SUPPORT SYSTEM) Required Actions.

At T = 1 day, System C (SUPPORT SYSTEM) becomes inoperable and has a Completion Time of 7 days. System C (SUPPORT SYSTEM) also supports System A (SUPPORTED SYSTEM). System B (SUPPORT SYSTEM)

continues to remain inoperable through its Completion Time T = 3

days.Once System C (SUPPORT SYSTEM) becomes inoperable concurrent with System B, General Rule 2 is applied at T=1, the Completion Times

are: T = 0 days to T = 3 days for System B (SUPPORT SYSTEM), and T = 1 day to T = 8 days for System C (SUPPORT SYSTEM).

At T = 3 days System B (SUPPORT SYSTEM) is not declared OPERABLE, and the appropriate subsequent Required Actions of System B (SUPPORT SYSTEM) are entered. The Required Actions of System A (SUPPORTED SYSTEM) A are not entered (unless SUPPORT SYSTEM B or C

Required Actions specifically direct them to be entered) until

T = 7 days (2 times System A's Completion Time after T = 1 day).

T = 7 days is less than System C's T = 8 days Completion Time. Not entering the Required Actions for System A (SUPPORTED SYSTEM) is

allowed under LCO 3.0.6 provided the inoperability of System A (SUPPORTED SYSTEM) is solely due to the inoperability of System B (SUPPORT SYSTEM) and subsequently System C (SUPPORT SYSTEM).

TRM Safety Function Determination Program (SFDP)

Appendix OBRAIDWOOD UNITS 1 & 243of 43Revision 87 Technical Requirements Manual Case C2-AtT = 0 day, System B (SUPPORT SYSTEM) becomes inoperable, withaCompletion Time of 3 days, and renders System A (SUPPORTED SYSTEM)inoperable. General Rule 1 is applied, which allows an overall Completion Time of 3 days for System B (SUPPORT SYSTEM).AtT = 1 days, System C (SUPPORT SYSTEM) becomes inoperable and has a Completion Time of 7 days. System C (SUPPORT SYSTEM) also supports SystemA(SUPPORTED SYSTEM). When System C (SUPPORT SYSTEM) becomes inoperable, General Rule 2 is triggered requiring System A (SUPPORTED SYSTEM)LCOAR entry no later than day 7 (2 x 3 days after T=1). The

Completion Times are:

From T = 0 day to T = 3 days for System B (SUPPORT SYSTEM), and From T = 1 day to T = 8 days for System C (SUPPORT SYSTEM).

System B (SUPPORT SYSTEM) is declared OPERABLE at T = 2 days.

System C (SUPPORT SYSTEM) remains inoperable and consequently, System A (SUPPORTED SYSTEM) is stillinoperable solely due to its SUPPORT SYSTEM (System C) being inoperable. At this point, General Rule 2 remainsin effectto eliminate continuous alternating inoperabilities. This would allowthe Required Action entry for System A (SUPPORTED SYSTEM) to still bedelayed only until day 7 (T = 1 + 6 days).

TRM Containment Leakage Rate Testing Program Appendix P BRAIDWOOD UNITS 1 & 2 1 of 6 Revision 57 Technical Requirements Manual CONTAINMENT LEAKAGE RATE TESTING PROGRAM BRAIDWOOD TABLE OF CONTENTS SECTIONS TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS 1.4 PROGRAM DESCRIPTION

1.5 PROGRAM IMPLEMENTATION 1.6 ACCEPTANCE CRITERIA 1.7 LCOARS/COMPENSATORY MEASURES

1.8 REPORTING REQUIREMENTS 1.9 CHANGE CONTROL

TRM Containment Leakage Rate Testing Program Appendix P BRAIDWOOD UNITS 1 & 2 2 of 6 Revision 57 Technical Requirements Manual

1.1 PURPOSE

This Program provides controls to implement 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 including routine inspections, tests, and reporting requirements pursuant to Technical Specification (TS) 5.5.16, "Containment Leakage Rate Testing Program." The Program

inspection and test frequencies and associated acceptance

criteria shall be in accordance with the guidelines contained in Regulatory Guide 1.163, September 1995, NEI 94-01, Revision 0, and ANSI/ANS-56.8-1994 as modified by approved exceptions as specified in TS 5.5.16. Exceptions to the guidance in NEI 94-01, Revision 0 and ANSI/ANS-56.8-1994 are as stated in Regulatory Guide 1.163 and TS 5.5.16.

1.2 REFERENCES

1. Technical Specifications:

a. 3.6.1, "Containment"

b. 3.6.2, "Containment Air Locks"

c. 3.6.3, "Containment Isolation Valves" d. 5.5.16, "Containment Leakage Rate Testing Program"

e. TS Amendment No. 149, "Request for Amendment to Technical Specification 5.5.16, "Containment Leakage Rate Testing Program,"" issued April 2, 2008

2. UFSAR:

a. Section 6.2, "Containment Systems" b. Section 6.2.6.1, "Containment Integrated Leakage Rate Test" c. Section 6.2.6.2, "Containment Penetration Leakage Rate Test"

3. NRC/Industry Documents:

a. NEI 94-01 Rev. 0, "Industry Guideline for Implementing Performance-Based Option of 10 CFR 50, Appendix J" TRM Containment Leakage Rate Testing Program Appendix P BRAIDWOOD UNITS 1 & 2 3 of 6 Revision 57 Technical Requirements Manual

b. ANSI/ANS-56.8-1994, "Containment System Leakage Testing Requirements" c. 10 CFR 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors" d. NRC Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program"

e. NUREG 1493, "Performance-Based Containment Leak-Test Program" 4. Braidwood Maintenance Rule 10 CFR 50.65

1.3 DEFINITIONS AND/OR ACRONYMS

1. PERFORMANCE CRITERIA - The performance standards against which test results are to be compared for establishing the acceptability of the containment system as a leakage-limiting boundary.

2. CONTAINMENT SYSTEM - The principal barrier, after the reactor coolant pressure boundary, to prevent the release of quantities of radioactive material that would have a significant radiological effect on the health of the public.

3. OVERALL INTEGRATED LEAKAGE RATE - The total leakage rate through all tested leakage paths, including containment welds, valves, fittings, and components that penetrate the containment system.

4. L a - The maximum allowable primary containment leakage rate, L a , shall be 0.20% of the primary containment air weight per day at the calculated peak containment pressure (P a). 5. P a - The maximum calculated primary pressure, P a , (Unit 1 =

42.8 psig) (Unit 2 = 38.4 psig) for the design basis loss of

coolant accident.

6. TYPE A TEST - An Integrated Leakage Rate Test (ILRT) to measure the CONTAINMENT SYSTEM overall integrated leakage rate under conditions representing DBA containment pressure and systems alignments.

TRM Containment Leakage Rate Testing Program Appendix P BRAIDWOOD UNITS 1 & 2 4 of 6 Revision 57 Technical Requirements Manual 7. TYPE B TEST - A Local Leakage Rate Test (LLRT) intended to detect or measure leakage across pressure-retaining or

leakage-limiting boundaries other than valves, such as:

a. containment penetrations whose design incorporates resilient seals, gaskets, sealant compounds, expansion

bellows, or flexible seal assemblies;

b. seals, including door operating mechanism penetrations, which are part of the primary containment; or

c. doors and hatches with resilient seals or gaskets except for seal-welded doors.

8. TYPE C TESTS - A pneumatic Local Leakage Rate Test (LLRT) to measure containment isolation valve leakage rates.

9. UPPER CONFIDENCE LIMIT (UCL) - A calculated value constructed from test data which places a statistical upper

bound on the true integrated leakage rate (%/24h).

10. MINIMUM PATHWAY LEAKAGE RATE (MNPLR) - The minimum leakage rate that can be attributed to a penetration leakage path (e.g., the smaller of either the inboard or outboard barrier's individual leakage rates).

11. MAXIMUM PATHWAY LEAKAGE RATE (MXPLR) - The maximum leakage rate attributed to a penetration leakage path. The MXPLR is the larger, not the total, leakage of two valves in series.

1.4 PROGRAM DESCRIPTION This Program provides administrative guidelines for the Braidwood Containment Leakage Rate Testing Program, guidelines for the

coordination of inspection, trending, reporting, performance evaluation, repair, establishing surveillance intervals, and regulatory compliance for Type A, B, and C leakage testing.

10 CFR 50 Appendix J Option B allows the use of a performance-based program to perform the Type A, B, and C containment leakage testing. Program requirements are further defined in References

3.a, 3.b, 3.c, and 3.d. These documents require that periodic testing be conducted to verify the leakage integrity of the containment and those systems and components which penetrate the containment. The objective for monitoring performance of TYPE A TESTS focuses on verifying the leakage integrity of a passive TRM Containment Leakage Rate Testing Program Appendix P BRAIDWOOD UNITS 1 & 2 5 of 6 Revision 57 Technical Requirements Manual containment structure.

TYPE B and C TESTS focus on assuring that containment penetrations are essentially leak tight. The results of these tests are

evaluated against performance criteria and the required testing intervals are adjusted based on the performance of the component/system.

Option B allows licensees with good ILRT performance history to

reduce the TYPE A TEST frequency from three tests in 10 years to one test in 10 years. Exception to the Option B TYPE A TEST frequency is as specified in TS 5.5.16. For TYPE B and TYPE C TESTS, Option B allows Braidwood Station to reduce testing frequency based on the experience history of each component, and establish controls to ensure continued performance during the extended testing interval. Type B and C LLRT intervals utilize the

requirements and guidance as stipulated in Reference 3.a and 3.d.

1.5 PROGRAM IMPLEMENTATION Inspection, trending, reporting, performance evaluation, repair, surveillance intervals, and regulatory compliance for Type A, B, and C leakage testing shall be initiated and maintained in

accordance with the Braidwood Containment Leakage Rate Testing Program. 1.6 ACCEPTANCE CRITERIA

Acceptance criteria for TYPE A TESTS are contained in applicable Station Procedures. Acceptance criteria for TYPE B and C TESTS are contained in applicable Station Procedures. The acceptance criteria specified in the individual leak rate test procedures are administrative guidelines that are used to help maintain low containment leakage rates. The acceptance criteria associated with the individual leak rate test procedures are not Technical

Specification requirements with the exception of the personnel/emergency airlock door seals and overall air lock leakage. The acceptance criteria associated with the personnel/emergency airlock door seals and overall air lock leakage are as specified in TS 5.5.16.

TRM Containment Leakage Rate Testing Program Appendix P BRAIDWOOD UNITS 1 & 2 6 of 6 Revision 57 Technical Requirements Manual 1.7 LCOARS/COMPENSATORY MEASURES If any abnormalities in containment leakage exceed the acceptance criteria, the Shift Manager will be immediately notified. The

Shift Manager shall determine OPERABILITY status and implement a LCOAR as applicable. In addition, an Issue Report (IR) may need to be generated to provide proper tracking and resolution of noted problems associated with the implementation of this Program.

1.8 REPORTING REQUIREMENTS Any reporting requirements associated with acceptance criteria of this Program not being met shall be reported in accordance with the requirements specified in the implementing procedures.

1.9 CHANGE CONTROL Changes to this Program, other than editorial changes, shall

include a 10 CFR 50.59 Review and a Station Qualified Review (SQR). The SQR composition shall include the Regulatory Assurance Department in all cases. As part of the SQR, Byron and Braidwood Plant Operations Review Committee (PORC) approval is required as determined by the Regulatory Assurance Manager.

Byron and Braidwood shall implement the same change unless the change being implemented at Braidwood has been reviewed and was determined not to be applicable to Byron.

SECTION 1.1 1.2 1.3 1.4 1.5 1.6 1. 7 1.8 1.9 TECHNICAL REQUIREMENTS MANUAL CONTROL PROGRAM TABLE OF CONTENTS TITLE PURPOSE REFERENCES DEFINITIONS AND/OR ACRONYMS PROGRAM DESCRIPTION PROGRAM IMPLEMENTATION ACCEPTANCE CRITERIA LCOARS/COMPENSATORY MEASURES REPORTING REQUIREMENTS CHANGE CONTROL BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 1 of 12 TRM TRM Control Program Appendix S Revision 64 1.1 PURPOSE TRM TRM Control Program Appendix S The purpose of this Program is to provide guidance for identifying, processing, and implementing changes to the Technical Requirements Manual (TRM). This Program implements and satisfies the requirements of TRM Section 1.6, .. Technical Requirements Manual Revisions." This Program is applicable to the preparation, review, implementation, and distribution of changes to the TRM. This Program also provides guidance for preparing TRM Change Packages for distribution.

1.2 REFERENCES

1. TRM Section 1.6, "Technical Requirements Manual Revisions" 2. 10 CFR 50.4, "Written Corrrnunications" 3. 10 CFR 50.59, "Changes, Tests and Experiments" 4. 10 CFR 50.71, "Maintenance of Records, Making of Reports" 5. 10 CFR 50.90, "Application for Amendment of License or Construction Permit" 1.3 DEFINITIONS AND/OR ACRONYMS 10 CFR 50.59 REVIEW -A written regulatory evaluation which provides the basis for the determination that a change does, or does not, require NRC approval pursuant to 10 CFR 50.59. The scope of the evaluation should be conmensurate with the potential safety significance of the change, but must address the relevant safety concerns included in the Safety Analysis Report and other owner controlled documents.

The depth of the evaluation must be sufficient to determine whether or not NRC approval is required prior to implementation.

Depending upon the significance of the change, the evaluation may be brief; however, a simple statement of conclusion is not sufficient.

BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 2 of 12 Revision 64 TRM TRM Control Program Appendix S EDITORIAL CHANGE -Editorial changes include correction of punctuation, insignificant word or title changes, style or fonnat changes, typographical errors, or correction of reference errors that do not change the intent, outcome, results, functions, processes, responsibilities, or performance requirements of the item being changed. Changes in numerical values shall .nQt be considered as editorial changes. Editorial changes do not constitute a change to the TRM and therefore do not require further 10 CFR 50.59 Reviews. If the full scope of this proposed change is encompassed by one or more of the below, then the change is considered editorial.

Rewording or format changes that do not result in changing actions to be accomplished.

Deletion of cycle-specific information that is no longer applicable.

Addition of clarifying information, such as: Spelling, grarrmar, or punctuation changes Changes to references Name or title references 1.4 PROGRAM DESCRIPTION

1. A Licensee may make changes to the TRM without prior NRC approval provided the changes do not require NRC approval pursuant to 10 CFR 50.59. 2. 3. 4. 5. Changes that require NRC approval pursuant to 10 CFR 50.59 shall be submitted to the NRC pursuant to 10 CFR 50.90 and reviewed and approved by the NRC prior to implementation.

The TRM is part of the Updated Final Safety Analysis Report (UFSAR) by reference and shall be maintained consistent with the remainder of the UFSAR. If a change to the TRM is not consistent with the remainder of the UFSAR, then the cognizant Engineer shall prepare and submit a UFSAR Change Package when the TRM Change Request is submitted to Regulatory Assurance (RA) for processing.

Changes to the TRM that do not require prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e), as modified by approved exemptions.

BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 3 of 12 Revision 64

6. 7. TRM TRM Control Program Appendix S TRM changes associated with a Technical Specifications (TS) I Amendment shall be implemented consistent with the implementation requirements of the TS Amendment.

RA is responsible for the control and distribution of the TRM. In order to prevent distribution errors (i.e., omissions or duplications), RA shall maintain the master TRM distribution list. 1.5 PROGRAM IMPLEMENTATION

1. TRM Change Requester identifies the need for a revision to the TRM and notifies the RA Licensing Engineer (i.e., hereafter referred to as RA LE). A TRM change can be initiated through any Stations' RA. TRM Change Requester notifies their counterparts on the need for a change. 2. RA LE notifies their counterparts of identified need for revision to the TRM. 3. RA LE assigns a TRM Change Request Nunt>er CCR#). 4. RA LE drafts TRM changes considering fonnat, rules of usage, and technical adequacy.

5. RA LE makes an electronic version of the proposed TRM changes available in a working directory for use in the preparation of the 10 CFR 50.59 REVIEW and Station Qualified Review (SQR) process. The RA LE shall ensure that the master electronic TRM files are revised per step 12 below upon receiving SOR approval.

The Revision number in the footer should be a sequential number {i.e., 1, 2, etc.). BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 4 of 12 Revision 64 TRM TRM Control Program Appendix S *************************************************************

NITTE * * *

If the TRM changes are applicable to more than one *

Station, the following steps should be performed

concurrently for each Station. * *************************************************************

6. 7. TRM Change Requestor provides a 10 CFR 50.59 REVIEW for the TRM changes in accordance with appropriate plant procedures.

An exception to this requirement applies when the changes are being requested in order to reflect an approved NRC Safety Evaluation (SE) associated with a site specific Operating License or TS change. The NRC SE is sufficient to support the changes provided it has been determined that the changes are consistent with and entirely bounded by the NRC SE. A 10 CFR 50.59 REVIEW shall be performed for TRM changes that reflect generic industry approval by an NRC SE to determine site specific applicability.

A 10 CFR 50.59 REVIEW is not required for an EDITORIAL CHANGE. TRM Change Requester completes AttachTient A, "Technical Requirements Manual Change Request Fann," as follows: a. b. c. d. e. Identifies the affected sections, and includes a copy of the proposed TRM changes; Briefly surrmarizes the changes including the TLCO, Action, Surveillance Requirement, or Bases (if applicable) to which the changes apply; Briefly surrmarizes the reason for the changes and attaches all supporting documentation; Identifies any schedule requirements and proposed implementation date that apply (i.e., describe any time limitations that might apply which would require expedited processing).

If the changes are outage related, then checks "yes" and lists the applicable outage identifier; Identifies any known implementation requirements such as procedure changes, UFSAR changes, Passport changes, Reportability Manual revisions, ifl{)lementation training requirenents, etc.; BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 5 of 12 Revision 64

f. g. h. i. j. k. TRM TRM Control Program Appendix S If a 10 CFR 50.59 REVIEW was prepared to support the TRM changes, the Requester then checks the appropriate box, lists the associated 10 CFR 50.59 REVIEW Number, and attaches the original; If the changes to the TRM are the result of an approved NRC SE associated with a site specific Operating License or TS change and the scope of the changes determined to be consistent with and entirely bounded by the NRC SE, then the Requester checks the appropriate box and attaches a copy; If the changes to the TRM are EDITORIAL CHANGES, then the Requester checks the appropriate box and no 10 CFR 50.59 REVIEW is required; Signs and dates as Requestor and identifies the originating department; Obtains approval to proceed from Department Supervisor (or designee);

and Returns Attachment A to the RA LE. 8. RA LE reviews the TRM Change Request Form, including supporting documentation, and documents the review by signing Attachment A. The review verifies that the following information or documentation is included:

a. Completed 10 CFR 50.59 REVIEW. If the changes are related to an approved NRC SE associated with a site specific Operating License or TS change and determined to be entirely bounded by the NRC SE, then only a copy of the SE is required to be attached and no 10 CFR 50.59 REVIEW is required.

A 10 CFR 50.59 REVIEW is not required for an EDITORIAL CHANGE; b. Identification of known documents requiring revisions; and c. Completed UFSAR Change Request with supporting docllllentation, in accordance with appropriate plant procedures, if applicable.

9. If the TRM change is not an EDITORIAL CHANGE, the RA LE/TRM Change Requester obtains SOR approval of the TRM change by performing the following:

BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 6 of 12 Revision 64

a. b. c. TRM TRM Control Program Appendix S RA LE prepares the TRM Change SOR package. The SOR package shall include Attachment A (including completed 10 CFR 50.59 REVIEW or NRC SE) and the revised TRM pages. Attachnent A is provided for the purpose of reviewing and finalizing the implementation requirements and ensuring the necessary actions have been initiated.

RA LE shall assign Action Tracking CAT) items, as necessary, to track implementation requirements; TRM Change Requester submits the TRM Change SOR package to the SOR Comnittee members for a preliminary review. The SOR composition shall include RA and Operating Departments in all cases; and TRM Change Requester resolves preliminary review comnents and finalizes the TRM Change SOR package. 10. The RAM shall detennine the need for Plant Operations Review Comnittee (PORC) approval.

The need for PORC approval shall be documented on Attachment A. 11. RA LE/TRM Change Requester obtains PORC approval, if necessary.

12. After approval of the TRM changes by SOR/PORC, RA LE ensures that the controlled master electronic files are updated. 13. RA LE completes Attachment B, "Technical Requirements Manual Change Instruction Fann," as follows: a. Indicates the effective date of the TRM changes consistent with the SOR/PORC approval or TS amendment required implementation date. If the TRM change is a result of a TS Amendment, the update shall be implemented consistent with the implementation requirements of the TS Amendment.

Otherwise, the update must be irfl>lemented by the date indicated on Attachment B; b. Lists each page to be removed and inserted, including the Affected Page List; and c. Provides the updated master file directory for updating Electronic Document Management System (EOMS), if applicable.

BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 7 of 12 Revision 64 TRM TRM Control Program Appendix S 14. RA LE creates a TRM Change Package. The TRM Change Package 15. 16. 17. 18. 20. shall consist of: 1. TRM Change Instruction Form (Attachment B); 2. Revised Affected Page List; and 3. Revised TRM pages. One RA LE shall assemble and approve the TRM Change Package for distribution and a second RA LE shall perform a peer check to verify completeness of the TRM Change Package. After verifying that SQR/PORC approval of the TRM changes has been obtained and that all AT items assigned to track implementation requirements have been completed, RA LE forwards the TRM Change Package to Station Records Management as notification of the need to update the onsite TRM controlled copies and EDMS, if applicable.

RA LE also forwards the TRM Change Package to Cantera Licensing (CL) Records Management as notification of the need to update the offsite (CL) TRM controlled copies and to transmit updates to the offsite (non-CL) TRM controlled copies. Upon completion of updating the onsite TRM controlled copies and EDMS (if applicable), Station Records Management Supervisor signs and dates Attachment B and returns Attachment B to the RA LE. Upon completion of updating the offsite (CL) TRM controlled copies and transmitting updates to the offsite (non-CL) TRM controlled copies, CL Records Management signs and dates Attac'11'Tx=nt B and returns Attachment B to the RA LE. RA LE ensures that the documentation required to be maintained as a quality record is provided to Station Records Management for the purpose of record retention.

BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 8 of 12 Revision 64 1.6 ACCEPTANCE CRITERIA Not applicable.

1.7 LCOARS/COMPENSATORY MEASURES TRM TRM Control Program Appendix S An Issue Report may need to be generated to provide proper tracking and resolution of noted problems associated with the implementation of this Program. The RAM will be responsible for ensuring that Program failures have been resolved.

1.8 REPORTING REQUIREMENTS

NITTE * * *

TRM changes requiring prior NRC approval shall be *

submitted in accordance with Reference

5. * * * *************************************************************

TRM changes not requiring prior NRC approval, as described in Section 1.4 of this Program, shall be submitted to the NRC in accordance with 10 CFR 50.71Ce).

1.9 CHANGE CONTROL Changes to this Program, other than EDITORIAL CHANGES, shall include a 10 CFR 50.59 REVIEW and a SQR. The SOR composition shall include RA Department in all cases. For a change to this Program, PORC approval from all Stations is required.

The concurrence shall be that the other Stations are implementing the same changes or that the changes have been reviewed and determined not to be applicable to the other Stations.

BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 9 of 12 Revision 64

1. ATIACHMENT A TRM TRM Control Program Appendix s TECHNICAL REQUIREMENTS MANUAL CHANGE REQUEST FORM Change Request #: Affected TRM Section(s):

2. Description of changes: 3. Reason for changes (attach all supporting documentation):

4. 5. 6. 7. 8. 9. 10. Schedule Requirements:

Outage Related (check one) Other (explain) 0 No 0 Yes, Outage# ___ _ Implementation Requirements (attach additional pages, as necessary):

Identify the impact of the changes on the following:

Affected NlA 0 0 0 0 0 0 0 0 0 0 D D 0 0 0 0 0 0 D 0 0 0 0 D 0 0 0 0 0 0 0 0 0 0 0 0 0 0 D 0 D 0 D 0 Check one: UFSAR _________________

_

TS Bases NRC Safety Evaluation Fire Protection NRC ConmitnEnts Vendor Docl.IOOntation Special Pennits/Licenses Procedures

__ ,,.......,,...,......,..-.-------------

Enviromental Qualification

___________

_

Basis Doct.11B1tation Engineering PRA Infonnation

Programs-----------------

Reportability Manual QA Topical Report---------------

Passport'---_...,._-=-.........,..____,-...--..-----------

Pre-lllf>lenEntation Training Required---------

Maintenance Offsite Dose Calculation Manual -----------

mher _________________________

__ 0 10 CFR 5"0.59 REVIEW Attached, 10 CFR 50.59 REVIEW #: _______ _ 0 NRC SE Attached, Changes consistent with and entirely bounded by NRC SE 0 EDITORIAL CHANGE, No 10 CFR 50.59 REVIEW required Requestor:

I ! ________ _ (Signature) (Date) (Department)

Requesting Supervisor Approval:

--,.....,----------'!

__________

__ (Signature) (Date) PORC Approval Required:

0 Yes 0 No ( Signature) (Date) Licensing Engineer Review: BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 10 of 12 Revision 64 TRM TRM Control Program Appendix S AITACHMENT B TECHNICAL REQUIREMENTS MANUAL CHANGE INSTRUCTION FORM FOR ONSITE/OFFSITE DISTRIBUTION AND FOR UPDATING EDMS Braidwood/Byron/Dresden/LaSalle/QC (circle one) TRM NOTE: This change is effective as of and shall be implemented by (SQR/PORC or Amendment Implementation Date) <Date) Approved for distribution: (RA LE Signature)

Verified: (RA LE Signature)

REMOVE REMOVE INSERT INSERT Section Paqe Section Paae Affected All Affected Page All Page List List BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 11 of 12 <Date) (Date) UPDATE EDMS UPDATE EDMS Section Paae N/A N/A Revision 64 TRM TRM Control Program Appendix S ATTACHMENT B TECHNICAL REQUIREMENTS MANUAL CHANGE INSTRUCTION FORM FOR ONSITE/OFFSITE DISTRIBUTION AND FOR UPDATING EDMS Braidwood/Byron/Dresden/LaSalle/QC (circle one) TRM Revision#

__ Station Records Management:

Onsite Distribution Completed: ( St at ion Records Mgmt. Supr.) (Date) EDMS Update Completed: (St at ion Records Mgmt. Supr.) (Date) ** Return this sheet to: Regulatory Assurance Braidwood/Byron/Dresden/LaSalle/QC (circle one) Station CL Records Management:

Offsite (CL) Distribution Completed:

CCL Records Mgmt. Dept.) (Date) Offsite (non-CU Distribution Transmitted:------------------(CL Records Mgmt. Dept.) (Date) ** Return this sheet to: Regulatory Assurance Braidwood/Byron/Dresden/LaSalle/QC (circle one) Station Offsite (non-CL) Controlled Copy Holders: Offsite (non-CL) Distribution Completed: (Signature)

- Return this sheet to: EXELON GENERATION COMPANY, LLC LICENSING AND REGULATORY AFFAIRS DEPARTMENT 4300 WINFILED ROAD WARRENVILLE, IL 60555 BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 12 of 12 (Date) Revision 64 TRM Configuration Risk Management Program Appendix T BRAIDWOOD UNITS 1 & 2 1 of 4 Revision 9 Technical Requirements Manual CONFIGURATION RISK MANAGEMENT PROGRAM BRAIDWOOD TABLE OF CONTENTS SECTION TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS

1.4 PROGRAM DESCRIPTION 1.5 PROGRAM IMPLEMENTATION 1.6 ACCEPTANCE CRITERIA 1.7 LCOARS/COMPENSATORY MEASURES

1.8 REPORTING REQUIREMENTS 1.9 CHANGE CONTROL

TRM Configuration Risk Management Program Appendix T BRAIDWOOD UNITS 1 & 2 2 of 4 Revision 9 Technical Requirements Manual

1.1 PURPOSE

This Configuration Risk Management Program provides a

proceduralized process to ensure that a configuration risk assessment is conducted prior to and during performance of maintenance activities that remove SSCs from service.

1.2 REFERENCES

1. Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants" 2. Regulatory Guide 1.174, "An Approach for using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis"

3. Regulatory Guide 1.177, "An Approach for Plant-Specific-Risk-Informed Decisionmaking: Technical Specifications" 4. NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants" 1.3 DEFINITIONS AND/OR ACRONYMS

1. Configuration Risk Management Program - CRMP

2. Probabilistic Risk Assessment - PRA

3. Structure, System, or Component - SSC TRM Configuration Risk Management Program Appendix T BRAIDWOOD UNITS 1 & 2 3 of 4 Revision 9 Technical Requirements Manual 1.4 PROGRAM DESCRIPTION The CRMP is a subset of the work management process. The CRMP ensures that configuration risk is assessed (probabilistic and/or deterministic), and managed, prior to initiating any maintenance activity consistent with the requirements of 10 CFR 50.65. The CRMP also ensures that risk is reassessed if an emergent condition results in a plant configuration that has not been previously

assessed.

Probabilistic risk assessments of online configurations are performed using the level 1 PRA model. Deterministic defense-in-depth evaluations of key safety functions are performed for online and shutdown configurations using a safety function assessment module. Deterministic evaluations of plant configurations that

result in a change to initiating event frequency and/or decrease in mitigation capability are performed using a plant transient assessment module.

The CRMP establishes risk thresholds and administrative limits for risk significant configuration out of service times to ensure that average baseline risk is maintained within an acceptable band.

Overall risk is managed to the most restrictive risk threshold specified within the CRMP. Risk significant configurations are generally avoided. If a risk significant configuration occurs, immediate actions are taken to protect redundant/diverse SSCs that

are relied upon to mitigate events.

The CRMP requires that the PRA model meet industry certification standards to ensure the scope and quality of the PRA is adequate.

The CRMP requires that the PRA model the current design configuration of the plant, and that plant modification and procedure changes are monitored and evaluated as to the impact on

the PRA model. The CRMP establishes compensatory measures in the event a plant configuration is outside the scope of the PRA, or PRA results are unavailable.

1.5 PROGRAM IMPLEMENTATION The CRMP is implemented through a company-wide standard procedure.

The Work Control and Risk Management Engineering Departments are responsible for the CRMP and associated procedure implementation at the stations.

TRM Configuration Risk Management Program Appendix T BRAIDWOOD UNITS 1 & 2 4 of 4 Revision 9 Technical Requirements Manual 1.6 ACCEPTANCE CRITERIA The configuration risk management acceptance criteria are contained within the implementing procedures.

1.7 LCOARS/COMPENSATORY MEASURES The CRMP provides administrative limits for Technical

Specification Limiting Condition of Operation Allowed Outage Time and Maintenance Rule unavailability time. When the administrative limit will be exceeded, compensatory measures are established to reduce risk, limit unavailability time, and implement a contingency plan to restore and/or mitigate the loss of a key safety function.

1.8 REPORTING REQUIREMENTS The normal work management process and control room logs provide adequate documentation of configuration risk.

1.9 CHANGE CONTROL Changes to this Program, other than editorial changes, shall include a 10 CFR 50.59 evaluation and an Independent Technical

Review (ITR). The ITR composition shall include Regulatory Assurance Department in all cases. As a part of the ITR, for a change to this Program, concurrence from Byron and the Braidwood Plant Operations Review Committee (PORC) approval is required.

The concurrence shall be that Byron is implementing the same change or that the change has been reviewed and determined not to be applicable to Byron.

TRM Battery Monitoring and Maintenance Program Appendix UBRAIDWOOD UNITS 1 & 21of 4Revision 26 Technical Requirements Manual BATTERY MONITORING AND MAINTENANCE PROGRAM BRAIDWOOD TABLE OF CONTENTS SECTIONS TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS 1.4 PROGRAM DESCRIPTION 1.5 PROGRAM IMPLEMENTATION 1.6 ACCEPTANCE CRITERIA 1.7 LCOARS/COMPENSATORY MEASURES 1.8 REPORTING REQUIREMENTS 1.9 CHANGE CONTROL TRM Battery Monitoring and Maintenance Program Appendix UBRAIDWOOD UNITS 1 & 22of 4Revision 26 Technical Requirements Manual1.1PURPOSE This Program provides guidance and clarifying information related to the Battery Monitoring and Maintenance Program. This Program

complies with the requirements of Technical Specification (TS) 5.5.17, "Battery Monitoring and Maintenance Program." This program provides for the restoration and maintenance of batteries

based on the recommendations given in Reference 2.

1.2REFERENCES

1.TS 5.5.17, "Battery Monitoring and Maintenance Program"2.IEEE Standard 450-1995, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications"3.UFSAR Chapter 8, "Electric Power"4.NRC Regulatory Guide 1.129, "Maintenance, Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants"1.3DEFINITIONS AND/OR ACRONYMS1.ELECTROLYTE LEVEL -The battery cell fluid level found by visual observation.2.BATTERY CELL PARAMETERS -Voltage, specific gravity, and resistance/impedance.3.INTER-CELL/INTER-TIER or INTER-RACK CONNECTIONS -

Connections made between rows/steps or racks of individual

battery cells.4.FLOAT VOLTAGE -The voltage applied to a battery to maintain it in a fully charged condition during normal

operation.5.SPECIFIC GRAVITY -A measurement of an individual battery cell electrolyte to determine the state of charge.6.ELECTROLYTE LEVEL MINIMUM ESTABLISHED DESIGN LIMIT -

1/2 inch below the minimum level indication mark.7.ELECTROLYTE TEMPERATURE MINIMUM ESTABLISHED DESIGN LIMIT -

60!F.

TRM Battery Monitoring and Maintenance Program Appendix UBRAIDWOOD UNITS 1 & 23of 4Revision 26 Technical Requirements Manual1.4PROGRAM DESCRIPTION This Program ensures the methodologies, parameters, and corrective actions comply with the reference requirements. This Program addresses the station 125 VDC Engineered Safety Features (ESF) Batteries (Division 11(21) and Division 12(22)).

The OPERABILITY requirements for the 125 VDC ESF Batteries are defined in TS Limiting Conditions for Operation (LCOs) 3.8.4, "DC Sources -Operating," 3.8.5, "DC Sources -Shutdown," and3.8.6, "Battery Parameters." LCO 3.8.6 delineates the limits on battery

float current as well as electrolyte temperature, level, and

float voltage.

This Program which complies with the requirements of TS 5.5.17 provides for monitoring various battery parameters based on the

recommendations of Reference 2.1.5PROGRAM IMPLEMENTATION The Battery Monitoring and Maintenance Program contains the

methodology and parameters used to ensure the station batteries

are capable of meeting design and operating requirements.

As required by TS 5.5.17, this Program provides for the restoration and maintenance, based on the recommendations of

Reference 2 or of the battery manufacturer of the following:1.Actions to restore battery cells with float voltage

< 2.13 V, and2.Actions to equalize and test battery cells that had been discovered with electrolyte level below the minimum established design limit.

This Program is implemented by Technical Requirements Manual Limiting Condition for Operation (TLCO) 3.8.c, "Battery

Monitoring and Maintenance." The Bases for TLCO 3.8.c is provided in Attachment A to this Program.

TRM Battery Monitoring and Maintenance Program Appendix UBRAIDWOOD UNITS 1 & 24of 4Revision 26 Technical Requirements Manual1.6ACCEPTANCE CRITERIA The acceptance criteria are contained in station operating or surveillance procedures. TLCO 3.8.c contains the Conditions, Required Actions and associated Completion Times, and Surveillance Requirements required to comply with TS 5.5.17.1.7LCOARS/COMPENSATORY MEASURES TLCO 3.8.c provides the Conditions, Required Actions and

associated Completion Times, and Surveillance Requirements

required to comply with TS 5.5.17. The requirements of TLCO

3.8.c are proceduralized via the associated LCOAR.1.8REPORTING REQUIREMENTS There are no reporting requirements for the Battery Monitoring

and Maintenance Program.1.9CHANGE CONTROL Changes to this Program, other than editorial changes, shall

include a 10 CFR 50.59 Review and a Station Qualified Review (SQR). The SQR composition shall include the Regulatory Assurance Department in all cases. As part of the SQR, Byron and

Braidwood Plant Operations Review Committee (PORC) approval is

required as determined by the Regulatory Assurance Manager.

Byron and Braidwood shall implement the same change unless the change has been reviewed and determined not to be applicable to Braidwood.

TRM Battery Monitoring and Maintenance Program Appendix U Attachment A Bases for TLCO 3.8.c, "Battery Monitoring and Maintenance" Battery Monitoring and Maintenance B 3.8.cBRAIDWOOD -UNITS 1 & 2B 3.8.c-1Revision26 B 3.8 ELECTRICAL POWER SYSTEMS B 3.8.c Battery Monitoring and Maintenance BASESBACKGROUNDThis TLCOdelineates the requirements of the Battery Monitoring and Maintenance Program in accordance with Technical Specification (TS) 5.5.17. A discussion of the

batteries and their OPERABILITY requirements is provided in the Bases for LCO3.8.4, "DC Sources-Operating," LCO3.8.5, "DC Sources-Shutdown," and LCO 3.8.6, "Battery Parameters."APPLICABLEThe initial conditions of Design Basis Accident (DBA) andSAFETY ANALYSEStransient analyses in the UFSAR, Chapter6 (Ref.1) and Chapter15 (Ref.2), assume Engineered Safety Feature

systems are OPERABLE. The DC electrical power system

provides normal and emergency DC electrical power for the diesel generators, emergency auxiliaries, and control and switching during all MODESof operation.

The OPERABILITY of the DC subsystems is consistent with the initial assumptions of the accident analyses and is based upon meeting the design basis of the plant. This includes maintaining at least one division of DC sources OPERABLE

during accident conditions, in the event of:a.An assumed loss of all offsite AC power or all onsite AC power; andb.A worst case single failure.

LCOBattery cell parameters must remain within acceptablelimits to ensure availability of the required DC power to shut down the reactor and maintain it in a safe condition after an

anticipated operational occurrence or a postulated DBA.

Electrolyte limits are conservatively established, allowing continued DC electrical system function even with CategoryA andB limits not met. OPERABILITY of the batteries is defined by LCO 3.8.6, "Battery Parameters."

Battery Monitoring and Maintenance B 3.8.cBRAIDWOOD -UNITS 1 & 2B 3.8.c-2Revision26 BASESAPPLICABILITYThe battery cell parameters are required solely for the support of the associated DC electrical power subsystems.

Therefore, battery electrolyte is only required when the DC power source is required to be OPERABLE. Refer to the Applicability discussion in Bases for LCO3.8.4 and LCO3.8.5.ACTIONSThe ACTIONS Tableis modified by a Note which indicates that separate Condition entry is allowed for each battery. This

is acceptable, since the Required Actions for each Condition provide appropriate compensatory actions for each affected battery. Complying with the Required Actions for one

battery may allow for continued operation, and subsequent

battery parameters out of limits are governed by separate Condition entry and application of associated Required Actions.A.1, A.2, and A.3 With one or more cells in one battery not within limits (i.e., CategoryA limits not met, CategoryB limits not met, or CategoryA andB limits not met) but within the CategoryC limits specified in TableT3.8.6-1 in the

accompanying TLCO, the battery is degraded but there is still sufficient capacity to perform the intended function.

Therefore, the affected battery is not required to be

considered inoperable solely as a result of Category A or B

limits not met and operation is permitted for a limited

period.The pilot cell electrolyte level and float voltage are required to be verified to meet the CategoryC limits within 1hour (Required ActionA.1). This check will provide a quick indication of the status of the remainder of the battery cells. Onehour provides time to inspect the

electrolyte level and to confirm the float voltage of the pilot cell. Onehour is considered a reasonable amount of

time to perform the required verification.

Battery Monitoring and Maintenance B 3.8.cBRAIDWOOD -UNITS 1 & 2B 3.8.c-3Revision26 BASES ACTIONS (continued)Verification that the CategoryC limits are met (Required ActionA.2) provides assurance that during the time needed to restore the parameters to the CategoryA and B limits, the battery is still capable of performing its intended function. A period of 24hours is allowed to complete the

initial verification because specific gravity measurements

must be obtained for each connected cell. Taking into consideration both the time required to perform the required verification and the assurance that thebattery cell

parameters are not severely degraded, this time is

considered reasonable. The verification is repeated at 7

day intervals until the parameters are restored to Category A or B limits. This periodic verification is consistent with the normal Frequency of pilot cell surveillances.Continued operation is only permitted for 31days before battery cell parameters must be restored to within CategoryA andB limits. With the consideration that, while

battery capacity is degraded, sufficient capacity exists to

perform the intended function and to allow time to fully

restore the battery cell parameters to normal limits, this time is acceptable.

Battery Monitoring and Maintenance B 3.8.cBRAIDWOOD -UNITS 1 & 2B 3.8.c-4Revision26 BASES ACTIONS (continued)

B.1 and B.2 With one battery with one or more battery cells with electrolyte level less than the minimum established design

limit (i.e., 1/2" below the minimum level indication mark),

TS 5.5.17 requires that the Battery Monitoring and

Maintenance Program provide actions to equalize and test the affected battery cell(s). The Specification 5.5.17 item b to initiate action to equalize and test in accordance with

manufacturer's recommendation is taken from Annex D of IEEE

Standard 450-1995, "IEEE Recommended Practice for

Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications." 31 days is allowed to equalize and test the affected battery cell(s). However, Condition B is modified by a Note which indicates that

Required Actions B.1 and B.2 must be completed after restoring the affected cell electrolyte level to greater than or equal to the minimum established design limits, i.e., after LCO 3.8.6, "Battery Parameters," Required Action

C.3 is completed. With the consideration that, while

battery capacity is degraded, sufficient capacity exists to perform the intended function and to allow time to fully restore the battery cell parameters to normal limits, this

time is acceptable. Based on the results of the

manufacturer's recommended testing the battery may have to

be declared inoperable and the affected cell(s) replaced.SURVEILLANCETSR 3.8.c.1 REQUIREMENTSThis TSR verifies that CategoryA battery cell parameters are consistent with IEEE-450 (Ref.3), which recommends regular battery inspections (at least one per month) including voltage, specific gravity, and electrolyte level

of pilot cells.

Battery Monitoring and Maintenance B 3.8.cBRAIDWOOD -UNITS 1 & 2B 3.8.c-5Revision26 BASES SURVEILLANCE REQUIREMENTS (continued)

TSR 3.8.c.2 The quarterly inspection of specific gravity and voltage is consistent with IEEE-450 (Ref.3). In addition, within 7days of a battery discharge 110V or a battery overcharge

145V, the battery must be demonstrated to meet CategoryB limits. Transients, such as motor starting transients, which may momentarily cause battery voltage to drop to 110 V, do not constitute a battery discharge provided the battery terminal voltage and float current

return to pre-transient values. This inspection is also consistent with IEEE-450 (Ref.3), which recommends special inspections following a severe discharge or overcharge, to ensure that no significant degradation of the battery occurs

as a consequence of such discharge or overcharge.

TSR 3.8.c.3 Visual inspection to detect corrosion of the battery cells and connections, or measurement of the resistance of each

intercell, interrack, intertier, and terminal connection, provides an indication of physical damage or abnormal deterioration that could potentially degrade battery

performance.

The limits established for this TSR must not be above the ceiling value established by the manufacturer.

Connection resistance is obtained by subtracting the normal resistance of the interrack (cross room rack) connector or

the intertier (bi-level rack) connector from the measured intercell (cell-to-cell) connection resistance.

The Surveillance Frequency for these inspections, which can detect conditions that can cause power losses due to resistance heating, is 92days. This Frequency is considered acceptablebased on operating experience related to detecting corrosion trends.

Battery Monitoring and Maintenance B 3.8.cBRAIDWOOD -UNITS 1 & 2B 3.8.c-6Revision26 BASES SURVEILLANCE REQUIREMENTS (continued)

TSR 3.8.c.4 Visual inspection of the battery cells, cell plates, and battery racks provides an indication of physical damage or

abnormal deterioration that could potentially degrade

battery performance. The presence of physical damage or

deterioration does not necessarily represent a failure of this TSR, provided an evaluation determines that the physical damage or deterioration does not affect the

OPERABILITY of the battery (its ability to perform its

design function).

TSR 3.8.c.5 and TSR 3.8.c.6 Visual inspection and resistance measurements of intercell, interrack, intertier, and terminal connections provide an indication of physical damage or abnormal deterioration that could indicate degraded battery condition. The anti-corrosion materialis used to help ensure good electrical

connections and to reduce terminal deterioration. The visual

inspection for corrosion is not intended to require removal of and inspection under each terminal connection. The removal of visible corrosion is a preventive maintenance

TSR. The presence of visible corrosion does not necessarily

represent a failure of this TSR provided visible corrosion is removed during performance of TSR3.8.c.5.The connection resistance limits for TSR3.8.c.6 shall not be above the ceiling value established by the manufacturer.

Connection resistance is obtained by subtracting the normal resistance of the interrack (cross room rack) connector or the intertier (bi-level rack) connector from the measured

intercell (cell-to-cell) connection resistance.TableT3.8.6-1This tabledelineates the limits on electrolyte level, float voltage, and specific gravity for three different

categories. The meaning of each category is discussed below.

Battery Monitoring and Maintenance B 3.8.cBRAIDWOOD -UNITS 1 & 2B 3.8.c-7Revision26 BASES SURVEILLANCE REQUIREMENTS (continued)CategoryA defines the normal parameter limit for each designated pilot cell in each battery. The cells selected as pilot cells are those whose temperature, voltage, and electrolyte specific gravity approximate the state of charge

of the entire battery.The CategoryA limits specified for electrolyte level are based on manufacturer recommendations and are consistent with the guidance in IEEE-450 (Ref.3), with the extra 1/4inch allowance above the high water level indication for

operating margin to account for temperatures and charge

effects. In addition to this allowance, footnote (a) to TableT3.8.6-1 permits the electrolyte level to be above the specified maximum level during equalizing charge, provided

it is not overflowing. These limits ensure that the plates

suffer no physical damage, and that adequate electron transfer capability is maintained in the event of transient conditions. IEEE-450 (Ref.3) recommends that electrolyte

level readings should be made only after the battery has been at float charge for at least 72hours.The CategoryA limit specified for float voltage is 2.13V per cell. This value is based on the recommendations of IEEE-450 (Ref.3), which states that prolonged operation of cells <2.13V can reduce the life expectancy of cells.The CategoryA limit specified for specific gravity for each pilot cell is 1.200 (0.015 below the manufacturer fully charged nominal specific gravity or a battery charging

current that had stabilized at a low value). This value is

characteristic of a charged cell with adequate capacity. According to IEEE-450 (Ref.3), the specific gravity readings are based on a temperature of 77

!F (25!C).The specific gravity readings are corrected for actual

electrolyte temperature. For each 3

!F (1.67!C) above 77

!F (25!C), 1point (0.001) is added to the reading; 1point is subtracted for each 3

!F below 77

!F.CategoryB defines the normal parameter limits for each

connected cell. The term "connected cell" excludes any battery cell that may be jumpered out.

Battery Monitoring and Maintenance B 3.8.cBRAIDWOOD -UNITS 1 & 2B 3.8.c-8Revision26 BASES SURVEILLANCE REQUIREMENTS (continued)The CategoryB limits specified for electrolyte level and float voltage are the same as those specified for CategoryA and have been discussed above. Footnote (b) to TableT3.8.6-1 requires the float voltage correction for average electrolyte temperature. The CategoryB limit

specified for specific gravity for each connected cell is 1.195 (0.020 below the manufacturer fully charged, nominal specific gravity) with the average of all connected cells

>1.205 (0.010 below the manufacturer fully charged, nominal

specific gravity). These values are based on manufacturer's

recommendations. The minimum specific gravity value

required for each cell ensures that the effects of a highly charged or newly installed cellwill not mask overall degradation of the battery.CategoryC defines the limits for each connected cell. Thesevalues, although reduced, provide assurance that sufficient capacity exists to perform the intended function

and maintain a margin of safety. The CategoryC limits specified for electrolyte level (above the top of the plates and not overflowing) ensure that the plates suffer no physical damage and maintain adequate electron transfer capability. The CategoryC limits for float voltage is basedon IEEE-450 (Ref.3), which states that a cell voltage of 2.07V or below, under float conditions and not caused by elevated temperature of the cell, indicates internal cell problems and may require cell

replacement.The CategoryC limit of average specific gravity 1.195 is based on manufacturer recommendations (0.020 below the manufacturer recommended fully charged, nominal specific

gravity). In addition to that limit, it is required that

the specific gravity for each connected cell must be no less

than 0.020 below the average of all connected cells. This limit ensures that the effect of a highly charged or new cell does not mask overall degradation of the battery.

Battery Monitoring and Maintenance B 3.8.cBRAIDWOOD -UNITS 1 & 2B 3.8.c-9Revision26 BASES SURVEILLANCE REQUIREMENTS (continued)

Because of specific gravity gradients that are produced during the recharging process, delays of severaldays may occur while waiting for the specific gravity to stabilize. Astabilized charger current is an acceptablealternative to

specific gravity measurement for determining the state of charge. This phenomenon is discussed in IEEE-450 (Ref.3).

Footnote(d) to TableT3.8.6-1 allows the float charge current to be used as an alternate to specific gravity for up to 7days following a battery recharge. Within 7days, each connected cell's specific gravity must be measured to

confirm the state of charge. Following a minor battery

recharge (such as equalizing charge that does not follow a deep discharge) specific gravity gradients are not significant, and confirming measurements may be made in less than 7days.REFERENCES1.UFSAR, Chapter6.2.UFSAR, Chapter15.3.IEEE-450-1995.

TRM Control Room Envelope Habitability Program Appendix V BRAIDWOOD UNITS 1 & 2 1 of 7 Revision 56 Technical Requirements Manual CONTROL ROOM ENVELOPE HABITABILITY PROGRAM BRAIDWOOD TABLE OF CONTENTS

SECTION TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS

1.4 PROGRAM DESCRIPTION 1.5 PROGRAM IMPLEMENTATION

1.6 ACCEPTANCE CRITERIA 1.7 LCOARS/COMPENSATORY MEASURES 1.8 REPORTING REQUIREMENTS 1.9 CHANGE CONTROL

TRM Control Room Envelope Habitability Program Appendix V BRAIDWOOD UNITS 1 & 2 2 of 7 Revision 56 Technical Requirements Manual

1.1 PURPOSE

This Program ensures that Control Room Envelope Habitability (CREH) is maintained such that, with an OPERABLE Control Room

Ventilation (VC) Filtration System, the Control Room Envelope (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 by assessing and performing testing in accordance with

Technical Specification (TS) 3.7.10, "Control Room Ventilation (VC) Filtration System" and the Control Room Habitability Program. The CREH Program is defined by TS 5.5.18.

1.2 REFERENCES

1. Technical Specifications:

a. 3.7.10, "Control Room Ventilation (VC) Filtration System" b. 5.5.18, "Control Room Envelope Habitability Program" 2. Update Final Safety Analysis Report Sections:

a. 6.4, "Habitability Systems"

b. 9.4.1, "Control Room HVAC System" 3. Regulatory Guide 1.196, "Control Room Habitability at Light-Water Nuclear Power Reactors," Revision 0

4. NEI 99-03, "Control Room Habitability Assessment Guidance,"

Revision 0

5. Design Basis Accident (DBA) Control Room Dose Calculations:

a. BRW-04-0038-M, "Loss Of Coolant Accident" b. BRW-04-0039-M, "Control Rod Ejection Accident" c. BRW-04-0040-M, "Main Steam Line Break Accident" d. BRW-04-0041-M, "Fuel Handling Building Accident" e. BRW-04-0042-M, "Steam Generator Tube Rupture Accident" f. BRW-04-0043-M, "Locked Rotor Accident" TRM Control Room Envelope Habitability Program Appendix V BRAIDWOOD UNITS 1 & 2 3 of 7 Revision 56 Technical Requirements Manual 1.3 DEFINITIONS AND/OR ACRONYMS

1. BREACH: Any work activity or testing that creates or enlarges an opening through a barrier, which would allow the propagation of a hazard through the barrier. Following are some examples: - Modification (addition, removal or degradation) of a penetration seal or structural component - Core boring - Blocking open a door/hatch or damper - Modification (addition, removal, or degradation) of a door/hatch or damper

2. CONTROL ROOM ENVELOPE (CRE): The area within the confines of the control room envelope boundary that contains the spaces Occupants inhabit to control the plant for normal and accident conditions. This area encompasses the control room and other non-critical areas to which frequent personnel access or continuous occupancy is not necessary in the event of an accident. The CRE is protected during normal operation, natural events, and accident conditions.

The Braidwood CRE is shown in drawing M-1033-13.

3. CRE BOUNDARY: A combination of walls, floor, roof, ducting, doors, penetrations and equipment that physically form the

CRE. 4. CRE INTEGRITY: The condition whereby the control room habitability systems (CRHSs) are functioning to ensure the protection of the Operators in the CRE during normal and accident conditions.

5. CONTROL ROOM HABITABILITY SYSTEMS (CRHS): The plant systems that help ensure CRE habitability. This includes the Control Room (CR) emergency ventilation/filtration system and the Control Room (CR) heating, ventilating and air-conditioning (HVAC) systems. The CRE boundary is considered as an integral part of the CRHS, since it is critical to maintaining CRE habitability.

TRM Control Room Envelope Habitability Program Appendix V BRAIDWOOD UNITS 1 & 2 4 of 7 Revision 56 Technical Requirements Manual

6. FILTERED INLEAKAGE: This inleakage occurs at a location in the CRHS that allows the inleakage air contamination to be

filtered prior to entering the habitability zone. An example is duct inleakage on the suction side of a

recirculation air carbon filter where the duct is outside the CRE. Radionuclides are removed from this air prior to it entering the CRE. There is no filtering assumed for hazardous chemical events.

7. INTEGRATED TRACER GAS TEST: A tracer gas test to determine total inleakage into the CRE. The tracer gas test is actually measuring the total amount of outside air entering the CRE, and the inleakage air is determined by subtracting the filtered outside air supply value from this figure.

This particular test may not locate leaks; it does, however, provide a value for total inleakage.

8. TRACER GAS (from ASTM E741): A gas that can be mixed with air in very small concentrations in order to study air movement.

9. UNFILTERED INLEAKAGE: This is inleakage that occurs at a location in the CRHS that allows inleakage air to enter the control room envelope without any contaminants being filtered prior to entry. Examples would be penetrations and dampers that are at a negative pressure with respect to potentially contaminated surroundings and located such that radionuclides are not removed prior to the inleakage air

entering the CRE.

1.4 PROGRAM DESCRIPTION This Program ensures that CRE Habitability is maintained in accordance with NRC regulations and plant-specific commitments.

Specifically, the CRE Habitability Program ensures compliance

with 10 CFR 50, Appendix A, General Design Criterion 19 - Control Room (GDC 19). CRE Habitability must be maintained during normal operations as well as during radiological, hazardous chemical, or smoke event emergencies. Administration of this Program, through periodic inleakage testing, periodic assessments, configuration control, and preventive maintenance, will ensure that CRE Habitability and Integrity are maintained. This CRE Habitability

Program is the result of an NRC commitment to Generic Letter 2003-01 for all Exelon Nuclear / AmerGen plant Technical Specifications to have an administrative program for CRE Habitability.

TRM Control Room Envelope Habitability Program Appendix V BRAIDWOOD UNITS 1 & 2 5 of 7 Revision 56 Technical Requirements Manual 1.5 PROGRAM IMPLEMENTATION A CRE Habitability Program shall be established and implemented

to ensure that CRE Habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation/Filtration System, 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 total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:

a. The definition of the CRE and CRE boundary.

b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive

maintenance.

c. Requirements for 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 assessing CRE

habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

d. Measurement 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 Control Room Emergency Ventilation/Filtration System, operating at the flow rate required by the Ventilation Filter Testing Program, at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 months assessment of the CRE boundary.

TRM Control Room Envelope Habitability Program Appendix V BRAIDWOOD UNITS 1 & 2 6 of 7 Revision 56 Technical Requirements Manual

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.

1.6 ACCEPTANCE CRITERIA

1. The quantitative limits on unfiltered air inleakage do not exceed the values assumed in the dose analysis for DBAs.

2. Periodic Assessments do not identify any degraded conditions or programs that could result in exceeding the

licensing basis analysis of DBA consequences to the CRE occupants.

1.7 LCOARS/COMPENSATORY MEASURES In the event any of the acceptance criteria is not met, the Shift

Manager will immediately be notified. The Shift Manager shall determine OPERABILITY status and implement a LCOAR as applicable.

In addition, an Issue Report may be generated to provide proper tracking and resolution of the noted problems associated with the implementation of this program.

1.8 REPORTING REQUIREMENTS Any reporting requirements associated with acceptance criteria of this Program not being met shall be reported in accordance with the requirements specified in the implementing procedures or determined through the Corrective Action Process.

TRM Control Room Envelope Habitability Program Appendix V BRAIDWOOD UNITS 1 & 2 7 of 7 Revision 56 Technical Requirements Manual 1.9 CHANGE CONTROL Changes to this Program, other than editorial changes, shall include a 10 CFR 50.59 Review and a Station Qualified Review (SQR). The SQR composition shall include Regulatory Assurance Department in all cases. As a part of the SQR, Byron and Braidwood Plant Operations Review Committee (PORC) approval is required as determined by the Regulatory Assurance Manager.

Byron and Braidwood shall implement the same change unless the

change being implemented at Braidwood has been reviewed and was determined not to be applicable to Byron.

TRM Surveillance Frequency Control Program Appendix WBRAIDWOOD UNITS 1 & 21 of 4Revision 74 Technical Requirements Manual SURVEILLANCE FREQUENCY CONTROL PROGRAM BRAIDWOOD TABLE OF CONTENTS SECTION TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS 1.4 PROGRAM DESCRIPTION 1.5 PROGRAM IMPLEMENTATION 1.6 ACCEPTANCE CRITERIA 1.7 LCOARS/COMPENSATORY MEASURES 1.8 REPORTING REQUIREMENTS 1.9 CHANGE CONTROL TRM Surveillance Frequency Control Program Appendix WBRAIDWOOD UNITS 1 & 22 of 4Revision 74 Technical Requirements Manual1.1PURPOSE The purpose of this Program is to provide the administrative controls for modifyingsurveillance frequencies in accordance with Technical Specification (TS) 5.5.19, "Surveillance Frequency

Control Program." The Surveillance Frequency Control Program (SFCP) ensures that Surveillance Requirements specified in the TSs are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

1.2REFERENCES

1.Technical Specification 5.5.19, "Surveillance Frequency Control Program"2.NEI 04-10, "Risk-Informed Method for Control of Surveillances Frequencies," Revision 13.Letter from N.J. DiFrancesco (U.S. NRC) to M.J. Pacilio (Exelon Generation Company, LLC), "Braidwood Station, Units

1 and 2 - Issuance of Amendments Regarding Technical

Specification Change for the Relocation of Specific Surveillance Frequency Requirements Based on Technical Specification Task Force-425," dated February 24, 2011.1.3DEFINITIONS AND/OR ACRONYMS Definitions and/or acronyms are consistent with definitions

provided in Technical Specification Section 1.0, "Use and

Application."1.4PROGRAM DESCRIPTIONS The list of periodic surveillances and associated TS Bases

information that were relocated to the SFCP as part of License

Amendment No. 165 for Braidwood Station, Units 1 and Unit 2 are provided in a separate tab in the TS LCO book for ease of locating.

Table 1 under this tab includes a reference to the TS SR number, a surveillance description, the frequency, and current revision.

The description is a summary description of the referenced TS SR which is provided for information purposes only and is not

intended to be a substitute for the actual TS requirements. Refer

to the TS for the specific action required by each respective TS SR identified in the list.

TRM Surveillance Frequency Control Program Appendix WBRAIDWOOD UNITS 1 & 23 of 4Revision 74 Technical Requirements Manual Table 2 under this tab provides the associated Bases description for each TS SR Frequency.

Changes to the type or scope of testing (e.g., Channel Check, Channel Functional Test, or Channel Calibration) are not allowed

without prior NRC approval. The specified frequencies ensure TS SRs are performed at intervals sufficient to assure associated Limiting Conditions for Operation (LCOs) are met.

Changes to the information in Tables 1 and 2 may occur for one of two reasons: 1.Addition, deletion, or modification of the associated TS SR through a license amendment request, or2.A change to a surveillance frequency in accordance with the SFCP and associated implementing procedures. Changes to individual surveillance frequencies are evaluated using the

methodology provided in NEI 04-10, "Risk-Informed Method

for Control of Surveillance Frequencies," Revision 1.

As noted in Tables 1 and 2, Surveillance Frequencies beyond

Revision 0 have been evaluated in accordance with TS Section

5.5.19, "Surveillance Frequency Control Program." Surveillance

frequencies at Revision 0 reflect the approved licensing basis upon initial SFCP implementation.

The provisions of TS SR 3.0.2 and 3.0.3 are applicable to the frequencies established in the SFCP. 1.5PROGRAM IMPLEMENTATION 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.

TRM Surveillance Frequency Control Program Appendix WBRAIDWOOD UNITS 1 & 24 of 4Revision 74 Technical Requirements Manual1.6ACCEPTANCE CRITERIA Not applicable.1.7LCOARS/COMPENSATORY MEASURES Noncompliance with the frequencies specified in the SFCP (e.g., a missed surveillance) requires generation of an Issue Report in

accordance with LS-AA-125.1.8REPORTING REQUIREMENTS Based on the guidance provided in NUREG-1022, "Event Reporting

Guidelines, 10 CFR 50.72 and 50.73," Revision 2, missed

surveillances are not reportable as a condition prohibited by TS unless the surveillance, once performed, indicates that the equipment was not capable of performing its specified safety

function(s) for a period of time longer than allowed by TS.1.9CHANGE CONTROL The change control process associated with revisions to

Surveillance Frequencies is defined in NEI 04-10, "Risk-Informed Method for Control of Surveillances Frequencies," Revision 1.

CORE OPERATING LIMITS REPORT (COLR)

FOR BRAIDWOOD UNIT 1 CYCLE 20 EXELON TRACKING ID:

COLR BRAIDWOOD 1 REVISION 13

COLR BRAIDWOOD 1 Revision 13 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 20 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 Cycle 20 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS).

The Technical Specification Safety Limits and Limiting Conditions for Operation (LCOs) affected by this report are listed below:

SL 2.1.1 Reactor Core Safety Limits (SLs)

LCO 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.4 Rod Group Alignment Limits LCO 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.6 Control Bank Insertion Limits LCO 3.1.8 PHYSICS TESTS Exceptions - MODE 2 LCO 3.2.1 Heat Flux Hot Channel Factor (F Q(Z)) LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F NH) LCO 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCO 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)

LCO 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.9 Boron Dilution Protection System (BDPS)

LCO 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.9.1 Boron Concentration The portions of the Technical Requirements Manual (TRM) affected by this report are listed below:

TRM TLCO 3.1.b Boration Flow Paths - Operating

TRM TLCO 3.1.d Charging Pumps - Operating TRM TLCO 3.1.f Borated Water Sources - Operating

TRM TLCO 3.1.g Position Indication System - Shutdown TRM TLCO 3.1.h Shutdown Margin (SDM) - MODE 1 and MODE 2 with keff 1.0 TRM TLCO 3.1.i Shutdown Margin (SDM) - MODE 5

TRM TLCO 3.1.j Shutdown and Control Rods TRM TLCO 3.1.k Position Indication System - Shutdown (Special Test Exception)

COLR BRAIDWOOD 1 Revision 13 Page 2of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1CYCLE20 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections.

These limits are applicable for the entire cycle unless otherwise identified.

These limits have been developed using the NRG-approved methodologies specified in Technical Specification 5.6.5. 2.1 Reactor Core Safety Limits (Sls) (SL 2.1.1) -LL CJ") (]) C) ...___...

(]) !>...... ::i _.. !>...... (]) 0.... E (]) I--(]) O'> 0 !>...... (]) > <( 2.1.1 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 Figure 2.1.1. 680 660 6 4 0 620 600 580 0 0.2 0.4 0.6 Q.8 1.2 F ro e i on o f N om inal P owe r Figure 2.1.1: Reactor Core Limits COLR BRAIDWOOD 1 Revision 13 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 20 2.2 SHUTDOWN MARGIN (SDM)

The SDM limit for MODES 1, 2, 3, and 4 is:

2.2.1 The SDM shall be greater than or equal to 1.3% k/k (LCOs 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.3.9; TRM TLCOs 3.1.b, 3.1.d, 3.1.f, 3.1.h, and 3.1.j).

The SDM limit for MODE 5 is:

2.2.2 SDM shall be greater than or equal to 1.3% k/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1.j).

2.3 Moderator Temperature Coefficient (MTC) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +2.104 x 10

-5 k/k/°F. 2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10

-4 k/k/°F. 2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10

-4 k/k/°F. 2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10

-4 k/k/°F. where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life HFP stands for Hot Full Thermal Power 2.4 Shutdown Bank Insertion Limits (LCO 3.1.5) 2.4.1 All shutdown banks shall be fully withdrawn to at least 224 steps.

2.5 Control Bank Insertion Limits (LCO 3.1.6) 2.5.1 The control banks, with Bank A greater than or equal to 224 steps, shall be limited in physical insertion as shown in Figure 2.5.1.

2.5.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 224 steps.

2.5.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C and Bank D. The control banks shall be sequenced in reverse order upon insertion.

2.5.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap limits as a function of park position:

Park Position (step) Overlap Limit (step) 226 111 227 112 228 113 229 114 COLR BRAIDWOOD 1 Revision 13 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 20 0 20 40 60 80 100 120 140 160 180 200 2200102030405060708090100Rod Bank Position (Steps Withdrawn)R e l a t i v e P o w e r ( P e r c e n t )

Figure 2.5.1:Control Bank Insertion Limits Versus Percent Rated Thermal Power (27%, 224)

(77%, 224)

(100%, 161)

BANK B BANK C BANK D (0%, 162)(0%, 47)(30%, 0)224 COLR BRAIDWOOD 1 Revision 13 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 20 2.6 Heat Flux Hot Channel Factor (F Q(Z)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F Q RTP = 2.60 K(Z) is provided in Figure 2.6.1.

(0.0, 1.0)

(6.0, 1.0)

(12.0,0.924) 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 1.10123456789101112K(Z) Normalized F Q (Z)BOTTOM Core Height (ft) TOP Figure 2.6.1K(Z) -Normalized F Q(Z) as a Function of Core Height LOCA Limiting Envelope 0.5 Pfor )(0.5 F (Z)F RTP Q Q Z xK 0.5 Pfor )(P F (Z)F RTP Q Q Z xK COLR BRAIDWOOD 1 Revision 13 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 20 2.6.2 W(Z) Values:

a) When the Power Distribution Monitoring System (PDMS) is OPERABLE, W(Z) = 1.00000 for all axial points.

b) When PDMS is inoperable, W(Z) is provided as:

1) Table 2.6.2.a are the normal operation W(Z) values that correspond to the NORMAL AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.a. The normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU. The Normal AFD Acceptable Operation Limits may be invoked at any time and must be used with the corresponding W(Z) values.

2) Table 2.6.2.b are the Expanded normal operation W(Z) values that correspond to the EXPANDED AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.b. The Expanded normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU. The Expanded AFD Acceptable Operation Limits may be invoked at any time and must be used with the corresponding W(Z) values.

Table 2.6.2.c shows the F C Q(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the F W Q(z) as per Surveillance Requirement 3.2.1.2. A 2% penalty factor shall be used at all cycle burnups that are outside the range of Table 2.6.2.c.

2.6.3 Uncertainty:

The uncertainty, U FQ, to be applied to the Heat Flux Hot Channel Factor F Q (Z) shall be calculated by the following formula UUUFQque where:

U qu = Base F Q measurement uncertainty = 1.05 when PDMS is inoperable (U qu is defined by PDMS when OPERABLE.)

U e = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:

F Q(Z) Warning Setpoint = 2% F Q(Z) Margin F Q(Z) Alarm Setpoint = 0% F Q(Z) Margin

COLR BRAIDWOOD 1 Revision 13 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 20 Table 2.6.2.a W(Z) versus Core Height for Normal AFD Acceptable Operation Limits in Figure 2.8.1.a (Top and Bottom 8% Excluded per WCAP-10216)

Height 150 6000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.1846 1.3192 1.2784 1.2178 0.20 1.1761 1.2860 1.2570 1.2116 0.40 1.1735 1.2680 1.2477 1.2118 0.60 1.1674 1.2574 1.2379 1.2100 0.80 1.1549 1.2388 1.2217 1.2029 1.00 1.1433 1.2202 1.2102 1.2015 1.20 1.1372 1.2102 1.1954 1.1921 1.40 1.1307 1.2051 1.1839 1.1861 1.60 1.1301 1.1876 1.1754 1.1767 1.80 1.1396 1.1715 1.1725 1.1676 2.00 1.1335 1.1564 1.1695 1.1569 2.20 1.1254 1.1383 1.1626 1.1437 2.40 1.1179 1.1232 1.1577 1.1313 2.60 1.1098 1.1072 1.1498 1.1164 2.80 1.1022 1.1070 1.1428 1.1073 3.00 1.0956 1.1067 1.1359 1.1043 3.20 1.0934 1.1043 1.1270 1.1042 3.40 1.0913 1.1040 1.1194 1.1117 3.60 1.0927 1.1023 1.1121 1.1202 3.80 1.0974 1.1018 1.1064 1.1289 4.00 1.1013 1.1011 1.1061 1.1427 4.20 1.1052 1.1001 1.1115 1.1554 4.40 1.1081 1.0990 1.1167 1.1668 4.60 1.1102 1.0959 1.1208 1.1764 4.80 1.1115 1.0937 1.1229 1.1864 5.00 1.1116 1.0918 1.1241 1.1935 5.20 1.1110 1.0879 1.1260 1.1991 5.40 1.1195 1.0848 1.1288 1.2028 5.60 1.1269 1.0848 1.1322 1.2043 5.80 1.1339 1.0917 1.1496 1.2082 6.00 1.1406 1.1002 1.1661 1.2247 6.20 1.1453 1.1069 1.1807 1.2383 6.40 1.1490 1.1136 1.1932 1.2499 6.60 1.1508 1.1194 1.2019 1.2565 6.80 1.1526 1.1233 1.2105 1.2622 7.00 1.1524 1.1283 1.2153 1.2639 7.20 1.1511 1.1362 1.2181 1.2617 7.40 1.1579 1.1451 1.2189 1.2556 7.60 1.1665 1.1532 1.2158 1.2456 7.80 1.1742 1.1614 1.2127 1.2346 8.00 1.1776 1.1678 1.2068 1.2226 8.20 1.1773 1.1735 1.1989 1.2058 8.40 1.1757 1.1794 1.1901 1.1910 8.60 1.1744 1.1895 1.1793 1.1752 8.80 1.1743 1.2061 1.1748 1.1629 9.00 1.1795 1.2205 1.1740 1.1651 9.20 1.1861 1.2374 1.1786 1.1653 9.40 1.1912 1.2495 1.1845 1.2010 9.60 1.1955 1.2624 1.1895 1.2470 9.80 1.1999 1.2716 1.2220 1.2860 10.00 1.2036 1.2791 1.2470 1.3200 10.20 1.2081 1.2795 1.2710 1.3566 10.40 1.2152 1.2848 1.2905 1.3884 10.60 1.2197 1.2830 1.3093 1.4162 10.80 1.2261 1.2916 1.3241 1.4320 11.00 1.2347 1.3023 1.3349 1.4418 11.20 1.2426 1.2988 1.3308 1.4347 11.40 1.2449 1.3089 1.3286 1.4176 11.60 1.2471 1.3118 1.3086 1.4116 11.80 1.2495 1.3147 1.2916 1.3956 12.00 (core top) 1.2557 1.3252 1.2794 1.3834 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle burnups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation

COLR BRAIDWOOD 1 Revision 13 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 20 Table 2.6.2.b W(Z) versus Core Height for Expanded AFD Acceptable Operation Limits in Figure 2.8.1.b (Top and Bottom 8% Excluded per WCAP-10216)

Height 150 6000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.3461 1.4594 1.4170 1.3451 0.20 1.3317 1.4199 1.3910 1.3358 0.40 1.3275 1.4011 1.3800 1.3350 0.60 1.3192 1.3900 1.3680 1.3362 0.80 1.2964 1.3686 1.3480 1.3268 1.00 1.2776 1.3461 1.3340 1.3233 1.20 1.2661 1.3332 1.3160 1.3110 1.40 1.2554 1.3260 1.3020 1.3025 1.60 1.2533 1.3026 1.2840 1.2902 1.80 1.2578 1.2819 1.2700 1.2788 2.00 1.2449 1.2612 1.2550 1.2654 2.20 1.2275 1.2368 1.2370 1.2483 2.40 1.2118 1.2153 1.2240 1.2330 2.60 1.1943 1.1924 1.2112 1.2140 2.80 1.1785 1.1835 1.2014 1.1958 3.00 1.1638 1.1785 1.1906 1.1796 3.20 1.1567 1.1718 1.1799 1.1625 3.40 1.1527 1.1674 1.1720 1.1565 3.60 1.1477 1.1605 1.1619 1.1552 3.80 1.1427 1.1547 1.1532 1.1543 4.00 1.1367 1.1473 1.1436 1.1534 4.20 1.1366 1.1385 1.1364 1.1554 4.40 1.1373 1.1301 1.1317 1.1668 4.60 1.1367 1.1203 1.1255 1.1764 4.80 1.1355 1.1104 1.1229 1.1864 5.00 1.1331 1.1006 1.1241 1.1935 5.20 1.1295 1.0888 1.1260 1.1991 5.40 1.1259 1.0848 1.1288 1.2028 5.60 1.1269 1.0848 1.1322 1.2043 5.80 1.1339 1.0917 1.1496 1.2082 6.00 1.1406 1.1002 1.1661 1.2247 6.20 1.1453 1.1069 1.1807 1.2383 6.40 1.1490 1.1136 1.1932 1.2499 6.60 1.1508 1.1194 1.2019 1.2565 6.80 1.1526 1.1233 1.2105 1.2622 7.00 1.1524 1.1283 1.2153 1.2639 7.20 1.1511 1.1362 1.2181 1.2617 7.40 1.1579 1.1451 1.2189 1.2556 7.60 1.1665 1.1532 1.2158 1.2456 7.80 1.1742 1.1614 1.2127 1.2346 8.00 1.1776 1.1678 1.2068 1.2226 8.20 1.1773 1.1735 1.1989 1.2058 8.40 1.1757 1.1794 1.1901 1.1910 8.60 1.1744 1.1895 1.1793 1.1752 8.80 1.1743 1.2061 1.1748 1.1629 9.00 1.1795 1.2205 1.1740 1.1651 9.20 1.1861 1.2374 1.1786 1.1653 9.40 1.1912 1.2495 1.1845 1.2010 9.60 1.1955 1.2624 1.1895 1.2470 9.80 1.1999 1.2716 1.2220 1.2860 10.00 1.2036 1.2791 1.2470 1.3200 10.20 1.2081 1.2795 1.2710 1.3566 10.40 1.2152 1.2848 1.2905 1.3884 10.60 1.2197 1.2830 1.3093 1.4162 10.80 1.2261 1.2916 1.3241 1.4320 11.00 1.2347 1.3023 1.3349 1.4418 11.20 1.2426 1.2988 1.3308 1.4347 11.40 1.2449 1.3089 1.3286 1.4176 11.60 1.2471 1.3118 1.3086 1.4116 11.80 1.2495 1.3147 1.2916 1.3956 12.00 (core top) 1.2557 1.3252 1.2794 1.3834 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle burnups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation

COLR BRAIDWOOD 1 Revision 13 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 20 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) F C Q(z) 0 1.0200 501 1.0200 676 1.0304 852 1.0392 1027 1.0450 1202 1.0487 1378 1.0501 2781 1.0200 13830 1.0200 14006 1.0207 14882 1.0203 15058 1.0200 16461 1.0200 17162 1.0225 17864 1.0255 18215 1.0258 18566 1.0255 18916 1.0230 19267 1.0200 24768 1.0200

Notes:

Linear interpolation is adequate for intermediate cycle burnups.

All cycle burnups outside the range of Table 2.6.2.c shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.

COLR BRAIDWOOD 1 Revision 13 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 20 2.7 Nuclear Enthalpy Rise Hot Channel Factor (F NH) (LCO 3.2.2) 2.7.1 F NH FHRTP[1.0 + PFH (1.0 - P)]

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)

FHRTP = 1.70 PFH = 0.3 2.7.2 Uncertainty:

The uncertainty, U FH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor F NH shall be calculated by the following formula:

U FH = U FHm where: U FHm = Base F NH measurement uncertainty = 1.04 when PDMS is inoperable (U FHm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

F NH Warning Setpoint = 2% F NH Margin F NH Alarm Setpoint = 0% F NH Margin 2.8 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3) 2.8.1 When PDMS is inoperable, the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided in the Figures described below or the latest valid PDMS Surveillance Report, whichever is more conservative.

a) Figure 2.8.1.a is the Normal AFD Acceptable Operation Limits associated with the W(Z) values in Table 2.6.2.a. Prior to changing to Figure 2.8.1.a, confirm that the plant is within the specified AFD envelope.

b) Figure 2.8.1.b is the Expanded AFD Acceptable Operation Limits associated with the W(Z) values in Table 2.6.2.b.

2.8.2 When PDMS is OPERABLE, no AFD Acceptable Operation Limits are applicable.

2.9 Departure from Nucleate Boiling Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBR APSL 1.563 The Axial Power Shape Limiting DNBR (DNBR APSL) is applicable with THERMAL POWER 50% RTP when PDMS is OPERABLE.

2.9.2 PDMS Alarms:

DNBR Warning Setpoint = 2% DNBR Margin DNBR Alarm Setpoint = 0% DNBR Margin

COLR BRAIDWOOD 1 Revision 13 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 20 Figure 2.8.1.a:

Normal Axial Flux Difference Limits as a Function of Rated Thermal Power 0 20 40 60 80100120 50 40 30 201001020304050

%ofRATEDTHERMALPOWER AXIALFLUXDIFFERENCE(%)NormalAxialFluxDifferenceLimits with PDMSInoperable Unacceptable Operation Unacceptable Operation Acceptable Operation ( 20,50)( 10,100)(+10,100)(+25,50)

COLR BRAIDWOOD 1 Revision 13 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 20 Figure 2.8.1.b: Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power

0 20 40 60 80100120 50 40 30 201001020304050

%ofRATEDTHERMALPOWER AXIALFLUXDIFFERENCE(%)ExpandedAxialFluxDifferenceLimits with PDMSInoperable Unacceptable Operation Unacceptable Operation Acceptable Operation ( 35,50)( 15,100)(+10,100)(+25,50)

COLR BRAIDWOOD 1 Revision 13 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 20 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature T Setpoint Parameter Values 2.10.1 The Overtemperature T reactor trip setpoint K 1 shall be equal to 1.325.

2.10.2 The Overtemperature T reactor trip setpoint Tavg coefficient K 2 shall be equal to 0.0297 / °F.

2.10.3 The Overtemperature T reactor trip setpoint pressure coefficient K 3 shall be equal to 0.00135 / psi.

2.10.4 The nominal Tavg at RTP (indicated) T shall be less than or equal to 588.0 °F.

2.10.5 The nominal RCS operating pressure (indicated) P shall be equal to 2235 psig.

2.10.6 The measured reactor vessel T lead/lag time constant 1 shall be equal to 8 sec.

2.10.7 The measured reactor vessel T lead/lag time constant 2 shall be equal to 3 sec.

2.10.8 The measured reactor vessel T lag time constant 3 shall be less than or equal to 2 sec. 2.10.9 The measured reactor vessel average temperature lead/lag time constant 4 shall be equal to 33 sec.

2.10.10 The measured reactor vessel average temperature lead/lag time constant 5 shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant 6 shall be less than or equal to 2 sec.

2.10.12 The f 1 (I) "positive" breakpoint shall be +10% I.

2.10.13 The f 1 (I) "negative" breakpoint shall be -18% I.

2.10.14 The f 1 (I) "positive" slope shall be +3.47% / % I. 2.10.15 The f 1 (I) "negative" slope shall be -2.61% / % I.

COLR BRAIDWOOD 1 Revision 13 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 20 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower T Setpoint Parameter Values 2.11.1 The Overpower T reactor trip setpoint K 4 shall be equal to 1.072.

2.11.2 The Overpower T reactor trip setpoint T avg rate/lag coefficient K 5 shall be equal to 0.02 / °F for increasing Tavg. 2.11.3 The Overpower T reactor trip setpoint T avg rate/lag coefficient K 5 shall be equal to 0 / °F for decreasing Tavg. 2.11.4 The Overpower T reactor trip setpoint T avg heatup coefficient K 6 shall be equal to 0.00245 / °F when T T. 2.11.5 The Overpower T reactor trip setpoint T avg heatup coefficient K 6 shall be equal to 0 / °F when T T.

2.11.6 The nominal Tavg at RTP (indicated) T shall be less than or equal to 588.0 °F.

2.11.7 The measured reactor vessel T lead/lag time constant 1 shall be equal to 8 sec.

2.11.8 The measured reactor vessel T lead/lag time constant 2 shall be equal to 3 sec.

2.11.9 The measured reactor vessel T lag time constant 3 shall be less than or equal to 2 sec.

2.11.10 The measured reactor vessel average temperature lag time constant 6 shall be less than or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant 7 shall be equal to 10 sec.

2.11.12 The f 2 (I) "positive" breakpoint shall be 0 for all I.

2.11.13 The f 2 (I) "negative" breakpoint shall be 0 for all I.

2.11.14 The f 2 (I) "positive" slope shall be 0 for all I. 2.11.15 The f 2 (I) "negative" slope shall be 0 for all I.

COLR BRAIDWOOD 1 Revision 13 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 20 2.12 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (LCO 3.4.1) 2.12.1 The pressurizer pressure shall be greater than or equal to 2209 psig.

2.12.2 The RCS average temperature (Tavg) shall be less than or equal to 593.1 °F.

2.12.3 The RCS total flow rate shall be greater than or equal to 386,000 gpm.

2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to the applicable value given in the Table below (LCO 3.9.1). The reported "prior to initial criticality" value also bounds the end-of-cycle requirements for the previous cycle.

2.13.2 To maintain keff 0.987 with all shutdown and control rods fully withdrawn in MODES 3, 4, or 5 (TRM TLCO 3.1.g Required Action B.2 and TRM TLCO 3.1.k.2), the Reactor Coolant System boron concentration shall be greater than or equal to the applicable value given in the Table below.

COLR Section Conditions Boron Concentration (ppm) 2.13.1 a) prior to initial criticality

1723 b) for cycle burnups 0 MWD/MTU and < 16000 MWD/MTU 1823 c) for cycle burnups 16000 MWD/MTU 1486 2.13.2 a) prior to initial criticality

1780 b) for cycle burnups 0 MWD/MTU and < 16000 MWD/MTU 2014 c) for cycle burnups 16000 MWD/MTU 1610

CORE OPERATING LIMITS REPORT (COLR)

FOR BRAIDWOOD UNIT 2 CYCLE 19 EXELON TRACKING ID:

COLR BRAIDWOOD 2 REVISION 9

COLR BRAIDWOOD 2 Revision 9 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 19 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS).

The Technical Specification Safety Limits and Limiting Conditions for Operation (LCOs) affected by this report are listed below:

SL 2.1.1 Reactor Core Safety Limits (SLs)

LCO 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.4 Rod Group Alignment Limits LCO 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.6 Control Bank Insertion Limits LCO 3.1.8 PHYSICS TESTS Exceptions - MODE 2 LCO 3.2.1 Heat Flux Hot Channel Factor (F Q(Z)) LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F NH) LCO 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCO 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)

LCO 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.9 Boron Dilution Protection System (BDPS)

LCO 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.9.1 Boron Concentration

The portions of the Technical Requirements Manual (TRM) affected by this report are listed below:

TRM TLCO 3.1.b Boration Flow Paths - Operating TRM TLCO 3.1.d Charging Pumps - Operating

TRM TLCO 3.1.f Borated Water Sources - Operating

TRM TLCO 3.1.g Position Indication System - Shutdown TRM TLCO 3.1.h Shutdown Margin (SDM) - MODE 1 and MODE 2 with keff 1.0 TRM TLCO 3.1.i Shutdown Margin (SDM) - MODE 5 TRM TLCO 3.1.j Shutdown and Control Rods TRM TLCO 3.1.k Position Indication System - Shutdown (Special Test Exception)

COLR BRAIDWOOD 2 Revision 9 Page 2of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections.

These limits are applicable for the entire cycle unless otherwise identified.

These limits have been developed using the NRG-approved methodologies specified in Technical Specification 5.6.5. 2.1 Reactor Core Safety Limits (Sls) (SL 2.1.1) ,...--..., LL_ en Q) 0 ...__,...

Q) \....._ ::::; -+--' 0 \....._ Q) o_ E Q) I--Q) en 0 \....._ Q) > <( 2.1.1 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 Figure 2.1.1. 680 2471 p s ia ----660 2250 p s ia .... _ 640 2000 p s i a ......_ 1 860 p s i a . ..........._

620 600

____________________

-+-________________

0 0.2 0.4 0.6 F ro ct i on of N o o.s in o l P owe r Figure 2.1.1: Reactor Core Limits 1.2 COLR BRAIDWOOD 2 Revision 9 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 2.2 SHUTDOWN MARGIN (SDM)

The SDM limit for MODES 1, 2, 3, and 4 is:

2.2.1 The SDM shall be greater than or equal to 1.3% k/k (LCOs 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.3.9; TRM TLCOs 3.1.b, 3.1.d, 3.1.f, 3.1.h, and 3.1.j).

The SDM limit for MODE 5 is:

2.2.2 SDM shall be greater than or equal to 1.3% k/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1.j).

2.3 Moderator Temperature Coefficient (MTC) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +2.296 x 10