ML15317A010

Susquehanna, Unit 2 - Technical Specifications Bases Manual

ML15317A010
Person / Time
Site:	Susquehanna
Issue date:	11/05/2015
From:	Gerlach R M Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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Download: ML15317A010 (45)

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Nov. 05, 2015Page1 of 2MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2015-44707USER INFORMATION:GERLACH*ROSEY NEMPL#:028401 CA#: 0363Address: NUCSA2Phone#: 254-3194TRANgMT'1'AT, TO: GERLACH*ROSEY N 11/05/2015LOCATION: 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.TSB2 -TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALREMOVE MANUAL TABLE OF CONTENTSADD MANUAL TABLE OF CONTENTSCATEGORY: DOCUMENTS TYPE: TSB2DATE: 08/05/2015DATE: 11/04/2015AocD Nov. 05, 2015Page2 of 2ID: TEXT 3.4.10ADD: REV: 4REMOVE: REV:3CATEGORY: DOCUMENTSID: TEXT 3.5.2ADD: REV: 2TYPE: TSB2REMOVE: REV:I1CATEGORY:ID: TEXTREMOVE:DOCUMENTS3.6.4.1REV:II1TYPE: TSB2ADD: REV: 12CATEGORY: DOCUMENTSID: TEXT LOESADD: REV: 125TYPE: TSB2REMOVE: REV:124ANY 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: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTable Of ContentsIssue Date: 11/04/2015Pr~ocedure Name RevTEXT LOES 125Title: LIST OF EFFECTIVE SECTIONSIssue Date11/ 04/2 015Change ID Change NumberTEXT T0CTitle: TABLE OF CONTENTS22 07/02/2014TEXT 2.1.1 5Title: SAFETY LIMITS (SLS) REACTORTEXT 2.1.2 1Title: SAFETY LIMITS (SLS) REACTOR01/22 /2 015CORE SLS10/04/2 007COOLANT SYSTEM(RCS) PRESSURE SLTEXT 3.0 3 08/20/2009Title: LIMITING CONDITION FOR OPERATION (LC0) APPLICABILITYTEXT 3.1.1Title: REACTIVITYTEXT 3.1.2Title: REACTIVITYTEXT 3.1.3Title: REACTIVITYTEXT 3.1.4Title: REACTIVITYTEXT 3.1.5Title: REACTIVITYTEXT 3.1.61 03/24/2005CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)0 11/18/2002CONTROL 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 02/24/2014Title: REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROLPagej. of 8 Report Date: 11/05/15Page ! ofReport Date: 11/05/15 SS~ES MANUALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.1.7 3 10/04/2007Title: 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 4 05/06/2009Title: POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)TEXT 3.2.2 3 05/06/2009Title: POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)TEXT 3.2.3 2 05/06/2009Title: POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE LHGRTEXT 3.3.1.1 5 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 3 02/24/2014Title: INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATIONTEXT 3.3.2.2 2 02/22/2012Title: INSTRUMENTATION FEEDWATER -MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATIONTEXT 3.3.3.1 8 02/28/2013Title: INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMNTATIONTEXT 3.3.3.2 1 04/18/2005Title: INSTRUMENTATION REMOTE SHUTDOWN SYSTEMTEXT 3.3.4.1Title: INSTRUMENTATION1 05/06/2009END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATIONWPage2 of *~. Report Date: 11/05/15Page ! ofReport Date: 11/05/15 SSES MANUALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.3.4.2 0 11/18/2002Title: INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP(ATWS-RPT) INSTRUMENTATIONTEXT 3.3.5.1 5 02/24/2014Title: INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATIONTEXT 3.3.5.2 0 11/18/2002Title: 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 3 12/17/2007Title: INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATIONTEXT 3.3.8.2 0 11/18/2002Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORINGTEXT 3.4.1Title: REACTOR COOLANTTEXT 3.4.2Title: REACTOR COOLANT4 07/20/2010SYSTEM (RCS) RECIRCULATION LOOPS OPERATING3 10/23/2013SYSTEM (RCS) JET PUMPSTEXT 3.4.3 3 01/13/2012Title: REACTOR COOLANT SYSTEM (RCS) SAFETY/RELIEF VALVES (S/RVS)TEXT 3.4.4Title: REACTOR COOLANT0 11/18/2002SYSTEM (RCS) RCS OPERATIONAL LEAKAGEPage~ of ~ Report Date: 11/05/15Page ofReport Date: 11/05/15 SSES ANI JAI.Manual Name: TSB2:i"Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.4.5 3 03/10/2010Titles 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---Title :_REACT0RCOOLANTTEXT 3.4.8Title: REACTOR COOLANT-HOT SHUTDOWNTEXT 3.4.9Title: REACTOR COOLANT-COLD SHUTDOWNTEXT 3.4.10Title: REACTOR COOLANTTEXT 3.4.11Title: REACTOR COOLANTTEXT 3.5.12 10/04/2007SYSTEM_(RCS) ACTIVITY __2 03/28/2013SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEMSYSTEM103/28/2013CRCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM4 11/04/2015(RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITSSYSTEM0 11/18/2002SYSTEM (RCS) REACTOR STEAM DOME PRESSURE4 07/16/2014Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTORSYSTEM ECCS -OPERATINGTEXT 3.5.2 2 11/04/2015Title: 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 05/06/2009Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKPage4 of 8 Report Date: 11/05/15Page A ofReport Date: 11/05/15 SSES M~ANUJALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.6.1.3CONTAINMYENTTEXT 3.6.1.4Title : CONTAINMENTTEXT 3.6.1.5__-Title: CONTAINMENTTEXT 3.6.1.6Title:. CONTAINMENTTEXT 3.6.2.1CONTAINMENTTEXT 3.6.2.2Title : CONTAINMENTTEXT 3.6.2.3Title : CONTAINMENTTEXT 3.6.2.4Title : CONTAINMENTTEXT 3.6.3.1Title : CONTAINMENTTEXT 3.6.3.2CONTAINMENTTEXT 3.6.3.3Title : CONTAINMENTTEXT 3.6.4.1Title: CONTAINMENT14 07/02/2014SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)1 05/06/2009SYSTEMS CONTAINMENT PRESSURE1 10/05/2005_SYSTEMSDRYWELLAIR TEMPERATURE -__0 11/18/2002SYSTEMS SUPPRESSION CHAMBER-T0-DRYWELL VACUU/MBREAKERS2 12/17/2007SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE0 11/18/2002SYSTEMS SUPPRESSION POOL WATER LEVEL1 01/16/2006SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING0 11/18/2002SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY2 06/13/2006SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS1 04/18/2005SYSTEMS DRYWELL AIR FLOW SYSTEM1 02/28/2013SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION12 11/04/2015SYSTEMS SECONDARY CONTAINMENTPages of 8 Report Date: 11/05/15Page ofReport Date: 11/05/15 SSES MANUALManual Nanme: TSB2[,Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.6.4.2 9 04/25/2014CONTAINMENT SYSTEMS SECONDARY CONTAINMThENT ISOLATION VALVES (SCIVS)TEXT 3.6,4.3 4 09/21/2006Title: CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEMTEXT 3.7.1-Title :_PLANTSYSTEMS_ULTIMATE HEAT5.. 04/27/2012_RESIDUAL HEAThREMOVAL SERVICEWATER (RHRSWLmSYSTEMANDTHESINK (UBS)TEXT 3.7.2Title: PLANTTEXT 3.7.3Title: PLANTTEXT 3.7.4Title: PLANTTEXT 3.7.5Title: PLANTTEXT 3.7.6Title: PLANTTEXT 3.7.7Title: PLANTTEXT 3.7.8Title: MAINETEXT 3.8.12 05/02/2008SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM1 01/08/2010SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM0 11/18/2002SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM1 10/04/2007SYSTEMS MAIN CONDENSER OFFGAS3 01/25/2011SYSTEMS MAIN TURBINE BYPASS SYSTEM1 10/04/2007SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL0 05/06/2009TURBINE PRESSURE REGULATION SYSTEM9 02/24/2014Title: ELECTRICAL POWER SYSTEMS AC SOURCES -OPERATINGTEXT 3.8.2 0 11/18/2002Title: ELECTRICAL POWER SYSTEMS AC SOURCES -SHUTDOWNPage 6 of 8 Report Date: 11/05/15Pageof 8Report Date: 11/05/15 S.SES MANUITALManul Nme: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.8.3 4 10/23/2013Title: ELECTRICAL POWER SYSTEMS DIESEL FUEL OIL LUBE OILAND STARTING AIRTEXT 3.8.4 3 01/19/2009Title: ELECTRICAL POWER SYSTEMS DC SOURCES -OPERATINGTEXT 3.8.5 1 .12/14/2006__Title: ELECTRICALPOWERSYSTEMS DC S0lURCES_= SHUTDOWN ____-TEXT 3.8.6 1 12/14/2006Title: ELECTRICAL POWER SYSTEMS BATTERY CELL PARAMETERSTEXT 3.8.7 4 10/05/2005Title: ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS -OPERATINGTEXT 3.8.8 0 11/18/2002Title: ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS -SHUTDOWNTEXT 3.9.1Title: REFUELINGTEXT 3.9.2Title: REFUELINGTEXT 3.9.3Title: REFUELINGTEXT 3.9.4Title: REFUELINGTEXT 3.9.5Title: REFUELINGOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONS0 11/18/2002REFUELING EQUIPMENT INTERLOCKS1 09/01/2010REFUEL POSITION ONE-ROD-OUT INTERLOCK0 11/18/2002CONTROL ROD POSITION0 11/18/2002CONTROL ROD POSITION INDICATION0 11/18/2002CONTROL ROD OPERABILITY -REFUELINGTEXT 3.9.61 10/04/2007Title: REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVELPage 7 of S Report Date: 11/05/15Page ! ofReport Date: 11/05/15 S.SES MANUALManual Name: TSB2'>Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.9.7 0 11/18/2002Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RER) -HIGH WATER LEVELTEXT 3.9.8 0 11/18/2002Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RER) -LOW WATER LEVELTEXT 3.10.1-Titl :_SPECIAL_TEXT 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: SPECIAL_OPERATIONS-OPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONS1.. 01/23/2008INSERVICELEAK AND HYDROSTAT~IC TESTINGOPERATION0 11/18/2002REACTOR NODE SWITCH INTERLOCK TESTING0 11/18/2002SINGLE CONTROL ROD WITHDRAWAL -HOT SHUTDOWN0 11/18/2002SINGLE CONTROL ROD WITHDRAWAL -COLD SHUTDOWN0 11/18/2002SINGLE CONTROL ROD DRIVE (CRD) REMOVAL -REFUELING0 11/18/2002MULTIPLE CONTROL ROD WITHDRAWAL -REFUELING1 03/24/2005CONTROL ROD TESTING -OPERATING2 04/09/2007SHUTDOWN MARGIN (SDM) TEST -REFUELINGPages of 8 Report Date: 11/05/15Page 8 ofReport Date: 11/05/15 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionTOC Table of Contents 228 2.0 SAFETY LIMITS BASESPage TS I B 2.0-1 2Pages TS I B 2.0-2 and TS / B 2.0-3 5Page TS /B 2.0-4 7Pages TS / 8 2.0-5 through TS I B 2.0-8 1B 3.0 LCO AND SR APPLICABILITY BASESPage TS /B 3.0-1 1Pages TS /8B3.0-2 through TS I B 3.0-4 0Pages TS /8B3.0-5 through TS /8B3.0-7 1Page TS /8B3.0-8 3Pages TS / B 3.0-9 through Page TS I B 3.0-1: 2Page TS /8B3.0-1 Ia 0Page TS /8B3.0-12 1Pages TS /8B3.0-13 through TS /8B3.0-1 2Pages TS /8B3.0-16 and TS /8 3.0- ,,0B 3.1 REACTIVITY CONTROL BASE Pages B 3.1-1 through 8 3.1 Page TS /8B3.1-5 -Pages TS /8B3.1-6 an 2Pages B3.1-8 throu Page TS /8B3.1-1 ,,0PageTS/B3. IPage 1Pages 17,through TS /B 3.1-19 0Pages Oand TS /B 3.1-21 1o0P /83.1-25 through TS /8B3.1-27 1TS ;/83.1-28 2/B 3.1-29 1Pgs TS / B 3.1-30 through TS / B 3.1-33 0Pages TS /8B 3.1.34 through TS /8B 3.1-36 1Page TS /8B3.1-37 2Page TS /8B3.1-38 3Pages TS /8B3.1-39 and TS / B 3.1-40 2Page TS /8B 3.1-40a 0Page TS /8B3.1-41 1Page TS / B 3.1-42 2SUSQUEHANNA -UNIT 2 TS/BLOES-1 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-1Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.1-43 1Page TS / B 3.1-44 0Page TS I B 3.1-45 3Page 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 BASESPages TS / B 3.2-1 and TS / B 3.2-2 2Page TS / B 3.2-3 4Page TS / B 3.2-4 *1Page TS / B 3.2-5 3Page TS I B 3.2-6 "4----Page TS--B 3.2 ---_- --3Pages TS / B 3.2-8 and TS / B 3.2-9 4Pages TS / B 3.2-10 through TS I B 3.2-12 2Page TS / B 3.2-13 1B 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 I B 3.3-8 4Pages TS I B 3.3-9 through TS / B 3.3-13 3Page TS / B 3.3-14 4Pages TS / B 3.3-15 and TS / B 3.3-16 2Pages TS I B 3.3-17 through TS / B 3.3-21 3Pages TS I B 3.3-22 through TS / B 3.3-27 2Page TS / B 3.3-28 3Page TS / B 3.3-29 4Pages TS / B 3.3-30 and TS / B 3.3-31 3Pages TS / B 3.3-32 and TS / B 3.3-33 4Page TS / B 3.3-34 2Pages TS / B 3.3-34a and TS / B 3.3-34b IPages TS l B 3.3.34c and TS / B 3.3-34d 0Page TS I B 3.3-34e IPages TS / B 3.3-34f through TS / B 3.3-34i 0Pages TS l B 3.3-35 and TS / B 3.3-36 2Pages TS l B 3.3-37 and TS l B 3.3-38 1SUSQUEHANNA -UNIT 2 TS/B LOES-2 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-2Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS / B 3.3-39 2Pages TS / B 3.3-40 through TS / B 3.3-43 1Pages TS / B 3.3-44 through TS / B 3.3-54 3Pages TS / B 3.3-54a through TS I B 3.3-54d 0Page TS I B 3.3.54e 1Page TSI/B 3.3-55 2Page TS I B 3.3-56 0Page TS/1$ 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 0....... -Pages TS-/-B 373-64-and-TS I B 3.3-65 .... ...__ 2 -Page TS / B 3.3-66 4Page TS / B 3.3-67 3Page TS / B 3.3-68 4Page TS / B 3.3.69 5Page TS / B3.3-70 4Page TS I B 3.3-71 3Pages TS /B 3.3-72 and TS I B 3.3-73 2Page TS I B 3.3-74 3Page TS I B 3.3-75 2Pages TS / B 3.3-75a through TS I B 3.3-75c 6Pages TS / B 3.3-76 and TS I B 3.3-77 0Page TSI/B 3.3-78 1Pages TS / B 3.3-79 through TS I B 3.3-81 0Page TS / B 3.3-82 1Page TS / B3.3-83 0Pages TS / B 3.3-84 and TS I B 3.3-85 1Page TS / B3.3-86 0Page TS / B3.3-871Page TS / B 3.3-88 0Page TS I B 3.3-89 1Pages TS I B 3.3-90 and TS I B 3.3-91 0Pages TS / B 3.3-92 through TS /B 3.3-103 1Page TS / B 3.3-104 3Pages TS I B 3.3-105 and TS I B 3.3-106 1Page TS I B 3.3-107 2Page TS I B 3.3-108 1Page TS I B 3.3-109 2Pages TS /B 3.3-110 through TS/IB 3.3-112 1Page TS I B 3.3-113 2SUSQUEHANNA -UNIT 2 TS/BLOES-3 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-3Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS /8B3.3-114 1Page TS /8B3.3-115 2Page TS /8B3.3-116 3Pages TS / B 3.3-117 and TS / B 3.3-118 2Page TS / B 3.3-119 1Page TS /8B3.3-120 2Pages TS / B 3.3-121. and TS /83.3-122 3Page TS / B3.3-123 1Page TS /8B3.3-124 2Page TS / B 3.3-124a 0Page TS /8B3.3-125 1Page TS / B3.3-126 2Page TS / B 3.3-127 "3Page TS-[- 8-3_3-1 ... .. ..... .2_ -Pages TS / B 3.3-129 through TS / B 3.3-131 1Page TS /8B3.3-132 2Pages TS / 8 3.3-133 and TS/B83.3-134 1Pages TS / B 3.3-135 through TS / B 3.3-137 0Page TS / B 3.3-138 1Pages TS / 8 3.3-139 through TSI 83.3-146 0Pages B 3.3-147 through B 3.3-1 49 0Page TS /8B3.3-150 1Pages TS / B 3.3-151 through TS /B 3.3-154 2Page TS /8B3.3-155 1Pages TS / B 3.3-156 through TS I B 3.3-158 2Pages TS / B 3.3-159 through TSI 8 3.3-162 1Pages TS / B 3.3-163 through TS I B 3.3-166 2Pages TS / 8 3.3-167 and TS /8B3.3-168 1Pages TS / 8 3.3-169 and TS /8B3.3-170 3Pages TS / B 3.3-171 through TS / B 3.3-174 1Page TS / B 3.3-174a 1Pages TS/ B 3.3-1 75 through TS/IB 3.3-177 1Page TS /8B3.3-178 2Page TS /8B3.3-179 3Page TS / B 3.3-179a 2Page TS /8B3.3-180 1Page TS /8B3.3-181 3Page TS /8B3.3-182 1Page TS /8B3.3-183 2Page TS /8B3.3-184 1.Page TS /8B3.3-185 4Page TS / 8 3.3-1 86 1Pages TS / 8 3.3-187 and TS /83.3-188 2Pages TS / B 3.3-189 through TS /B 3.3-191 1Page TS / B83.3-192 0SUSQUEHANNA -UNIT 2 TS/B LOES-4 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-4Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS / B 3.3-193 IPages TS I B 3.3-194 and TS / B 3.3-195 0Page TS / B 3.3-196 2Pages TS I B 3.3-197 through TS /B 3.3-205 0Page TS / B 3.3-206 1Pages B 3.3-207 through B 3.3-209 0Page TS / B 3.3-210 1Page TS /B 3.3-211 2Pages TS / B 3.3-212 and TS I B 3.3-213 1Pages B 3.3-214 through B 3.3-220 0B 3.4 REACTOR COOLANT SYSTEM BASES___Pages TS/B 3_.4_-1 and _TS /8_3.4-2 ___ _- -__2Pages TS /8B3.4-3 through TS /8B3.4-5 4-,-Pages TS /8B3.4-6 through TS /8B3.4-9 3Page TS /8B3.4-10 1Pages TS /8B3.4-11 and TS /8B3.4-12 0Page TS / B 3.4-13 2Page TS /8B3.4-14 1Page TS/B 83.4-15 2Pages TS /8B3.4-16 and TS /8B3.4-17 4Page TS /8B3.4-18 2Pages B 3.4-19 through B 3.4-23 0Pages TS /8B3.4-24 through TS /8B3.4-27 0Page TS /8B3.4-28 1Page TS /8B3.4-29 3Page TS /8B3.4-30 2Page TS /8B3.4-31 1Pages TS /8B3.4-32 and TS /8B3.4-33 2Page TS / B 3.4-34 1Page TS / B 3.4-34a 0Pages TS / B 3.4-35 and TS /8B3.4-36 1Page TS /B 3.4-37 2Page B 3.4-38 1Pages B 3.4-39 and B 3.4-40 0Page TS /8B3.4-41 2Pages TS / B 3.4-42 through TSI/B 3.4-45 0Page TS /8B3.4.4-46 1Pages TS / B 3.4.4-47 and TS / B 3.4.4-48 0Page TS /8B 3.4-493Pages TS /8B3.4-50 and TS / B 3.4-51 2Page TS /8B3.4-52 3Page TS / B 3.4-52a 0Pages TS /8B3.4-53 through TS / B 3.4-56 2Page TS /8B3.4-57 3Pages TS / B 3.4-58 through TS / B 3.4-60 1SUSQUEHANNA -UNIT 2TS / B LOES-5Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionB 3.5 ECCS AND RCIC BASESPages TS / B 3.5-1 and TS I B 3.5-2 1Pages TS I B 3.5-3 and TS I B 3.5-4 2Page TS /8B3.5-5 3Page TS /8B3.5-6 2Pages TS/I.B 3.5-7 through TS / B 3.5-10 1Pages TS / B 3.5-11 and TS /8B3.5-12 2Pages TS / B 3.5-13 and TS /8B3.5-14 1Pages TS / 8 3.5-15 through TS / 8.3.5-17 3Pages TS /8B3.5-18 through TS /8B3.5-21 1Page TS /8B3.5-22 2Page TS / 8.3.5-23 1___Page B 3.5-24 0Page TS /B 3.5-25 1Pages TS /8B3.5-26 and TS /8B3.5-27 2Page TS /8B3.5-28 0Page TS / B 3.5-29 through TS I B 3.5-31 1B 3.6 CONTAINMENT SYSTEMS BASESPage TS /8B3.6-1 2Page TS /8B3.6-la 4Page TS /8B3.6-2 4Page TS /8B3.6-3 3Page TS /B 3.6-4 4Page TS /8B3.6-5 .3Page TS /8B3.6-6 4Page TS /B 3.6-6a 4Page TS /8B 3.6-6b 3Page TS /8B 3.6-6c 0Page B 3.6 0Page TS / 3.6-8 1Pages B 3.6-9 through 8 3.6-14 0Page TS /8B3.6-15 4Page TS /8B 3.6-15a 0Page TS /8B 3.6-15b 3Pages TS /8B3.6-16 and TS /8B3.6-17 3Page TS /8B 3.6-17a 1Pages TS /8B3.6-18 and TS /8B3.6-19 1Page TS /8B3.6-20 2Page TS /8B3.6-21 3SUSQUEHANNA -UNIT 2 TS/B LOES-6 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-6Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Titl__e RevisionPages TS I B 3.6-21a and TS I B 3.6-21b 0Pages TS / B 3.6-22 and TS I B 3.6-23 2Pages TS / B 3.6-24 and TS I B 3.6-25 1Pages TS / B 3.6-26 and TS / B 3.6-27 3Page TS I B 3.6-28 7Page TS I B 3.6-29 5Page TS /B 3.6-29a 0Page TS / B 3.6-30 2Page TS / B3.6-31 3Pages TS / B 3.6-32 and TS / B 3.6-33 2Page TS / B 3.6-34 1Pages TS / B 3.6-35 and TS / B 3.6-36 3__ Page TS /B 3.6-37 ___2Page TS / B 3.6-38 3Page TSI/B 3.6-39 7Page TS / B 3.6-39a IPage TS/1. 3.6-40 1Pages B 3.6-41 and B 3.6-42 0Pages TS / B 3.6-43 and TS / B 3.6-44 1Page TS / B 3.6-45 2Pages TS / B 3.6-46 through TS / B 3.6-50 1Page TS / B 3.6-51 2Pages TS / B 3.6-52 through TS / B 3.6-55 0Pages TS / B 3.6-56 and TS / B 3.6-57 2Pages B 3.6-58 through B 3.6-62 0Pages TS / B 3.6-63 and TS / B 3.6-64 1Pages B 3.6-65 through B 3.6-68 0Pages TS / B 3.6-69 through TS / B 3.6-71 1Page TS I B 3.6-72 2Pages TS / B 3.6-73 and TS / B 3.6-74 1Pages B 3.6-75 and B 3.6-76 0Page TS / B 3.6-77 1Pages B 3.6-78 and B 3.6-79 0Page TS / B 3.6-80 1Pages TS / B 3.6-81 and TS / B 3.6-82 0Page TS I B 3.6-83 4Page TS I B 3.6-84 2Page TS / B 3.6-85 4Pages TS / B 3.6-86 and TS I B 3.6-87 2Page TS /8B 3.6-87a 3Page TSI/B 3.6-88 6Page TS /8B3.6-89 4Page TS /8B 3.6-89a 0SUSQUEHANNA -UNIT 2 TSIB LOES-7 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-7Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.6-90 and TS / B 3.6-91 3Page TS I B 3.6-92 2Pages TS / B 3.6-93 through TS / B 3.6-95 1Page TS / B 3.6-96 2Page TS / B 3.6-97 1Page TS / B3.6-98 2Page TS / B 3.6-99 7Page TS / B 3.6-99a 6Page TS I B 3.6-99b 4Page TS / B 3.6-99c 0Pages TS / B 3.6-100 and TS / B 3.6-101 1Pages TS / B 3.6-102 and TS / B 3.6-103 *2Page TS / B 3.6-104 3Page TS / B 3.6-105 -2Page TS / B 3.6-106 3B 3.7 PLANT SYSTEMS BASESPage TS / B3.7-1 3Page TS / B 3.7-2 4Pages TS / B 3.7-3 through TS I B 3.7-5 3Page TS I B 3.7-5a 2Page TS/B 3.7.-6 4Page TSI!B 3.7-6a 3Page TS / B 3.7-6b 2Page TSI!B 3.7-6c 3Page TS / B 3.7-7 3Page TS I B 3.7-8 2Pages B 3.7-9 through B 3.7-11 0Pages TS / B 3.7-12 and TS I B 3.7-13 2Pages TS / B 3.7-14 through TS / B 3.7-18 3Page TS I B 3.7-18a IPages TS / B 3.7-18B through TS I B 3.7-18E 0Pages TS / B 3.7-19 through TS / B 3.7-24 1Pages TS / B 3.7-25 and TS I B 3.7-26 0Page TSI/B 3.7-27 4Pages TS / B 3.7-28 and TS / B 3.7-29 3Pages TS / B 3.7-30 and TS / B 3.7-31 1Page TS I B 3.7-32 0Page TSI/B 3.7-33 1Pages TS / B 3.7-34 through TS / B 3.7-37 0SUSQUEHANNA -UNIT 2 TS / B LOES-8 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-8Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionB 3.8 ELECTRICAL POWER SYSTEMS BASESPage TS / B 3.8-1 1Pages B 3.8-2 and B 3.8-3 0Page TS / B 3.8-4 1Pages TS / B 3.8-4a and TS / B 3.8-4b 0Pages TS / B 3.8-5 and TS / B 3.8-6 3Page TS / B 3.8-6a 1Pages B 3.8-7 and B 3.8-8 0Page TS / B 3.8-9 2Pages TS / B 3.8-10 and TS / B 3.8-11 1Pages B 3.8-12 through B 3.8-18 0Page TS / B 3.8-19 1Pages B 3.8-20 through B 3.8-22 ....0Page TS / B 3.8-23 1Page B 3.8-24 0Pages TS / B 3.8-25 and TS I B 3.8-26 1Pages B 3.8-27 through B 3.8-30 0Page TS I B 3.8-31 1Pages TS / B 3.8-32 through TS / B 3.8-35 0Page TS I B 3.8-36 1Page TS I B 3.8-37 0Page TS / B 3.8-38 1Pages B 3.8-39 through B 3.8-46 0Page TS / B 3.8-47 3Pages TS / B 3.8-48 through TS / B 3.8-50 0Pages TS / B 3.8-51 and TS / B 3.8-52 3Page TS / B 3.8-53 1Page TS / B 3.8-54 0Page TS / B 3.8-55 1Pages TS / B 3.8-56 through TS I B 3.8-59 2Pages TS / B 3.8-60 through TS / B 3.8-64 3Page TS I B 3.8-65 4Page TS / B3.8-66 5Pages TS / B 3.8-67 and TS I B 3.8-68 4Page TS I B 3.8-69 5Pages TS / B 3.8-70 through TS / B 3.8-83 1Pages TS I B 3.8-83A through TS I B 3.8-830 0Pages B 3.8-84 through B 3.8-85 0Page TS / B 3.8-86 1Page TS / B 3.8-87 2Pages TS / B 3.8-88 and TS I B 3.8-89 1Page TS I B 3.8-90 2Pages TS / B 3.8-91 through TS / B 3.8-93 1Pages B 3.8-94 through B 3.8-99 0.SUSQUEHANNA -UNIT 2 TSIB LOES-9 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-9Revision 125 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 3.9-2 1Page TS I B 3.9-2a IPages TS / B 3.9-3 through TS I B 3.9-5 1Pages TS /8B3.9-6 through TS I B 3.9-8 0Pages B 3.9-9 through B 3.9-18 0Pages TS /8B3.9-19 through TS /8B3.9-21 1Pages B 3.9-22 through B 3.9-30 08 3.10 SPECIAL OPERATIONS BASESPage TS /8B3.10-1 *2___Pages TS / B 3.10-2 through TSL/B 3.10-5 __ 1Pages 8 3.10-6 through 8 3.10-32 0Page TS /8B3.10-33 2Page B 3.10-34 0Page TS /8B3.10-35 1Pages B 3.10-36 and B 3.10-37 0Page TS /8B3.10-38 1Page TS / 8 3.10-39 2SUSQUEHANNA -UNIT 2 TS I B LOES-lO Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-10Revision 125 Rev. 4RCS P/T LimitsB 3.4.10B 3.4 REACTOR COOLANT SYSTEM (RCS)B 3.4.10 RCS Pressure and Temperature (PIT) LimitsBASESBACKGROUND All components of the RCS are designed to withstand effects of cyclic loadsdue to system pressure and temperature changes. These loads areintroduced by startup (heatup) and shutdown (cooldown) operations, powertransients, and reactor trips. This LCO limits the pressure and temperaturechanges during RCS heatup and cooldown, within the design assumptionsand the stress limits for cyclic operation.~This Specification contains P/T" limit curves for heatup, cooldown, andinservice leakage and hydrostatic testing, and limits for the maximum rate of...... ....-change-of-reactor coolant-temperature. The heatup curve provides limits for* both heatup and criticality.Each P/T limit curve defines an acceptable region for normal operation. Theusual use of the curves is operational guidance during heatup or cooldownmaneuvering, when pressure and temperature indications are monitored andcompared to the applicable curve to determine that operation is within theallowable region.The LCO establishes operating limits that provide a margin to brittle failure ofthe reactor vessel and piping of the reactor coolant pressure boundary(RCPB). The vessel is the component most subject to brittle failure.Therefore, the LCO limits apply mainly to the vessel.10 CFR 50, Appendix G (Ref. 1), requires the establishment of P/T limits formaterial fracture toughness requirements of the RCPB materials.Reference I requires an adequate margin to brittle failure during normaloperation, anticipated operational occurrences, and system hydrostatic tests.It mandates the use of the ASME Code, Section Xl, Appendix G (Ref. 2).The actual shift in the RTNDT of the vessel material will be establishedperiodically by removing and evaluating the irradiated reactor vessel materialspecimens, in accordance with ASTM E 185 (Ref. 3) and Appendix H of10 CFR 50 (Ref. 4). The operating P/l" limit curves will be adjusted,as necessary, based on the evaluation findings and the recommendations ofRG 1.99, "Radiation Embrittlement of Reactor Vessel Materials (Ref. 5).The calculations to determine neutron fluence will be developed using theBWRVIP RAMA code methodology, which is NRC approved and meets theintent of RG 1.190, "Calculational and Dosimetry Methods for DeterminingPressure Vessel Neutron Fluence" (Ref. 11). See FSAR Section 4.1.4.5 fordetermining fluence (Ref. 12).(continued)SUSQUEHANNA -UNIT 2 T .-9RvsoTS / B 3.4-49Revision 3 Rev. 4RCS P/T" LimitsB 3.4.10BASESBACKGROUND(continued)The P/T limit curves are composite curves established by superimposinglimits derived from stress analyses of those portions of the reactor vesseland head that are the most restrictive. At any specific pressure,temperature, and temperature rate of change, one location within the reactorvessel will dictate the most restrictive limit. Across the span of the P/T limitcurves, different locations are more restrictive, and, thus, the curves arecomposites of the most restrictive regions.The heatup curve used to develop the P/T limit curve composite representsa different set of restrictions than the cooldown curve used to develop theP/T limit curve composite because the directions of the thermal gradientsthrough the vessel wall are reversed. The thermal gradient reversal altersthe location of the tensile stress between the outer and inner walls.The criti~lity limits incluide R~fer-n-ce- 1 requi~rnentth~t-th-ey be at le~t40°F above the heatup curve or the cooldown curve and not lower than theminimum permissible temperature for the inservice leakage and hydrostatictesting.The consequence of violating the LCO limits is that the RCS has beenoperated under conditions that can result in brittle failure of the RCPB,possibly leading to a nonisolable leak or loss of coolant accident. In theevent these limits are exceeded, an evaluation must be performed todetermine the effect on the structural integrity of the RCPB components.ASME Code, Section Xl, Appendix E (Ref. 6), provides a recommendedmethodology for evaluating an operating event that causes an excursionoutside the limits.APPLICABLESAFETYANALYSESThe P/T limits are not derived from Design Basis Accident (DBA) analyses.They are prescribed during normal operation to avoid encountering pressure,temperature, and temperature rate of change conditions that might causeundetected flaws to propagate and cause nonductile failure of the RCPB, acondition that is unanalyzed. Reference 7 establishes the methodology fordetermining the P/T limits. Since the P/T limits are not derived from anyDBA, there are no acceptance limits related to the P/T limits. Rather, the P/Tlimits are acceptance limits themselves since they preclude operation in anunanalyzed condition.RCS P/T limits satisfy Criterion 2 of the NRC Policy Statement (Ref. 8).The Effective Full Power Years (EFPY) shown on the curves are approxi-mations of the ratio of the energy that has been and is anticipated to begenerated in a year to the energy that could have been generated if theunit ran at original thermal power rating of 3293 MWT for the entire year.These values are based on fluence limits that are not to be exceeded.(continued)Revision 2SUSQUEHANNA -UNIT 2TSIB345TS / B 3.4-50 Rev. 4RCS PIT LimitsB 3.4.10BASES. (continued)LCO The elements of this LCO are:a. RCS pressure and temperature are to the right of the applicable curvesspecified in Figures 3.4.10-1 through 3.4.10-3 and within the applicableheat-up or cool down rate specified in SR 3.4.10.1 during RCS heatup,cooldown, and inservice leak and hydrostatic testing;b. The temperature difference between the reactor vessel bottom headcoolant and the reactor pressure vessel (RPV) coolant is < 145°F duringrecirculation pump startup, and during increases in THERMAL POWERor loop flow while operating at low THERMAL POWER or loop flow;c. -The-temperature difference between-the reactor-coolant-in-the respective---.recirculation loop and in the reactor vessel is _< 50°F during recirculationpump startup, and during increases in THERMAL POWER or loop flowwhile operating at low THERMAL POWER or loop flow;d. RCS pressure and temperature are to the right of the criticality limitsspecified in Figure 3.4.10-3 prior to achieving criticality; ande. The reactor vessel flange and the head flange temperatures are >_ 700Fwhen tensioning the reactor vessel head bolting studs.These limits define allowable operating regions and permit a large number ofoperating cycles while also providing a wide margin to nonductile failure.The PIT limit composite curves are calculated using the worst case ofmaterial properties, stresses, and temperature change rates anticipatedunder all heatup and cooldown conditions. The design calculations accountfor the reactor coolant fluid temperature impact on the inner wall of thevessel and the temperature gradients through the vessel wall. Becausethese fluid temperatures drive the vessel wall temperature gradient,monitoring reactor coolant temperature provides a conservative method ofensuring the PIT limits are not exceeded. Proper monitoring of vesseltemperatures to assure compliance with brittle fracture temperature limitsand vessel thermal stress limits during normal heatup and cooldown, andduring inservice leakage and hydrostatic testing, is established in PPLCalculation EC 062-0573 (Ref. 9). For PIT curves A, B, and C, the bottomhead drain line coolant temperature should be monitored and maintained tothe right of the most limiting curve.(continued)SUSQUEHANNA -UNIT 2 Sl34-1Rvso2TS / B 3.4-51Revision 2 Rev. 4RCS P/T LimitsB 3.4.10BASESLCO(continued)Curve A must be used for any ASME Section III Design Hydrostatic Testsperformed at unsaturated reactor conditions. Curve A may also be usedfor ASME Section Xl inservice leakage and hydrostatic testing whenheatup and cooldown rates can be limited to 20°F in a one-hour period.Curve A is based on pressure stresses only. Thermal stresses areassumed to be insignificant. Therefore, heatup and cooldown rates arelimited to 20°F in a one-hour period when using Curve A to ensure minimalthermal stresses. The recirculation loop suction line temperatures shouldbe monitored to determine the temperature change rate.Curves B and C are to be used for non-nuclear and nuclear heatup andcooldown, respectively. In addition, Curve B may be used for ASME SectionXl inservice leakage and hydrostatic testing, but not for ASME Section IIIDesignHydrostatic Tests Performed at u~nsa~turated_ re~actor con~diti~ons._.Heatup and cooldown rates are limited to 100°F in a one-hour period whenusing Curves B and C. This limits the thermal gradient through the vesselwall, which is used to calculate the thermal stresses in the vessel wall. Thus,the LCO for the rate of coolant temperature change limits the thermalstresses and ensures the validity of the P/T curves. The vessel belt-linefracture analysis assumes a 100°F/hr coolant heatup or cooldown rate in thebeltline area. The 100°F limit in a one-hour period applies to the coolant inthe beltline region, and takes into account the thermal inertia of the vesselwall. Steam dome saturation temperature (TSAT), as derived from steamdome pressure, should be monitored to determine the beltline temperaturechange rate at temperatures above 212°F. At temperatures below 212°F,the recirculation loop suction line temperatures should be monitored.During heatups and cooldowns, the reactor vessel could experience avacuum (negative pressure) at low temperatures (unsaturated conditions)and low rates of temperature change. Under a vacuum, the vessel wallwould experience a uniform compressive loading, which would counteractthe tensile stress due to any thermal gradients through the vessel wall. Toensure the margin to brittle fracture is no less than at any other pressure,Curves A, B, and C require a minimum vessel metal temperature of 70°Fwhen the reactor vessel is at a negative pressure.(continued)Revision 3SUSQUEHANNA -UNIT 2 TI345TS / B 3.4-52 Rev. 4RCS P/T LimitsB 3.4.10BASESLCD(continued)Violation of the limits places the reactor vessel outside of the bounds of thestress analyses and can increase stresses in other RCS components. Theconsequences depend on several factors, as follows:a. The severity of the departure from the allowable operating pressuretemperature regime or the severity of the rate of change of temperature;b. The length of time the limits were violated (longer violations allow thetemperature gradient in the thick vessel walls to become morepronounced); andc. The existences, sizes, and orientations of flaws in the vessel material.APPLICABILITYThe potential for violating a P/T limit exists at all times. For example, P/Tlimit violations could result from ambient temperature conditions that result inthe reactor vessel metal temperature being less than the minimum allowedtemperature for boltup. Therefore, this LCO is applicable even when fuel isnot loaded in the core.ACTIONSA.1 and A.2Operation outside the P/l" limits while in MODES 1, 2, and 3 must becorrected so that the RCPB is returned to a condition that has been verifiedby stress analyses.The 30 minute Completion Time reflects the urgency of restoring theparameters to within the analyzed range. Most violations will not be severe,and the activity can be accomplished in this time in a controlled manner.Besides restoring operation within limits, an evaluation is required todetermine if RCS operation can continue. The evaluation must verify theRCPB integrity remains acceptable and must be completed if continuedoperation is desired. Several methods may be used, including comparisonwith pre-analyzed transients in the stress analyses, new analyses, orinspection of the components.(continued)SUSQUEHANNA -UNIT 2TS/B345aRvso0TS / B 3.4-52aRevision 0 Rev. 4RCS PIT" LimitsB 3.4.10BASESACTIONSA.1 and A.2 (continued).ASME Code, Section Xl, Appendix E (Ref. 6), may be used to support theevaluation. However, its use is restricted to evaluation of the vessel beitline.The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is reasonable to accomplish the evaluation ofa mild violation. More severe violations may require special, event specificstress analyses or inspections. A favorable evaluation must be completed ifcontinued operation is desired.Condition A is modified by a Note requiring Required Action A.2 be* completed whenever the Condition is entered. The Note emphasizes the-- -___ --need to-perform the evaluation of-the-effects of the excursion-outside the -allowable limits. Restoration alone per Required Action A. 1 is insufficientbecause higher than analyzed stresses may have occurred and may haveaffected the RCPB integrity.B. I and B.2If a Required Action and associated Completion Time of Condition A are notmet, the plant must be placed in a lower MODE because either the RCSremained in an unacceptable PIT region for an extended period of increasedstress, or a sufficiently severe event caused entry into an unacceptableregion. Either possibility indicates a need for more careful examination ofthe event, best accomplished with the RCS at reduced pressure andtemperature. With the reduced pressure and temperature conditions, thepossibility of propagation of undetected flaws is decreased.(continued)SUSQUEHANNA -UNIT 2 T .-3RvsoTS / B 3.4-53Revision 2 Rev. 4RCS P/T LimitsB 3.4.10BASESACTIONS B.1 and B.2 (continued)Pressure and temperature are reduced by placing the plant in at leastMODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowedCompletion Times are reasonable, based on operating experience, to reachthe required plant conditions from full power conditions in an orderly mannerand without challenging plant systems.C.1 and C.2Operation outside the PIT limits in other than MODES 1, 2, and 3 (includingdefueled conditions) must be corrected so that the RCPB is returned to acondition that has been verified by stress analyses. The Required Actionmust be initiated without delay and continued until the limits are restored.Besides restoring the PIT limit parameters to within limits, an evaluation isrequired to determine if RCS operation is allowed. This evaluation mustverify that the RCPB integrity is acceptable and must be completed beforeapproaching criticality or heating up to > 200°F. Several methods may beused, including comparison with pre-analyzed transients, new analyses, orinspection of the components. ASME Code, Section Xl, Appendix E (Ref. 6),may be used to support the evaluation; however, its use is restricted toevaluation of the beltline.SURVEILLANCE SR 3.4.10.1REQUIREMENTSVerification that operation is within limits (i.e., to the right of the applicablecurves in Figures 3.4.10-1 through 3.4.10-3) is required every 30 minuteswhen RCS pressure and temperature conditions are undergoing plannedchanges. This Frequency is considered reasonable in view of the controlroom indication available to monitor RCS status. Also, since temperaturerate of change limits are specified in hourly increments, 30 minutes permits areasonable time for assessment and correction of minor deviations.Surveillance for heatup, cooldown, or inservice leakage and hydrostatictesting may be discontinued when the criteria given in the relevant plantprocedure for ending the activity are satisfied.This SR has been modified with a Note that requires this Surveillance to beperformed only during system heatup and cooldown operations andinservice leakage and hydrostatic testing.Notes to the acceptance criteria for heatup and cooldown rates ensure thatmore restrictive limits are applicable when the PIT" limits associated withhydrostatic and inservice testing are being applied.(continued)SUSQUEHANNA -UNIT 2TS34-4Rvso2TS / B 3.4-54Revision 2 Rev. 4RCS P/T" LimitsB 3.4.10BASESSURVEILLANCE SR 3.4.10.2REQUIREMENTS(continued) A separate limit is used when the reactor is approaching criticality.Consequently, the RCS pressure and temperature must be verified withinthe appropriate limits (i.e., to the right of the criticality curve in Figure3.4.10-3) before withdrawing control rods that will make the reactor critical.Performing the Surveillance within 15 minutes before control rod withdrawalfor the purpose of achieving criticality provides adequate assurance that thelimits will not be exceeded between the time of the Surveillance and the timeof reactor criticality. Although no Surveillance Frequency is specified, therequirements of SR 3.4.10.2 must be met at all times when the reactor iscritical.SR 3.4.10.3 and SR 3.4.10.4Differential temperatures within the applicable limits ensure that thermalstresses resulting from the startup of an idle recirculation pump will notexceed design allowances. In addition, compliance with these limits ensuresthat the assumptions of the analysis for the startup of an idle recirculationloop (Ref. 10) are satisfied.Performing the Surveillance within 15 minutes before starting the idlerecirculation pump provides adequate assurance that the limits will not beexceeded between the time of the Surveillance and the time of the idle pumpstart.An acceptable means of demonstrating compliance with the temperaturedifferential requirement in SR 3.4.10.4 is to compare the temperatures of theoperating recirculation loop and the idle loop. If both loops are idle, comparethe temperature difference between the reactor coolant within the idle loop tobe started and coolant in the reactor vessel.SR 3.4.10.3 has been modified by a Note that requires the Surveillance to beperformed only in MODES 1, 2, 3, and 4. In MODE 5, the overall stress onlimiting components is lower. Therefore, AT limits are not required. TheNote also states the SR is only required to be met during a recirculationpump start-up, because this is when the stresses occur.(continued)SUSQUEHANNA -UNIT 2 T .-5RvsoTS / B 3.4-55Revision 2 Rev. 4RCS P/I- LimitsB 3.4.10BASESSURVEILLANCE SR 3.4.10.5 and SR 3.4.10.6REQUIREMENTS(continued) Differential temperatures within the applicable limits ensure that thermalstresses resulting from increases in THERMAL POWER or recirculation loopflow during single recirculation loop operation will not exceed designallowances. Performing the Surveillance within 15 minutes before beginningsuch an increase in power or flow rate provides adequate assurance that thelimits will not be exceeded between the time of the Surveillance and the timeof the change in operation.An acceptable means of demonstrating compliance with the temperaturedifferential requirement in SR 3.4.10.6 is to compare the temperatures of theoperating recirculation loop and the idle loop.--Plant startup test data t~s-determined that the bottom head is notsubject to temperature stratification at power levels > 27% of RTP and withsingle loop flow rate > 21,320 gpm (50% of rated loop flow). Therefore,SR 3.4.10.5 and SR 3.4.10.6 have been modified by a Note that requires theSurveillance to be met only under these conditions. The Note forSR 3.4.10.6 further limits the requirement for this Surveillance to excludecomparison of the idle loop temperature if the idle loop is isolated from theRPV since the water in the loop can not be introduced into the remainder ofthe Reactor Coolant System.SR 3.4.10.7, SR 3.4.10.8. and SR 3.4.10.9Limits on the reactor vessel flange and head flange temperatures aregenerally bounded by the other P/T limits during system heatup andcooldown. However, operations approaching MODE 4 from MODE 5 and inMODE 4 with RCS temperature less than or equal to certain specified valuesrequire assurance that these temperatures meet the LCO limits.The flange temperatures must be verified to be above the limits 30 minutesbefore and while tensioning the vessel head bolting studs to ensure thatonce the head is tensioned the limits are satisfied. When in MODE 4 withRCS temperature _< 80°F, 30 minute checks of the flange temperatures arerequired because of the reduced margin to the limits. When in MODE 4 withRCS temperature __ 1 00°F, monitoring of the flange temperature is requiredevery 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to ensure the temperature is within the specified limits.The 30 minute Frequency reflects theurgency of maintaining thetemperatures within limits, and also limits the time that the temperature limitscould be exceeded. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is reasonable based on the rateof temperature change possible at these temperatures.(continued)SUSQUEHANNA -UNIT 2 T .-6RvsoTS / B 3.4-56Revision 2 Rev. 4RCS P/T LimitsB 3.4.10BASES (continuedREFERENCES)1. 10 CFR 50, Appendix G.2. ASME, Boiler and Pressure Vessel Code,Section XI, Appendix G.3. ASTM E 185-734. 10 CFR 50, Appendix H.5. Regulatory Guide 1.99, Revision 2, May 1988.6. ASME, Boiler and Pressure Vessel Code, Section Xl, Appendix E.7. Licensed Topical Reports:a. Structural Integrity Associates Report No. SIR-05-044, Revision 1-A,"Pressure-Temperature Limits Report Methodology for Boiling WaterReactors," June 2013.b. Structural Integrity Associates Report No. 0900876.401, Revision0-A, "Linear Elastic Fracture Mechanics Evaluation of GE BWR WaterLevel Instrument Nozzles for Pressure-Temperature CurveEvaluations," May 2013.8. Final Policy Statement on Technical Specifications Improvements,July 22, 1993 (58 FR 39132).9. PPL Calculation EC-062-0573, "Study to Support the Bases Section ofTechnical Specification 3.4.10."10. FSAR, Section 15.4.4.11. Regulatory Guide 1.190, March 2001.12 FSAR, Section 4.1.4.5.SUSQUEHANNA -UNIT 2 T .-7RvsoTS / B 3.4-57Revision 3 B 3.5B 3.5.2BASESRev. 2ECCS-ShutdownB 3.5.2EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR COREISOLATION COOLING (RCIC) SYSTEMECCS-ShutdownBACKGROUNDA description of the Core Spray (CS) System and the Low PressureCoolant Injection (LPCI) mode of the Residual Heat Removal (RHR)System is provided in the Bases for LCO 3.5.1, "ECCS-Operating."APPLICABLESAFETYA NA LYS ESThe ECCS performance is evaluated for the entire spectrum of breaksizes for-a postulated loss of coolant accident- (LOCA). -The long termcooling analysis following a design basis LOCA (Reference 1)demonstrates that only one low pressure ECCS injection /spraysubsystem is required, post LOCA, to maintain adequate reactor vesselwater level in the event of an inadvertent vessel draindown. It isreasonable to assume, based on engineering judgement, that while inMODES 4 and 5, one low pressure ECCS injection/spray subsystem canmaintain adequate reactor vessel water level. To provide redundancy, aminimum of two low pressure ECCS injection/spray subsystems arerequired to be OPERABLE in MODES 4 and 5.The low pressure ECCS subsystems satisfy Criterion 3 of the NRC PolicyStatement (Ref. 2).LCOTwo low pressure ECCS injection/spray subsystems are required to beOPERABLE. The low pressure ECCS injection/spray subsystems consistof two CS subsystems and two LPCI subsystems. Each CS subsystemconsists of two motor driven pumps, piping, and valves to transfer waterfrom the suppression pool or condensate storage tank (CST) to thereactor pressure vessel (RPV). Each LPCI subsystem consists of one ofthe two motor driven pumps, piping, and valves to transfer water from thesuppression pool to the RPV. Only a single LPCI pump is required persubsystem because of the larger injection capacity in relation to a CSsubsystem. In MODES 4 and 5, the RHR System cross tie valves are notrequired to be closed.(continued)SUSQUEHANNA -UNIT 2 TSB5-9RvsoITS / B 3.5-19Revision 1 Rev. 2ECCS-ShutdownB 3.5.2BASESLCO(continued)LPCI subsystems may be aligned for decay heat removal and consideredOPERABLE for the ECCS function, if they can be manually realigned(remote or local) to the LPCI mode and are not otherwise inoperable.Because of low pressure and low temperature conditions in MODES 4 and5, sufficient time will be available to manually align and initiate LPCIsubsystem operation to provide core cooling prior to postulated fueluncovery.APPLICABILITYOPERABILITY of the low pressure ECCS injection/spray subsystems isrequired in MODES 4 and 5 to ensure adequate coolant inventory andsufficient heat removal capability for the irradiated fuel in .the core in caseof an inadvertent draindown of the vessel. Requirements for ECCSOPERABILITY during MODES 1, 2, and 3 are discussed in theApplicability section of the Bases for LCO 3.5.1. ECCS subsystems arenot required to be OPERABLE during MODE 5 with the spent fuel storagepool gates removed and the water level maintained at >_22 ft. above theRPV flange. This provides sufficient coolant inventory to allow operatoraction to terminate the inventory loss prior to fuel uncovery in case of aninadvertent draindown.The Automatic Depressurization System is not required to be OPERABLEto be OPERABLE during MODES 4 and 5 because the RPV pressure is 150 psig, and the CS System and the LPCI subsystems can providecore cooling without any depressurization of the primary system.The High Pressure Coolant Injection System is not required to beOPERABLE during MODES 4 and 5 since the low pressure ECCSinjection/spray subsystems can provide sufficient flow to the vessel.ACTIONSA.1 and B.1If any one required low pressure ECCS injection/spray subsystemis inoperable, the inoperable subsystem must be restored toOPERABLE status in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. In this Condition, the remainingOPERABLE subsystem can provide sufficient vessel floodingcapability to recover from an inadvertent(continued)SUSQUEHANNA -UNIT 2T/B520RvsoITS / B 3.5-20Revision 1 Rev. 2ECCS-ShutdownB 3.5.2BASESACTIONS A.1 and B.1 (continued)Vessel draindown. However, overall system reliability is reduced becausea single failure in the remaining OPERABLE subsystem concurrent with avessel draindown could result in the ECCS not being able to perform itsintended function. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time for restoring the requiredlow pressure ECCS injection/spray subsystem to OPERABLE status isbased on engineering judgement that considered the remaining availablesubsystem and the low probability of a vessel draindown event.With the inoperable subsystem not restored to OPERABLE status in therequired Completion Time, action must be immediately initiated tosuspend operations with a potential for draining the reactor vessel(OPDRVs) to minimize the probability of a vessel draindown and thesubsequent potential for fission product release. Actions must continueuntil OPDRVs are suspended.C.1, C.2, D.1, D.2, and D.3With both of the required ECCS injectionlspray subsystems inoperable, allcoolant inventory makeup capability may be unavailable. Therefore,actions must immediately be initiated to suspend OPDRVs to minimize theprobability of a vessel draindown and the subsequent potential for fissionproduct release. Actions must continue until OPDRVs are suspended.One ECCS injection/spray subsystem must also be restored toOPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.If at least one low pressure ECCS injection/spray subsystem is notrestored to OPERABLE status within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time,additional actions are required to minimize any potential fission productrelease to the environment. This includes ensuring secondarycontainment is OPERABLE; one standby gas treatment subsystem isOPERABLE; and secondary containment isolation capability (i.e., oneisolation valve and associated instrumentation are OPERABLE or otheracceptable administrative controls to assure isolation capability) in eachsecondary containment penetration flow path not isolated and required tobe isolated to mitigate radioactivity releases. OPERABILITY may beverified by an administrative check, or by examining logs or otherinformation, to determine whether the components are out of(continued)SUSQUEHANNA -UNIT 2TSB.21RvsoITS / B 3.5-21Revision 1 Rev. 2ECCS-ShutdownB 3.5.2BASESACTIONS C.1, C.2. D.1, D.2, and D.3 (continued)}service for maintenance or other reasons. It is not necessary to performthe Surveillances needed to demonstrate the OPERABILITY of thecomponents. If, however, any required component is inoperable, then itmust be restored to OPERABLE status. In this case, the Surveillance mayneed to be performed to restore the component to OPERABLE status.Actions must continue until all required components are OPERABLE.The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time to restore at least one low pressure ECCSinjection/spray subsystem to OPERABLE status ensures that promptaction will be taken to provide the required cooling capacity or to initiateactions to place the plant in a condition that minimizes any potentialfission product release to the environment.SURVEILLANCEREQUIRMENTSSR 3.5.2.1 and SR 3.5.2.2The minimum water level of 20 ft. 0 inches required for the suppressionpool is periodically verified to ensure that the suppression pool will provideadequate net positive suction head (NPSH) for the CS System and LPCIsubsystem pumps, recirculation volume, and vortex prevention. With thesuppression pool water level less than the required limit, all ECCSinjection/spray subsystems are inoperable unless they are aligned to anOPERABLE CST.When suppression pool level is < 20 ft. 0 inches, the CS System isconsidered OPEABLE only if it can take suction from the CST, and theCST water level is sufficient to provide the required NPSH for the CSpump. Therefore, a verification that either the suppression pool waterlevel is 20 ft. 0 inches or that CS is aligned to take suction from theCST and the CST contains >135,000 gallons of water, equivalent to49% of capacity, ensures that the CS System can supply at least135,000 gallons of makeup water to the RPV. However, as noted, onlyone required CS subsystem may take credit for the CST option duringOPDRVs. During OPDRVs, the volume in the CST may not provideadequate makeup if the RPV were completely drained. Therefore, onlyone CS subsystem is allowed to use the CST. This ensures(continued)SUSQUEHANNA -UNIT 2 /B5-2Rvso2TS / B 3.5-22Revision 2 Rev. 2ECCS-ShutdownB 3.5.2BASESSURVEILLANCEREQUIRMENTSSR 3.5.2.1 and SR 3.5.2.2 (continued)the other required ECOS subsystem has adequate makeup volume.The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency of these SRs was developed consideringoperating experience related to suppression pool water level and CSTwater level variations and instrument drift during the applicable MODES.Furthermore, the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is considered adequate in view ofother indications available in the control room, including alarms, to alertthe operator to an abnormal suppression pool or CST water levelcondition.SR 3.5.2.3, SR 3.5.2.5, SR 3.5.2.6, and SR 3.5.2.7The Bases provided for SR 3.5.1.1, SR 3.5.1.7, SR 3.5.1.10, andSR 3.5.1.13 are applicable to SR 3.5.2.3, SR 3.5.2.5, SR 3.5.2.6 andSR 3.5.2.7, respectively.SR 3.5.2.4Verifying the correct alignment for manual, power operated, and automaticvalves in the ECCS flow paths provides assurance that the proper flowpaths will exist for ECCS operation. This SR does not apply to valves thatare locked, sealed, or otherwise secured in position, since these valveswere verified to be in the correct position prior to locking, sealing, orsecuring. A valve that receives an initiation signal is allowed to be in anonaccident position provided the valve will automatically reposition in theproper stroke time. This SR does not require any testing or valvemanipulation; rather, it involves verification that those valves capable ofpotentially being mispositioned are in the correct position. This SR doesnot apply to valves that cannot be inadvertently misaligned, such as checkvalves. The 31 day Frequency is appropriate because the valves areoperated under procedural control and the probability of their beingmispositioned during this time period is low.In MODES 4 and 5, the RHR System may operate in the shutdowncooling mode to remove decay heat and sensible heat from thereactor. Therefore, RHR valves that are required for LPCI(continued)SUSQUEHANNA -UNIT 2TSB35-3RvsoITS / B 3.5-23Revision 1 Rev. 2ECCS-ShutdownB 3.5.2BAS ESSURVEILLANCE SR 3.5.2.4 (continued)REQUIREMENTSsubsystem operation may be aligned for decay heat removal. Therefore,this SR is modified by a Note that allows LPCI subsystems of the RHRSystem to be considered OPERABLE for the ECCS function if all therequired valves in the LPCI flow path can be manually realigned (remoteor local) to allow injection into the RPV, and the systems are not otherwiseinoperable. This will ensure adequate core cooling if an inadvertent RPVdraindown should occur.*REFERNCES 1. FSAR, Section 6.3.2.2. Final Policy Statement on Technical Specifications Improvements,July 22, 1993 (58 FR 39132).SUSQUEHANNA -UNIT2 B2.-4RvsoB 3.5-24Revision 0 Rev. 12Secondary ContainmentB 3.6.4.1B 3.6 CONTAINMENT SYSTEMSB 3.6.4.1 Secondary ContainmentBASESBACKGROUNDThe secondary containment structure completely encloses the primarycontainment structure such that a dual-containment design is utilized to limitthe spread of radioactivity to the environment to within limits. The function ofthe secondary containment is to contain, dilute, and hold up fission productsthat may leak from primary containment into secondary containmentfollowing a Design Basis Accident (DBA). In conjunction with operation ofthe Standby Gas Treatment (SGT) System and closure of certain valveswhose lines penetrate the secondary containment, the secondary-containment is designed to reduce the activity level of the fission productsprior to release to the environment and to isolate and contain fission productsthat are released during certain operations that take place inside primarycontainment, when primary containment is not required to be OPERABLE, orthat take place outside primary containment (Ref. 1).The secondary containment is a structure that completely encloses theprimary containment and reactor coolant pressure boundary components.This structure forms a control volume that serves to hold up and dilute thefission products. It is possible for the pressure in the control volume to riserelative to the environmental pressure (e.g., due to pump and motor heatload additions).The secondary containment boundary consists of the reactor buildingstructure and associated removable walls and panels, hatches, doors,dampers, sealed penetrations and valves. Certain plant piping systems(e.g., Service Water, RHR Service Water, Emergency Service Water,Feedwater, etc.) penetrate the secondary containment boundary. The intactpiping within secondary containment provides a passive barrier whichmaintains secondary containment requirements. Breaches of these pipingsystems within secondary containment will be controlled to maintainsecondary containment requirements. The secondary containment is dividedinto Zone I, Zone II and Zone IlI, each of which must be OPERABLEdepending on plant status and the alignment of the secondary containmentboundary. Specifically, the Unit I secondary containment boundary can bemodified to exclude Zone 11. Similarly, the Unit 2 secondary containmentboundary can be modified to exclude Zone I. Secondary containment mayconsist of only Zone Ill when in MODE 4 or 5 during CORE ALTERATIONS,or during handling of irradiated fuel within the Zone ill secondarycontainment boundary.(continued)SUSQUEHANNA -UNIT 2 T .-3RvsoTS / B 3.6-83Revision 4 Rev. 12Secondary ContainmentB 3.6.4.1BASESBACKGROUND(continued)To prevent ground level exfiltration while allowing the secondary containmentto be designed as a conventional structure, the secondary containmentrequires support systems to maintain the control volume pressure at lessthan the external pressure. Requirements for the safety related systems arespecified separately in LCO 3.6.4.2, "Secondary Containment IsolationValves (SCIVs)," and LCO 3.6.4.3, "Standby Gas Treatment (SGT) System."When one or more zones are excluded from secondary containment, thespecific requirements for support systems will also change (e.g., requiredsecondary containment isolation valves).APPLICABLESAFETYANALYSESThere are two principal accidents for which credit is taken for secondarycontainment OPERABILITY. These are a loss of coolant-accident (LOCA)(Ref. 2) and a fuel handling accident inside secondary containment (Ref. 3).The secondary containment performs no active function in response to eitherof these limiting events; however, its leak tightness is required to ensure thatthe release of radioactive materials from the primary containment is restrictedto those leakage paths and associated leakage rates assumed in theaccident analysis and that fission products entrapped within the secondarycontainment structure will be treated by the SGT System prior to discharge tothe environment.Secondary containment satisfies Criterion 3 of the NRC Policy Statement(Ref. 4).LCOAn OPERABLE secondary containment provides a control volume into whichfission products that bypass or leak from primary containment, or arereleased from the reactor coolant pressure boundary components located insecondary containment, can be diluted and processed prior to release to theenvironment. For the secondary containment to be considered OPERABLE,it must have adequate leak tightness to ensure that the required vacuum canbe established and maintained. The leak tightness of secondarycontainment must also ensure that the release of radioactive materials to theenvironment is restricted to those leakage paths and associated leakagerates assumed in the accident analysis. For example, secondarycontainment bypass leakage must be restricted to the leakage rate requiredby LCO 3.6.1.3. The secondary containment boundary required to beOPERABLE is dependent on the operating status of both units, as well asthe configuration of walls, doors, hatches, SCIVs, and available flow paths tothe SGT System.(continued)SUSQUEHANNA -UNIT 2 T .-4RvsoTS / B 3.6-84Revision 2

" Rev. 12Secondary ContainmentB 3.6.4.1BASES (continued)APPLICABILITY In MODES .1, 2, and 3, a LOCA could lead to a fission product release toprimary containment that leaks to secondary containment. Therefore,secondary containment OPERABILITY is required during the same operatingconditions that require primary containment OPERABILITY.In MODES 4 and 5, the probability and consequences of the LOCA arereduced due to the pressure and temperature limitations in these MODES.Therefore, maintaining secondary containment OPERABLE is not required inMODE 4 or 5 to ensure a control volume, except for other situations forwhich significant releases of radioactive material can be postulated, such asduring operations with a potential for draining the reactor vessel (OP DRVs),during CORE ALTERATIONS, or during movement of irradiated fuelassemblies in the secondary containment.ACTIONS A. 1If secondary containment is inoperable, it must be restored to OPERABLEstatus within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time provides a period of timeto correct the problem that is commensurate with the importance ofmaintaining secondary containment during MODES 1, 2, and 3. This timeperiod also ensures that the probability of an accident (requiring secondarycontainment OPERABILITY) occurring during periods where secondarycontainment is inoperable is minimal.A temporary (one-time) Completion Time is connected to the CompletionTime Requirements above (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) with an "OR" connector. TheTemporary Completion Time is 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and applies to the replacement ofthe Reactor Building Recirculating Fan Damper Motors. The TemporaryCompletion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> may only be used once, and expires onDecember 31, 2005.B.1 and B.2If secondary containment cannot be restored to OPERABLE status within therequired Completion Time, the plant must be brought to a MODE in whichthe LCO does not apply. To achieve this status, the plant must be brought toat least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Theallowed Completion Times are reasonable, based on operating experience,to reach the required plant conditions from full power conditions in an orderlymanner and without challenging plant systems.(continued)SUSQUEHANNA -UNIT 2 T .-5RvsoTS / B 3.6-85Revision 4 Rev. 12Secondary ContainmentB 3.6.4.1BASESACTIONS C.1, C.2, and C.3(continued)Movement of irradiated fuel assemblies in the secondary containment,CORE ALTERATIONS, and OPDRVs can be postulated to cause fissionproduct release to the secondary containment. In such cases, the secondarycontainment is the only barrier to release of fission products to theenvironment. CORE ALTERATIONS and movement of irradiated fuelassemblies must be immediately suspended if the secondary containment isinoperable.Suspension of these activities shall not preclude completing an action thatinvolves moving a component to a safe position. Also, action must beimmediately initiated to suspend OPDRVs to minimize the probability of avessel draindown and subsequent potential for fission product release.Actions must continue until OPDRVs are suspended.Required Action C.1 has been modified by a Note stating that LCO 3.0.3 isnot applicable. If moving irradiated fuel assemblies while in MODE 4 or 5,LCO 3.0.3 would not specify any action. If moving irradiated fuel assemblieswhile in MODE 1, 2, or 3, the fuel movement is independent of reactoroperations. Therefore, in either case, inability to suspend movement ofirradiated fuel assemblies would not be a sufficient reason to require areactor shutdown.SURVEILLANCE SR 3.6.4.1.1REQUIREMENTS-This SR ensures that the secondary containment boundary is sufficiently leaktight to preclude exfiltration under expected wind conditions. Expected windconditions are defined as sustained wind speeds of less than or equal to16 mph at the 60m meteorological tower or less than or equal to 11 mph atthe 10Om meteorological tower if the 60m tower wind speed is not available.Changes in indicated reactor building differential pressure observed duringperiods of short-term wind speed gusts above these sustained speeds do notby themselves impact secondary containment integrity. However, ifsecondary containment integrity is known to be compromised, the LCO mustbe entered regardless of wind speed.(continued)SUSQUEHANNA -UNIT 2 T .-6RvsoTS / B 3.6-86Revision 2 Rev. 12Secondary ContainmentB 3.6.4.1BASESSURVEILLANCE SR 3.6.4.1.1 (continued)REQUIREMENTSThe 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency of this SR was developed based on operatingexperience related to secondary containment vacuum variations during theapplicable MODES and the low probability of a DBA occurring betweensurveillances.Furthermore, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is considered adequate in view of otherindications available in the control room, including alarms, to alert theoperator to an abnormal secondary containment vacuum condition.SR 3.6.4.1.2 and SR 3.6.4.1.3Verifying that secondary containment equipment hatches, removable wallsand one access door in each access opening required to be closed areclosed ensures that the infiltration of outside air of such a magnitude as toprevent maintaining the desired negative pressure does not occur.Verifying that all such openings are closed also provides adequateassurance that exfiltration from the secondary containment will not occur.In this application, the term "sealed" has no connotation of leak tightness.An access opening typically contains one inner and one outer door.Maintaining secondary containment OPERABILITY requires verifying onedoor in each access opening to secondary containment zones is closed.In some cases (e.g., railroad bay), secondary containment access openingsare shared such that a secondary containment barrier may have multipleinner or multiple outer doors. The intent is to maintain the secondarycontainment barrier intact, which is achieved by maintaining the inner orouter portion of the barrier closed at all times. However, all secondarycontainment access doors are normally kept closed, except when theaccess opening is being used for entry and exit or when maintenance isbeing performed on an access opening.When the railroad bay door (No. 101) is closed; all Zone I and Ill hatches,removable walls, dampers, and one door in each access opening connectedto the railroad access bay are closed; or, only Zone I removable walls and/ordoors are open to the railroad access shaft; or, only Zone Ill hatches and/ordampers are open to the railroad access shaft. When the railroad bay door(No. 101) is open; all Zone I and Ill hatches, removable walls, dampers, andone door in each access opening connected to the railroad access bay areclosed. The truck bay hatch is closed and the truck bay door (No. 102) isclosed unless Zone II is isolated from Zones I and Ill.(continued)SUSQUEHANNA -UNIT2 2Sl .-7RvsoTS / B 3.6-87Revision 2 Rev. 12Secondary ContainmentB 3.6.4.1BASESSURVEILLANCEREQUIREMENTSSR 3.6.4.1.2 and SR 3.6.4.1.3 (continued)When an access opening between required secondary containment zones isbeing used for exit and entry, then at least one door (where two doors areprovided) must remain closed. The access openings between secondarycontainment zones which are not provided with two doors areadministratively controlled to maintain secondary containment integrity duringexit and entry. This Surveillance is modified by a Note that allows accessopenings with a single door (i.e., no airlock) within the secondarycontainment boundary (i.e., between required secondary containmentzones) to be opened for entry and exit. Opening of an access door forentry and exit allows sufficient administrative control by individual personnelmaking the entries and exits to-assure the secondary containment functionis not degraded. When one of the zones is not a zone required forsecondary containment OPERABILITY, the Note allowance would notapply.The 31 day Frequency for these SRs has been shown to be adequate,based on operating experience, and is considered adequate in view of theother indications of door and hatch status that are available to the operator.(continued)SUSQUEHANNA -UNIT 2TSIB368aRvso3TS / B 3.6-87aRevision 3 Rev. 12Secondary ContainmentB 3.6.4.1BASESSURVEILLANCEREQUIREMENTS(continued)SR 3.6.4.1.4 and SR 3.6.4.1.5The SGT System exhausts the secondary containment atmosphere to theenvironment through appropriate treatment equipment. To ensure that allfission products are treated, SR 3.6.4.1.4 verifies that the SGT System willrapidly establish and maintain a pressure in the secondary containment thatis less than the pressure external to the secondary containment boundary.This is confirmed by demonstrating that one SGT subsystem will draw downthe secondary containment to _> 0.25 inches of vacuum, water gauge in lessthan or equal to the maximum time allowed. This cannot be accomplished ifthe secondary containment boundary is not intact. SR 3.6.4.1.5demonstrates that one SGT Subsystem can maintain _> 0.25 inches ofvacuum water gauge for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at less than or equal to the maximumflow rate permitted for the secondary containment configuration that isoperable. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> test period allows secondary containment to be inthermal equilibrium at steady state conditions. As noted, both SR 3.6.4.1.4and SR 3.6.4.1.5 acceptance limits are dependent upon the secondarycontainment configuration when testing is being performed. The acceptancecriteria for the SRs based on secondary, containment configuration is definedas follows:SECONDARY MAXIMUM DRAWDOWN TIME(SEC) MAXIMUM FLOW RATE (CFM)CONTAINMENT (SR 3.6.4.1.4 (SR 3.6.4.1.5TEST CONFIGURATION ACCEPTANCE CRITERIA) ACCEPTANCE CRITERIA)Group 1Zones I, II and III (Unit 1 <300 Seconds < 5400 CFMRailroad Bay aligned to (Zones 1, II, and III) (From Zones 1, I1, and IlI)Secondary Containment).Zones II and Ill (Unit 1 <300 Seconds 4000 CFMRailroad Bay aligned to (Zones Il and Ill) (From Zones II and Ill)Zone Ill).Group 2Zones I, II and Ill (Unit 1 < 300 Seconds < 5300 CFMRailroad Bay not aligned to (Zones 1, II, and III) (From Zones 1, 11, and III)Secondary Containment).Zones II and Ill (Unit 1 <300 Seconds < 3900 CFMRailroad Bay not aligned to (Zones II and III) (From Zones II and Ill)SecondaryContainment). ___________________Only one of the above listed configurations needs to be tested to confirm secondary containmentOPERABILITY.(continued)SUSQUEHANNA- UNIT 2TSB36-8Rvso6TS / B 3.6-88Revision 6 Rev. 12Secondary ContainmentB 3.6.4.1BASESSURVEILLANCE SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)REQUIREMENTSA Note also modifies the Frequency for each SR. This Note identifies thateach configuration is to be tested every 60 months. Testing eachconfiguration every 60 months assures that the most limiting configurationis tested every 60 months. The 60 month Frequency is acceptable becauseoperating experience has shown that these components usually pass theSurveillance and all active components are tested more frequently.Therefore, these tests are used to ensure secondary containment boundaryintegrity.The secondary containment testing configurations are discussed in furtherdetail to ensure the appropriate configurations are tested,- Three zonetesting (Zones, I, 11 and Ill aligned to the recirculation plenum) should beperformed with the Railroad Bay aligned to secondary containment andanother test with the Railroad Bay not aligned to secondary containment.Each test should be performed with each division on a STAGGERED TESTBASIS.Two zone testing (Zones II and Ill aligned to the recirculation plenum) shouldbe performed with the Railroad Bay aligned to secondary containment andanother test with the Railroad Bay not aligned to secondary containment.Each test should be performed with each division on a STAGGERED TESTBASIS. The normal operating fans of the non-tested HVAC zone (Zone Ifans 1V202A&B, 1V205A&B and 1V206A&B) should not be in operation.Additionally, a controlled opening of adequate size should be maintained inZone I Secondary Containment during testing to assure that atmosphericconditions are maintained in that zone.The Unit 1 Railroad Bay can be aligned as a No Zone (isolated fromsecondary containment) or as part of secondary containment (Zone I or III).Due to the different leakage pathways that exist in the Railroad Bay, theRailroad Bay should be tested when aligned to secondary containment andalso not aligned to secondary containment. It is preferred to align theRailroad Bay to Zone IIl when testing with the Railroad Bay aligned tosecondary containment since Zone Ill is included in all possible secondarycontainment isolation alignments. Note that when performing the three zonetesting (Zones 1, II and Ill aligned to the recirculation plenum) aligning theRailroad Bay to either Zone I or III is acceptable since either zone is part ofsecondary containment. When performing the Zone II & Ill testing with theRailroad Bay aligned to secondary containment, the Unit 1 Railroad Baymust be aligned to Zone III.(continued)SUSQUEHANNA -UNIT 2 T .-9RvsoTS / B 3.6-89Revision 4 Rev. 12Secondary ContainmentB 3.6.4.1BASESSURVEILLANCEREQU IREM ENTSSR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)Since these SRs are secondary containment tests, they need not beperformed with each SGT subsystem. The SGT subsystems are tested on aSTAGGERED TEST BASIS, however, to ensure that in addition to therequirements of LCO 3.6.4.3, either SGT subsystem will performSR 3.6.4.1.4 and SR 3.6.4.1.5. Operating experience has shown thesecomponents usually pass the Surveillance when performed at the 24 monthFrequency. Therefore, the Frequency was concluded to be acceptable froma reliability standpoint_REFERENCES- 1. FSAR, Section 6.2.3.2. FSAR, Section 15.6.3. FSAR, Section 15.7.4.4. Final Policy Statement on Technical Specifications Improvements,July 22, 1993 (58 FR 39132).(continued)SUSQUEHANNA -UNIT 2TSIB368aRvso0TS / B 3.6-89aRevision 0 Nov. 05, 2015Page1 of 2MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2015-44707USER INFORMATION:GERLACH*ROSEY NEMPL#:028401 CA#: 0363Address: NUCSA2Phone#: 254-3194TRANgMT'1'AT, TO: GERLACH*ROSEY N 11/05/2015LOCATION: 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.TSB2 -TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALREMOVE MANUAL TABLE OF CONTENTSADD MANUAL TABLE OF CONTENTSCATEGORY: DOCUMENTS TYPE: TSB2DATE: 08/05/2015DATE: 11/04/2015AocD Nov. 05, 2015Page2 of 2ID: TEXT 3.4.10ADD: REV: 4REMOVE: REV:3CATEGORY: DOCUMENTSID: TEXT 3.5.2ADD: REV: 2TYPE: TSB2REMOVE: REV:I1CATEGORY:ID: TEXTREMOVE:DOCUMENTS3.6.4.1REV:II1TYPE: TSB2ADD: REV: 12CATEGORY: DOCUMENTSID: TEXT LOESADD: REV: 125TYPE: TSB2REMOVE: REV:124ANY 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. 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SSES MANUALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTable Of ContentsIssue Date: 11/04/2015Pr~ocedure Name RevTEXT LOES 125Title: LIST OF EFFECTIVE SECTIONSIssue Date11/ 04/2 015Change ID Change NumberTEXT T0CTitle: TABLE OF CONTENTS22 07/02/2014TEXT 2.1.1 5Title: SAFETY LIMITS (SLS) REACTORTEXT 2.1.2 1Title: SAFETY LIMITS (SLS) REACTOR01/22 /2 015CORE SLS10/04/2 007COOLANT SYSTEM(RCS) PRESSURE SLTEXT 3.0 3 08/20/2009Title: LIMITING CONDITION FOR OPERATION (LC0) APPLICABILITYTEXT 3.1.1Title: REACTIVITYTEXT 3.1.2Title: REACTIVITYTEXT 3.1.3Title: REACTIVITYTEXT 3.1.4Title: REACTIVITYTEXT 3.1.5Title: REACTIVITYTEXT 3.1.61 03/24/2005CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)0 11/18/2002CONTROL 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 02/24/2014Title: REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROLPagej. of 8 Report Date: 11/05/15Page ! ofReport Date: 11/05/15 SS~ES MANUALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.1.7 3 10/04/2007Title: 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 4 05/06/2009Title: POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)TEXT 3.2.2 3 05/06/2009Title: POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)TEXT 3.2.3 2 05/06/2009Title: POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE LHGRTEXT 3.3.1.1 5 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 3 02/24/2014Title: INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATIONTEXT 3.3.2.2 2 02/22/2012Title: INSTRUMENTATION FEEDWATER -MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATIONTEXT 3.3.3.1 8 02/28/2013Title: INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMNTATIONTEXT 3.3.3.2 1 04/18/2005Title: INSTRUMENTATION REMOTE SHUTDOWN SYSTEMTEXT 3.3.4.1Title: INSTRUMENTATION1 05/06/2009END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATIONWPage2 of *~. Report Date: 11/05/15Page ! ofReport Date: 11/05/15 SSES MANUALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.3.4.2 0 11/18/2002Title: INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP(ATWS-RPT) INSTRUMENTATIONTEXT 3.3.5.1 5 02/24/2014Title: INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATIONTEXT 3.3.5.2 0 11/18/2002Title: 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 3 12/17/2007Title: INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATIONTEXT 3.3.8.2 0 11/18/2002Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORINGTEXT 3.4.1Title: REACTOR COOLANTTEXT 3.4.2Title: REACTOR COOLANT4 07/20/2010SYSTEM (RCS) RECIRCULATION LOOPS OPERATING3 10/23/2013SYSTEM (RCS) JET PUMPSTEXT 3.4.3 3 01/13/2012Title: REACTOR COOLANT SYSTEM (RCS) SAFETY/RELIEF VALVES (S/RVS)TEXT 3.4.4Title: REACTOR COOLANT0 11/18/2002SYSTEM (RCS) RCS OPERATIONAL LEAKAGEPage~ of ~ Report Date: 11/05/15Page ofReport Date: 11/05/15 SSES ANI JAI.Manual Name: TSB2:i"Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.4.5 3 03/10/2010Titles 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---Title :_REACT0RCOOLANTTEXT 3.4.8Title: REACTOR COOLANT-HOT SHUTDOWNTEXT 3.4.9Title: REACTOR COOLANT-COLD SHUTDOWNTEXT 3.4.10Title: REACTOR COOLANTTEXT 3.4.11Title: REACTOR COOLANTTEXT 3.5.12 10/04/2007SYSTEM_(RCS) ACTIVITY __2 03/28/2013SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEMSYSTEM103/28/2013CRCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM4 11/04/2015(RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITSSYSTEM0 11/18/2002SYSTEM (RCS) REACTOR STEAM DOME PRESSURE4 07/16/2014Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTORSYSTEM ECCS -OPERATINGTEXT 3.5.2 2 11/04/2015Title: 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 05/06/2009Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKPage4 of 8 Report Date: 11/05/15Page A ofReport Date: 11/05/15 SSES M~ANUJALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.6.1.3CONTAINMYENTTEXT 3.6.1.4Title : CONTAINMENTTEXT 3.6.1.5__-Title: CONTAINMENTTEXT 3.6.1.6Title:. CONTAINMENTTEXT 3.6.2.1CONTAINMENTTEXT 3.6.2.2Title : CONTAINMENTTEXT 3.6.2.3Title : CONTAINMENTTEXT 3.6.2.4Title : CONTAINMENTTEXT 3.6.3.1Title : CONTAINMENTTEXT 3.6.3.2CONTAINMENTTEXT 3.6.3.3Title : CONTAINMENTTEXT 3.6.4.1Title: CONTAINMENT14 07/02/2014SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)1 05/06/2009SYSTEMS CONTAINMENT PRESSURE1 10/05/2005_SYSTEMSDRYWELLAIR TEMPERATURE -__0 11/18/2002SYSTEMS SUPPRESSION CHAMBER-T0-DRYWELL VACUU/MBREAKERS2 12/17/2007SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE0 11/18/2002SYSTEMS SUPPRESSION POOL WATER LEVEL1 01/16/2006SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING0 11/18/2002SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY2 06/13/2006SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS1 04/18/2005SYSTEMS DRYWELL AIR FLOW SYSTEM1 02/28/2013SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION12 11/04/2015SYSTEMS SECONDARY CONTAINMENTPages of 8 Report Date: 11/05/15Page ofReport Date: 11/05/15 SSES MANUALManual Nanme: TSB2[,Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.6.4.2 9 04/25/2014CONTAINMENT SYSTEMS SECONDARY CONTAINMThENT ISOLATION VALVES (SCIVS)TEXT 3.6,4.3 4 09/21/2006Title: CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEMTEXT 3.7.1-Title :_PLANTSYSTEMS_ULTIMATE HEAT5.. 04/27/2012_RESIDUAL HEAThREMOVAL SERVICEWATER (RHRSWLmSYSTEMANDTHESINK (UBS)TEXT 3.7.2Title: PLANTTEXT 3.7.3Title: PLANTTEXT 3.7.4Title: PLANTTEXT 3.7.5Title: PLANTTEXT 3.7.6Title: PLANTTEXT 3.7.7Title: PLANTTEXT 3.7.8Title: MAINETEXT 3.8.12 05/02/2008SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM1 01/08/2010SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM0 11/18/2002SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM1 10/04/2007SYSTEMS MAIN CONDENSER OFFGAS3 01/25/2011SYSTEMS MAIN TURBINE BYPASS SYSTEM1 10/04/2007SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL0 05/06/2009TURBINE PRESSURE REGULATION SYSTEM9 02/24/2014Title: ELECTRICAL POWER SYSTEMS AC SOURCES -OPERATINGTEXT 3.8.2 0 11/18/2002Title: ELECTRICAL POWER SYSTEMS AC SOURCES -SHUTDOWNPage 6 of 8 Report Date: 11/05/15Pageof 8Report Date: 11/05/15 S.SES MANUITALManul Nme: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.8.3 4 10/23/2013Title: ELECTRICAL POWER SYSTEMS DIESEL FUEL OIL LUBE OILAND STARTING AIRTEXT 3.8.4 3 01/19/2009Title: ELECTRICAL POWER SYSTEMS DC SOURCES -OPERATINGTEXT 3.8.5 1 .12/14/2006__Title: ELECTRICALPOWERSYSTEMS DC S0lURCES_= SHUTDOWN ____-TEXT 3.8.6 1 12/14/2006Title: ELECTRICAL POWER SYSTEMS BATTERY CELL PARAMETERSTEXT 3.8.7 4 10/05/2005Title: ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS -OPERATINGTEXT 3.8.8 0 11/18/2002Title: ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS -SHUTDOWNTEXT 3.9.1Title: REFUELINGTEXT 3.9.2Title: REFUELINGTEXT 3.9.3Title: REFUELINGTEXT 3.9.4Title: REFUELINGTEXT 3.9.5Title: REFUELINGOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONS0 11/18/2002REFUELING EQUIPMENT INTERLOCKS1 09/01/2010REFUEL POSITION ONE-ROD-OUT INTERLOCK0 11/18/2002CONTROL ROD POSITION0 11/18/2002CONTROL ROD POSITION INDICATION0 11/18/2002CONTROL ROD OPERABILITY -REFUELINGTEXT 3.9.61 10/04/2007Title: REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVELPage 7 of S Report Date: 11/05/15Page ! ofReport Date: 11/05/15 S.SES MANUALManual Name: TSB2'>Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.9.7 0 11/18/2002Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RER) -HIGH WATER LEVELTEXT 3.9.8 0 11/18/2002Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RER) -LOW WATER LEVELTEXT 3.10.1-Titl :_SPECIAL_TEXT 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: SPECIAL_OPERATIONS-OPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONS1.. 01/23/2008INSERVICELEAK AND HYDROSTAT~IC TESTINGOPERATION0 11/18/2002REACTOR NODE SWITCH INTERLOCK TESTING0 11/18/2002SINGLE CONTROL ROD WITHDRAWAL -HOT SHUTDOWN0 11/18/2002SINGLE CONTROL ROD WITHDRAWAL -COLD SHUTDOWN0 11/18/2002SINGLE CONTROL ROD DRIVE (CRD) REMOVAL -REFUELING0 11/18/2002MULTIPLE CONTROL ROD WITHDRAWAL -REFUELING1 03/24/2005CONTROL ROD TESTING -OPERATING2 04/09/2007SHUTDOWN MARGIN (SDM) TEST -REFUELINGPages of 8 Report Date: 11/05/15Page 8 ofReport Date: 11/05/15 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionTOC Table of Contents 228 2.0 SAFETY LIMITS BASESPage TS I B 2.0-1 2Pages TS I B 2.0-2 and TS / B 2.0-3 5Page TS /B 2.0-4 7Pages TS / 8 2.0-5 through TS I B 2.0-8 1B 3.0 LCO AND SR APPLICABILITY BASESPage TS /B 3.0-1 1Pages TS /8B3.0-2 through TS I B 3.0-4 0Pages TS /8B3.0-5 through TS /8B3.0-7 1Page TS /8B3.0-8 3Pages TS / B 3.0-9 through Page TS I B 3.0-1: 2Page TS /8B3.0-1 Ia 0Page TS /8B3.0-12 1Pages TS /8B3.0-13 through TS /8B3.0-1 2Pages TS /8B3.0-16 and TS /8 3.0- ,,0B 3.1 REACTIVITY CONTROL BASE Pages B 3.1-1 through 8 3.1 Page TS /8B3.1-5 -Pages TS /8B3.1-6 an 2Pages B3.1-8 throu Page TS /8B3.1-1 ,,0PageTS/B3. IPage 1Pages 17,through TS /B 3.1-19 0Pages Oand TS /B 3.1-21 1o0P /83.1-25 through TS /8B3.1-27 1TS ;/83.1-28 2/B 3.1-29 1Pgs TS / B 3.1-30 through TS / B 3.1-33 0Pages TS /8B 3.1.34 through TS /8B 3.1-36 1Page TS /8B3.1-37 2Page TS /8B3.1-38 3Pages TS /8B3.1-39 and TS / B 3.1-40 2Page TS /8B 3.1-40a 0Page TS /8B3.1-41 1Page TS / B 3.1-42 2SUSQUEHANNA -UNIT 2 TS/BLOES-1 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-1Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.1-43 1Page TS / B 3.1-44 0Page TS I B 3.1-45 3Page 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 BASESPages TS / B 3.2-1 and TS / B 3.2-2 2Page TS / B 3.2-3 4Page TS / B 3.2-4 *1Page TS / B 3.2-5 3Page TS I B 3.2-6 "4----Page TS--B 3.2 ---_- --3Pages TS / B 3.2-8 and TS / B 3.2-9 4Pages TS / B 3.2-10 through TS I B 3.2-12 2Page TS / B 3.2-13 1B 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 I B 3.3-8 4Pages TS I B 3.3-9 through TS / B 3.3-13 3Page TS / B 3.3-14 4Pages TS / B 3.3-15 and TS / B 3.3-16 2Pages TS I B 3.3-17 through TS / B 3.3-21 3Pages TS I B 3.3-22 through TS / B 3.3-27 2Page TS / B 3.3-28 3Page TS / B 3.3-29 4Pages TS / B 3.3-30 and TS / B 3.3-31 3Pages TS / B 3.3-32 and TS / B 3.3-33 4Page TS / B 3.3-34 2Pages TS / B 3.3-34a and TS / B 3.3-34b IPages TS l B 3.3.34c and TS / B 3.3-34d 0Page TS I B 3.3-34e IPages TS / B 3.3-34f through TS / B 3.3-34i 0Pages TS l B 3.3-35 and TS / B 3.3-36 2Pages TS l B 3.3-37 and TS l B 3.3-38 1SUSQUEHANNA -UNIT 2 TS/B LOES-2 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-2Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS / B 3.3-39 2Pages TS / B 3.3-40 through TS / B 3.3-43 1Pages TS / B 3.3-44 through TS / B 3.3-54 3Pages TS / B 3.3-54a through TS I B 3.3-54d 0Page TS I B 3.3.54e 1Page TSI/B 3.3-55 2Page TS I B 3.3-56 0Page TS/1$ 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 0....... -Pages TS-/-B 373-64-and-TS I B 3.3-65 .... ...__ 2 -Page TS / B 3.3-66 4Page TS / B 3.3-67 3Page TS / B 3.3-68 4Page TS / B 3.3.69 5Page TS / B3.3-70 4Page TS I B 3.3-71 3Pages TS /B 3.3-72 and TS I B 3.3-73 2Page TS I B 3.3-74 3Page TS I B 3.3-75 2Pages TS / B 3.3-75a through TS I B 3.3-75c 6Pages TS / B 3.3-76 and TS I B 3.3-77 0Page TSI/B 3.3-78 1Pages TS / B 3.3-79 through TS I B 3.3-81 0Page TS / B 3.3-82 1Page TS / B3.3-83 0Pages TS / B 3.3-84 and TS I B 3.3-85 1Page TS / B3.3-86 0Page TS / B3.3-871Page TS / B 3.3-88 0Page TS I B 3.3-89 1Pages TS I B 3.3-90 and TS I B 3.3-91 0Pages TS / B 3.3-92 through TS /B 3.3-103 1Page TS / B 3.3-104 3Pages TS I B 3.3-105 and TS I B 3.3-106 1Page TS I B 3.3-107 2Page TS I B 3.3-108 1Page TS I B 3.3-109 2Pages TS /B 3.3-110 through TS/IB 3.3-112 1Page TS I B 3.3-113 2SUSQUEHANNA -UNIT 2 TS/BLOES-3 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-3Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS /8B3.3-114 1Page TS /8B3.3-115 2Page TS /8B3.3-116 3Pages TS / B 3.3-117 and TS / B 3.3-118 2Page TS / B 3.3-119 1Page TS /8B3.3-120 2Pages TS / B 3.3-121. and TS /83.3-122 3Page TS / B3.3-123 1Page TS /8B3.3-124 2Page TS / B 3.3-124a 0Page TS /8B3.3-125 1Page TS / B3.3-126 2Page TS / B 3.3-127 "3Page TS-[- 8-3_3-1 ... .. ..... .2_ -Pages TS / B 3.3-129 through TS / B 3.3-131 1Page TS /8B3.3-132 2Pages TS / 8 3.3-133 and TS/B83.3-134 1Pages TS / B 3.3-135 through TS / B 3.3-137 0Page TS / B 3.3-138 1Pages TS / 8 3.3-139 through TSI 83.3-146 0Pages B 3.3-147 through B 3.3-1 49 0Page TS /8B3.3-150 1Pages TS / B 3.3-151 through TS /B 3.3-154 2Page TS /8B3.3-155 1Pages TS / B 3.3-156 through TS I B 3.3-158 2Pages TS / B 3.3-159 through TSI 8 3.3-162 1Pages TS / B 3.3-163 through TS I B 3.3-166 2Pages TS / 8 3.3-167 and TS /8B3.3-168 1Pages TS / 8 3.3-169 and TS /8B3.3-170 3Pages TS / B 3.3-171 through TS / B 3.3-174 1Page TS / B 3.3-174a 1Pages TS/ B 3.3-1 75 through TS/IB 3.3-177 1Page TS /8B3.3-178 2Page TS /8B3.3-179 3Page TS / B 3.3-179a 2Page TS /8B3.3-180 1Page TS /8B3.3-181 3Page TS /8B3.3-182 1Page TS /8B3.3-183 2Page TS /8B3.3-184 1.Page TS /8B3.3-185 4Page TS / 8 3.3-1 86 1Pages TS / 8 3.3-187 and TS /83.3-188 2Pages TS / B 3.3-189 through TS /B 3.3-191 1Page TS / B83.3-192 0SUSQUEHANNA -UNIT 2 TS/B LOES-4 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-4Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS / B 3.3-193 IPages TS I B 3.3-194 and TS / B 3.3-195 0Page TS / B 3.3-196 2Pages TS I B 3.3-197 through TS /B 3.3-205 0Page TS / B 3.3-206 1Pages B 3.3-207 through B 3.3-209 0Page TS / B 3.3-210 1Page TS /B 3.3-211 2Pages TS / B 3.3-212 and TS I B 3.3-213 1Pages B 3.3-214 through B 3.3-220 0B 3.4 REACTOR COOLANT SYSTEM BASES___Pages TS/B 3_.4_-1 and _TS /8_3.4-2 ___ _- -__2Pages TS /8B3.4-3 through TS /8B3.4-5 4-,-Pages TS /8B3.4-6 through TS /8B3.4-9 3Page TS /8B3.4-10 1Pages TS /8B3.4-11 and TS /8B3.4-12 0Page TS / B 3.4-13 2Page TS /8B3.4-14 1Page TS/B 83.4-15 2Pages TS /8B3.4-16 and TS /8B3.4-17 4Page TS /8B3.4-18 2Pages B 3.4-19 through B 3.4-23 0Pages TS /8B3.4-24 through TS /8B3.4-27 0Page TS /8B3.4-28 1Page TS /8B3.4-29 3Page TS /8B3.4-30 2Page TS /8B3.4-31 1Pages TS /8B3.4-32 and TS /8B3.4-33 2Page TS / B 3.4-34 1Page TS / B 3.4-34a 0Pages TS / B 3.4-35 and TS /8B3.4-36 1Page TS /B 3.4-37 2Page B 3.4-38 1Pages B 3.4-39 and B 3.4-40 0Page TS /8B3.4-41 2Pages TS / B 3.4-42 through TSI/B 3.4-45 0Page TS /8B3.4.4-46 1Pages TS / B 3.4.4-47 and TS / B 3.4.4-48 0Page TS /8B 3.4-493Pages TS /8B3.4-50 and TS / B 3.4-51 2Page TS /8B3.4-52 3Page TS / B 3.4-52a 0Pages TS /8B3.4-53 through TS / B 3.4-56 2Page TS /8B3.4-57 3Pages TS / B 3.4-58 through TS / B 3.4-60 1SUSQUEHANNA -UNIT 2TS / B LOES-5Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionB 3.5 ECCS AND RCIC BASESPages TS / B 3.5-1 and TS I B 3.5-2 1Pages TS I B 3.5-3 and TS I B 3.5-4 2Page TS /8B3.5-5 3Page TS /8B3.5-6 2Pages TS/I.B 3.5-7 through TS / B 3.5-10 1Pages TS / B 3.5-11 and TS /8B3.5-12 2Pages TS / B 3.5-13 and TS /8B3.5-14 1Pages TS / 8 3.5-15 through TS / 8.3.5-17 3Pages TS /8B3.5-18 through TS /8B3.5-21 1Page TS /8B3.5-22 2Page TS / 8.3.5-23 1___Page B 3.5-24 0Page TS /B 3.5-25 1Pages TS /8B3.5-26 and TS /8B3.5-27 2Page TS /8B3.5-28 0Page TS / B 3.5-29 through TS I B 3.5-31 1B 3.6 CONTAINMENT SYSTEMS BASESPage TS /8B3.6-1 2Page TS /8B3.6-la 4Page TS /8B3.6-2 4Page TS /8B3.6-3 3Page TS /B 3.6-4 4Page TS /8B3.6-5 .3Page TS /8B3.6-6 4Page TS /B 3.6-6a 4Page TS /8B 3.6-6b 3Page TS /8B 3.6-6c 0Page B 3.6 0Page TS / 3.6-8 1Pages B 3.6-9 through 8 3.6-14 0Page TS /8B3.6-15 4Page TS /8B 3.6-15a 0Page TS /8B 3.6-15b 3Pages TS /8B3.6-16 and TS /8B3.6-17 3Page TS /8B 3.6-17a 1Pages TS /8B3.6-18 and TS /8B3.6-19 1Page TS /8B3.6-20 2Page TS /8B3.6-21 3SUSQUEHANNA -UNIT 2 TS/B LOES-6 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-6Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Titl__e RevisionPages TS I B 3.6-21a and TS I B 3.6-21b 0Pages TS / B 3.6-22 and TS I B 3.6-23 2Pages TS / B 3.6-24 and TS I B 3.6-25 1Pages TS / B 3.6-26 and TS / B 3.6-27 3Page TS I B 3.6-28 7Page TS I B 3.6-29 5Page TS /B 3.6-29a 0Page TS / B 3.6-30 2Page TS / B3.6-31 3Pages TS / B 3.6-32 and TS / B 3.6-33 2Page TS / B 3.6-34 1Pages TS / B 3.6-35 and TS / B 3.6-36 3__ Page TS /B 3.6-37 ___2Page TS / B 3.6-38 3Page TSI/B 3.6-39 7Page TS / B 3.6-39a IPage TS/1. 3.6-40 1Pages B 3.6-41 and B 3.6-42 0Pages TS / B 3.6-43 and TS / B 3.6-44 1Page TS / B 3.6-45 2Pages TS / B 3.6-46 through TS / B 3.6-50 1Page TS / B 3.6-51 2Pages TS / B 3.6-52 through TS / B 3.6-55 0Pages TS / B 3.6-56 and TS / B 3.6-57 2Pages B 3.6-58 through B 3.6-62 0Pages TS / B 3.6-63 and TS / B 3.6-64 1Pages B 3.6-65 through B 3.6-68 0Pages TS / B 3.6-69 through TS / B 3.6-71 1Page TS I B 3.6-72 2Pages TS / B 3.6-73 and TS / B 3.6-74 1Pages B 3.6-75 and B 3.6-76 0Page TS / B 3.6-77 1Pages B 3.6-78 and B 3.6-79 0Page TS / B 3.6-80 1Pages TS / B 3.6-81 and TS / B 3.6-82 0Page TS I B 3.6-83 4Page TS I B 3.6-84 2Page TS / B 3.6-85 4Pages TS / B 3.6-86 and TS I B 3.6-87 2Page TS /8B 3.6-87a 3Page TSI/B 3.6-88 6Page TS /8B3.6-89 4Page TS /8B 3.6-89a 0SUSQUEHANNA -UNIT 2 TSIB LOES-7 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-7Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.6-90 and TS / B 3.6-91 3Page TS I B 3.6-92 2Pages TS / B 3.6-93 through TS / B 3.6-95 1Page TS / B 3.6-96 2Page TS / B 3.6-97 1Page TS / B3.6-98 2Page TS / B 3.6-99 7Page TS / B 3.6-99a 6Page TS I B 3.6-99b 4Page TS / B 3.6-99c 0Pages TS / B 3.6-100 and TS / B 3.6-101 1Pages TS / B 3.6-102 and TS / B 3.6-103 *2Page TS / B 3.6-104 3Page TS / B 3.6-105 -2Page TS / B 3.6-106 3B 3.7 PLANT SYSTEMS BASESPage TS / B3.7-1 3Page TS / B 3.7-2 4Pages TS / B 3.7-3 through TS I B 3.7-5 3Page TS I B 3.7-5a 2Page TS/B 3.7.-6 4Page TSI!B 3.7-6a 3Page TS / B 3.7-6b 2Page TSI!B 3.7-6c 3Page TS / B 3.7-7 3Page TS I B 3.7-8 2Pages B 3.7-9 through B 3.7-11 0Pages TS / B 3.7-12 and TS I B 3.7-13 2Pages TS / B 3.7-14 through TS / B 3.7-18 3Page TS I B 3.7-18a IPages TS / B 3.7-18B through TS I B 3.7-18E 0Pages TS / B 3.7-19 through TS / B 3.7-24 1Pages TS / B 3.7-25 and TS I B 3.7-26 0Page TSI/B 3.7-27 4Pages TS / B 3.7-28 and TS / B 3.7-29 3Pages TS / B 3.7-30 and TS / B 3.7-31 1Page TS I B 3.7-32 0Page TSI/B 3.7-33 1Pages TS / B 3.7-34 through TS / B 3.7-37 0SUSQUEHANNA -UNIT 2 TS / B LOES-8 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-8Revision 125 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionB 3.8 ELECTRICAL POWER SYSTEMS BASESPage TS / B 3.8-1 1Pages B 3.8-2 and B 3.8-3 0Page TS / B 3.8-4 1Pages TS / B 3.8-4a and TS / B 3.8-4b 0Pages TS / B 3.8-5 and TS / B 3.8-6 3Page TS / B 3.8-6a 1Pages B 3.8-7 and B 3.8-8 0Page TS / B 3.8-9 2Pages TS / B 3.8-10 and TS / B 3.8-11 1Pages B 3.8-12 through B 3.8-18 0Page TS / B 3.8-19 1Pages B 3.8-20 through B 3.8-22 ....0Page TS / B 3.8-23 1Page B 3.8-24 0Pages TS / B 3.8-25 and TS I B 3.8-26 1Pages B 3.8-27 through B 3.8-30 0Page TS I B 3.8-31 1Pages TS / B 3.8-32 through TS / B 3.8-35 0Page TS I B 3.8-36 1Page TS I B 3.8-37 0Page TS / B 3.8-38 1Pages B 3.8-39 through B 3.8-46 0Page TS / B 3.8-47 3Pages TS / B 3.8-48 through TS / B 3.8-50 0Pages TS / B 3.8-51 and TS / B 3.8-52 3Page TS / B 3.8-53 1Page TS / B 3.8-54 0Page TS / B 3.8-55 1Pages TS / B 3.8-56 through TS I B 3.8-59 2Pages TS / B 3.8-60 through TS / B 3.8-64 3Page TS I B 3.8-65 4Page TS / B3.8-66 5Pages TS / B 3.8-67 and TS I B 3.8-68 4Page TS I B 3.8-69 5Pages TS / B 3.8-70 through TS / B 3.8-83 1Pages TS I B 3.8-83A through TS I B 3.8-830 0Pages B 3.8-84 through B 3.8-85 0Page TS / B 3.8-86 1Page TS / B 3.8-87 2Pages TS / B 3.8-88 and TS I B 3.8-89 1Page TS I B 3.8-90 2Pages TS / B 3.8-91 through TS / B 3.8-93 1Pages B 3.8-94 through B 3.8-99 0.SUSQUEHANNA -UNIT 2 TSIB LOES-9 Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-9Revision 125 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 3.9-2 1Page TS I B 3.9-2a IPages TS / B 3.9-3 through TS I B 3.9-5 1Pages TS /8B3.9-6 through TS I B 3.9-8 0Pages B 3.9-9 through B 3.9-18 0Pages TS /8B3.9-19 through TS /8B3.9-21 1Pages B 3.9-22 through B 3.9-30 08 3.10 SPECIAL OPERATIONS BASESPage TS /8B3.10-1 *2___Pages TS / B 3.10-2 through TSL/B 3.10-5 __ 1Pages 8 3.10-6 through 8 3.10-32 0Page TS /8B3.10-33 2Page B 3.10-34 0Page TS /8B3.10-35 1Pages B 3.10-36 and B 3.10-37 0Page TS /8B3.10-38 1Page TS / 8 3.10-39 2SUSQUEHANNA -UNIT 2 TS I B LOES-lO Revision 125SUSQUEHANNA -UNIT 2TS / B LOES-10Revision 125 Rev. 4RCS P/T LimitsB 3.4.10B 3.4 REACTOR COOLANT SYSTEM (RCS)B 3.4.10 RCS Pressure and Temperature (PIT) LimitsBASESBACKGROUND All components of the RCS are designed to withstand effects of cyclic loadsdue to system pressure and temperature changes. These loads areintroduced by startup (heatup) and shutdown (cooldown) operations, powertransients, and reactor trips. This LCO limits the pressure and temperaturechanges during RCS heatup and cooldown, within the design assumptionsand the stress limits for cyclic operation.~This Specification contains P/T" limit curves for heatup, cooldown, andinservice leakage and hydrostatic testing, and limits for the maximum rate of...... ....-change-of-reactor coolant-temperature. The heatup curve provides limits for* both heatup and criticality.Each P/T limit curve defines an acceptable region for normal operation. Theusual use of the curves is operational guidance during heatup or cooldownmaneuvering, when pressure and temperature indications are monitored andcompared to the applicable curve to determine that operation is within theallowable region.The LCO establishes operating limits that provide a margin to brittle failure ofthe reactor vessel and piping of the reactor coolant pressure boundary(RCPB). The vessel is the component most subject to brittle failure.Therefore, the LCO limits apply mainly to the vessel.10 CFR 50, Appendix G (Ref. 1), requires the establishment of P/T limits formaterial fracture toughness requirements of the RCPB materials.Reference I requires an adequate margin to brittle failure during normaloperation, anticipated operational occurrences, and system hydrostatic tests.It mandates the use of the ASME Code, Section Xl, Appendix G (Ref. 2).The actual shift in the RTNDT of the vessel material will be establishedperiodically by removing and evaluating the irradiated reactor vessel materialspecimens, in accordance with ASTM E 185 (Ref. 3) and Appendix H of10 CFR 50 (Ref. 4). The operating P/l" limit curves will be adjusted,as necessary, based on the evaluation findings and the recommendations ofRG 1.99, "Radiation Embrittlement of Reactor Vessel Materials (Ref. 5).The calculations to determine neutron fluence will be developed using theBWRVIP RAMA code methodology, which is NRC approved and meets theintent of RG 1.190, "Calculational and Dosimetry Methods for DeterminingPressure Vessel Neutron Fluence" (Ref. 11). See FSAR Section 4.1.4.5 fordetermining fluence (Ref. 12).(continued)SUSQUEHANNA -UNIT 2 T .-9RvsoTS / B 3.4-49Revision 3 Rev. 4RCS P/T" LimitsB 3.4.10BASESBACKGROUND(continued)The P/T limit curves are composite curves established by superimposinglimits derived from stress analyses of those portions of the reactor vesseland head that are the most restrictive. At any specific pressure,temperature, and temperature rate of change, one location within the reactorvessel will dictate the most restrictive limit. Across the span of the P/T limitcurves, different locations are more restrictive, and, thus, the curves arecomposites of the most restrictive regions.The heatup curve used to develop the P/T limit curve composite representsa different set of restrictions than the cooldown curve used to develop theP/T limit curve composite because the directions of the thermal gradientsthrough the vessel wall are reversed. The thermal gradient reversal altersthe location of the tensile stress between the outer and inner walls.The criti~lity limits incluide R~fer-n-ce- 1 requi~rnentth~t-th-ey be at le~t40°F above the heatup curve or the cooldown curve and not lower than theminimum permissible temperature for the inservice leakage and hydrostatictesting.The consequence of violating the LCO limits is that the RCS has beenoperated under conditions that can result in brittle failure of the RCPB,possibly leading to a nonisolable leak or loss of coolant accident. In theevent these limits are exceeded, an evaluation must be performed todetermine the effect on the structural integrity of the RCPB components.ASME Code, Section Xl, Appendix E (Ref. 6), provides a recommendedmethodology for evaluating an operating event that causes an excursionoutside the limits.APPLICABLESAFETYANALYSESThe P/T limits are not derived from Design Basis Accident (DBA) analyses.They are prescribed during normal operation to avoid encountering pressure,temperature, and temperature rate of change conditions that might causeundetected flaws to propagate and cause nonductile failure of the RCPB, acondition that is unanalyzed. Reference 7 establishes the methodology fordetermining the P/T limits. Since the P/T limits are not derived from anyDBA, there are no acceptance limits related to the P/T limits. Rather, the P/Tlimits are acceptance limits themselves since they preclude operation in anunanalyzed condition.RCS P/T limits satisfy Criterion 2 of the NRC Policy Statement (Ref. 8).The Effective Full Power Years (EFPY) shown on the curves are approxi-mations of the ratio of the energy that has been and is anticipated to begenerated in a year to the energy that could have been generated if theunit ran at original thermal power rating of 3293 MWT for the entire year.These values are based on fluence limits that are not to be exceeded.(continued)Revision 2SUSQUEHANNA -UNIT 2TSIB345TS / B 3.4-50 Rev. 4RCS PIT LimitsB 3.4.10BASES. (continued)LCO The elements of this LCO are:a. RCS pressure and temperature are to the right of the applicable curvesspecified in Figures 3.4.10-1 through 3.4.10-3 and within the applicableheat-up or cool down rate specified in SR 3.4.10.1 during RCS heatup,cooldown, and inservice leak and hydrostatic testing;b. The temperature difference between the reactor vessel bottom headcoolant and the reactor pressure vessel (RPV) coolant is < 145°F duringrecirculation pump startup, and during increases in THERMAL POWERor loop flow while operating at low THERMAL POWER or loop flow;c. -The-temperature difference between-the reactor-coolant-in-the respective---.recirculation loop and in the reactor vessel is _< 50°F during recirculationpump startup, and during increases in THERMAL POWER or loop flowwhile operating at low THERMAL POWER or loop flow;d. RCS pressure and temperature are to the right of the criticality limitsspecified in Figure 3.4.10-3 prior to achieving criticality; ande. The reactor vessel flange and the head flange temperatures are >_ 700Fwhen tensioning the reactor vessel head bolting studs.These limits define allowable operating regions and permit a large number ofoperating cycles while also providing a wide margin to nonductile failure.The PIT limit composite curves are calculated using the worst case ofmaterial properties, stresses, and temperature change rates anticipatedunder all heatup and cooldown conditions. The design calculations accountfor the reactor coolant fluid temperature impact on the inner wall of thevessel and the temperature gradients through the vessel wall. Becausethese fluid temperatures drive the vessel wall temperature gradient,monitoring reactor coolant temperature provides a conservative method ofensuring the PIT limits are not exceeded. Proper monitoring of vesseltemperatures to assure compliance with brittle fracture temperature limitsand vessel thermal stress limits during normal heatup and cooldown, andduring inservice leakage and hydrostatic testing, is established in PPLCalculation EC 062-0573 (Ref. 9). For PIT curves A, B, and C, the bottomhead drain line coolant temperature should be monitored and maintained tothe right of the most limiting curve.(continued)SUSQUEHANNA -UNIT 2 Sl34-1Rvso2TS / B 3.4-51Revision 2 Rev. 4RCS P/T LimitsB 3.4.10BASESLCO(continued)Curve A must be used for any ASME Section III Design Hydrostatic Testsperformed at unsaturated reactor conditions. Curve A may also be usedfor ASME Section Xl inservice leakage and hydrostatic testing whenheatup and cooldown rates can be limited to 20°F in a one-hour period.Curve A is based on pressure stresses only. Thermal stresses areassumed to be insignificant. Therefore, heatup and cooldown rates arelimited to 20°F in a one-hour period when using Curve A to ensure minimalthermal stresses. The recirculation loop suction line temperatures shouldbe monitored to determine the temperature change rate.Curves B and C are to be used for non-nuclear and nuclear heatup andcooldown, respectively. In addition, Curve B may be used for ASME SectionXl inservice leakage and hydrostatic testing, but not for ASME Section IIIDesignHydrostatic Tests Performed at u~nsa~turated_ re~actor con~diti~ons._.Heatup and cooldown rates are limited to 100°F in a one-hour period whenusing Curves B and C. This limits the thermal gradient through the vesselwall, which is used to calculate the thermal stresses in the vessel wall. Thus,the LCO for the rate of coolant temperature change limits the thermalstresses and ensures the validity of the P/T curves. The vessel belt-linefracture analysis assumes a 100°F/hr coolant heatup or cooldown rate in thebeltline area. The 100°F limit in a one-hour period applies to the coolant inthe beltline region, and takes into account the thermal inertia of the vesselwall. Steam dome saturation temperature (TSAT), as derived from steamdome pressure, should be monitored to determine the beltline temperaturechange rate at temperatures above 212°F. At temperatures below 212°F,the recirculation loop suction line temperatures should be monitored.During heatups and cooldowns, the reactor vessel could experience avacuum (negative pressure) at low temperatures (unsaturated conditions)and low rates of temperature change. Under a vacuum, the vessel wallwould experience a uniform compressive loading, which would counteractthe tensile stress due to any thermal gradients through the vessel wall. Toensure the margin to brittle fracture is no less than at any other pressure,Curves A, B, and C require a minimum vessel metal temperature of 70°Fwhen the reactor vessel is at a negative pressure.(continued)Revision 3SUSQUEHANNA -UNIT 2 TI345TS / B 3.4-52 Rev. 4RCS P/T LimitsB 3.4.10BASESLCD(continued)Violation of the limits places the reactor vessel outside of the bounds of thestress analyses and can increase stresses in other RCS components. Theconsequences depend on several factors, as follows:a. The severity of the departure from the allowable operating pressuretemperature regime or the severity of the rate of change of temperature;b. The length of time the limits were violated (longer violations allow thetemperature gradient in the thick vessel walls to become morepronounced); andc. The existences, sizes, and orientations of flaws in the vessel material.APPLICABILITYThe potential for violating a P/T limit exists at all times. For example, P/Tlimit violations could result from ambient temperature conditions that result inthe reactor vessel metal temperature being less than the minimum allowedtemperature for boltup. Therefore, this LCO is applicable even when fuel isnot loaded in the core.ACTIONSA.1 and A.2Operation outside the P/l" limits while in MODES 1, 2, and 3 must becorrected so that the RCPB is returned to a condition that has been verifiedby stress analyses.The 30 minute Completion Time reflects the urgency of restoring theparameters to within the analyzed range. Most violations will not be severe,and the activity can be accomplished in this time in a controlled manner.Besides restoring operation within limits, an evaluation is required todetermine if RCS operation can continue. The evaluation must verify theRCPB integrity remains acceptable and must be completed if continuedoperation is desired. Several methods may be used, including comparisonwith pre-analyzed transients in the stress analyses, new analyses, orinspection of the components.(continued)SUSQUEHANNA -UNIT 2TS/B345aRvso0TS / B 3.4-52aRevision 0 Rev. 4RCS PIT" LimitsB 3.4.10BASESACTIONSA.1 and A.2 (continued).ASME Code, Section Xl, Appendix E (Ref. 6), may be used to support theevaluation. However, its use is restricted to evaluation of the vessel beitline.The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is reasonable to accomplish the evaluation ofa mild violation. More severe violations may require special, event specificstress analyses or inspections. A favorable evaluation must be completed ifcontinued operation is desired.Condition A is modified by a Note requiring Required Action A.2 be* completed whenever the Condition is entered. The Note emphasizes the-- -___ --need to-perform the evaluation of-the-effects of the excursion-outside the -allowable limits. Restoration alone per Required Action A. 1 is insufficientbecause higher than analyzed stresses may have occurred and may haveaffected the RCPB integrity.B. I and B.2If a Required Action and associated Completion Time of Condition A are notmet, the plant must be placed in a lower MODE because either the RCSremained in an unacceptable PIT region for an extended period of increasedstress, or a sufficiently severe event caused entry into an unacceptableregion. Either possibility indicates a need for more careful examination ofthe event, best accomplished with the RCS at reduced pressure andtemperature. With the reduced pressure and temperature conditions, thepossibility of propagation of undetected flaws is decreased.(continued)SUSQUEHANNA -UNIT 2 T .-3RvsoTS / B 3.4-53Revision 2 Rev. 4RCS P/T LimitsB 3.4.10BASESACTIONS B.1 and B.2 (continued)Pressure and temperature are reduced by placing the plant in at leastMODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowedCompletion Times are reasonable, based on operating experience, to reachthe required plant conditions from full power conditions in an orderly mannerand without challenging plant systems.C.1 and C.2Operation outside the PIT limits in other than MODES 1, 2, and 3 (includingdefueled conditions) must be corrected so that the RCPB is returned to acondition that has been verified by stress analyses. The Required Actionmust be initiated without delay and continued until the limits are restored.Besides restoring the PIT limit parameters to within limits, an evaluation isrequired to determine if RCS operation is allowed. This evaluation mustverify that the RCPB integrity is acceptable and must be completed beforeapproaching criticality or heating up to > 200°F. Several methods may beused, including comparison with pre-analyzed transients, new analyses, orinspection of the components. ASME Code, Section Xl, Appendix E (Ref. 6),may be used to support the evaluation; however, its use is restricted toevaluation of the beltline.SURVEILLANCE SR 3.4.10.1REQUIREMENTSVerification that operation is within limits (i.e., to the right of the applicablecurves in Figures 3.4.10-1 through 3.4.10-3) is required every 30 minuteswhen RCS pressure and temperature conditions are undergoing plannedchanges. This Frequency is considered reasonable in view of the controlroom indication available to monitor RCS status. Also, since temperaturerate of change limits are specified in hourly increments, 30 minutes permits areasonable time for assessment and correction of minor deviations.Surveillance for heatup, cooldown, or inservice leakage and hydrostatictesting may be discontinued when the criteria given in the relevant plantprocedure for ending the activity are satisfied.This SR has been modified with a Note that requires this Surveillance to beperformed only during system heatup and cooldown operations andinservice leakage and hydrostatic testing.Notes to the acceptance criteria for heatup and cooldown rates ensure thatmore restrictive limits are applicable when the PIT" limits associated withhydrostatic and inservice testing are being applied.(continued)SUSQUEHANNA -UNIT 2TS34-4Rvso2TS / B 3.4-54Revision 2 Rev. 4RCS P/T" LimitsB 3.4.10BASESSURVEILLANCE SR 3.4.10.2REQUIREMENTS(continued) A separate limit is used when the reactor is approaching criticality.Consequently, the RCS pressure and temperature must be verified withinthe appropriate limits (i.e., to the right of the criticality curve in Figure3.4.10-3) before withdrawing control rods that will make the reactor critical.Performing the Surveillance within 15 minutes before control rod withdrawalfor the purpose of achieving criticality provides adequate assurance that thelimits will not be exceeded between the time of the Surveillance and the timeof reactor criticality. Although no Surveillance Frequency is specified, therequirements of SR 3.4.10.2 must be met at all times when the reactor iscritical.SR 3.4.10.3 and SR 3.4.10.4Differential temperatures within the applicable limits ensure that thermalstresses resulting from the startup of an idle recirculation pump will notexceed design allowances. In addition, compliance with these limits ensuresthat the assumptions of the analysis for the startup of an idle recirculationloop (Ref. 10) are satisfied.Performing the Surveillance within 15 minutes before starting the idlerecirculation pump provides adequate assurance that the limits will not beexceeded between the time of the Surveillance and the time of the idle pumpstart.An acceptable means of demonstrating compliance with the temperaturedifferential requirement in SR 3.4.10.4 is to compare the temperatures of theoperating recirculation loop and the idle loop. If both loops are idle, comparethe temperature difference between the reactor coolant within the idle loop tobe started and coolant in the reactor vessel.SR 3.4.10.3 has been modified by a Note that requires the Surveillance to beperformed only in MODES 1, 2, 3, and 4. In MODE 5, the overall stress onlimiting components is lower. Therefore, AT limits are not required. TheNote also states the SR is only required to be met during a recirculationpump start-up, because this is when the stresses occur.(continued)SUSQUEHANNA -UNIT 2 T .-5RvsoTS / B 3.4-55Revision 2 Rev. 4RCS P/I- LimitsB 3.4.10BASESSURVEILLANCE SR 3.4.10.5 and SR 3.4.10.6REQUIREMENTS(continued) Differential temperatures within the applicable limits ensure that thermalstresses resulting from increases in THERMAL POWER or recirculation loopflow during single recirculation loop operation will not exceed designallowances. Performing the Surveillance within 15 minutes before beginningsuch an increase in power or flow rate provides adequate assurance that thelimits will not be exceeded between the time of the Surveillance and the timeof the change in operation.An acceptable means of demonstrating compliance with the temperaturedifferential requirement in SR 3.4.10.6 is to compare the temperatures of theoperating recirculation loop and the idle loop.--Plant startup test data t~s-determined that the bottom head is notsubject to temperature stratification at power levels > 27% of RTP and withsingle loop flow rate > 21,320 gpm (50% of rated loop flow). Therefore,SR 3.4.10.5 and SR 3.4.10.6 have been modified by a Note that requires theSurveillance to be met only under these conditions. The Note forSR 3.4.10.6 further limits the requirement for this Surveillance to excludecomparison of the idle loop temperature if the idle loop is isolated from theRPV since the water in the loop can not be introduced into the remainder ofthe Reactor Coolant System.SR 3.4.10.7, SR 3.4.10.8. and SR 3.4.10.9Limits on the reactor vessel flange and head flange temperatures aregenerally bounded by the other P/T limits during system heatup andcooldown. However, operations approaching MODE 4 from MODE 5 and inMODE 4 with RCS temperature less than or equal to certain specified valuesrequire assurance that these temperatures meet the LCO limits.The flange temperatures must be verified to be above the limits 30 minutesbefore and while tensioning the vessel head bolting studs to ensure thatonce the head is tensioned the limits are satisfied. When in MODE 4 withRCS temperature _< 80°F, 30 minute checks of the flange temperatures arerequired because of the reduced margin to the limits. When in MODE 4 withRCS temperature __ 1 00°F, monitoring of the flange temperature is requiredevery 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to ensure the temperature is within the specified limits.The 30 minute Frequency reflects theurgency of maintaining thetemperatures within limits, and also limits the time that the temperature limitscould be exceeded. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is reasonable based on the rateof temperature change possible at these temperatures.(continued)SUSQUEHANNA -UNIT 2 T .-6RvsoTS / B 3.4-56Revision 2 Rev. 4RCS P/T LimitsB 3.4.10BASES (continuedREFERENCES)1. 10 CFR 50, Appendix G.2. ASME, Boiler and Pressure Vessel Code,Section XI, Appendix G.3. ASTM E 185-734. 10 CFR 50, Appendix H.5. Regulatory Guide 1.99, Revision 2, May 1988.6. ASME, Boiler and Pressure Vessel Code, Section Xl, Appendix E.7. Licensed Topical Reports:a. Structural Integrity Associates Report No. SIR-05-044, Revision 1-A,"Pressure-Temperature Limits Report Methodology for Boiling WaterReactors," June 2013.b. Structural Integrity Associates Report No. 0900876.401, Revision0-A, "Linear Elastic Fracture Mechanics Evaluation of GE BWR WaterLevel Instrument Nozzles for Pressure-Temperature CurveEvaluations," May 2013.8. Final Policy Statement on Technical Specifications Improvements,July 22, 1993 (58 FR 39132).9. PPL Calculation EC-062-0573, "Study to Support the Bases Section ofTechnical Specification 3.4.10."10. FSAR, Section 15.4.4.11. Regulatory Guide 1.190, March 2001.12 FSAR, Section 4.1.4.5.SUSQUEHANNA -UNIT 2 T .-7RvsoTS / B 3.4-57Revision 3 B 3.5B 3.5.2BASESRev. 2ECCS-ShutdownB 3.5.2EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR COREISOLATION COOLING (RCIC) SYSTEMECCS-ShutdownBACKGROUNDA description of the Core Spray (CS) System and the Low PressureCoolant Injection (LPCI) mode of the Residual Heat Removal (RHR)System is provided in the Bases for LCO 3.5.1, "ECCS-Operating."APPLICABLESAFETYA NA LYS ESThe ECCS performance is evaluated for the entire spectrum of breaksizes for-a postulated loss of coolant accident- (LOCA). -The long termcooling analysis following a design basis LOCA (Reference 1)demonstrates that only one low pressure ECCS injection /spraysubsystem is required, post LOCA, to maintain adequate reactor vesselwater level in the event of an inadvertent vessel draindown. It isreasonable to assume, based on engineering judgement, that while inMODES 4 and 5, one low pressure ECCS injection/spray subsystem canmaintain adequate reactor vessel water level. To provide redundancy, aminimum of two low pressure ECCS injection/spray subsystems arerequired to be OPERABLE in MODES 4 and 5.The low pressure ECCS subsystems satisfy Criterion 3 of the NRC PolicyStatement (Ref. 2).LCOTwo low pressure ECCS injection/spray subsystems are required to beOPERABLE. The low pressure ECCS injection/spray subsystems consistof two CS subsystems and two LPCI subsystems. Each CS subsystemconsists of two motor driven pumps, piping, and valves to transfer waterfrom the suppression pool or condensate storage tank (CST) to thereactor pressure vessel (RPV). Each LPCI subsystem consists of one ofthe two motor driven pumps, piping, and valves to transfer water from thesuppression pool to the RPV. Only a single LPCI pump is required persubsystem because of the larger injection capacity in relation to a CSsubsystem. In MODES 4 and 5, the RHR System cross tie valves are notrequired to be closed.(continued)SUSQUEHANNA -UNIT 2 TSB5-9RvsoITS / B 3.5-19Revision 1 Rev. 2ECCS-ShutdownB 3.5.2BASESLCO(continued)LPCI subsystems may be aligned for decay heat removal and consideredOPERABLE for the ECCS function, if they can be manually realigned(remote or local) to the LPCI mode and are not otherwise inoperable.Because of low pressure and low temperature conditions in MODES 4 and5, sufficient time will be available to manually align and initiate LPCIsubsystem operation to provide core cooling prior to postulated fueluncovery.APPLICABILITYOPERABILITY of the low pressure ECCS injection/spray subsystems isrequired in MODES 4 and 5 to ensure adequate coolant inventory andsufficient heat removal capability for the irradiated fuel in .the core in caseof an inadvertent draindown of the vessel. Requirements for ECCSOPERABILITY during MODES 1, 2, and 3 are discussed in theApplicability section of the Bases for LCO 3.5.1. ECCS subsystems arenot required to be OPERABLE during MODE 5 with the spent fuel storagepool gates removed and the water level maintained at >_22 ft. above theRPV flange. This provides sufficient coolant inventory to allow operatoraction to terminate the inventory loss prior to fuel uncovery in case of aninadvertent draindown.The Automatic Depressurization System is not required to be OPERABLEto be OPERABLE during MODES 4 and 5 because the RPV pressure is 150 psig, and the CS System and the LPCI subsystems can providecore cooling without any depressurization of the primary system.The High Pressure Coolant Injection System is not required to beOPERABLE during MODES 4 and 5 since the low pressure ECCSinjection/spray subsystems can provide sufficient flow to the vessel.ACTIONSA.1 and B.1If any one required low pressure ECCS injection/spray subsystemis inoperable, the inoperable subsystem must be restored toOPERABLE status in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. In this Condition, the remainingOPERABLE subsystem can provide sufficient vessel floodingcapability to recover from an inadvertent(continued)SUSQUEHANNA -UNIT 2T/B520RvsoITS / B 3.5-20Revision 1 Rev. 2ECCS-ShutdownB 3.5.2BASESACTIONS A.1 and B.1 (continued)Vessel draindown. However, overall system reliability is reduced becausea single failure in the remaining OPERABLE subsystem concurrent with avessel draindown could result in the ECCS not being able to perform itsintended function. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time for restoring the requiredlow pressure ECCS injection/spray subsystem to OPERABLE status isbased on engineering judgement that considered the remaining availablesubsystem and the low probability of a vessel draindown event.With the inoperable subsystem not restored to OPERABLE status in therequired Completion Time, action must be immediately initiated tosuspend operations with a potential for draining the reactor vessel(OPDRVs) to minimize the probability of a vessel draindown and thesubsequent potential for fission product release. Actions must continueuntil OPDRVs are suspended.C.1, C.2, D.1, D.2, and D.3With both of the required ECCS injectionlspray subsystems inoperable, allcoolant inventory makeup capability may be unavailable. Therefore,actions must immediately be initiated to suspend OPDRVs to minimize theprobability of a vessel draindown and the subsequent potential for fissionproduct release. Actions must continue until OPDRVs are suspended.One ECCS injection/spray subsystem must also be restored toOPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.If at least one low pressure ECCS injection/spray subsystem is notrestored to OPERABLE status within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time,additional actions are required to minimize any potential fission productrelease to the environment. This includes ensuring secondarycontainment is OPERABLE; one standby gas treatment subsystem isOPERABLE; and secondary containment isolation capability (i.e., oneisolation valve and associated instrumentation are OPERABLE or otheracceptable administrative controls to assure isolation capability) in eachsecondary containment penetration flow path not isolated and required tobe isolated to mitigate radioactivity releases. OPERABILITY may beverified by an administrative check, or by examining logs or otherinformation, to determine whether the components are out of(continued)SUSQUEHANNA -UNIT 2TSB.21RvsoITS / B 3.5-21Revision 1 Rev. 2ECCS-ShutdownB 3.5.2BASESACTIONS C.1, C.2. D.1, D.2, and D.3 (continued)}service for maintenance or other reasons. It is not necessary to performthe Surveillances needed to demonstrate the OPERABILITY of thecomponents. If, however, any required component is inoperable, then itmust be restored to OPERABLE status. In this case, the Surveillance mayneed to be performed to restore the component to OPERABLE status.Actions must continue until all required components are OPERABLE.The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time to restore at least one low pressure ECCSinjection/spray subsystem to OPERABLE status ensures that promptaction will be taken to provide the required cooling capacity or to initiateactions to place the plant in a condition that minimizes any potentialfission product release to the environment.SURVEILLANCEREQUIRMENTSSR 3.5.2.1 and SR 3.5.2.2The minimum water level of 20 ft. 0 inches required for the suppressionpool is periodically verified to ensure that the suppression pool will provideadequate net positive suction head (NPSH) for the CS System and LPCIsubsystem pumps, recirculation volume, and vortex prevention. With thesuppression pool water level less than the required limit, all ECCSinjection/spray subsystems are inoperable unless they are aligned to anOPERABLE CST.When suppression pool level is < 20 ft. 0 inches, the CS System isconsidered OPEABLE only if it can take suction from the CST, and theCST water level is sufficient to provide the required NPSH for the CSpump. Therefore, a verification that either the suppression pool waterlevel is 20 ft. 0 inches or that CS is aligned to take suction from theCST and the CST contains >135,000 gallons of water, equivalent to49% of capacity, ensures that the CS System can supply at least135,000 gallons of makeup water to the RPV. However, as noted, onlyone required CS subsystem may take credit for the CST option duringOPDRVs. During OPDRVs, the volume in the CST may not provideadequate makeup if the RPV were completely drained. Therefore, onlyone CS subsystem is allowed to use the CST. This ensures(continued)SUSQUEHANNA -UNIT 2 /B5-2Rvso2TS / B 3.5-22Revision 2 Rev. 2ECCS-ShutdownB 3.5.2BASESSURVEILLANCEREQUIRMENTSSR 3.5.2.1 and SR 3.5.2.2 (continued)the other required ECOS subsystem has adequate makeup volume.The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency of these SRs was developed consideringoperating experience related to suppression pool water level and CSTwater level variations and instrument drift during the applicable MODES.Furthermore, the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is considered adequate in view ofother indications available in the control room, including alarms, to alertthe operator to an abnormal suppression pool or CST water levelcondition.SR 3.5.2.3, SR 3.5.2.5, SR 3.5.2.6, and SR 3.5.2.7The Bases provided for SR 3.5.1.1, SR 3.5.1.7, SR 3.5.1.10, andSR 3.5.1.13 are applicable to SR 3.5.2.3, SR 3.5.2.5, SR 3.5.2.6 andSR 3.5.2.7, respectively.SR 3.5.2.4Verifying the correct alignment for manual, power operated, and automaticvalves in the ECCS flow paths provides assurance that the proper flowpaths will exist for ECCS operation. This SR does not apply to valves thatare locked, sealed, or otherwise secured in position, since these valveswere verified to be in the correct position prior to locking, sealing, orsecuring. A valve that receives an initiation signal is allowed to be in anonaccident position provided the valve will automatically reposition in theproper stroke time. This SR does not require any testing or valvemanipulation; rather, it involves verification that those valves capable ofpotentially being mispositioned are in the correct position. This SR doesnot apply to valves that cannot be inadvertently misaligned, such as checkvalves. The 31 day Frequency is appropriate because the valves areoperated under procedural control and the probability of their beingmispositioned during this time period is low.In MODES 4 and 5, the RHR System may operate in the shutdowncooling mode to remove decay heat and sensible heat from thereactor. Therefore, RHR valves that are required for LPCI(continued)SUSQUEHANNA -UNIT 2TSB35-3RvsoITS / B 3.5-23Revision 1 Rev. 2ECCS-ShutdownB 3.5.2BAS ESSURVEILLANCE SR 3.5.2.4 (continued)REQUIREMENTSsubsystem operation may be aligned for decay heat removal. Therefore,this SR is modified by a Note that allows LPCI subsystems of the RHRSystem to be considered OPERABLE for the ECCS function if all therequired valves in the LPCI flow path can be manually realigned (remoteor local) to allow injection into the RPV, and the systems are not otherwiseinoperable. This will ensure adequate core cooling if an inadvertent RPVdraindown should occur.*REFERNCES 1. FSAR, Section 6.3.2.2. Final Policy Statement on Technical Specifications Improvements,July 22, 1993 (58 FR 39132).SUSQUEHANNA -UNIT2 B2.-4RvsoB 3.5-24Revision 0 Rev. 12Secondary ContainmentB 3.6.4.1B 3.6 CONTAINMENT SYSTEMSB 3.6.4.1 Secondary ContainmentBASESBACKGROUNDThe secondary containment structure completely encloses the primarycontainment structure such that a dual-containment design is utilized to limitthe spread of radioactivity to the environment to within limits. The function ofthe secondary containment is to contain, dilute, and hold up fission productsthat may leak from primary containment into secondary containmentfollowing a Design Basis Accident (DBA). In conjunction with operation ofthe Standby Gas Treatment (SGT) System and closure of certain valveswhose lines penetrate the secondary containment, the secondary-containment is designed to reduce the activity level of the fission productsprior to release to the environment and to isolate and contain fission productsthat are released during certain operations that take place inside primarycontainment, when primary containment is not required to be OPERABLE, orthat take place outside primary containment (Ref. 1).The secondary containment is a structure that completely encloses theprimary containment and reactor coolant pressure boundary components.This structure forms a control volume that serves to hold up and dilute thefission products. It is possible for the pressure in the control volume to riserelative to the environmental pressure (e.g., due to pump and motor heatload additions).The secondary containment boundary consists of the reactor buildingstructure and associated removable walls and panels, hatches, doors,dampers, sealed penetrations and valves. Certain plant piping systems(e.g., Service Water, RHR Service Water, Emergency Service Water,Feedwater, etc.) penetrate the secondary containment boundary. The intactpiping within secondary containment provides a passive barrier whichmaintains secondary containment requirements. Breaches of these pipingsystems within secondary containment will be controlled to maintainsecondary containment requirements. The secondary containment is dividedinto Zone I, Zone II and Zone IlI, each of which must be OPERABLEdepending on plant status and the alignment of the secondary containmentboundary. Specifically, the Unit I secondary containment boundary can bemodified to exclude Zone 11. Similarly, the Unit 2 secondary containmentboundary can be modified to exclude Zone I. Secondary containment mayconsist of only Zone Ill when in MODE 4 or 5 during CORE ALTERATIONS,or during handling of irradiated fuel within the Zone ill secondarycontainment boundary.(continued)SUSQUEHANNA -UNIT 2 T .-3RvsoTS / B 3.6-83Revision 4 Rev. 12Secondary ContainmentB 3.6.4.1BASESBACKGROUND(continued)To prevent ground level exfiltration while allowing the secondary containmentto be designed as a conventional structure, the secondary containmentrequires support systems to maintain the control volume pressure at lessthan the external pressure. Requirements for the safety related systems arespecified separately in LCO 3.6.4.2, "Secondary Containment IsolationValves (SCIVs)," and LCO 3.6.4.3, "Standby Gas Treatment (SGT) System."When one or more zones are excluded from secondary containment, thespecific requirements for support systems will also change (e.g., requiredsecondary containment isolation valves).APPLICABLESAFETYANALYSESThere are two principal accidents for which credit is taken for secondarycontainment OPERABILITY. These are a loss of coolant-accident (LOCA)(Ref. 2) and a fuel handling accident inside secondary containment (Ref. 3).The secondary containment performs no active function in response to eitherof these limiting events; however, its leak tightness is required to ensure thatthe release of radioactive materials from the primary containment is restrictedto those leakage paths and associated leakage rates assumed in theaccident analysis and that fission products entrapped within the secondarycontainment structure will be treated by the SGT System prior to discharge tothe environment.Secondary containment satisfies Criterion 3 of the NRC Policy Statement(Ref. 4).LCOAn OPERABLE secondary containment provides a control volume into whichfission products that bypass or leak from primary containment, or arereleased from the reactor coolant pressure boundary components located insecondary containment, can be diluted and processed prior to release to theenvironment. For the secondary containment to be considered OPERABLE,it must have adequate leak tightness to ensure that the required vacuum canbe established and maintained. The leak tightness of secondarycontainment must also ensure that the release of radioactive materials to theenvironment is restricted to those leakage paths and associated leakagerates assumed in the accident analysis. For example, secondarycontainment bypass leakage must be restricted to the leakage rate requiredby LCO 3.6.1.3. The secondary containment boundary required to beOPERABLE is dependent on the operating status of both units, as well asthe configuration of walls, doors, hatches, SCIVs, and available flow paths tothe SGT System.(continued)SUSQUEHANNA -UNIT 2 T .-4RvsoTS / B 3.6-84Revision 2

" Rev. 12Secondary ContainmentB 3.6.4.1BASES (continued)APPLICABILITY In MODES .1, 2, and 3, a LOCA could lead to a fission product release toprimary containment that leaks to secondary containment. Therefore,secondary containment OPERABILITY is required during the same operatingconditions that require primary containment OPERABILITY.In MODES 4 and 5, the probability and consequences of the LOCA arereduced due to the pressure and temperature limitations in these MODES.Therefore, maintaining secondary containment OPERABLE is not required inMODE 4 or 5 to ensure a control volume, except for other situations forwhich significant releases of radioactive material can be postulated, such asduring operations with a potential for draining the reactor vessel (OP DRVs),during CORE ALTERATIONS, or during movement of irradiated fuelassemblies in the secondary containment.ACTIONS A. 1If secondary containment is inoperable, it must be restored to OPERABLEstatus within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time provides a period of timeto correct the problem that is commensurate with the importance ofmaintaining secondary containment during MODES 1, 2, and 3. This timeperiod also ensures that the probability of an accident (requiring secondarycontainment OPERABILITY) occurring during periods where secondarycontainment is inoperable is minimal.A temporary (one-time) Completion Time is connected to the CompletionTime Requirements above (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) with an "OR" connector. TheTemporary Completion Time is 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and applies to the replacement ofthe Reactor Building Recirculating Fan Damper Motors. The TemporaryCompletion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> may only be used once, and expires onDecember 31, 2005.B.1 and B.2If secondary containment cannot be restored to OPERABLE status within therequired Completion Time, the plant must be brought to a MODE in whichthe LCO does not apply. To achieve this status, the plant must be brought toat least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Theallowed Completion Times are reasonable, based on operating experience,to reach the required plant conditions from full power conditions in an orderlymanner and without challenging plant systems.(continued)SUSQUEHANNA -UNIT 2 T .-5RvsoTS / B 3.6-85Revision 4 Rev. 12Secondary ContainmentB 3.6.4.1BASESACTIONS C.1, C.2, and C.3(continued)Movement of irradiated fuel assemblies in the secondary containment,CORE ALTERATIONS, and OPDRVs can be postulated to cause fissionproduct release to the secondary containment. In such cases, the secondarycontainment is the only barrier to release of fission products to theenvironment. CORE ALTERATIONS and movement of irradiated fuelassemblies must be immediately suspended if the secondary containment isinoperable.Suspension of these activities shall not preclude completing an action thatinvolves moving a component to a safe position. Also, action must beimmediately initiated to suspend OPDRVs to minimize the probability of avessel draindown and subsequent potential for fission product release.Actions must continue until OPDRVs are suspended.Required Action C.1 has been modified by a Note stating that LCO 3.0.3 isnot applicable. If moving irradiated fuel assemblies while in MODE 4 or 5,LCO 3.0.3 would not specify any action. If moving irradiated fuel assemblieswhile in MODE 1, 2, or 3, the fuel movement is independent of reactoroperations. Therefore, in either case, inability to suspend movement ofirradiated fuel assemblies would not be a sufficient reason to require areactor shutdown.SURVEILLANCE SR 3.6.4.1.1REQUIREMENTS-This SR ensures that the secondary containment boundary is sufficiently leaktight to preclude exfiltration under expected wind conditions. Expected windconditions are defined as sustained wind speeds of less than or equal to16 mph at the 60m meteorological tower or less than or equal to 11 mph atthe 10Om meteorological tower if the 60m tower wind speed is not available.Changes in indicated reactor building differential pressure observed duringperiods of short-term wind speed gusts above these sustained speeds do notby themselves impact secondary containment integrity. However, ifsecondary containment integrity is known to be compromised, the LCO mustbe entered regardless of wind speed.(continued)SUSQUEHANNA -UNIT 2 T .-6RvsoTS / B 3.6-86Revision 2 Rev. 12Secondary ContainmentB 3.6.4.1BASESSURVEILLANCE SR 3.6.4.1.1 (continued)REQUIREMENTSThe 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency of this SR was developed based on operatingexperience related to secondary containment vacuum variations during theapplicable MODES and the low probability of a DBA occurring betweensurveillances.Furthermore, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is considered adequate in view of otherindications available in the control room, including alarms, to alert theoperator to an abnormal secondary containment vacuum condition.SR 3.6.4.1.2 and SR 3.6.4.1.3Verifying that secondary containment equipment hatches, removable wallsand one access door in each access opening required to be closed areclosed ensures that the infiltration of outside air of such a magnitude as toprevent maintaining the desired negative pressure does not occur.Verifying that all such openings are closed also provides adequateassurance that exfiltration from the secondary containment will not occur.In this application, the term "sealed" has no connotation of leak tightness.An access opening typically contains one inner and one outer door.Maintaining secondary containment OPERABILITY requires verifying onedoor in each access opening to secondary containment zones is closed.In some cases (e.g., railroad bay), secondary containment access openingsare shared such that a secondary containment barrier may have multipleinner or multiple outer doors. The intent is to maintain the secondarycontainment barrier intact, which is achieved by maintaining the inner orouter portion of the barrier closed at all times. However, all secondarycontainment access doors are normally kept closed, except when theaccess opening is being used for entry and exit or when maintenance isbeing performed on an access opening.When the railroad bay door (No. 101) is closed; all Zone I and Ill hatches,removable walls, dampers, and one door in each access opening connectedto the railroad access bay are closed; or, only Zone I removable walls and/ordoors are open to the railroad access shaft; or, only Zone Ill hatches and/ordampers are open to the railroad access shaft. When the railroad bay door(No. 101) is open; all Zone I and Ill hatches, removable walls, dampers, andone door in each access opening connected to the railroad access bay areclosed. The truck bay hatch is closed and the truck bay door (No. 102) isclosed unless Zone II is isolated from Zones I and Ill.(continued)SUSQUEHANNA -UNIT2 2Sl .-7RvsoTS / B 3.6-87Revision 2 Rev. 12Secondary ContainmentB 3.6.4.1BASESSURVEILLANCEREQUIREMENTSSR 3.6.4.1.2 and SR 3.6.4.1.3 (continued)When an access opening between required secondary containment zones isbeing used for exit and entry, then at least one door (where two doors areprovided) must remain closed. The access openings between secondarycontainment zones which are not provided with two doors areadministratively controlled to maintain secondary containment integrity duringexit and entry. This Surveillance is modified by a Note that allows accessopenings with a single door (i.e., no airlock) within the secondarycontainment boundary (i.e., between required secondary containmentzones) to be opened for entry and exit. Opening of an access door forentry and exit allows sufficient administrative control by individual personnelmaking the entries and exits to-assure the secondary containment functionis not degraded. When one of the zones is not a zone required forsecondary containment OPERABILITY, the Note allowance would notapply.The 31 day Frequency for these SRs has been shown to be adequate,based on operating experience, and is considered adequate in view of theother indications of door and hatch status that are available to the operator.(continued)SUSQUEHANNA -UNIT 2TSIB368aRvso3TS / B 3.6-87aRevision 3 Rev. 12Secondary ContainmentB 3.6.4.1BASESSURVEILLANCEREQUIREMENTS(continued)SR 3.6.4.1.4 and SR 3.6.4.1.5The SGT System exhausts the secondary containment atmosphere to theenvironment through appropriate treatment equipment. To ensure that allfission products are treated, SR 3.6.4.1.4 verifies that the SGT System willrapidly establish and maintain a pressure in the secondary containment thatis less than the pressure external to the secondary containment boundary.This is confirmed by demonstrating that one SGT subsystem will draw downthe secondary containment to _> 0.25 inches of vacuum, water gauge in lessthan or equal to the maximum time allowed. This cannot be accomplished ifthe secondary containment boundary is not intact. SR 3.6.4.1.5demonstrates that one SGT Subsystem can maintain _> 0.25 inches ofvacuum water gauge for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at less than or equal to the maximumflow rate permitted for the secondary containment configuration that isoperable. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> test period allows secondary containment to be inthermal equilibrium at steady state conditions. As noted, both SR 3.6.4.1.4and SR 3.6.4.1.5 acceptance limits are dependent upon the secondarycontainment configuration when testing is being performed. The acceptancecriteria for the SRs based on secondary, containment configuration is definedas follows:SECONDARY MAXIMUM DRAWDOWN TIME(SEC) MAXIMUM FLOW RATE (CFM)CONTAINMENT (SR 3.6.4.1.4 (SR 3.6.4.1.5TEST CONFIGURATION ACCEPTANCE CRITERIA) ACCEPTANCE CRITERIA)Group 1Zones I, II and III (Unit 1 <300 Seconds < 5400 CFMRailroad Bay aligned to (Zones 1, II, and III) (From Zones 1, I1, and IlI)Secondary Containment).Zones II and Ill (Unit 1 <300 Seconds 4000 CFMRailroad Bay aligned to (Zones Il and Ill) (From Zones II and Ill)Zone Ill).Group 2Zones I, II and Ill (Unit 1 < 300 Seconds < 5300 CFMRailroad Bay not aligned to (Zones 1, II, and III) (From Zones 1, 11, and III)Secondary Containment).Zones II and Ill (Unit 1 <300 Seconds < 3900 CFMRailroad Bay not aligned to (Zones II and III) (From Zones II and Ill)SecondaryContainment). ___________________Only one of the above listed configurations needs to be tested to confirm secondary containmentOPERABILITY.(continued)SUSQUEHANNA- UNIT 2TSB36-8Rvso6TS / B 3.6-88Revision 6 Rev. 12Secondary ContainmentB 3.6.4.1BASESSURVEILLANCE SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)REQUIREMENTSA Note also modifies the Frequency for each SR. This Note identifies thateach configuration is to be tested every 60 months. Testing eachconfiguration every 60 months assures that the most limiting configurationis tested every 60 months. The 60 month Frequency is acceptable becauseoperating experience has shown that these components usually pass theSurveillance and all active components are tested more frequently.Therefore, these tests are used to ensure secondary containment boundaryintegrity.The secondary containment testing configurations are discussed in furtherdetail to ensure the appropriate configurations are tested,- Three zonetesting (Zones, I, 11 and Ill aligned to the recirculation plenum) should beperformed with the Railroad Bay aligned to secondary containment andanother test with the Railroad Bay not aligned to secondary containment.Each test should be performed with each division on a STAGGERED TESTBASIS.Two zone testing (Zones II and Ill aligned to the recirculation plenum) shouldbe performed with the Railroad Bay aligned to secondary containment andanother test with the Railroad Bay not aligned to secondary containment.Each test should be performed with each division on a STAGGERED TESTBASIS. The normal operating fans of the non-tested HVAC zone (Zone Ifans 1V202A&B, 1V205A&B and 1V206A&B) should not be in operation.Additionally, a controlled opening of adequate size should be maintained inZone I Secondary Containment during testing to assure that atmosphericconditions are maintained in that zone.The Unit 1 Railroad Bay can be aligned as a No Zone (isolated fromsecondary containment) or as part of secondary containment (Zone I or III).Due to the different leakage pathways that exist in the Railroad Bay, theRailroad Bay should be tested when aligned to secondary containment andalso not aligned to secondary containment. It is preferred to align theRailroad Bay to Zone IIl when testing with the Railroad Bay aligned tosecondary containment since Zone Ill is included in all possible secondarycontainment isolation alignments. Note that when performing the three zonetesting (Zones 1, II and Ill aligned to the recirculation plenum) aligning theRailroad Bay to either Zone I or III is acceptable since either zone is part ofsecondary containment. When performing the Zone II & Ill testing with theRailroad Bay aligned to secondary containment, the Unit 1 Railroad Baymust be aligned to Zone III.(continued)SUSQUEHANNA -UNIT 2 T .-9RvsoTS / B 3.6-89Revision 4 Rev. 12Secondary ContainmentB 3.6.4.1BASESSURVEILLANCEREQU IREM ENTSSR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)Since these SRs are secondary containment tests, they need not beperformed with each SGT subsystem. The SGT subsystems are tested on aSTAGGERED TEST BASIS, however, to ensure that in addition to therequirements of LCO 3.6.4.3, either SGT subsystem will performSR 3.6.4.1.4 and SR 3.6.4.1.5. Operating experience has shown thesecomponents usually pass the Surveillance when performed at the 24 monthFrequency. Therefore, the Frequency was concluded to be acceptable froma reliability standpoint_REFERENCES- 1. FSAR, Section 6.2.3.2. FSAR, Section 15.6.3. FSAR, Section 15.7.4.4. Final Policy Statement on Technical Specifications Improvements,July 22, 1993 (58 FR 39132).(continued)SUSQUEHANNA -UNIT 2TSIB368aRvso0TS / B 3.6-89aRevision 0