ML15034A310

Susquehanna Steam Electric Station Technical Specification Bases Unit 1 Manual

ML15034A310
Person / Time
Site:	Susquehanna
Issue date:	01/23/2015
From:	Susquehanna
To:	Office of Nuclear Reactor Regulation
References
Download: ML15034A310 (26)

Text

Jan. 23, 2015Page1 of 2MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2015-2824USER INFORMATION:GERLACH*ROSEY MEMPL#:028401 CA#: 0363Address: NUCSA2Phone#: 254-3194TPANqMTTTAT, TNTORMATTOCThTO: GERLACH*ROSEY M 01/23/2015LOCATION: USNRCFROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNEDTO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ONTHIS TRANSMITTAL. WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THEUPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLSFROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OFERRORS.ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore noTOC will be issued with the updated material.TSB1 -TECHNICAL SPECIFICATION BASES UNIT 1 MANUALREMOVE MANUAL TABLE OF CONTENTS DATE: 11/06/2014ADD MANUAL TABLE OF CONTENTS DATE: 01/22/2015CATEGORY: DOCUMENTS TYPE: TSB1 Jan. 23, 2015Page 2 of 2ID: TEXT 2.1.1REMOVE: REV:5ADD: REV: 6CATEGORY: DOCUMENTS TYPE: TSB1ID: TEXT LOESADD: REV: 120REMOVE: REV:119ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 FORASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 DAYS INACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGECOMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUALUSERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE INYOUR NIMS INBOX.

SSES MANUALManual Name: TSB1Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTable Of ContentsIssue Date: 01/22/2015Procedure Name RevTEXT LOES 120Title: LIST OF EFFECTIVE SECTIONSIssue Date01/22/2015Change ID Change NumberTEXT TOCTitle: TABLE OF CONTENTS23 07/02/2014TEXT 2.1.1 6Title: SAFETY LIMITS (SLS) REACTORTEXT 2.1.2 1Title: SAFETY LIMITS (SLS) REACTOR01/22/2015CORE SLS10/04/2007COOLANT SYSTEM(RCS) PRESSURE STEXT 3.0 3 08/20/2009Title: LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITYTEXT 3. 1.1Title: REACTIVITYTEXT 3.1.2Title: REACTIVITYTEXT 3.1.3Title: REACTIVITYTEXT 3.1.4Title: REACTIVITYTEXT 3.1.5Title: REACTIVITYTEXT 3.1.6Title: REACTIVITY1 04/18/2006CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)0 11/15/2002CONTROL SYSTEMS REACTIVITY ANOMALIES2 01/19/2009CONTROL SYSTEMS CONTROL ROD OPERABILITY4 01/30/2009CONTROL SYSTEMS CONTROL ROD SCRAM TIMES1 07/06/2005CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS3 02/24/2014CONTROL SYSTEMS ROD PATTERN CONTROLPagel of 8 Report Date: 01/22/15Page I of .8Report Date: 01/22/15 SSES MANUAL~Manual Name: TSBIManual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTEXT 3.1.7 3 04/23/2008Title: REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEMTEXT 3.1.8 3 05/06/2009Title: REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVESTEXT 3.2.1 2 04/23/2008Title: POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATIONRATE (APLHGR)TEXT 3.2.2 3 05/06/2009Title: POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)TEXT 3.2.3 2 04/23/2008Title: POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)TEXT 3.3.1.1 6 02/24/2014Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATIONTEXT 3.3.1.2 2 01/19/2009Title: INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATIONTEXT 3.3.2.1 4 02/24/2014Title: INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATIONTEXT 3.3.2.2 2 04/05/2010Title: INSTRUMENTATION FEEDWATER MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATIONTEXT 3.3.3.1 9 02/28/2013Title: INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATIONTEXT 3.3.3.2Title: INSTRUMENTATIONTEXT 3.3.4.1Title: INSTRUMENTATION1 04/18/2005REMOTE SHUTDOWN SYSTEM2 02/24/2014 aEND OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATIONPage 2 of 8 Report Date: 01/22/15Page 2 of 8Report Date: 01/22/15 SSES MANUALManual Name: TSBIW Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTEXT 3.3.4.2 0 11/15/2002Title: INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP(ATWS-RPT) INSTRUMENTATIONTEXT 3.3.5.1 3 08/20/2009Title: INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATIONTEXT 3.3.5.2 0 11/15/2002Title: INSTRUMENTATION REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATIONTEXT 3.3.6.1 7 03/31/2014Title: INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATIONTEXT 3.3.6.2 4 09/01/2010Title: INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATIONTEXT 3.3.7.1Title: INSTRUMENTATIONINSTRUMENTATION2 10/27/2008CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEMTEXT 3.3.8.1 2 12/17/2007Title: INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATIONTEXT 3.3.8.2 0 11/15/2002Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORINGTEXT 3.4.1 4 04/27/2010Title: REACTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATINGTEXT 3.4.2 3 10/23/2013Title: REACTOR COOLANT SYSTEM (RCS) JET PUMPSTEXT 3.4.3 3 01/13/2012Title: REACTOR COOLANT SYSTEM RCS SAFETY RELIEF VALVES S/RVSh TEXT 3.4.4 0 11/15/2002Title: REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGEPage 3 of .8Report Date: 01/22/15 SSES MANUALManual Name: TSB1Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTEXT 3.4.5 1 01/16/2006Title: REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGETEXT 3.4.6 4 02/19/2014Title: REACTOR COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATIONTEXT 3.4.7 2 10/04/2007Title: REACTOR COOLANT SYSTEM (RCS) RCS SPECIFIC ACTIVITYTEXT 3.4.8Title: REACTOR COOLANT-HOT SHUTDOWNTEXT 3.4.9Title: REACTOR COOLANT-COLD SHUTDOWN2SYSTEM (RCS)1SYSTEM (RCS)03/28/2013RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM03/28/2013RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEMTEXT 3.4.10 3 04/23/2008Title: REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITSTEXT 3.4.11 0 11/15/2002Title: REACTOR COOLANT SYSTEM (RCS) REACTOR STEAM DOME PRESSURETEXT 3.5.14 07/16/2014Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTORSYSTEM ECCS -OPERATINGTEXT 3.5.2 0 11/15/2002Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTORSYSTEM ECCS -SHUTDOWNTEXT 3.5.3 3 02/24/2014Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTORSYSTEM RCIC SYSTEMCORE ISOLATION COOLING (RCIC)CORE ISOLATION COOLING (RCIC)CORE ISOLATION COOLING (RCIC)TEXT 3.6.1.1Title: PRIMARY CONTAINMENT5 02/24/2014TEXT 3.6.1.2 1 04/23/2008Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKPage of Reort ate 01/2/1Page 4 of 8Report Date: 01/211/15 SSES MANUAL.! Manual Name: TSB1Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTEXT 3.6.1.3 11 07/02/2014Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)TEXT 3.6.1.4 1 04/23/2008Title: CONTAINMENT SYSTEMS CONTAINMENT PRESSURETEXT 3.6.1.5 1 10/05/2005Title: CONTAINMENT SYSTEMS DRYWELL AIR TEMPERATURETEXT 3.6.1.6 0 11/15/2002Title: CONTAINMENT SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERSTEXT 3.6.2.1 2 04/23/2008Title: CONTAINMENT SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURETEXT 3.6.2.2 0 11/15/2002Title: CONTAINMENT SYSTEMS SUPPRESSION POOL WATER LEVELTEXT 3.6.2.3 1 01/16/2006Title: CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLINGTEXT 3.6.2.4 0 11/15/2002Title: CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAYTEXT 3.6.3.1 2 06/13/2006Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERSTEXT 3.6.3.2 1 04/18/2005Title: CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEMTEXT 3.6.3.3 1 02/28/2013Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION.TEXT 3.6.4.1 11 11/06/2014Title: CONTAINMENT SYSTEMS SECONDARY CONTAINMENTPage 5 of -8Report Date: 01/22/15 SSES MANUALManual Name: TSB1Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTEXT 3.6.4.2 9 04/25/2014Title: CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)TEXT 3.6.4.3 4 09/21/2006Title: CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEMTEXT 3.7.1Title: PLANT SYSTEMSULTIMATE HEAT4 04/05/2010RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THESINK (UHS)TEXT 3.7.2Title: PLANTTEXT 3.7.3Title: PLANTTEXT 3.7.4Title: PLANTTEXT 3.7.5Title: PLANTTEXT 3. 7.6Title: PLANTTEXT 3.7.7Title: PLANT2 02/11/2009SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM1 01/08/2010SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM0 11/15/2002SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM1 10/04/2007SYSTEMS MAIN CONDENSER OFFGAS2 04/23/2008SYSTEMS MAIN TURBINE BYPASS SYSTEM1 10/04/2007SYSTEMS SPENT FUEL STORAGE POOL WATER LEVELTEXT 3.7.8Title: PLANT SYSTEMS0 04/23/2008TEXT 3.8.17 02/24/2014Title: ELECTRICAL POWER SYSTEMS AC SOURCES -OPERATINGTEXT 3.8.2 0 11/15/2002Title: ELECTRICAL POWER SYSTEMS AC SOURCES -SHUTDOWNPage6 of 8 Report Date: 01/22/15Page 6 of aReport Date: 01/22/15 SSES MANUALJManual Name: TSB1Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTEXT 3.8.3Title: ELECTRICALTEXT 3.8.4Title: ELECTRICALTEXT 3.8.5Title: ELECTRICALTEXT 3.8.6Title: ELECTRICALTEXT 3.8.7Title: ELECTRICALTEXT 3.8.8Title: ELECTRICALTEXT 3.9.1Title: REFUELINGTEXT 3.9.2Title: REFUELINGTEXT 3.9.3Title: REFUELINGTEXT 3.9.4Title: REFUELINGTEXT 3.9.5Title: REFUELINGTEXT 3.9.6Title: REFUELING4 10/23/2013POWER SYSTEMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIRPOWER SYS=POWER SYSTPOWER SYSTPOWER SYSTPOWER SYSTOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONS3 01/19/20092EMS DC SOURCES -OPERATING1 12/14/2006'EMS DC SOURCES -SHUTDOWN1 12/14/2006FEMS BATTERY CELL PARAMETERS1 10/05/2005'EMS DISTRIBUTION SYSTEMS -OPERATING0 11/15/20022EMS DISTRIBUTION SYSTEMS -SHUTDOWN0 11/15/2002REFUELING EQUIPMENT INTERLOCKS1 09/01/2010REFUEL POSITION ONE-ROD-OUT INTERLOCK0 11/15/2002CONTROL ROD POSITION0 11/15/2002CONTROL ROD POSITION INDICATION0 11/15/2002CONTROL ROD OPERABILITY -REFUELING1 10/04/2007REACTOR PRESSURE VESSEL (RPV) WATER LEVELPage 7 Report Date: 01/22/15Page7Report Date: 01/22/15 SSES MANUALManual Name: TSBIManual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTEXT 3.9.7 0 11/15/2002Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -HIGH WATER LEVELTEXT 3.9.8 0 11/15/2002Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -LOW WATER LEVELTEXT 3.10.1Title: SPECIALTEXT 3.10.2Title: SPECIALTEXT 3.10.3Title: SPECIALTEXT 3.10.4Title: SPECIALTEXT 3.10.5Title: SPECIALTEXT 3.10.6Title: SPECIALTEXT 3.10.7Title: SPECIALTEXT 3.10.8Title: SPECIALOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONS1 01/23/2008INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION0 11/15/2002REACTOR MODE SWITCH INTERLOCK TESTING0 11/15/2002SINGLE CONTROL ROD WITHDRAWAL -HOT SHUTDOWN0 11/15/2002SINGLE CONTROL ROD WITHDRAWAL -COLD SHUTDOWN0 11/15/2002SINGLE CONTROL ROD DRIVE (CRD) REMOVAL -REFUELING0 11/15/2002MULTIPLE CONTROL ROD WITHDRAWAL -REFUELING1 04/18/2006CONTROL ROD TESTING -OPERATING1 04/12/2006SHUTDOWN MARGIN (SDM) TEST -REFUELING?age8 of 8 Report Date: 01/22/15?age 8 of 8Report Date: 01/22/15 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionTOC Table of Contents 23B 2.0 SAFETY LIMITS BASESPage TS / B 2.0-1 1Page TS / B 2.0-2 3Page TS / B 2.0-3 6Page TS / B 2.0-4 4Page TS / B 2.0-5 6Page TS / B 2.0-6 1Pages TS / B 2.0-7 through TS / B 2.0-9 1B 3.0 LCO AND SR APPLICABILITY BASESPage TS / B 3.0-1 1Pages TS / B 3.0-2 through TS / B 3.0-4 0Pages TS / B 3.0-5 through TS / B 3.0-7 A, 1Page TS / B 3.0-8 3Pages TS / B 3.0-9 through TS / B 3.0-11 2Page TS / B 3.0-1 Ia 0Page TS / B 3.0-12 1Pages TS / B 3.0-13 through TS --2Pages TS / B 3.0-16 and TS /B3 0B 3.1 REACTIVITY CONTROL BPages B 3.1-1 through 3.1- 0Page TS / B 3.1-5 1Pages TS / B 3.1 andT 13E-7 2Pages B 3.1-8 thiuirhu B 3.1-i'R1 0Page TS/B 3.14 -1Page B 3. 0.Page TS 1hrough B 3.1-19 0Pa e -20 and TS/B 3.1-21 1PaT 1-22P T 3.1-23 19T / B 31-24 0.ITS / B 3.1-25 through TS / B 3.1-27 1NgTS / B 3.1-28 2Page TS / B 3.1-29 1Pages B 3.1-30 through B 3.1-33 0Pages TS / B 3.3-34 through TS / B 3.3-36 1Page TS / B 3.1-37 2Page TS / B 3.1-38 3Pages TS / B 3.1-39 and TS / B 3.1-40 2Page TS / B 3.1-40a 0Pages TS / B 3.1-41 and TS / B 3.1-42 2SUSQUEHANNA -UNIT 1 TS / B LOES-1 Revision 120SUSQUEHANNA -UNIT 1TS / B LOES-1Revision 120 SUSQUEHANNA* STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS / B,3.1.43 1Page TS / B 3.1-44 0Page TS / B 3.1-45 3Pages TS / B 3.1-46 through TS / B 3.1-49 1Page TS / B 3.1-50 0Page TS / B 3.1-51 3B 3.2 POWER DISTRIBUTION LIMITS BASESPage TS / B 3.2-1 2Pages TS / B 3.2-2 and TS / B 3.2-3 3Pages TS / B 3.2-4 and TS / B 3.2-5 2Page TS I B 3.2-6 3Page B 3.2-7 1Pages TS / B 3.2-8 and TS / B 3.2-9 3Page TS / B 3.2.10 2Page TS / B 3.2-11 3Page TS / B 3.2-12 1Page TS / B 3.2-13 2B 3.3 INSTRUMENTATIONPages TS / B 3.3-1 through TS / B 3.3-4 1Page TS / B 3.3-5 2Page TS / B 3.3-6 1Page TS / B 3.3-7 3Page TS / B 3.3-7a 1Page TS / B 3.3-8 5Pages TS / B 3.3-9 through TS / B 3.3-12 3Pages TS / B 3.3-12a 1Pages TS / B 3.3-12b and TS / B 3.3-12c 0Page TS / B 3.3-13 1Page TS / B 3.3-14 3Pag'es TS / B 3.3-15 and TS / B 3.3-16 1Pages TS / B 3.3-17 and TS / B 3.3-18 4Page TS / B 3.3-19 1Pages TS / B 3.3-20 through TS / B 3.3-22 2Page TS / B 3.3-22a 0Pag'es TS / B 3.3-23 and TS / B 3.3-24 2Pages TS / B 3.3-24a and TS / B 3.3-24b 0Page TS / B 3.3-25 3Page TS / B 3.3-26 2Page TS / B 3.3-27 1Page TS / B 3.3-28 3Page TS / B 3.3-29 4Page TS I B 3.3-30 3Page TS /B 3.3-30a 0'SO800EHANNA -UNIT 1TS / B LOES-2k6v:,ision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST 6F EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS / B 3.3-31 4Page TS / B 3.3-32 5Pages TS / B 3.3-32a 0Page TS / B 3.3-32b 1Page TS / B 3.3-33 5Page TS / B 3.3-33a 0Page TS / B 3.3-34 1Pages TS / B 3.3-35 and TS / B 3.3-36 2Pages TS / B 3.3-37 and TS / B 3.3-38 1Page TS/. B 3.3-39 2Pages TS / B 3.3-40 through TS / B 3.3-43 1Page TS / B 3.3-44 4Pages TS / B 3.3-44a and TS J B 3.3-44b 0Page TS / B 3.3-45 3Pages TS / B 3.3-45a and TS / B 3.3-45b 0Page TS / B 3.3-46 3Pages TS /B 3.3-47 2Pages TS / B 3.3-48 through TS / B 3.3-51 3Pages TS / B 3.3-52 and TS / B 3.3-53 2Page TS / B 3-3-53a 0Page TS / B 3.3-54 5Page TS-/ B 3.3-55 2Pages TS / B 3.3-56 and TS / B 3.3-57 1Page TS / B 3.3-58 0Page TS / B 3.3-59 1Page TS / B 3.3-60 0Page TS / B 3.3-61 1Pages TS / B 3.3-62 and TS / B 3.3-63 0Pages TS / B3.3-64 and TS / B 3.3-65 2Page TS / B 3.3-66 4Page TS / B 3.3-67 3Page TS / B 3.3-68 4Page TS / B 3.3-69 5Pages TS / B 3.3-70 4Page TS / B 3.3-71 3Pages TS / B 3.3-72 and TS / B 3.3-73 2Page TS / B 3.3-74 3Page TS / B 3.3-75 2Page TS / B 3.3-75a 6Page TS / B 3.3-75b 7Page TS / B 3.3-75c 6Pages B 3.3-76 through B 3.3-77 0Page TS / B 3.3-78 1-SU]QUEH".A NA -NT1 T OS3Rvso 2809QUEWANNA -UNIT 1TS / B LOES-3ReVisi6n 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages B 3.3-79 through B 3.3-81 0Page TS / B 3.3-82 2Page B 3.3-83 0Pages B 3.3-84 and B 3.3-85 1Page B 3.3-86 0Page B 3.3-87 1Page B 3.3-88 0Page B 3.3-89 1Page TS / B 3.3-90 1Page B 3.3-91 0Pages TS / B 3.3-92 through TS I B 3.3-100 1Pages TS / B 3.3-101 through TS / B 3.3-103 0Page TS / B 3.3-104 2Pages TS / B 3.3-105 and TS / B 3.3-106 0Page TS / B 3.3-107 1Page TS / B 3.3-108 0Page TS / B 3.3-109 1Pages TS / B 3.3-110 and TS / B 3.3-111 0Pages TS / B 3.3-112 and TS / B 3.3-112a 1Pages TS / B 3.3-113 through TS / B 3.3-115 1Page TS / B 3.3-116 3Page TS / B 3.3-117 1Pages TS / B 3.3-118 through TS / B 3.3-122 0Pages TS / B 3.3-123 and TS / B 3.3-124 1Page TS / B 3.3-124a 0Page TS / B 3.3-125 0Pages TS / B 3.3-126 and TS / B 3.3-127 1Pages TS / B 3.3-128 through TS/ B 3.3-130 0Page TS / B 3.3-131 1Paddes TS / B 3.3-132 through TS / B 3.3-134 0Pages B 3.3-135 through B 3.3-137 0Page TS / B 3.3-138 1Pages B 3.3-139 through B 3.3-149 0Pages TS / B 3.3-150 and TS / B 3.3-151 1Pages TS / B 3.3-152 through TS / B 3.3-154 2Page TS / B 3.3-155 1Pages TS / B 3.3-156 through TS / B 3.3-158 2Pages TS / B 3.3-159 and TS / B 3.3-160 1Page TS / B 3.3-161 2Page TS / B 3.3-162 1Page TS / B 3.3-163 2Page TS / B 3.3-164 1Pages TS / B 3.3-165 through TS / B 3.3-167 2SU0SQUEHANNA -UNIT 1TS FB LOES-4Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS'/ B 3.3-168 and TS / B 3.3-169 1Page TS / B 3.3-170 3Page TS / B 3.3-171 2Pages TS / B 3.3-172 through TS / B 3.3-177 1Pages TS / B 3.3-178 and TS / B 3.3-179 2Page TS / B 3.3-179a 2Pages TS / B 3.3-179b and TS / B 3.3-179c 0Page TS / B 3.3-180 1Page TS / B 3.3-181 3Page TS / B 3.3-182 1Page TS / B 3.3-183 2Page TS / B 3.3-184 1Page TS / B 3.3-185 4Page TS / b 3.3-186 1Pages TS / B 3.3-187 and TS / B 3.3-188 2Pages TS / B 3.3-189 through TS / B 3.3-191 1Page TS / B 3.3-192 0Page TS / B 3.3-193 1Pages TS / B 3.3-194 and TS / B 3.3-195 0Page TS / B 3.3-196 2Pages TS / B 3.3-197 through TS / B 3.3-204 0Page TS / B 3.3-205 1Pages B 3.3-206 through B 3.3-209 0Page TS / B 3.3-210 1Pages B 3.3-211 through B 3.3-219 0-B 3.4 REACTOR COOLANT SYSTEM BASESPages B 3.4-1 and B 3.4-2 0Pages TS / B 3.4-3 and Page TS / B 3.4-4 4Page TS / B 3.4-5 3Pages TS / B 3.4-6 through TS / B 3.4-9 2Page TS / 8 3.4-10 1Pages TS / 3.4-11 and TS /B 3.4-12 0Page TS / B 3.4-13 2Page TS / 8 3.4-14 1Page TS / 8 3.4-15 2Pages TS / B 3.4-16 and TS / B 3.4-17 4Page TS / B 3.4-18 2Pages B 3.4-19 through B 3.4-27 0Pages TS / B 3.4-28 and TS / B 3.4-29 1Page TS/B 3.4-30 2Page TS B 3.4-31 1,Pages TS / B 3.4-32 and TS / B 3.4-33 2Page TS / B 3.4-34 1Page TS / B 3.4-34a 05ll."fi IFHANNlA -I INJIT 1 TR B P I fLFO--5 RAi'inin 192S V I V i i SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS I B 3.4-35 and TS / B 3.4-36 1Page TS / B 3.4-37 2Page TS / B 3.4-38 1Pages B' 3.4-39 and B 3.4-40 0Page TS / B 3.4-41 2Pages TS / B 3.4-42 through TS / B 3.4-45 0,Page TS / B 3.4-46 1Pages TS B 3.4-47 and TS / B 3.4-48 0Page TS/B 3.4-49 3Page TS / B 3.4-50 1Page TS / B 3.4-51 3Page TS / B 3.4-52 2Page TS / B 3.4-53 1Pages TS / B 3.4-54 through TS / B 3.4-56 2Page TS / B 3.4-57 3Pages TS / B 3.4-58 through TS / B 3.4-60 1B 3.5 ECCS AND RCIC BASESPages B 3.5-1 and B 3.5-2 0Page TS / B 3.5-3 3Page TS / B 3.5-4 1Page TS / B 3.5-5 2Page TS / B 3.5-6 1Pages B 3.5-7 through B 3.5-10 0Page TS /B 3.5-11 1Page TS / B 3.5-12 0Page TS / B 3.5-13 2Pages TS / B 3.5-14 and TS / B 3.5-15 0Pages TS / B 3.5-16 and TS / B 3.5-17 3'Page TS / B 3.5-18 1Pages B 3.5-19 through B 3.5-24 0Page TS / B 3.5-25 1Page TS / B 3.5-26 and TS / B 3.5-27 2Page TS / B 3.5-28 0Page TS / B 3.5-29 1Pages TS / B 3.5-30 and TS / B 3.5-31 0B 3.6 CONTAINMENT SYSTEMS BASESPage TS / B 3.6-1 2Page TS / B 3.6-1a 3Page TS / B 3.6-2 4Page TS / B 3.6-3 3Page TS / B 3.6-4 4Pages TS / B 3.6-5 and TS / B 3.6-6 3.U .E AN A-..... BLO S-.Rviio 12. 0 :SUSQUEHANNA -UNIT 1TS / B LOES-6Revision 120 SUSQUEHANNA.STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS / B 3.6-6a 2Page TS / B 3.6-6b 4Page TS / B 3.6-6c 0Page B 3.6-7 0Page B 3.6-8 1Pages B 3.6-9 through B 3.6-14 0Page TS / B3.6-15 3Page TS / B 3.6-15a 0Page TS / B 3.6-15b 2Pages TS / B 3.6-16 and TS / B 3.6-17 2Page TS / B 3.6-17a 1Pages TS / B 3.6-18 and TS / B 3.6-19 0Page TS / B 3.6-20 1Page TS / B 3.6-21 2Page TS / B 3.6-22 1Page TS / B 3'.6-22a 0Page TS / B 3.6-23 1Pages TS / B 3.6-24 and TS / B 3.6-25 0Pages TS / B 3.6-26 and TS / B 3.6-27 2Page TS / B 3.6-28 7Page TS / B 3.6-29 2Page TS / B 3.6-30 1Page TS / B 3.6-31 3Pages TS / B 3.6-32 and TS / B 3.6-33 1Pages TS / B 3.6-34 and TS / B 3.6-35 0Page TS / B 3.6-36 1Page TS / B 3.6-37 0Page TS / B 3.6-38 3Page TS / B. 3.6-39 2Page TS / B 3.6-40 6Page TS / B 3.6-40a 1Page B 3.6-41 1Pages B 3.6-42 and B 3.6-43 0Pages TS / B 3.6-44 and TS / B 3.6-45 1Page TS / B 3.6-46 2Pages TS / B, 3.6-47 through TS / B 3.6-51 1Page TS / B 3.6-52 2Pages TS / B 3.6-53 through TS / B 3.6-56 0Page TS / B 3.6-57 1Page TS / 3.6-58 2Pages B 3.6-59 through B 3.6-63 0Pages TS / B 3.6-64 and TS / B 3.6-65 1Pages B 3.6-66 through B 3.6-69 0SUSQUHANNA--UNT-1 T ..B..ES. .e...o 120s0sQ0EHANNA -UNIT 1TS / B LOES-7Rev/i~ion 1.20 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.6-70 through TS /B 3.6-75 1Pages B 3.6-76 and B 3.6-77 0Page TS / B 3.6-78 1Pages B 3.6-79 and B 3.3.6-80 0Page TS / B 3.6-81 1Pages TS / B 3.6-82 and TS / B 3.6-83 0Page TS / B 3.6-84 4Page TS / B 3.6-85 2Page TS / B 3.6-86 4Pages TS / B 3.6-87 through TS / B 3.6-88a 2Page TS / B 3.6-89 6Page TS / B 3.6-90 4Page TS / B 3.6-90a 0Pages TS / B 3.6-91 and TS I B 3.6-92 3Page TS / B 3.6-93 2Pages TS / B 3.6-94 through TS / B 3.6-96 1Page TS /B 3.6-97 2Page TS / B 3.6-98 1Page TS / B 3.6-99 2Pages TS / B 3.6-100 and TS / B 3.6-100a 6Page TS / B 3.6-100b 4Page TS / B 3.6-100c 0Pages TS I B 3.6-101 and TS / B 3.6-102 1Pages TS / B 3.6-103 and TS B 3.6-104 2Page TS / B 3.6-105 3Page TS / B 3.6-106 2Page TS / B 3.6-107 3B 3.7 PLANT SYSTEMS BASESPages TS / B 3.7-1 3Page TS / B 3.7-2 4Pages TS I B 3.7-3 through TS / B 3.7-5 3Page TS / B 3.7-5a 3Page TS / B 3.7-6 3Page TS /B 3.7-6a 2Page TS / B 3.7-6b 2Page TS / B 3.7-6c 2Page TS / B 3.7-7 3Page TS / B 3.7-8 2Pages TS / B 3.7-9 through TS / B 3.7-11 1Pages TS / B 3.7-12 and TS / B 3.7-13 2Pages TS / B 3.7-14 through TS / B 3.7-18 3Page TS / B 3.7-18a 1Pages TS I B 3.7-18b through TS I B 3.7-18e 0SUS'QUEHANNA -UNIT 1 TS / B LOES-8 Rkevs ion 120 SUSQUEHANNA STEAM ELECTRIC STATIONLISTQOFEFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.7-19 through TS / B 3.7-23 1Page TS / B 3.7-24 1Pages TS / B 3.7-25 and TS / B 3.7-26 0.Pages TS / B 3.7-27 through TS I B 3.7-29 5Page TS / B 3.7-30 2Page TS / B 3.7-31 1Page TS / B 3.7-32 0Page TS / B 3.7-33 1Pages TS B 3.7-34 through TS I B 3.7-37 0B 3.8 ELECTýRICAL POWER SYSTEMS BASESPage TS / B: 3.8-1 3Pages TS / B 3.8-2 and TS / B 3.8-3 2Page TS / B 3.8-4 3Pages TS / B 3.8-4a and TS / B 3.8-4b 0Page TS /B 3.8-5 5Page TS / B 3.8-6 3Pages TS / B 3.8-7 through TS/B 3.8-8 2Page TS / B 3.8-9 4Page TS / B 3.8-10 '3Pages TS / B 3.8-11 and TS/ B 3.8-17 2Page TS-/B 3.8-18 3-Pages TS / B 3.8-19 through TS / B 3.8-21 2Pages TS / B 3.8-22 and TS / B 3.8-23 3Pages TS / B 3.8-24 through TS / B 3.8-30 2Pages TS / B 3.8-31 and TS / B 3.8-32 3'Pages TS / B 3.8-33 through TS / B 3.8-37 2Pages B 3.8-38 through B 3.8-44 0Page TS / B 3.8-45 .3Pages TS / B 3.8-46 through TS / B 3.8-48 0Pages TS / B 3.8-49 and TS I B 3.8-50 3Page TS / B 3.8-51 1Page TS / B 3.8-52 0Page TS / B 3.8-53 1Pages TS / B 3.8-54 through TS / B 3.8-57 2Pages TS / B 3.8-58 through TS / B 3.8-61 3Pages TS / B 3.8-62 and TS / B 3.8-63 5Page TS / B 3.8-64 4Page TS / 8 3.8-65 5Pages TS / B 3.8-66 through TS / B 3.8-77 1Pages TS / B 3.8-77A through TS / B 3.8-77C 0Pages B 3.8-78 through B 3.8-80 0Page TS / B 3.8-81 1Pages B 3.8-82 through B 3.8-90 0SUSQU9 HANNA -UNIT 1 TS B LOES-9 Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionB 3.9 REFUELING OPERATIONS BASESPages TS / B 3.9-1 and TS / B 3.9-1a 1Pages TS / B 3.9-2 through TS / B 3.9-5 1Pages TS / B 3.9-6 through TS / B 3.9-8 0Pages, B 3.9-9 through B 3.9-18 0Pages TS / B 3.9-19 through TS / B 3.9-21 1Pages B 3.9-22 through B 3.9-30 0B 3.10 SPECIAL OPERATIONS BASESPage TS / B 3.10-1 2Pages TS /B 3.10-2 through TS /B 3.10-5 1Pages B 3.10-6 through B 3.10-31. 0Page TS / B 3.10-32 2Page B 3.10-33 0Page TS / B 3.10-34 1Pages 83.10-35 and B 3.10-36 0Page TS / B 3.10-37 1Page TS / B 3.10-38 2SIUSQOEPANNA -UNIT 1SUQ E A N* NT1T / ,O Sl R. ....... 120TS / B LOES-1 0We~i91on h 20, PPL Rev. 6Reactor Core. SLsB 2. 1.1B 2.0 SAFETY LIMITS (SLs)B 2.1.1 Reactor Core SLsBASESBACKGROUND GDC 10 (Ref. 1) requires, and SLs ensure' that specified acceptable fueldesign limits are not exceeded during steady state operation, normaloperational transients, and anticipated operational occurrences (AOOs).,The fuel cladding integrity SL is set such that no significant fuel damage is,calculated to occur if the limit is not violated. Because fuel damage is notdirectly observable, a stepback approach i's used to establish an SL, suchthat the MCPR is not less than the linmit specified- in Specification 2.1.1.2for AREVA NP fuel. MCPR greater than the specified limit represents aconservative margin relative to the conditions required to maintain fuelcladding integrity.The fuel cladding is one of the physical barriers that separate theradioactive materials from the environs. The integrity of this claddingbarrier is related to its relative freedom from perforations or cracking.Although some corrosion or use related cracking may occur during the lifeof the cladding, fission product migration from this source is incrementallycumulative and continuously measurable. Fuel cladding perforations,however, can result from thermal stresses, which occur from reactoroperation significantly above design" conditions.While fission product migration from cladding perfbration, is just asmeasurable as that from use related crack ing,. the thermally caused.cladding perforations signal a.%thr6shOld beyond which still'greater thermalstresses may cause gross, rather th6n: ~crenental,. detbriQration.Therefore, the fuel cladding SL is defined wi'-h 'a margin to the that Would produce onset of transition b6iling (i.e., MCPR.= 1.00). Thesecondioons represent a significant from the condition intended bydesign for planned operation. Th. MCP fuel cladding integrityýSL.ensures that during normal operation: a'iddurirng Aoos, at'least 99.9% of'the fuel rods in the core do not exp0erience transition boiling.(contir -(d)-Q*I'r .Cl l -IAMKlA _ I lIMIT -I T M 0 r) / _I D i7,, .,4

/PPL Rev. 6-Reactor Core, S'LsB 2.1.1BASESBACKGROUND(Continued)Operation above the boundary of the nucleate boi~ingýregime couldresult in. excessive cladding temnperature b ceoau ef the , ons6et oftransition boiling and the resultant1 sharp reduction in, eaft transfercoefficient. Inside the steam film, .hig'K:hcla.din te Umpeatres;aiereached, and a cladding water(zirc6riiurn water)reactioe r may ta keplace. This chemical reaction results int fuel claddingto a structurally weaker form. Tills' w`a`ker fori mai resulting in an uncontrolled release of, activity to th-.ereactbr coolant":APPLICABLESAFETY ANALYSESThe fuel cladding must not sustain damage: as a result of normaloperation and AOOs. The reactor-core SLs are established topreclude violation of the fuel de'sign criteriorn th ,at. an- fMCPR limit is tobe established, such that at least 99.9% of the fuel rods in the corewould not be expected to experience the onset of transition boiling.The Reactor Protection System setpoints (LCO 3.3.1.1, "ReactorProtection System (RPS),lInstrumentation"), in combination with theother LCOs, are designed to preveLnt anylanticiqpateýt -combination oftransient conditions for Reactor Co'olant'Systee r level, pressure,and THERMAL POWER level that *oull'result in! re6chinrg the MCPRlim it.2.1.1.1 Fuel Cladding Integrity'The use of the SPCB (Reference 4).correlati6r is vald fbr criticalpower calculations at pressures >.571.4 psia ad, urd e mass fluxes'> 0.087 x 106 lb/hr-ft2.For operation at. 6ft,,.i pre re:-Irlow'flows thefuel cladding integrity SL is established by a'h liftingl condition on coreTHERMAL POWER, with the foiiowing..bdsis:.Provided that the water -level in. the vessel dovnd6omer ismaintained abo5ve the top: of the act vfuei :,atqral&citcUlation issufficient to ensure a minimum bundrefi bforlII 'ual 'assembliesthat have a relatively high power arid 06t'enti'llV can64 approach acritical heat flux condition..1:AAekcontifiwed)',ýý.SUSQUEHANNA -UNIT 1TS /B 2.0-2 BASESAPPLICABLESAFETY1ANALYSES2.1.1.1 Fuel Cladding IntecqFor the > 28-x, 103 lb/hr. For theAlcoolant minimum bundle flomass flux is always > 0.25data taken from various ARfrom 14.7 psia to 1400 psia0.25 x 106 lb/hr-ft2 is appro0power of approximately 3.3peaking factor of approxim.the expected peaking facto23% RTP for reactor presstconditions of lesser powerV2.1.1.2 MCPR.. ........PPLERev. 6 .Reactor ore& SLsB 2.1.1 Airity (continued).the minimum bundle flow'isREVA NP ATRIUM-I.0 fuel desjigni the'.w arid maximum airea. 8ae thatthe..10'1 b/hr-ft2.Full, scal'ditei. Fa lpower test ..EVA NP-and:-GEfuel desigrns-a-t pressures "indica ..the fuelassemblrc Critica.l power atcimat6ty .3.35 Mwt, At 23% R1rP, a .bundle56MW6'C166rresp.ond's.toa bundle radialately 2.8, which :is significa.t ly-jhiher than 0r. Thus, a THERMAL POWER lfimit of.ures..< 557 psig is conservative and for .4wVould remain conservative. " * " "The MCPR SL ensures sufficient conservatism ih the operating MCPRlimit that, in the event of an AOd"frim the limiting condition of.operation, at least 99.9% of the' fuieltrods in the core would be expected:to avoid boiling transition. The mrargih between calculatedl boilingtransition(i.e., MCPR = 1-.00) and the MCPR SL is based on a detailed statisticalprocedure that considers the. uncertainties in monitoring the coreoperating state. One specific uhn6reaintyinIuded in: the SL is theuncertainty in the critical power correlation: References'.2, 4, and 5describe the methodology used in determining theMCPR SL.The SPCB critical power correlation is based on apractical test data. As long, s'the cOre, resraige of validity of the correlations (refer toSectioiassumed reacfor conditions..sed in. defining thelSlconservatism into the limit, b.cause: bounding: hig:"and bounding flat Io-o" kpeaKgasmtibutions Cnumber of rods.in boiling, tr~astiti6n. These corierinh~erent accuracy of th'e.SP.C"co ..rrela'tio ..provi'd,of assurance that during sustaihne'd &peration aktftwould be no transition, boi ig i the core.4, .41(continued)Revision 6:SUSQUEHANNA -UNIT 1TIS /B 2.0-3

9....BASESAPPLICABLESAFETY ANALYSES2.1.1.2 MCPR (continued)If boiling transition were to occur, there is reason tintegrity of the fuel would fifot be Significant test data, accumulted by the, NRC andorganizations indicate that the 'traprotect against cladding failure is a very'c66nserValof the.data indicate .hat BWR if'ue"li canýs"u'rvive forof time in an environment of boiling tran'sition.AREVA NP ATRIUM-10 fuel is: monitor.edusing thiPower Correlation. The effects of chanhol- bwo" onincluded in the calculation' of the, M.PRkSL' Explichannel bow in the MCQR SL addresses, the con .cNo. 90-02 entitled "Loss of Thermal.Margin CauseBow.".PP.L.ev 6...SLso beliveý that t~he',privateisition limritation to'iy:a'pproa dh.' Muchan,. ent ne- eriode.`PC'B; CrticalI MIRare,.expl icitlyci treatm6n..ferns. of NRýC Bulletin'd by Chatnel BoxAM.Monitoring. required, for compliance with the MCPR SL; is specified inLCO 3.2.2, Minimum Critical Power Ratio.2.1.1.3 Reactor Vessel Water LevelDuring MODES 1 and 2 the reactor vessel water level. is re~quired to beabove the top-,of the active fuel% t, provide. core cooling- capatijitý. "With fuel in the reactor Vessel' during-peio ds vh'en"the rbenactoris Shutdown, consideration must be.g'e!n towater level requiirem'ets .d'ue t.the effect of decay heat. if the er, evei s .'shoialdý dropý below th to'tpof the active irradiated fuel during thi speiod..the'abity to remo'vedacay heat isreduced. This r'dti cobo ng.cpabii.tycould. eardto elevated cladding temperatuesand clad perforation an.. the. eventthat the water level becomes <-2/'3.oteoff;thedo6h6ight. The reactor-vessel water level SL has been- es~bi shed at the 5f t veirrad .ated fuel-to provide a .poi ht.ittcan be monitored and to also "provide adequate margin for effective action.(c6ntihued) .k .;SUSQUEHANNA -UNIT 1TS / B 2.0-4Revisibn 4,----------------------------------.:.

sxBASES .PPL Re,6v. 6Reactor SLsL.ct the'"integrity of the fuelterilals to the environs.re operates Within the fu e'lr."eactor vessel**water lev.e'li'-.d fuel in order to preventadperforations.SAFETY LIMITSThe reactor core SLs are established.tolproclad barrier to 'the release Of radioactive ma;SL 2.1.1.1 and SL 2.1.1.2 ensure t;a~tth.e cdesign criteria. SL 2.1.1.3 ensures.thatte"is greater than the top of the actieie,.radia'eelevated clad temperatures and: resutbnt cc-APPLICABILITY SLs 2.1.1.1, 2.1.1.2, and 2.1.1.3 are applicable in alrMODES.SAFETY LIMIT Exceeding an SL may cause fuel damage and create a potential forVIOLATIONS radioactive limits. Therefore, it isrequired to inse6rt al. insertablie ;i.rods and restore compli ancewith .the SLs within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The&2 hour Completion Time ensures thatthe operators take prompt reme:ial action and also ensures that theprobability of an accident occurring during. this period is minimal.REFERENCES 1. 10 CFR 50, Appendix A, GDC 10.2. ANF-524. (P)(A), Revision 2,. Cnritical Power Meth.odology forBoiling Water Reactors," Syipplement 1 Revision 2 andSupplement 2, Novembýer l1990.3.' Deleted.4. EMF-2209(P)(A), "SPCGB Critical-. owe r Co rrelation,." AREVANP, [See Core'Operating Limits ReSpi-t for Revision LeVel].5. EMF-2ý158(P)(A), Revision 0 .e ationMethodBoiliJpm, einms. Po-wer. CorporationMethodology for Boihng. ateM R etors: ..Evaluatib.o andValidation of CASMO-4/Mi'oburB2, October 1q99.41.I -1,7I 9 : ...K .,I: , ., , ; 5* I SUSQUEHANNA -UNIT 1TS / B 2.0-5Revsio 6,.."12.,. .. 4 BrE* : ..: -. ..- .. ..1: .ReV*'i§uSbEH AN'NA -UNIT 1TS / B 2.0-6