Text

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
References
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SSES MANUALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTable Of ContentsIssue Date: 11/04/2015 Pr~ocedure Name RevTEXT LOES 125Title: LIST OF EFFECTIVE SECTIONSIssue Date11/ 04/2 015Change ID Change NumberTEXT T0CTitle: TABLE OF CONTENTS22 07/02/2014 TEXT 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 08/20/2009 Title: LIMITING CONDITION FOR OPERATION (LC0) APPLICABILITY TEXT 3.1.1Title: REACTIVITY TEXT 3.1.2Title: REACTIVITY TEXT 3.1.3Title: REACTIVITY TEXT 3.1.4Title: REACTIVITY TEXT 3.1.5Title: REACTIVITY TEXT 3.1.61 03/24/2005 CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)0 11/18/2002 CONTROL SYSTEMS REACTIVITY ANOMALIES 2 01/19/2009 CONTROL SYSTEMS CONTROL ROD OPERABILITY 4 01/30/2009 CONTROL SYSTEMS CONTROL ROD SCRAM TIMES1 07/06/2005 CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS 3 02/24/2014 Title: 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 10/04/2007 Title: REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEMTEXT 3.1.8 3 05/06/2009 Title: REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVESTEXT 3.2.1 4 05/06/2009 Title: POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)TEXT 3.2.2 3 05/06/2009 Title: POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)TEXT 3.2.3 2 05/06/2009 Title: POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE LHGRTEXT 3.3.1.1 5 02/24/2014 Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 2 01/19/2009 Title: INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 3 02/24/2014 Title: INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 2 02/22/2012 Title: INSTRUMENTATION FEEDWATER

-MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 8 02/28/2013 Title: INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMNTATION TEXT 3.3.3.2 1 04/18/2005 Title: INSTRUMENTATION REMOTE SHUTDOWN SYSTEMTEXT 3.3.4.1Title: INSTRUMENTATION 1 05/06/2009 END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)

INSTRUMENTATIONW Page2 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 11/18/2002 Title: INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP(ATWS-RPT)

INSTRUMENTATION TEXT 3.3.5.1 5 02/24/2014 Title: INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION TEXT 3.3.5.2 0 11/18/2002 Title: INSTRUMENTATION REACTOR__CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATION TEXT 3.3.6.1 7 03/31/2014 Title: INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.6.2 4 09/01/2010 Title: INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.7.1Title: INSTRUMENTATION INSTRUMENTATION 2 10/27/2008 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)

SYSTEMTEXT 3.3.8.1 3 12/17/2007 Title: INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATION TEXT 3.3.8.2 0 11/18/2002 Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING TEXT 3.4.1Title: REACTOR COOLANTTEXT 3.4.2Title: REACTOR COOLANT4 07/20/2010 SYSTEM (RCS) RECIRCULATION LOOPS OPERATING 3 10/23/2013 SYSTEM (RCS) JET PUMPSTEXT 3.4.3 3 01/13/2012 Title: REACTOR COOLANT SYSTEM (RCS) SAFETY/RELIEF VALVES (S/RVS)TEXT 3.4.4Title: REACTOR COOLANT0 11/18/2002 SYSTEM (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 03/10/2010 Titles REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGETEXT 3.4.6 4 02/19/2014 Title: REACTOR COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION TEXT 3.4.7---Title :_REACT0RCOOLANT TEXT 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 10/04/2007 SYSTEM_(RCS)

ACTIVITY

__2 03/28/2013 SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEMSYSTEM103/28/2013 CRCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM4 11/04/2015 (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITSSYSTEM0 11/18/2002 SYSTEM (RCS) REACTOR STEAM DOME PRESSURE4 07/16/2014 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTORSYSTEM ECCS -OPERATING TEXT 3.5.2 2 11/04/2015 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTORSYSTEM ECCS -SHUTDOWNTEXT 3.5.3 3 02/24/2014 Title: 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 CONTAINMENT 5 02/24/2014 TEXT 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 3.6.1.3CONTAINMYENT TEXT 3.6.1.4Title : CONTAINMENT TEXT 3.6.1.5__-Title: CONTAINMENT TEXT 3.6.1.6Title:. CONTAINMENT TEXT 3.6.2.1CONTAINMENT TEXT 3.6.2.2Title : CONTAINMENT TEXT 3.6.2.3Title : CONTAINMENT TEXT 3.6.2.4Title : CONTAINMENT TEXT 3.6.3.1Title : CONTAINMENT TEXT 3.6.3.2CONTAINMENT TEXT 3.6.3.3Title : CONTAINMENT TEXT 3.6.4.1Title: CONTAINMENT 14 07/02/2014 SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)1 05/06/2009 SYSTEMS CONTAINMENT PRESSURE1 10/05/2005

_SYSTEMSDRYWELLAIR TEMPERATURE

-__0 11/18/2002 SYSTEMS SUPPRESSION CHAMBER-T0-DRYWELL VACUU/MBREAKERS 2 12/17/2007 SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE 0 11/18/2002 SYSTEMS SUPPRESSION POOL WATER LEVEL1 01/16/2006 SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING0 11/18/2002 SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY2 06/13/2006 SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS 1 04/18/2005 SYSTEMS DRYWELL AIR FLOW SYSTEM1 02/28/2013 SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION 12 11/04/2015 SYSTEMS SECONDARY CONTAINMENT Pages 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 09/21/2006 Title: CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEMTEXT 3.7.1-Title :_PLANTSYSTEMS_

ULTIMATE HEAT5.. 04/27/2012

_RESIDUAL HEAThREMOVAL SERVICEWATER (RHRSWLmSYSTEMANDTHE SINK (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 05/02/2008 SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM1 01/08/2010 SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)

SYSTEM0 11/18/2002 SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM1 10/04/2007 SYSTEMS MAIN CONDENSER OFFGAS3 01/25/2011 SYSTEMS MAIN TURBINE BYPASS SYSTEM1 10/04/2007 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL0 05/06/2009 TURBINE PRESSURE REGULATION SYSTEM9 02/24/2014 Title: ELECTRICAL POWER SYSTEMS AC SOURCES -OPERATING TEXT 3.8.2 0 11/18/2002 Title: 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 10/23/2013 Title: ELECTRICAL POWER SYSTEMS DIESEL FUEL OIL LUBE OILAND STARTING AIRTEXT 3.8.4 3 01/19/2009 Title: ELECTRICAL POWER SYSTEMS DC SOURCES -OPERATING TEXT 3.8.5 1 .12/14/2006

__Title:

ELECTRICALPOWERSYSTEMS DC S0lURCES_=

SHUTDOWN

____-TEXT 3.8.6 1 12/14/2006 Title: ELECTRICAL POWER SYSTEMS BATTERY CELL PARAMETERS TEXT 3.8.7 4 10/05/2005 Title: ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS -OPERATING TEXT 3.8.8 0 11/18/2002 Title: ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS -SHUTDOWNTEXT 3.9.1Title: REFUELING TEXT 3.9.2Title: REFUELING TEXT 3.9.3Title: REFUELING TEXT 3.9.4Title: REFUELING TEXT 3.9.5Title: REFUELING OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 0 11/18/2002 REFUELING EQUIPMENT INTERLOCKS 1 09/01/2010 REFUEL POSITION ONE-ROD-OUT INTERLOCK 0 11/18/2002 CONTROL ROD POSITION0 11/18/2002 CONTROL ROD POSITION INDICATION 0 11/18/2002 CONTROL ROD OPERABILITY

-REFUELING TEXT 3.9.61 10/04/2007 Title: 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 11/18/2002 Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RER) -HIGH WATER LEVELTEXT 3.9.8 0 11/18/2002 Title: 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-OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 1.. 01/23/2008 INSERVICELEAK AND HYDROSTAT~IC TESTINGOPERATION 0 11/18/2002 REACTOR NODE SWITCH INTERLOCK TESTING0 11/18/2002 SINGLE CONTROL ROD WITHDRAWAL

-HOT SHUTDOWN0 11/18/2002 SINGLE CONTROL ROD WITHDRAWAL

-COLD SHUTDOWN0 11/18/2002 SINGLE CONTROL ROD DRIVE (CRD) REMOVAL -REFUELING 0 11/18/2002 MULTIPLE CONTROL ROD WITHDRAWAL

-REFUELING 1 03/24/2005 CONTROL ROD TESTING -OPERATING 2 04/09/2007 SHUTDOWN MARGIN (SDM) TEST -REFUELING Pages 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 INSTRUMENTATION Pages'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 temperature changes during RCS heatup and cooldown, within the design assumptions and 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 established periodically 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 Determining Pressure Vessel Neutron Fluence" (Ref. 11). See FSAR Section 4.1.4.5 fordetermining fluence (Ref. 12).(continued)

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-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 superimposing limits 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 represents a different set of restrictions than the cooldown curve used to develop theP/T limit curve composite because the directions of the thermal gradients through 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 hydrostatic testing.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 recommended methodology for evaluating an operating event that causes an excursion outside the limits.APPLICABLE SAFETYANALYSESThe 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 applicable heat-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 recirculation pump 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 anticipated under 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)

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-UNIT 2 Sl34-1Rvso2 TS / 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-line fracture 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 temperature change 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 counteract the 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.

APPLICABILITY The 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 continued operation is desired.

Several methods may be used, including comparison with pre-analyzed transients in the stress analyses, new analyses, orinspection of the components.

(continued)

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-UNIT 2TS/B345aRvso0 TS / 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 insufficient because 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 increased stress, or a sufficiently severe event caused entry into an unacceptable region. 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)

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-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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . 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 (including defueled 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 3.4.10.1REQUIREMENTS Verification that operation is within limits (i.e., to the right of the applicable curves 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 temperature rate 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 hydrostatic testing 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 2TS34-4Rvso2 TS / 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 withdrawal for 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 recirculation loop (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 temperature differential 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 recirculation pump start-up, because this is when the stresses occur.(continued)

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-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 beginning such 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 temperature differential 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 (continued REFERENCES

)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-Shutdown B 3.5.2EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR COREISOLATION COOLING (RCIC) SYSTEMECCS-Shutdown BACKGROUND A 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."

APPLICABLE SAFETYA 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 subsystem consists 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 TSB5-9RvsoI TS / B 3.5-19Revision 1

Rev. 2ECCS-Shutdown B 3.5.2BASESLCO(continued)

LPCI subsystems may be aligned for decay heat removal and considered OPERABLE 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.

APPLICABILITY OPERABILITY 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 subsystem is inoperable, the inoperable subsystem must be restored toOPERABLE status in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . In this Condition, the remaining OPERABLE subsystem can provide sufficient vessel floodingcapability to recover from an inadvertent (continued)

SUSQUEHANNA

-UNIT 2T/B520RvsoI TS / B 3.5-20Revision 1

Rev. 2ECCS-Shutdown B 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time for restoring the requiredlow pressure ECCS injection/spray subsystem to OPERABLE status isbased on engineering judgement that considered the remaining available subsystem 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .If at least one low pressure ECCS injection/spray subsystem is notrestored to OPERABLE status within the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time,additional actions are required to minimize any potential fission productrelease to the environment.

This includes ensuring secondary containment 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.21RvsoI TS / B 3.5-21Revision 1

Rev. 2ECCS-Shutdown B 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 potential fission product release to the environment.

SURVEILLANCE REQUIRMENTSSR 3.5.2.1 and SR 3.5.2.2The minimum water level of 20 ft. 0 inches required for the suppression pool 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 /B5-2Rvso2 TS / B 3.5-22Revision 2

Rev. 2ECCS-Shutdown B 3.5.2BASESSURVEILLANCE REQUIRMENTSSR 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Frequency of these SRs was developed considering operating 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 automatic valves 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 2TSB35-3RvsoI TS / B 3.5-23Revision 1

Rev. 2ECCS-Shutdown B 3.5.2BAS ESSURVEILLANCE SR 3.5.2.4 (continued)

REQUIREMENTS subsystem 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 otherwise inoperable.

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.-4Rvso B 3.5-24Revision 0

Rev. 12Secondary Containment B 3.6.4.1B 3.6 CONTAINMENT SYSTEMSB 3.6.4.1 Secondary Containment BASESBACKGROUND The 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 containment following 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 containment boundary.

Specifically, the Unit I secondary containment boundary can bemodified to exclude Zone 11. Similarly, the Unit 2 secondary containment boundary 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 secondary containment boundary.

(continued)

SUSQUEHANNA

-UNIT 2 T .-3RvsoTS / B 3.6-83Revision 4

Rev. 12Secondary Containment B 3.6.4.1BASESBACKGROUND (continued)

To prevent ground level exfiltration while allowing the secondary containment to be designed as a conventional structure, the secondary containment requires 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 Isolation Valves (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).APPLICABLE SAFETYANALYSESThere are two principal accidents for which credit is taken for secondary containment 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 restricted to those leakage paths and associated leakage rates assumed in theaccident analysis and that fission products entrapped within the secondary containment 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 secondary containment 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, secondary containment 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 Containment B 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 operating conditions 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 secondary containment OPERABILITY) occurring during periods where secondary containment is inoperable is minimal.A temporary (one-time)

Completion Time is connected to the Completion Time Requirements above (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ) with an "OR" connector.

TheTemporary Completion Time is 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and applies to the replacement ofthe Reactor Building Recirculating Fan Damper Motors. The Temporary Completion Time of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . 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 Containment B 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 secondary containment 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 assemblies while 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 3.6.4.1.1 REQUIREMENTS-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 Containment B 3.6.4.1BASESSURVEILLANCE SR 3.6.4.1.1 (continued)

REQUIREMENTS The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency of this SR was developed based on operating experience 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 3.6.4.1.3 Verifying 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 secondary containment barrier intact, which is achieved by maintaining the inner orouter portion of the barrier closed at all times. However, all secondary containment 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 connected to 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 Containment B 3.6.4.1BASESSURVEILLANCE REQUIREMENTS SR 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 secondary containment 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 secondary containment boundary (i.e., between required secondary containment zones) to be opened for entry and exit. Opening of an access door forentry and exit allows sufficient administrative control by individual personnel making 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 2TSIB368aRvso3 TS / B 3.6-87aRevision 3

Rev. 12Secondary Containment B 3.6.4.1BASESSURVEILLANCE REQUIREMENTS (continued)

SR 3.6.4.1.4 and SR 3.6.4.1.5 The 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 3.6.4.1.5 demonstrates that one SGT Subsystem can maintain

_> 0.25 inches ofvacuum water gauge for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at less than or equal to the maximumflow rate permitted for the secondary containment configuration that isoperable.

The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months test period allows secondary containment to be inthermal equilibrium at steady state conditions.

As noted, both SR 3.6.4.1.4 and SR 3.6.4.1.5 acceptance limits are dependent upon the secondary containment configuration when testing is being performed.

The acceptance criteria 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 3.6.4.1.5 TEST 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 containment OPERABILITY.

(continued)

SUSQUEHANNA-UNIT 2TSB36-8Rvso6 TS / B 3.6-88Revision 6

Rev. 12Secondary Containment B 3.6.4.1BASESSURVEILLANCE SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)

REQUIREMENTS A 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 configuration is 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 atmospheric conditions 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 secondary containment 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)

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Rev. 12Secondary Containment B 3.6.4.1BASESSURVEILLANCE REQU 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)

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