Text

Technical Specifications Bases Unit 2 Manual
	ML050330152
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Site:	Susquehanna
Issue date:	01/18/2005
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.:SSES,--MANUAL WN I

Manual Name: TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL Table Of Contents Issue Date:

01/17/20(

Procedure Name TEXT LOES

Title:

LIST OF EFFECTIVE TEXT TOC 05

..t.

< Rev - Issue Date 53 01/17/2005 SECTIONS i

5 11/22/2004

. Change'ID I Change Number

Title:

TABLE OF CONTENTS TEXT 2.1.1 1

10/27/2004

Title:

SAFETY LIMITS (SLS) REACTOR CORE SLS TEXT 2.1.2 0

11/18/2002 a

Title:

SAFETY LIMITS (SLS)

REACTOR COOLANT SYSTEM (RCS)

PRESSURE SL TEXT 3.0 0

11/18/2002 l

Title:

LIMITING CONDITION FOR OPERATION (LCO)APPLICABILITY TEXT 3.1.1 0/

11/8/2002

Title:

REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)

TEXT 3.1.2 iy

0

,, 11/18/2002

Title:

REACTIVITY CONTROL SYSTEMS REACTIVITY ANOMALIES TEXT 3.1.3

(

j0 11/18/2002

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD OPERABILITY Na.,.,

TEXT 3.1.4 0

11/18/2002

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM TIMES TEXT 3.1.5

Title:

REACTIVITY CONTROL TEXT 3.1.6 0

11/18/2002 SYSTEMS CONTROL ROD'SCRAM ACCUMULATORS 0.

1 1

/18/.20 0

11/18/2002

Title:

REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL Pagel of 8 Report Date: 01/17/05 Page 1 of ~8 Report Date: 01/17/05

n SSES MAIdUAL Manual Name: TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL.-

.I I

a TEXT 3.1.7 0

11/18/2002.'.I

Title:

REACTIVITY CONTROL SYSTEMS STANDBY-LIQUID CQNTROL'(SLC)

SYSTEM TEXT 3.1.8 0

11/18/2002- '

Title:

REACTIVITY CONTROL-SYSTEMS SCRAM DISCHARGE VOLUME (SDV)

VENT AND DRAIN VALVES TEXT 3.2.1 0

11/18/2002

Title:

POWER DISTRIBUTION LIMITS AVERAGE PLAN.R. LINEAR. HEAT GENERATION RATE (APLHGRf TEXT 3.2.2 0

11/18/2002

Title:

POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)

TEXT 3.2.3

, 0 -

11/18/2002

Title:

POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION. RATE (LHGR)

TEXT 3.2.4

, 0 11/18/20C2,

Title:

POWER DISTRIBUTION LIMITS AVERAGE POWER RANGE MONITOR; (APRM) GAIN AND SETPOINTS....

TEXT 3.3.1.1 0

11/18/2002

Title:

INSTRUMENTATION REACTOR PROTECTION SYSTEM' (RPS) INSTRUMENTATION TEXT 3.3.1.2 0

11/18/2002.-

Title:

INSTRUMENTATION SOURCE RANGE MONITOR :(SRM) INSTRUMENTATION TEXT 3.3.1.3

Title:

OPRM INSTRUMENTATION 0

11/22/2004 TEXT 3.3.2.1 0

11/18/2002

Title:

INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 0

11/18/2002

Title:

INSTRUMENTATION FEEDWATER -

MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 0

11/18/2002

Title:

INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION LDCN 3710 Page2 of 8

Report Date: 01/17/05 Page 2 of 8 Report Date: 01/17/05~

£SSES MANUAL Manual Name: TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES'UNIT 2 MANUAL '-

TEXT 3.3.3.2 0

11/18/2002

Title:

INSTRUMIENTATION REMOTE SHUTDOWNSYSTEM TEXT 3.3.4.1 0

11/18/2002

Title:

INSTRUMENTATION ENDOF. CYCLE 'PECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATION TEXT 3.3.4.2 0

11/18/2002','

Title:

INSTRUMENTATIONANTICIPATED'^TRANSIENT WITHOUT SCRAMRECIRCULATION PUMP TRIP-(ATWS-RPT) INSTRUMENTATION TEXT 3.3.5.1 1

11/09/2004'

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 1

11/09/2004

Title:

XINSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION -

TEXT 3.3.6.2 1

11/09/2004

Title:

INSTRUMENTATION SECONDARY CONTAINMENT6'ISOLATION INSTRUMENTATION TEXT 3.3.7.1 0

11/18/2002'

Title:

INSTRUMENTATION CONTROL-.ROOM EMERGENCY'OUTSIDE AIR SUPPLY.(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

11/18/2002

Title:

INSTRUMENTATION REACTOR PROTECTION'SYSTEM (RPS) ELECTRIC POWER MONITORING TEXT 3.4.1 2

11/22/2004-

-Title: REACTOR-COOLANT SYSTEM :(RCS): RECIRCULATION'LOOPS OPERATING-'

TEXT 3.4.2 0

11/18/2002

-Title: REACTOR COOLANT SYSTEM (RCS) JET PUMPS Page 3 of 8 Report Date:. 01/17/05

S S C

b'PJ!

-'A L Manual Name:

TSB2 A

Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL-TEXT 3.4.3 0

11/18/2002' _

Title:

REACTOR COOLANT SYSTEM (RCS) SAFETY/RELIEF VALVES.'(StRVS).:

TEXT 3.4.4 0

11/18/2002

Title:

REACTOR COOLANT SYSTEM (RCS) RCS'OPERArIONAL LEAkAGE.-

hi*

TEXT 3.4.5 0

11/18/2002'-

Title:

REACTOR COOLANTSYSTEM (RCS)':RCS PRESSUJRE-ISOLATION VALV9 (PIV)' LEAKAGE'.:

TEXT 3.4.6 0

11/18/2002'

Title:

REACTOR COOLANT SYSTEM (RCS)

RCS LEAKAGE"DETECTION INSTRUMENTATION.'

TEXT 3.4.7 0

11/18/2002

Title:

REACTOR COOLANT SYSTEM (RCS). RCS SPECIFIC ACTIVITY TEXT 3.4.8 0

11/18/2002

Title:

REACTOR COOLANT SYSTEM {RCS) RESIDUAL HEAT. REMOVAL (RHR) SHUTDOWN COOLING;SYSTE1-I HOT SHUTDOWN TEXT 3.4.9 0

11/18/2002

Title:

REACTOR COOLANT SYSTEM (RCS)'RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING-SYSTEM COLD SHUTDOWN TEXT 3.4.10 0

11/18/2002

Title:

REACTOR COOLANT SYSTEM'(RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS TEXT 3.4.11 0

11/18/2002

Title:

REACTOR COOLANT SYSTEMA(RCS) REACTOR STEAM DOME PRESSURE TEXT 3.5.1 0

11/18/2002

Title:

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

SYSTEM ECCS -

OPERATING TEXT 3.5.2 0

11/18/2002

Title:

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

SYSTEM ECCS -

SHUTDOWN TEXT 3.5.3 0

11/18/2002

Title:

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

SYSTEM RCIC SYSTEM Page 4 of 8 Report Date: 01/17/05

.ssI~s'IAANUALa Manual Name:

TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES-UNIT 2 MANUAL' TEXT 3.6.1.1 0

11/18/2002

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINME'PT TEXT 3.6.1.2 0

11/1-8/2002 x..

Title:

CONTAINMENT SYSTEMS PRIMARY,CONTAINMENT.:.AIR LOCK.

TEXT 3.6.1.3

Title:

,CONTAINMENT TEXT 3.6.1.4

Title:

CONTAINMENT TEXT 3.6.1.5 0

11/18/2002 SYSTEMS PRIMARYl.CQNTAINMENT.:ISOLATION.VALVES

.(PCIVS) 0 11/1.8/2002 :

SYSTEMS CONTAINMENT.-PRESSURE 0

11/18/2002

Title:

CONTAINMENT SYSTEMS DRYWELL.:AIR -EMPERATURE TEXT.3.6.1.6 0

11/18/20(72'

-Title: CONTAINMENT SYSTEMS SUPPRESSION CHAMBER-TO:-DRYWELL:VACUUM BREAKERS TEXT 3.6.2.1 0

11/18/2002

Title:

,CONTAINMENTSYSTEMS SUPPRESSION'-POOL AVERAGE TEMPERATURE TEXT 3.6.2.2

Title:

CONTAINMENT TEXT 3.6.2.3

Title:

CONTAINMENT TEXT 3.6.2.4

Title:

CONTAINMENT TEXT 3.6.3.1

Title:

CONTAINMENT TEXT 3.6.3.2

Title:

CONTAINMENT 0

11/18/20Q2 SYSTEMS SSUPPRESSION.POOL:WATER LEVEL.:

0 11/18/2002 SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING--.'--

0 11/18/2002 SYSTEMS RESIDUAL HEATREMOVAL-:(RHR)

SUPPRESSION.POOL SPRAY 0

11/18/2002 SYSTEMS PRIMARY:CONTAINMENT HYDROGEN RECOMBINERS*

0 11/18/2002 ' !

SYSTEMS DRYWELL AIR FLOW 'SYSTEM I

PageS of 8 Report Date: 01/17/05 Page 5 -

of.8 Report Date: 01/17/05

SSES 2. MANUAL

7.

I Manual Name: TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIX 2 MANUAL'.

TEXT 3.6.3.3

Title:

CONTAINMENT TEXT 3.6.4.1

Title:

CONTAINMENT TEXT 3.6.4.2

Title:

CONTAINMENT TEXT 3.6.4.3

Title:

CONTAINMENT TEXT 3.7.1

Title:

PLANT SYSTEM ULTIMATE HEU 0

11/18/2002 '-'

SYSTEMS PRIMARY CONTAINMENT OXYGEN-'CONCENTRATION 1

01/03/20C5' SYSTEMS SECONDARY CONTAINMENT-'.:

i 2

01/03/2005 SYSTEMS SECONDARY CONTAINMENT--ISOLATION VALVES-(SCIVS) 2 11/09/2004 SYSTEMS STANDBY GAS TREATMENT (SGT)

SYSTEM 0

11/18/2002

[S RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW)

SYSTEM AND VT SINK (UHS) jd.

=,-

I THE-TEXT 3.7.2

Title:

PLANT 1

11/09/2004 SYSTEMS EMERGE1NCY SERVICE WATER (ESW)

SYSTEM TEXT 3.7.3

Title:

PLANT 0

11/18/2002 SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)

SYSTEM:

TEXT 3.7.4

Title:

PLANT TEXT 3.7.5

Title:

PLANT TEXT 3.7.6

Title:

PLANT TEXT 3.7.7

Title:

PLANT TEXT 3.8.1 0

11/1t3/2002 SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM' 0

11/18/2002 SYSTEMS MAIN CONDENSER OFFGAS 1

01/17/2005 SYSTEMS MAIN TURBINE BYPASS SYSTEM 0

11/18/2002 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL 1

10/17/2003

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES - OPERATING Page6 of 8 Report Date: 01/17/05 Page 6 of &.

Report Date: 01/17/05'

4 SSESJMAIU7~L

? Manual Name: TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES.UNIT 2 MANUAL TEXT 3.8.2 0

11/18/2002:

Title:

ELECTRICAL EPOWER SYSnEMS. AC 'SOURCES

StITDOWN -

TEXT 3.8.3 0

11/18/2002' :..,

Title:

ELECTRICAL POWER SYSTEMS DIESELI',UETL'OIL, 'L`BE'O1L; 'AND,'STARTING AIR TEXT 3.8.4 0

+/-1/13/2002'

Title:

ELECTRICAL POWER SYSTEMS,DC SOUFCES A-.OPERATING D

TEXT 3.8.5 0

11/18/2002W.

Title:

ELECTRICAL POWER SYSTEMS DC 'SOURCES

'--- SHUTDOqN TEXT 3.8.6 0

11/18/2002

Title:

ELECTRICAL, POWER.SYSTEMS BAr.TERY.ACEI1 `PARAMETERS TEXT 3.8.7 0

11/18/2002

\\

Title:

ELECTRICAL,POWER SYSTEMS DISTRIBUTION SYSTEMS OPERATING TEXT 3.8.8 0

11/18/2002

Title:

ELECTRICAL POWER SYSTEMS, DISTRIBUTION.eSYSTEMS' -'a SHUTDOWN TEXT 3.9.1 0

11/18/.2002a-

Title:

REFUELING OPERATIONS REFUELING %EQUIPMENTINTERLOCKS TEXT 3.9.2 0

11/18/2002

Title:

REFUELING OPERATIONS REFUEL POSITION; ONE-ROD-OUT INTERLOCK TEXT 3.9.3 0

11/18/2002

^

Title:

REFUELING OPERATIONS -CONTROL ROD-POSITION TEXT 3.9.4 0

11/18/2002

Title:

REFUELING OPERATIONS CONTROL. ROD POSITION INDICATION:

TEXT 3.9.5 0

11/18/2002

Title:

REFUELING OPERATIONS CONTROL ROD OPERABILITY -

REFUELING Page7 of 8 Report Date: 01/17/05 Page 7 of -8 Report Date: 01/17/05

SSES MANUAL Manual Name: TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL, TEXT 3.9.7 0

11/18/2002 t

Title:

REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR)

-HIGH.WATER LEVEL TEXT 3.9.8 0

11/18/2002 A

71

Title:

REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) iLOW WATER' LEVEL TEXT 3.10.1

Title:

SPECIAL TEXT 3.10.2

Title:

SPECIAL TEXT 3.10.3

Title:

SPECIAL TEXT. 3.10.4

Title:

SPECIAL TEXT 3.10.5

Title:

SPECIAL TEXT 3.10.6

Title:

SPECIAL TEXT 3.10.7

Title:

SPECIAL TEXT 3.10.8

Title:

SPECIAL OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 0

11/18/2002-INSERVICE LEAK AND,.WYDfOSTATIC TESTrNG OPERATION 0

11/18/2002 REACTOR MODE SWITCH INTERLOCK TESTING 0

11/18/2002 SINGLE CONTROL ROD.WITHDRAWAL -

HOT.SHUTDOWN 0

11/18/2002 SINGLE CONTROL ROD WITHDRAWAL -'COLD'SHUTDOWN 0

11/18/2002 SINGLE CONTROL ROD DRIVFE (CRD)

REMOVAL -REFUELING 0

11/18/2002 MULTIPLE CONTROL ROD WITHDRAWAL REFUELING 0

11/18/2002 CONTROL ROD TESTING -

OPERATING 0

11/18/2002'-

SHUTDOWN MARGIN (SDM)

TEST -

REFUELING Page8 of 8

Report Date: 01/17/05 Page 8 of 8 Report Date: 01/17/05

'. ' 'T N 011 I I

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.. 19-SUSQUEHANNA STEAM ELECTRIC STATION LISTOFEFFECTIVESECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section TOC

.B 2.0 B3.0 B3.1 B 3.2 B 3.3 Title Table of Contents Revision 5

".'I. 1..

2 3

SAFETY LIMITS BASES PageTS/-B2.0-3 Pa~ge' tS~ lB 2.0-2 Page TS / B 2.0-3 Page TS /,B 2.0-4

'PageTS/.I2.0-5.:

t g B 2 Pages B 2.0-6 through B 2.0-8 LCO AND SR APPLICABILITY BASES

,Pages B 3.0-1 through B 3.'0-7:

t; -

Pages TS / B 3.0-8 and TS / B 3.0-9 Pages B 3.0-10 through B 3.0-12

.r

/

Pages TS / B 3.0-13 through TS/ B 3.0:15 REACTIVITY CONTROL BASES Pages B 3.1-1 through B 3.1-5.'

Pages TS / B 3.1-6 and TS /.B 3.1-7 %

7 Pages B 3.1-8 through'B 3.1-27 Page TS / B-3.1-28 361)

Pages B 3.1-29 through B X36.-

,,f Page TS / B 3.1-37 Pages B 3.1-38 fhrougfB-POWER DISTRIBUTIONI LIMITS'BASES Pages TS / B 32-1 through TS / B 3.2-4 Pages TS /B3.2-5'and TS / B 3.2-6 Page TS /B 3.2-7, PagesTS-/ B'32-8 and TS I B 3.2-9 Paget TS>I 3:10'throughTS / B 3.2-19 INSTRU1MENTATION Pages TS / B 3.3-1 through TS / B 3.3-10

?Page,TS I B 3.3-1 1A,

Pages TS / B 3.3-12 through TS / B 3.3-27 Pages TS / B 3.3-28 through TS I B 3.3-30 Page TS / B 3.3-31 Pages TS / B 3.3-32 and TS / B 3.3-33 Pages TS / B 3.3-34 through TS I B 3.3-43 Pages TS I B 3.3-43a though TS I B 3.3-43i Pages TS / B 3.3-44 through TS I B 3.3-54 Pages B 3.3-55 through B 3.3-63 Pages TS / B 3.3-64 and TS / B 3.3-65 Page TS / B 3.3-66 Page TS / B 3.3-67 Page TS / B 3.3-68 i-4.

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SUSQUEHANNA - UNIT 2 TS I B LOES-1 Revision 53

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

Section Title Pages TS / B 3.3-69 and TS I B 3.3-70 Pages TS / B 3.3-71 through TS / B 3.3-75 Page TS / B 3.3-75a Pages TS / B 3.3-75b through TS / B 3;3-75c Pages B 3.3-76 through B 3.3-91 Pages TS / B 3.3-92 through TS / B 3.3-103.

Page'TS / B 3.3-104 Pages TS / B 3.3-105 and TS I B 3.3-106 Page TS I B 3.3-107 Page TS/ B 3.3-108 Page TS B 3.3-109 Pages TS / B 3.3-110 through TS / B 3.3-115 Pages TS / B 3.3-116 through TS / B 3.3-118 Pages TS / B 3.3-119 through TS / B 3.3-120 Pages TS / B 3.3-121 and TS /B 3.3-122 Page TS / B 3.3-123 Page TS / B 3.3-124 Page TS / B 3.3-124a Pages'TS / B 3.3-125 and TS I B 3.3-126 Page TS/B3.3-127 Pages TS / B 3.3-128 through TS I B 3.3-131 Page TS / B'3.3-132 Pages TS / B 3.3-133 and TS I B 3.3-134 Pages B 3.3-135 through B 3.3-137 Page TS / B 3.3-138 Pages B 3.3-139 through B 3.3-149 Pages TS/ B 3.3-150 through TS I B 3.3-162 PageTS/B3.3-163 Pages TS / B 3.3-164 through TS / B 3.3-177 Page TS / B 3.3-178 Page TS / B 3.3-179 Page TS / B 3.3-179a Page TS / B 3.3-180 Page TS / B 3.3-181 Pages TS / B 3.3-182 through TS I B 3.3-186 Pages TS / B 3.3-187 and TS / B 3.3-188 Pages TS / B 3.3-189 through TS / B 3.3-191 Pages B 3.3-192 through B 3.3-205 Page TS / B 3.3-206 Pages B 3.3-207 through B 3.3-220 B 3.4 REACTOR COOLANT SYSTEM BASES Pages TS / B 3.4-1 and TS / B 3.4-2 Pages TS / B 3.4-3 through TS / B 3.4-9 Pages B 3.4-10 through B 3.4-14 PageTS/B3.4-15 Pages TS / B 3.4-16 and TS / B 3.4-17 Revision

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SUSQUEHANNA - UNIT 2 TS./ B LOES-2 Revision 53

SUSQUEHANNA STEAM ELECTRIC STATION USTOFEFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Sectio B 3.5 B 3.6 n

Title PageTS/B3.4-i8 Pages B 3.4-19 through B 3.428 Page TS/B3.4-29 Pages B 3.3-30 through B 3.3-48 Page TS / B 3.4-49 Page TS / B 3.4-50 Page TS / B 3.4-51 Pages TS I B 3.4-52 and TS I B 3.453 Pages TS I B 3.4-54 and TS I B 3.4-55 Pages TS I B 3.4-56 through TS / B 3.4-60 ECCS AND RCIC BASES Pages TS I B 3.5-1 and TS I B 3.5-2 PageTS/B3.5-3 Pages TS / B 3.5-4 through TS / B 3.5-10 Page TS I B 3.5-11 Pages TS I B 3.5-12 through TS / B 3.5-14 Pages TS / B 3.5-15 through TS / B.3.5-17 Page TS/ B 3.18 Pages B 3.5-19 through B 3.5-24 Page TS / B 3.5-25 Pages B 3.5-26 through B 3.5-31 CONTAINMENT SYSTEMS BASES Page TS / B 3.6-1 Page TS l B 3.6-1a Pages TS / B 3.6-2 through TS B 3.6-5 PageTS/B3.6-6 Pages TS I B 3.6-6a and TS i B 3.6-6b Page TS/B3.6-6c Pages B 3.6-7 through B 3.6-14 Page TS / B 3.6-15 Pages TS / B 3.6-15a and TS / B 3.6-15b Page TS / B 3.6-16 Page TS / B 3.6-17 Page TS / B 3.6-17a Pages TS / B 3.6-18 and TS/ B 3.6-19 Page TS / B 3.6-20 Page TS / B 3.6-21 Pages TS / B 3.6-21a and TS I B 3.6-21b Pages TS / B 3.6-22 and TS / B 3.6-23 Pages TS / B 3.6-24 through TS I B 3.6-26 Page TS / B 3.6-27 Page TS / B 3.6-28 Page TS / B 3.6-29 Page TS / B 3.6-29a Page TS/B3.6-30 Revision 1

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..TS / B LOES-3 Revision 53

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

Section Title Page TS B 3.6-31 Pages TS / B 3.6-32 through TS I B 3.6-34 Pages TS / B 3.6-35 through TS / B 3.6-37 Page TS I B 3.6-38 Page TS B 3.6-39 Pages B 3.640 through B 3.6-42 Pages TS / B 3.643 through TS/ B 3.6-50 Page TS / B 3.6-51 Pages B 3.6-52 through B 3.6-62 PageTS/B3.6-63 Pages B 3.6-64 through B 3.6-82 Page TS / B 3.6-83 Pages TS I B 3.6-84 and TS / B 3.6-85 Pages TS I B 3.6-86 through TS / B 3.6-87a PageTS/B3.6-88 Page TS / B 3.6-89 Page TS / B 3.3-90 Pages.TS / B 3.6-91 through TS I B 3.6-95 Page TS / B 3.6-96 Pages TS / B 3.6-97 and TS i B 3.6-98 Page TS / B 3.6-99 Page TS / B 3.6-99a Pages TS / B 3.6-1 00 and TS I B 3.6-101 Pages TS / B 3.6-102 through TS / B 3.6-104 Pages TS / B 3.6105 and TS I B 3.6-106 3.7 PLANT SYSTEMS BASES Pages TS / B 3.7-1 through TS I B 3.7-6 Page TS / B 3.7-6a Pages TS I B 3.7-6b and TS i B 3.7-6c Page TS I B 3.7-7 PageTS/B3.7-8 Pages B 3.7-9 through B 3.7-11 Pages TS / B 3.7-12 and TS/ B 3.7-13 Pages TS / B 3.7-14 through TS / B 3.7-18 Page TS I B 3.7-18a Pages TS I B 3.7-19 through TS I B 3.7-26 Pages B 3.7-24 through B 3.7-26 Pages TS / B 3.7-27 through TS / B 3.7-29 Page TS / B 3.7-30 Pages B 3.7-31 through B 3.7-33

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

P Section Title Pages B 3.8-12 through B 3.8-18 Page TS I B 3.8-19 Pages B 3.8-20 through B 3.8-22 Page TS / B 3.8-23 Page B 3.8-24 Pages TS I B 3.8-25 and TS B 3.8-26 Pages B 3.8-27 through B 3.8-37 Page TS / B 3.8-38 Pages TS I B 3.8-39 through TS / B 3.8-55 Pages TS I B 3.8-56 through TS I B 3.8-64 Page TS I B 3.8-65 Page TS I B 3.8-66 Pages TS I B 3.8-67 through-TS / B 3.8-68 Page TS I B 3.8-69 '.

Pages B 3.8-70 through B 3.8-99 B 3.9 REFUELING OPERATIONS BASES Pages TS I B 3.9-1 and TS I B 3.9-2 Page TS I B 3.9-2a Pages TS I B 3.9-3 and TS I B 3.9-4 Pages B 3.9-5 through B 3.9-30 B 3.10 SPECIAL OPERATIONS BASES PageTS/B3.10-1 Pages B 3.10-2 through B 3.10-32 Page TS / B 3.1D-33 Pages B 3.10-34 through B 3.10-38 Page TS B 3.10-39 TSB2LOES 12I29/04

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I PPL Rev. 1 Main Turbine Bypass System B 3.7.6 B 3.7 B 3.7.6 BASES PLANT SYSTEMS Main Turbine Bypass System BACKGROUND The Main Turbine Bypass System is designed to control steam pressure when reactor steam generation exceeds turbine requirements during unit startup, sudden load reduction, and cooldown. It allows excess steam flow from the reactor to the condenser without going through the turbine. The full bypass capacity of the system is approximately 25% of-the Nuclear Steam Supply System rated steam flow. Sudden load reductions within the capacity of the steam bypass can be accommodated without reactor scram.

The Main Turbine Bypass System consists of five valves connected to the main steam lines between the main steam isolation valves and the turbine stop valve bypass valve chest. Each of these five valves is 'operated by hydraulic cylinders. The bypass Valves are controlled by the pressure regulation function of the Turbine Electro Hydraulic Control System, as discussed in the FSAR, Section 7.7.1.5 (Ref. 1). The bypass valves are' normally closed, and the pressure regulator controls the turbine control valves that direct all steam flow to the turbine. If the speed governor or the load limiter restricts steam flow to the turbine, the pressure regulator controls the system pressure by opening the bypass valves..' When the bypass valves open, the steam flows from the bypass chest, through connecting piping,-to the pressure breakdown assemblies,-where a series of orifices are used to further reduce the steam pressure before the steam enters the condenser.

APPLICABLE SAFETY ANALYSES The Main Turbine Bypass System has two modes of operation. A fast opening mode is assumed to function during the turbine generator load rejection, turbine trip, and feedwater controller failure transients as discussed in FSAR Sections 15.2.2, 15.2.3, and 15.1.2 (Refs. 2, 3, and 4).

A pressure regulation mode is assumed to function during the control rod withdrawal error and recirculation flow controller failure transients as discussed in FSAR Sections 15.4.2 and 15.4.5 (Refs. 5 and 6). Both modes of operation are assumed to function for all bypass valves assumed in the applicable safety analyses. Opening the bypass valves during the above transients mitigates the increase in reactor vessel pressure, which affects both MCPR and LHGR during the event. An inoperable Main Turbine Bypass System may result in a MCPR and / or LHGR penalty.

The Main Turbine Bypass System satisfies Criterion 3 of the NRC Policy Statement (Ref. 7) 1-

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, I LCO The Main Turbine Bypass System fast opening and pressure regulation modes are required to be OPERABLE to limit the pressure increase in the main steam lines and reactor pressure vessel during transients that cause a pressurization so that the Safety Umit MCPR and LHGR are not exceeded. With the Main Turbine Bypass System inoperable, modifications to the MCPR limits (LCO 3.2.2, TMINIMUM CRITiCAL POWER RATIO (MCPR)U) and LHGR limits (LCO 3.2.3, 'LINEAR HEAT GENERATION RATE (LHGR)") may be applied to allow this LCO to be met The MCPR and LHGR limits for the inoperable Main Turbine Bypass System are specified in the COLR. An OPERABLE Main Turbine Bypass System requires the bypass valves to open in response to increasing main steam line pressure. Licensing analyses credit an OPERABLE Main Turbine Bypass System as having both the bypass valve fast opening mode and pressure regulation mode. The fast opening mode is required for transients initiated by a turbine control valve or turbine stop valve closure. The pressure regulation mode is required for transients where the power increase exceeds the capability of the turbine control valves.

The cycle specific safety analyses assume a certain number of OPERABLE main turbine bypass valves as an input (i.e., one through five). Therefore, the Main Turbine Bypass System is considered OPERABLE when the number of OPERABLE bypass valves is greater than or equal to the number assumed in the safety analyses. The number of bypass valves assumed in the safety analyses is specified in the COLR. This response is within the assumptions of the applicable analysis (Refs. 2 - 6).

APPLICABILIT The Main Turbine Bypass System is required to be OPERABLE at Ž 25% RTP Y

to ensure that the fuel dadding integrity Safety Limit is not violated during all applicable transients. As discussed in the Bases for LCOs 3.2.2 and 3.2.3, sufficient margin to these limits exists at < 25% RTP. Therefore, these requirements'are only necessary when operating at or above this power level.

ACTIONS A.1 If the Main Turbine Bypass System is inoperable and the MCPR and LHGR limits for an inoperable Main Turbine Bypass System, as specified in the COLR, are not'applied, the assumptions of the design basis transient analysis may not be met I

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Under such circumstances, prompt action should be taken to restore the Main Turbine Bypass System to OPERABLE status or adjust the MCPR and LHGR limits accordingly. The 2-hour Completion Time is reasonable,' based on the time to complete the Required.Action and the low probability of an event occurring during this period requiring the Main Turbine Bypass'System.

B.1 If the Main Turbine Bypass System cannot be restored to OPERABLE status or the MCPR and LHGR limits for an inoperable Main Turbine Bypass System l are not applied, THERMAL POWER must be reduced to < 25% RTP. As

.discussed in the Applicability section, operation at < 25% RTP results in sufficient margin to the required limits, and the Main Turbine Bypass System is not required to protect fuel integrity during the applicable transients. The 4-hour Completion Time is reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

SURVEILLANCE SR 7.61 REQUIREMENTS Cycling each required main turbine bypass valve through one complete cycle of full travel (including the fast opening feature) demonstrates that the valves are mechanically OPERABLE and will function when required. The 31-day Frequency is based on engineering judgment, is consistent with the procedural controls governing valve operation, and ensures correct valve positions. Operating experience has shown that these components usually pass the SR when performed at the 31 day Frequency. Therefore, the Frequency is acceptable from a reliability standpoint.

SR 3.7.6.2 The Main Turbine Bypass System is required to actuate automatially to perform its design function. This SR demonstrates that, with the required system initiation signals (simulate automatic actuation), the valves will actuate to their required position. The 24 month Frequency is based on the need to (continued)

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SR 3.7.6.2 (continued) perform this Surveillance under the conditions that apply during a unit outage and because of the potential for an unplanned transient if the Surveillance were performed with the'reactor at power. Operating experience has shown the 24-month Frequency, which is based on the refueling cycle, is acceptable from a reliability standpoint.

SR 3.7.6.3 This SRensures that the TURBINE BYPASS SYSTEM RESPONSE TIME is in compliance with the assumptions of the appropriate safety analysis. The response time limits are specified in unit specific documentation. The 24-month Frequency is based on the need to perform this Surveillance under the conditions that apply during a unit outage and because of the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown the 24-month Frequency, which is based on the refueling cycle, is acceptable from a reliability standpoint.

REFERENCES

1. FSAR, Section 7.7.1.5.

2. FSAR, Section 15.2.2.

3. FSAR, Section.15.2.3

4. FSAR, Section 15.1.2

5. FSAR, Section 15.4.2

6. FSAR, Section 15.4.5

7. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).

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