ML052560408

Susquehnanna Steam Electric Station Technical Specifications Bases Unit 1 Manual TSB1, Rev. 63

ML052560408
Person / Time
Site:	Susquehanna
Issue date:	08/31/2005
From:	Susquehanna
To:	Office of Nuclear Reactor Regulation
References
028401
Download: ML052560408 (24)

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SSES MANUAL

- Manual Name: TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date: 08/30/2005 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES b3 08/30/2005

Title:

LIST OF EFFECTIVE SECTIONS

.LIclLA MA mrI:m s% W 7' 04/18R/2005c

Title:

TABLE OF CONTENTS /

TEXT 2.1.1 1 04/27/2004 ,

Title:

SAFETY LIMITS (SLS) REACTOR CORE SLS TEXT 2.1.2 0 11/15/2002

Title:

SAFETY LIMITS (SLS) REACTOR COOLANT SYSTEM -(RCS) `PRESSURE SL

~~~~~~~ . .,'-.-.'.-rn,, ,e #,,,,

TEXT 3.0 1 04/18/2005\i" n*

Title:

LIMITING CONDITION FOR OPERATION '(LCO)'APPLICABILITY TEXT 3.1.1 0 /A 11/15/2002

-,8 ' . 'n ....... !,.,.  :

Title:

REACTIVITY CONTROL SYSTEMS.SHUTDOWN MARGIN (SDM)

TEXT 3.1.2 ,- 0 ,11/15/2002

Title:

REACTIVITY CONTROL:SYSTEMS REACTIVITY ANOMALIES TEXT 3.1.3 07/06/2005

Title:

REACTIVITY CONTROL-SYSTEMS CONTROL ROD OPERABILITY

-A:,7 If'A ',r A TEXT 3.1.4 L UIfUUVZUUJ

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM TIMES TEXT 3.1.5 1 07/06/2005

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS

-. . I . .......... .. I.. .. .. ...........

., I ..

TEXT 3.1.6 1 02/17/2005

Title:

REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL Report Date: 08/30/05 Pagel1 Page of of 88 Report Date: 08/30/05

SSE,-. ME.NhL Manual Name: TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES.UNIT.1,MANUAL .

J TEXT 3.1.7 1 08/30/2005

Title:

REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM .

TEXT 3.1.8 0 11/15/2002

Title:

REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVES TEXT 3.2.1 0 11/15/2002

Title:

POWER DISTRIBUTION LIMITS AVERAGE PLANAR: LINEAR HEAT GENERATION RATE-(A~?LHGR)

TEXT 3.2.2 0 11/15/2002

Title:

POWER DISTRIBUTIONLIMITS MINIMUM CRITICAL POWER RATIO (MCPR)

TEXT 3.2.3 0 11/15/2002

Title:

POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)'

TEXT 3.2.4 1 07/06t2005

Title:

POWER DISTRIBUTION LIMITS AVERAGE POWER.-ANGE;MONITOR'(APRM)--GAIN AND SETPOINTS j TEXT 3.3.1.1 . 2 07/06/2'005 ... -

Title:

INSTRUMENTATION REACTOR PROTECTION'SYSTEM,'(RPS) INSTRUMENTATION TEXT 3.3.1.2 0 11/15/2002

Title:

INSTRUMENTATION SOURCE RANGE.-MONITCR (SRM) INSTRUMENTATION.

TEXT 3.3.1.3 0 11/22/2004.'.

Title:

OPRM INSTRUMENTATION,.

TEXT 3.3.2.1 1 02/17/2005 .

Title:

INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 0 11/15/2002 .

Title:

INSTRUMENTATION FEEDWATER - MAIN TURBINE.HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 2 07/06/2005

Title:

INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Report Date: 08/30/05 Page22 Page of of 8 8 Report Date: 08/30/05

SSES 'MANUAL Manual Name: TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL.

TEXT 3.3.3.2 1 04/18/2005

Title:

INSTRUMENTATION REMOTE SHUTDOWN SYSTEM TEXT 3.3.4.1 0 11/15/2002

Title:

INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATION TEXT 3.3.4.2 0 11/15/2002

Title:

INSTRUMENTATION ANTICIPATED:TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP (ATWS-RPT) INSTRUMENTATION TEXT 3.3.5.1 2 07/06/2005

Title:

INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION TEXT 3.3.5.2 0 11/15/2002

Title:

INSTRUMENTATION REACTOR CORE ISOLATION COOLING ARCIC) SYSTEM INSTRUMENTATION TEXT 3.3.6.1 1 11/09/2004'.

Title:

INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION -

TEXT 3.3.6.2 . 1 11/09/2004  : -

Title:

INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.7.1 0 11/15/2002. ..

Title:

INSTRUMENTATION CONTROL ROOM EMERGENCY OUTSIDE'AIRR'UPPLY (CREOAS) SYSTEM INSTRUMENTATION TEXT 3.3.8.1 1 09/02/2004) ..

Title:

INSTRUMENTATION LOSS OF POWER (LOP).INSTRUMENTATION -

TEXT 3.3.8.2 0 11/15/2002 -

Title:

INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING' TEXT 3.4.1 2 11/22/2004

Title:

REACTOR COOLANT SYSTEMA.(RCS) RECIRCULATION LOOPS OPERATING TEXT 3.4.2 0 11/15/2002

Title:

REACTOR COOLANT SYSTEM (RCS) JET PUMPS Report Date: 08/30/05 Page3 Page 3 of of 8 8 Report Date: 08/30/05

SSES!CANUALJ i Manual Name: TSB1 J

Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT.1 MANUAL, j

TEXT 3.4.3 0 11/15/2002

Title:

REACTOR COOLANT SYSTEM (RCS) SAFETY/RELIEF.VALVES (S/RVS)

TEXT 3.4.4 0 11/15/2002

Title:

REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE TEXT 3.4.5 0 11/15/2002-

Title:

REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE:.*ISOLATION VALVE (PIV) LEAKAGE TEXT 3.4.6 1 04/18/2005

Title:

REACTOR COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION-TEXT 3.4.7 1 04/18/2005

Title:

REACTOR COOLANT SYSTEM (RCS) RCS SPECIFIC-ACTIVITY TEXT 3.4.8 1 04/18/2005:

Title:

REACTOR COOLANT-SYSTEMA(RCS). RESIDUAL' HEAT:.REMOVAL (RHR) SHUTDOWN'COOLING 'SYSTEM' vJ

- HOT SHUTDOWN TEXT 3.4.9 0 11/15/2002'.;

Title:

REACTOR COOLANT'SYSTEM (RCS) RESIDUAL.-HEAT REMOVAL (RHR)-'SHUTDOWN COOLING..SYSTEM

- COLD SHUTDOWN TEXT 3.4.10 0 11/15/2002'.

Title:

REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE;AND TEMPERATURE (P/T) LIMITS TEXT 3.4.11 0 11/15/2002CTOR SS

Title:

REACTOR COOLANT SYSTEM (RCS4 REACTOR.STEAM D0OME PRESSURE-TEXT 3.5.1 1 04/18/2005

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTORCORE ISOLATION COOLING (RCIC)

SYSTEM ECCS - OPERATING TEXT 3.5.2 0 11/15/2002

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS) AND'REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM ECCS - SHUTDOWN TEXT 3.5.3 1 04/18/2005

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM RCIC SYSTEM Report Date: 08/30/05 Page44 Page of of 88 Report Date: 08/36/05

e k t - - ;

SSES J-tA ctUAL zManual Name: TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.1.1 0 11/15/2002' .

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT TEXT 3.6.1.2 0 11/15Z2002

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR'LOCK TEXT 3.6.1.3 2 08/24/2005.

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAIN.ENT ISOLATION VALVES (PCIVS)

TEXT 3.6.1.4 0 11/15/2002

Title:

CONTAINMENT SYSTEMS CONTAINMENT PRESSURE TEXT 3.6.1.5 0 11/15/2002'

Title:

CONTAINMENT SYSTEMS DRYWELL 'AIR TEMPERATURE TEXT 3.6.1.6 0 11/15/2002

Title:

CONTAINMENT SYSTEMS SUPPRESSION -CHhMBER-TO-DRYTWELL -VACUUM BREAKERS TEXT 3.6.2.1 '0 11/15/2002 Ti.tle:' CONTAINMENT !SYSTEMS SUPPRESSION POOL ;AVERAGE TEMPER2TURE TEXT 3.6.2.2 0 11/15/2002'. '^

Title:

CONTAINMENT SYSTEMS SUPPRESSION1POOL WATER LEVEL L:' -'-".:U TEXT 3.6.2.3 0 11/1512002: '-

Title:

CONTAINMENT SYSTEMS RESIDUAL HEAT: REMOVAL (RHR) SUPPRESSION-POOL COOLING TEXT 3.6.2.4 0 11/15/2002.

Title:

CONTAINMENT SYSTEMS RESIDUAL' HEAT REMOVAL. (RHR) SUPPRESSION POOL SPRAY TEXT 3.6.3.1 1 04/18/2005,

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS TEXT 3.6.3.2 1 04/18/2005

Title:

CONTAINMENT SYSTEMS DRYWELL AIR FLOW -SYSTEM P ao g 8Re 5 _ e o t D t : 0 / / 5 Page 5 of 8 Report Date: 08/30/05

I. I I _ I11 1 SSES. NANUAL Manual Name: TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL . .. .. J TEXT 3.6.3.3 0 11/15/2002

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT.OXYGEN CONCENTRATION TEXT 3.6.4.1 2 03/01/2005

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT  :

TEXT 3.6.4.2 2 01/03/2005

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)

TEXT 3.6.4.3 2 11/09/2004

Title:

CONTAINMENT SYSTEMS STANDBY-.GAS TREATMENT (SGT) SYSTEM TEXT 3.7.1 0 11/15/2002 .

Title:

PLANT SYSTEM[S RESIDUAL HEAT;.REMOVAL:,SERVICE.WATER:(RHRSW) SYSTEM AND.THE ULTIMATE HEA,T SINK (UHS)

TEXT 3.7.2 1 11/09/2004

Title:

PLANT SYSTEMS EMERGENCY SERV^ICE WATER"(ESW) SYSTEM ~ji TEXT 3.7.3 0 11/15/2002.

Title:

PLANT SYSTEMS CONTROL.;ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM -.

TEXT 3.7.4 0 11/15/2.002.

Title:

PLANT SYSTEMS CONTROLv ROOM: FLOOR COOLING SYSTEM TEXT 3.7.5 0 11/15/2002

Title:

PLANT SYSTEMS MAIN CONDENSER OFFGAS ..

TEXT 3.7.6 1 01/17/2005

Title:

PLANT SYSTEMS MAIN TURBINE BYPASS SYSTEM TEXT 3.7.7 0 11/15/2002

Title:

PLANT SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL TEXT 3.8.1 2 04/18/2005

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES - OPERATING i

Page 6 of 8 Report Date: 08/30/05

• SSE~S. "MANUAL

. Manual Name: TSBI MZanual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.8.2 0 11/15/2002

Title:

ELECTRICAL POWFR SYSTEMS AC SOURCES - SHUTDOWN TEXT 3.8.3 0 11/15/2002

Title:

ELECTRICAL POWER SYSTEMS DIESEL:FUEL OIL, LUBE OIL, AND'STARTING AIR TEXT 3.8.4 0 11/15/2002

Title:

ELECTRICAL POWER SYSTEMS DC SOURCES - OPERATING TEXT 3.8.5 0 11/15/2002

Title:

ELECTRICAL POWER SYSTEMS DC SOURCES - SHUTDOWN TEXT 3.8.6 0 11/15/2002

Title:

ELECTRICAL POWER SYSTEMS-BATTERY CELL PARAMETERS TEXT 3.8.7 0 11/15/2002 w-

Title:

ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS - OPERATING TEXT 3.8.8 ,0 11/15/2002

Title:

ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS - SHUTDOWN TEXT 3.9.1 0 11/15/2002

Title:

REFUELING C1PERATIONS REFUELING EQUIPMENTINTERLOCKS:

TEXT 3.9.2 0 11/15/2002

Title:

REFUELING CIPERATIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK TEXT 3.9.3 0 11/15/2002

Title:

REFUELING CIPERATIONS CONTROL ROD POSITION TEXT 3.9.4 0 11/15/2002 .

Title:

REFUELING CIPERATIONS CONTROL ROD-POSITION INDICATION TEXT 3.9.5 0 11/15/2002

Title:

REFUELING OPERATIONS CONTROL ROD OPERABILITY - REFUELING Report Date: 08/30/05 Page7 Page 7 of of 88 Report Date: 08/30/05

SSES MANUAL Manual Name: TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES'UNIT 1 MANUAL j

TEXT 3.9.6 0 11/15/2002

Title:

REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVEL TEXT 3.9.7 0 11/15/2002

Title:

REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) - HIGH WATER LEVEL TEXT 3.9.8 0 11/15/2002

Title:

REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) - LOW WATER LEVEL TEXT 3.10.1 0 11/15/2002 .

Title:

SPECIAL OPERATIONS INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION TEXT 3.10.2 0 11/15/2002 --

Title:

SPECIAL OPERATIONS REACTOR MODE SWITCH INTERLOCK TESTING TEXT 3.10.3 0 11/15/2002

Title:

SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - HOT SHUTDOWN J, TEXT 3.10.4 o

- 11/15/2002

Title:

SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - COLD SHUTDOWN TEXT 3.10.5 0 11/15/2002

Title:

SPECIAL OPERATIONS SINGLE CONTROL ROD DRIVE (CRD) REMOVAL-- REFUELING TEXT 3.10.6 0 11/15/2002. .

Title:

SPECIAL OPERATIONS MULTIPLE CONTROL ROD WITHDRAWAL - REFUELING TEXT 3.10.7 0 11/15/2002

Title:

SPECIAL OPERATIONS CONTROL ROD TESTING - OPERATING TEXT 3.10.8 0 11/15/2002

Title:

SPECIAL OPERATIONS SHUTDOWN MARGIN (SDM) TEST.- REFUELING I

Report Date: 08/30/05 PageB Page 8 of of 8 8 Report Date: 08/30/05

.... I........

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision TOC Table of Contents 7 B 2.0 SAFETY LIMITS BASES Page B 2.0-1 .. . . . ..

'Page TS i B,2.0-2 ' 2

- Page TS/B2.0-3 3 Pages TSI B 2.0-4 and TS lB 2.0-5 2 Page TS/B2.0-6; .....

Pages B 2.0-7 through B 20-9 0 B 3.0 LCO AND SR APPLICABILITY BASES Pages B 3.0-1 through B 3.0-4 -4 jl  !

/>,.a,>A0 Pages TS I B 3.0-5 through TS I B 3.0-7 Pages TS I B 3.0-8 through TS I B 3.0-9 Pages TS / B 3.0-10 throughTS'/ B 3.0-12 .  ; I<

Pages TS / B 3.0-13 through TS./ B 3.0-15 Pages TS IfB 3.0-16 and TS I B 3.0-17 N. 0 B 3.1 REACTIVITY CONTROL BASES>>

Pages B 3.1-1 through B 3.1-5 .-

0 PagesTS/B3.1-6andTS/B3.1-7 ',

Pages B 3.1-8 through B 3.1-13( O 0

PageTS/B3.1-14 Pages B 3.1-15 through B3.1-223i " C, Page TS I B'3.1-23 .< * ,_ , . . . 0 Pages B 3.1-24 through B 3.1-27 Page TS / B 3:1-28 . . -1 Page TS /B 3.1-29 ... . - -. - I1 Pages B 3.1-30 through B'3.1-33 Pages TS / B3.3-34 through TS.,I B.3.3-36 Page TS / B 3.1-37 2' Page TS I B 3.1-38,'... C.

uO"  :; '1 .

Pages B 3.1-39 through B 3.1-44 0 Page TS B 3:1-45 1 Pages B 3.1-46 through B 3.1-51 0 B 3.2 'POWER DISTRIBUTION LIMITS BASES Page TS I B 3.2-1 1*

Page TS/B3.2-2 2.

PageTS/B3.2-3 ' - ; ' 1 Page TS / B 3.2-4 2 Pages TS / B 3.2-5 and TS I B 3.2-6 Page B 3.2-7 0 Pages TS I B 3.2-8 through TS I B 3.2-10 PageTS / B 3.2-11 2 Page B 3.2-12 *I0 Page TS I B 3.2-13 2 .-

Revision 63 SUSQUEHANNA - UNIT SUSQUEHANNA - UNIT I1 TS / B LOES-1 TSIB LOES-1 . Revision 63

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision Pages B 3.2-14 and B 3.2-15 0 Page TS / B 3.2-16 2 Pages B 3.2-17 and B 3.2-18 0 Page TS B 3.2-19 3 B 3.3 INSTRUMENTATION Pages TS /B 3.3-1 through TS / B 3.3-4 1 Page TS/B 3.3-5 2 Page TS /B 3.3-6 1 Pages TS I B 3.3-7 through TS B 3.3-11 2 Page TS /B 3.3-12 2 Page TS / B 3.3-13 1 Page TS / B 3.3-14 2 Pages TS B 3.3-15 and TS B 3.3-16 1 Pages TS B 3.3-17 and TS IB 3.3-18 2 Pages TS B 3.3-19 through TS /B 3.3-27 1 Pages TS /B 3.3-28 through TS /B 3.3-31 2 Pages TS /B 3.3-32 and TS I B 3.3-33 4 Pages TS /B 3.3-34 through TS I B 3.3-43 I Pages TS /B 3.3-43a through TS I B 3.3-43i 0 Pages TS /B 3.3-44 through TS / B 3.3-50 2 Pages TS I B 3.3-51 through TS /B 3.3 1 Page TS/B 3.3-54 2 Pages B 3.3-55 through B 3.3-63 0 Pages TS IB 3.3-64 and TS B 3.3-65 - 2

-Page TS/B 3.3-66 . 4 Page TS/B 3.3-67 -- 3 Page TS / B 3.3-68 4 Pages TS /B 3.3-69 and TS/ B 3.3-70 3 Page TS/B 3.3-71 - 3 Pages TS/3.3-72 through TS /3.3-75 2 Page TS/B 3.3-75a 4 Pages TS /B 3.3-75b and TS B 3.3-75c 4 Pages B 3.3-76 through 3.3-77 0 Page TS / B 3.3-78 1 Pages B 3.3-79 through B 3.3-89 0 Page TS /B 3.3-90 - 1 Page B 3.3-91 0 Page TS /B 3.3-92 through TS B 3.3-100 - 1 Pages B 3.3-1 01 through B 3.3-103 0 Page TS/B 3.3-104 - 1 Pages B 3.3-105 and B 3.3-106 0 Page TS/B 3.3-107 -1 Page B 3.3-108- 0 Page TS / B 3.3-109 1 Pages B 3.3-110 and B 3.3-111 0 Pages TS/B 3.3-112 and TS/B 3.3-112a 1 Revision 63 SUSQUEHANNA -UNIT

. SUSQUEHANNA - UNIT I1 TS B LOES-2 TS I/ B LOES-2 .Revision 63

SUSQUEHANNA STEAM ELECTRIC STATION LIST OFEFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision Pages TS / B 3.3-113 and TS / B 3.3-114 Page TS / B 3.3-115 1~

Page TS / B 3.3-116 2 Page TS / B 3.3-117 Pages B 3.3-118 through B 3.3-122 0 Pages TS / B 3.3-123 and TS / B 3.3-124 1 Page TS / B 3.3-124a 0 Page B 3.3-125 0 Page TS / B 3.3-126

• 1.

Page TS / B 3.3-127 1 Pages B 3.3-128 through B 3.3-130 0 Page TS / B 3.3-131 Pages B 3.3-132 through B 3.3-137 0 Page TS / B 3.3-138 Pages B 3.3-139 through B 3.3-149

• 12

• Page TS / B 3.3-150 through TS I B 3.3-162 Page TS / B 3.3-163 20 Pages TS / B 3.3-164 through TS I B 3.3-177. 1' Pages TS / B 3.3-178 and TS / B 3.3-179 2 Page TS / B 3.3-179a 2 Page TS / B 3.3-179b *0*

Page TS / B 3.3-179c Page TS / B 3.3-180 Page TS / B 3.3-181 Pages TS / B 3.3-182 through TS / B 3.3-186 2 Pages TS / B 3.3-187 and TS / B 3.3-188 '12 Pages TS / 8B3.3-189 through TS / B 3.3-191 Pages B 3.3-192 through B 3.3-204 0 Page TS / B 3.3-205

• 1 Pages B 3.3-20S through B 3.3-219 B3.4 REACTOR COOLANT SYSTEM BASES 0.

Pages B 3.4-1 and B 3.4-2 Page TS/B 3.4-3 and Page TS/B3.4-4 3 Pages TS / B 3.4-5 through TS / B 3.4-9 2 Pages B 3.4-10 through B 3.4-14 0 Page TS / B 3.4-15 1 Pages TS / B 3.4-16 and TS / B 3.4-17 2 Page TS / B 3.4-18 1 Pages B 3.4-19 through B 3.4-28 0 Page TS / B 3.4-29 Pages B 3.4-30 and B 3.4-31 *I 0 Page TS / B 3.4-32 Pages B 3.4-33 through B 3.4-36 0 Page TS/B3.4-37 *I Pages B 3.4-38 through B 3.4-40 0 Page TS/B3.441 ,:I TSIB LOES-3 Revision 63 SUSQUEHANNA-UNIT SUSQUEHANNA - UNIT 1I TS / B LOES-3 Revision 63

SUSQUEHANNA STEAM ELECTRIC STATION , I :

LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision:

Pages B 3.4-42 through B 3.4-48 *0 Page TS/ B 3.4-49 *..2 Page TS / B 3.450 1 Page TS / B 3.451 2 Pages TS / B 3.4-52 and TS I B 3.4-53 1

- Page TS / B 3.4-54 2 Page TS / B 3.4-55 2 Page TS / B 3.4-56 1 Page TS / B 3.4-57 .2 Pages TS / B 3.4-58 through TS / B 3.4-60 1 B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 0 Page TS / B 3.5-3 2 PageTS/B 3.5-4 1 Page TS / B 3.5-5 2 Page TS / B 3.5-6 1 Pages B 3.5-7 through B 3.5-10 0 PageTS/B3.5-11 1 Pages B 3.5-12 through B 3.5-15 0 Pages TS / B 3.5-16 through TS / B 3.5-18 1 Pages B 3.5-19 through B 3.5-24 0 Page TS / B 3.5-25 I1 Pages TS I B 3.5-26 and TS I B 3.5-27 1' Pages B 3.5-28 through B 3.5-31 0 B 3.6 CONTAINMENT SYSTEMS BASES:

Page TS B 3.6-1 2 Page TS B 3.6-1a 3 Pages TS / B 3.6-2 through TS I B 3.6-5 *2 PageTS/B3.6-6 3 Pages TS / B 3.6-6a and TS lB 3.6-6b 2 Page TS / B 3.6-6c Pages B 3.6-7 through B 3.6-14 0 Page TS / B 3.6-15 *. 2 Pages TS / B 3.6-15a and TS I B 3.6-15b 0 Page B 3.6-16 .0 Page TS / B 3.6-17 I Page TS / B 3.6-17a 0 Pages TS / B 3.6-18 and TS/ B 3.6-19 0 Page TS / B 3.6-20 I Page TS/B3.6-21 .2 Page TS / B 3.6-22 I Page TS / B 3.6-22a

• 0 Page TS / B 3.6-23 Pages TS / 8 3.6-24 through TS I B 3.6-25 0 Page TS/B3.6-26 1 TS/BLOES-4 Revision 63 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT I1 TS / B LOES4 Revision 63

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

K) Section Title Revision Page TS / B 3.6-27 2 Page TS / B 3.6-28 5 Page TS / B 3.6-29 Page TS / B 3.6-30 Page TS/B3.6-31 - 3 Page B 3.6-32 0 Page TS / B 3.6-33 1 Pages B 3.6-34 and B 3.6-35 0 Page TS l B 3.6-36 Page B 3.6-37 0 Page TS/B3.6-38 1 Page B 3.6-39 0 Page TS/B3.6-40 3 Pages B 3.6-41 through B 3.6-43 0 Pages TS / B 3.6-44 through TS I B 3.6-51 Page TS / B 3.6-52 2 Pages B 3.6-53 through B 3.6-63 0 PageTS/B3.6-64 I0 Pages B 3.6-65 through B 3.6-72 Page TS / B 3.6-73 Pages B 3.6-74 through B 3.6-77 0 1

Page TS / B 3.6-78 Pages B 3.6-79 through B 3.3.6-83 Page TS / B 3.6-84 3 Pages TS / B 3.6-85 and TS / B 3.6-86 2 Pages TS / B 3.6-87 through TS / B 3.6-88a 1 PageTS/B36-89 3 Page TS / B 3.8-90 Page TS / B 3.6-91 3 Pages TS / B 3.6-92 through TS / B 3.6-96 .1' PageTS/B3.6-97 Pages TS / B 3.6-98 and TS /B 3.6-99 -2 Page TS / B 3.6-100 Pages TS / 8 3.6-101 and TS / B 3.6-102 -2 Pages TS / B 3.6-103 through TS / B 3.6-105 1 Pages TS / B 3.6-106 and TS / B 3.6-107 B 3.7 PLANT SYSTEMS BASES Pages TS / B 3.7-1 through TS / B3.7-6 2 PageTS/B3.7-6a . 2 Pages TS /B3 3.7-6b and TS / B 3.7-6c 0 Page TS/B3.7-7 2 Pages TS / B 3.7-8 through TS I B 3.7-11 *1 Pages TS / B 3.7-12 and TS / B 3.7-13 I Pages TS / B 3.7-14 through TS/ B 3.7-18 2 Page TS / B 3.7-18a 0 Pages TS / B 3.7-19 through TS / B 3.7-23 I TSIBLOES-5 Revision 63 SUSQUEHANNA - UNIT

- UNIT I1 TS / B LOES-5 .Revision 63

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECT7ONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision Pages B 3.7-24 through B 3.7-26 - 0 Pages TS / B 3.7-27 through TS / B 3.7-29 4 Page TS / B 3.7-30 2 Pages B 3.7-31 through B 3.7-33 0 B 3.8 ELECTRICAL POWER SYSTEMS BASES Pages TS / B 3.8-1 through TS / B 3.8-4 2 Page TS/B3.8-5 4 PageTS/B3.8-6 3 Pages TS I B 3.8-7 through TS/B 3.8-8 2 Pages TS / B 3.8-9 and TS / B 3.8-10 3 Pages TS / B 3.8-11 and TS/ B 3.8-17 2 PageTS/B3.8-18 - 3 Pages TS / B 3.8-19 through TS / B 3.8-21 2 Pages TS / B 3.8-22 and TS / B 3.8-23 3 Pages TS / B 3.8-24 through TS / B 3.8-37 2 Pages B 3.8-38 through B 3.8-53 0 Pages TS / B 3.8-54 through TS /B 3.8-61 1 Page TS / B 3.8-62 2 Page TS / B 3.8-63 2 Page TS/B3.8-64 1 PageTS/ B 3.8-65 2 Pages B 3.8-66 through B 3.8-90 0 B 3.9 REFUELING OPERATIONS BASES Pages TS/ B 3.9-1 and TS / B 3.9-1 a , 1 Pages TS Ba.9-2 through TS / B 3.9-4 1 Pages B 3.9-5 through B 3.9 0 B 3.10 SPECIAL OPERATIONS BASES Page TS / B 3.10-1 -

Pages B 3.10-2 through 8 3.10-31 0 Page TS I B 3.10-32 -

Pages B 3.10-33 through B 3.10-37 0 Page TS B 3.10-38 *1 TSB1 texd LOES 8t23/0' Revision 63 SUSQUEHANNA - UNITI1SUSQUEHANNA TSUNIT TSIB I B ILOES-6 LOES-6 Revision 63

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PPL Rev. 1 SLC System B 3.1.7 B 3.1 REACTIVITY CONTROL SYSTEMS B 3.1.7 Standby Liquid Control (SLC) System BASES BACKGROUND The SLC System is designed to provide the capability of bringing the reactor, at any time in a fuel cycle, from full power and minimum control rod inventory to a subcritical condition with the reactor in the most reactive, xenon free state without taking credit for control rod movement.

The SLC system satisfies the requirements of 10 CFR 50.62 (Ref. 1) for anticipated transient without scram.

The SLC System consists of a sodium pentaborate solution storage tank, two positive displacement pumps, two explosive valves that are provided in parallel for redundancy, and associated piping and valves used to transfer borated water from the storage tank to the reactor pressure vessel (RPV). The borated solution is discharged near the bottom of the core shroud, where it then mixes with the cooling water rising through the

-core. A smaller tank containing demineralized water is provided for testing purposes.

APPLICABLE The SLC System is manually initiated from the'main control room, as SAFETY directed by the emergency operating procedures, if the operator believes ANALYSES the reactor cannot be shut down, or kept shut down, with the control rods.

The SLC System is used in the event that enough control rods cannot be inserted to accomplish shutdown and cooldown in the normal manner.

The SLC System injects borated water into the reactor core to add negative reactivity to compensate for all of the various reactivity effects that could occur during plant operations. To meet this objective, it is necessary to inject a quantity of boron, which produces a concentration of 660 ppm of natural boron, in the reactor coolant at 68 0F. To allow for potential leakage and imperfect mixing in the reactor system, an amount of boron equal to 25% of the amount cited above is added (Ref. 2). The volume versus concentration limits in Figure 3.1.7-1 and the temperature versus concentration limits in Figure 3.1.7-2 are calculated such that the required concentration is achieved accounting for dilution in the RPV with normal water level and including the water volume in

' '(continued)

SUSQUEHANNA - UNIT 1 B 3.1-39 Revision 0

- - ;PPL Rev. 1 SLC System B 3.1.7 BASES APPLICABLE the residual heat removal shutdown cooling piping and in the recirculation

' ' SAFETY loop piping. This quantity of borated solution is the amount that is above ANALYSES the pump suction shutoff level in the boron solution storage tank. No I (continued) credit is taken for the portion of the tank volume that cannot be injected.

The minimum concentration of 13.6 weight'percent ensures compliance with the requirements of 10 CFR 50.62 (Ref. 1).

The SLC System satisfies the requirements of the NRC Policy Statement (Ref. 3) because operating experience and probabilistic risk assessments have shown the SLC System to be important to public health and safety.

Thus, it is retained in the Technical Specifications.

LCO The OPERABILITY of the SLC System provides backup capability for.

reactivity control independent of normal reactivity control provisions provided by the control rods. The OPERABILITY of the SLC System is based on the conditions of the borated solution in the storage tank and the availability of a flow path to the RPV, including the OPERABILITY of the pumps and valves. Two SLC subsystems are required to be OPERABLE; each contains an OPERABLE pump, an explosive valve, and associated piping,'valves, and instruments and controls -to ensure an OPERABLE flow path.

APPLICABILITY In MODES 1 and 2, shutdown capability is required. In MODES 3 and 4, control rods are not able to be withdrawn (except as permitted by LCO 3.10.3 and LCO 3.10.4) since the reactor mode switch is in shutdown and a control rod block is applied. This provides adequate controls to ensure that the reactor remains subcritical. In MODE 5, only a single control rod can be withdrawn from a core cell containing fuel assemblies.

Demonstration of adequate SDM (LCO 3.1.1, "SHUTDOWN MARGIN (SDM)") ensures that the reactor will not become critical. Therefore, the SLC System is not required to be OPERABLE when only a single control rod can be withdrawn.

(continued)

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PPL Rev. 1 SLC System B 3.1.7 BASES ACTIONS A.1 If the boron solution concentration is less than the required limits for compliance with 10 CFR 50.62 (Ref. 1) (2 13.6 weight percent) but greater than the concentration required for cold shutdown (original licensing basis), the concentration must be restored to within limits > 13.6 weight percent in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. It is not necessary unde'r these conditions to enter Condition C for both SLC subsystems inoperable since they are capable of performing their original design basis function. Because of the low probability of an event and the fact that the SLC System capability still exists for vessel injection under these conditions, the allowed Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is acceptable and provides adequate time to restore concentration to'within limits.

The second Completion Time for Required Action A.1 establishes a limit on the maximum time allowed for any combination of concentration out of limits or inoperable SLC subsystems during any single continuous '

occurrence of failing to meet the LCO. If Condition A is entered while, for

'instance, an SLC subsystem is inoperable and that subsystem is subsequently returned to OPERABLE, the LCO may already.have been not met for up to'7 days. This situation could lead to a total duration of 10 days (7 days in Condition B, followed by 3 days in Condition A), since initial failure of the LCO, to restore the SLC System. Then an SLC subsystem could be found inoperable again, and concentration could be restored to within limits. 'This could continue indefinitely.

This Completion Time allows for an exception to the normal "Time zero" for

-beginning the allowed outage time "clock," resulting in establishing the "time zero" at the time the LCO was initially not met instead of at the time Condition A was entered. The 10 day Completion Time is an acceptable limitation on this potential to fail to meet the LCO indefinitely.

B.1 If one SLC subsystem is inoperable for reasons other than Condition A, the inoperable subsystem must be restored to OPERABLE status within 7 days. Inthis condition, the remaining OPERABLE subsystem is adequate to perform the (continued)

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PPL Rev. 1 SLC System B 3.1.7 BASES ACTIONS B.1 (continued) shutdown function.- However, the overall reliability is reduced because a single failure in the remaining OPERABLE subsystem could result in reduced SLC System shutdown capability. The 7 day Completion Time is based on the availability of an OPERABLE subsystem capable of performing the intended SLC System function and the low probability of an event occurring concurrent with the failure of the Control Rod Drive (CRD) System to shut down the plant.

The second Completion Time for Required Action B.1 establishes a limit on the maximum time allowed for any combination of concentration out of limits or inoperable SLC subsystems during any single continuous occurrence of failing to meet the LCO. If Condition B is entered while, for instance, concentration is out of limits, and is subsequently returned to within limits, the LCO may already have been not met for up to 3 days.

This situation could lead to a total duration of 10 days (3 days in Condition A, followed by 7 days in Condition B), since initial failure of the LCO, to restore the SLC System. Then concentration could be found out of limits again, and the SLC subsystem could be restored to OPERABLE.

This could continue indefinitely.

This Completion Time allows for an exception to the normal "time zero" for beginning the allowed outage time "clock," resulting in'.eitablishing the "time zero" at the time the LCO was initially not met instead of at the time Condition B was entered. The 10 day Completion Time is an acceptable limitation on this potential to fail to meet the LCO indefinitely.

C.1 If both SLC subsystems are inoperable for reasons other than Condition A, at least one subsystem must be restored to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The allowed Completion Time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is considered acceptable given the low probability of an event occurring concurrent with the failure of the control rods to shut down the reactor.

(continued)

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- PPL Rev. 1 SLC System B 3.1.7 I.

BASES ACTIONS D.1 (continued)

If any Required Action and associated Completion lme is not met, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The allowed Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.1.7.1. SR 3.1.7.2. and SR 3.1.7.3 REQUIREMENTS SR 3.1.7.1 through SR 3.1.7.3 are 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Surveillances verifying certain characteristics of the SLC System (e.g., the volume and temperature of the borated solution in the storage tank), thereby ensuring SLC System OPERABILITY without disturbing normal plant operation. These Surveillances ensure that the proper borated solution volume and temperature, including the temperature of the pump suction piping', are maintained. Maintaining a minimum specified borated solution temperature is important in ensuring that the sodium pentaborate remains in solution and does not precipitate out in the storage tank or in the pump suction piping. The temperature versus concentration curve of Figure 3.1.7-2 ensures that a 10F margin will be maintained above the saturation temperature. An alternate method of performing SR 3.1.7.3 is

'to verify the OPERABILITY of the SLC heat trace system. This verifies the continuity of the heat trace lines and ensures proper heat trace operation, which ensure that the SLC suction piping temperature is maintained. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is based on operating experience and has shown there are relatively slow variations in the measured parameters of volume and temperature.

SR 3.1.7.4 and SR 3.1.7.6 SR 3.1.7.4 verifies the continuity of the explosive charges in the injection valves to ensure that proper operation will occur if required. Other administrative controls, such as those that limit the shelf life of the explosive charges, must be followed. The 31 day Frequency is based on (continued)

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PPL Rev. 1 SLC System B 3.1.7 BASES SURVEILLANCE SR 3.1.7.4 and SR 3.1.7.6 (continued)

REQUIREMENTS operating experience and has demonstrated the reliability of the explosive charge continuity.

SR 3.1.7.6 verifies that each valve in the system is in its correct position, but does not apply to the squib (i.e., explosive) valves. Verifying the correct alignment for manual and power operated valves in the SLC System flow path provides assurance that the proper flow paths will exist for system operation. A valve is also allowed to be in the nonaccident position provided it can be aligned to the accident position from the control room, or locally by a dedicated operator at the valve control. This is

'acceptable since the SLC System is a manually initiated system. This Surveillance also does not apply to valves that are locked, sealed, or otherwise secured in position since they are verified to be in the correct position prior to locking, sealing, or securing. This verification of valve alignment does not require any testing or valve manipulation; rather, it involves verification that those valves capable of being mispositioned are in the correct position. This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves. The 31 day Frequency is based on engineering judgment and is consistent with the procedural controls governing valve operation that ensures correct valve positions.

SR 3.1;7.5 This Surveillance requires an examination of the sodium pentaborate solution by using chemical analysis to ensure that the proper concentration of sodium pentaborate exists in the storage tank.

SR 3.1.7.5 must be performed anytime sodium pentaborate or water is added to the storage tank solution to determine that the sodium pentaborate solution concentration is within the specified limits.

SR 3.1.7.5 must also be performed anytime the temperature is restored to within the limits of Figure 3.1.7-2, to ensure that no significant sodium pentaborate precipitation occurred. The 31 day Frequency of this Surveillance is appropriate because of the relatively slow variation of sodium pentaborate concentration between surveillances.

(continued)

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PPL Rev. 1 SLC System B 3.1.7 BASES SURVEILLA NCE SR 3.1.7.7

' REQUIREM ENTS (continfiec i) Demonstrating that each SLC System pump devetops a flow rate 2 41.2 gpm at a discharge pressure 2 1395 psig without actuating the pump's relief valve ensures that pump performance has not degraded during the fuel cycle. -Testing at 1395 psig assures that the functional capability of the SLC system meets'the ATWS Rule (10 CFR 50.62) (Ref.

1) requirements.. This minimum pump flow rate requirement ensures that, when combined with the sodium pentaborate solution concentration requirements, the rate of negative reactivity insertion from the SLC System will adequately compensate for the positive reactivity effects encountered during power reduction, cooldown of the moderator, and xenon decay. This test confirms one point on the pump design curve and is indicative of overall performance. Such inservice inspections confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance. The Frequency of this Surveillance is in accordance with the Inservice Testing Program.

SR 3.1.7.8 and SR 3.1.7.9 These Surveillances ensure that there is-a functioning flow path from the boron solution storage tank to the RPV, including the firing of an explosive valve. The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch that has been certified by having one of that batch successfully fired. The pump and explosive valve tested should be alternated such that both complete flow paths are tested every 48 months at alternating 24 month intervals.

The Surveillance may be performed in separate steps to prevent injecting solution into the RPV. An acceptable method for verifying flow from the pump to the RPV is to pump demineralized water from a test tank through one SLC subsystem and into the RPV. The 24 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the Surveillance when performed at the 24 month Frequency; therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

Demonstrating that all heat traced piping between the boron solution storage tank and the suction inlet to the injection (continued)

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PPL Rev. 1 SLC System B 3.1.7 BASES SURVEILLANCE SR 3.1.7.8 and SR 3.1.7.9 (continued)

REQUIREMENTS pumps is unblocked ensures that there is a functioning flow path for injecting the sodium pentaborate solution. An acceptable method for verifying that the suction piping is unblocked is to pump from the storage tank to the test tank. This test can be performed by any series of overlapping or total flow path test so that the entire flow path is included.

The 24 month Frequency is acceptable since there is a low probability that the subject piping will be blocked due to precipitation of the boron from solution in the heat traced piping. This is especially true in light of the temperature verification of this piping required by SR 3.1.7.3.

However, if, in performing SR 3.1.7.3, it is determined that the temperature of this piping has fallen below the specified minimum or the heat trace was not properly energized and building temperature was below the temperature at which the SLC solution would precipitate out, SR 3.1.7.9 must be performed once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the piping temperature is restored to within the limits of Figure 3.1.7-2.

REFERENCES 1. 10 CFR 50.62.

2.. FSAR, Section 9.3.5.

3. Final Policy Statement on Technical Specifications improvements,

July 22,1993 (58 FR 39132).

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