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MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2006-34054

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SSES MANUAL

Manual Name : TSBI-

"¶anual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL

Table Of ContentsIssue Date: 08/08/2006

Procedure Name Rev

TEXT LOES 76

Title: LIST OF EFFECTIVE SECTIONS

Issue Date

08/08/2006

Chimnge ID Change Number

TEXT TOC

Title: TABLE OF CONTENTS

10 06/13/2006

TEXT 2.1.1 2

Title: SAFETY LIMITS (SLS) REACTOR

04/18/2006

CORE SLS

TEXT 2.1.2 0 11/15/2002

Title: SAFETY LIMITS (SLS) REACTOR COOLANT SYSTEM (RCS) PRESSURE SL

TEXT 3.0 1 04/18/2005

Title: LIMITING CONDITION FOR OPERATION-(LCO)'APPLICABILITY

TEXT 3.1.1

Title: REACTIVITY

TEXT 3.1.2

Title: REACTIVITY

1

CONTROL SYSTEMS

0

CONTROL SYSTEMS

'04718/2006

SHUTDOWN MARGIN (SDM)

11/15/2002

REACTIVITY ANOMALIES

TEXT 3.1.3 1 07/06/2005

Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD OPERABILITY

TEXT 3.1.4

Title: REACTIVITY

TEXT 3.1.5

Title: REACTIVITY

TEXT 3.1.6

Title: REACTIVITY

2 04/18/2006

CONTROL SYSTEMS CONTROL ROD SCRAM TIMES

1 07/06/2005

CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS

2

CONTROL SYSTEMS

04/18/2006

ROD PATTERN CONTROL

Page 1 of 8 Report Date: 08/08/06


SSES MAUJAL

Manual Name: TSBt-

Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL

4

TEXT 3.1.7

Title: REACTIVITY CONTROL

TEXT 3.1.8

Title: REACTIVITY CONTROL

1 08/30/2005

SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM

1 10/-19/2005

SYSTEMS SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVES

TEXT 3.2.1 1 04/18/2006

Title: POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

TEXT 3.2.2

Title: POWER DISTRIBUTION

.i 04/18/2006

LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)

TEXT 3.2.3 0 11/15/2002

Title: POWER DISTRIBUTION, LIMITS LINEAR _IEAT GENERATION RATE (LHGR)

TEXT 3.2.4 2 04/12/2006

Title: POWER DISTRIBUTION LIMITS AVERAGZ POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS (,-/I

TEXT 3.3.1.1

Title: INSTRUMENTATION

3 04/12/2006

REACTOR PROTECTION SYSTEM (RPS) INSTRUtxENTATION

TEXT 3.3.1.2 1 04/12/2006

Title: INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION

TEXT 3.3.2.1


TEXT 3.3.2.2


TEXT 3.3.3.1


2 04/12/2006

CONTROL ROD BLOCK iNSTRU!4ENTATION

0 11/15/2002

FEEDWATER - MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION

5 06/13/2006

POST ACCIDENT MONITORING (PAM) INSTRUMENTATION

TEXT 3.3.3.2 - 1 04/18/2005

Title: INSTRUMENTATION REMOTE SHOITDOWN SYSTEM

Report Date: 08/08/06Page 2 of 8

SSESrM MNUTAL •

Manual Name: TSBT•


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


TEXT 3.3.5.2


TEXT 3.3.6.1


TEXT 3.3.6.2


TEXT 3.3.7.1


INSTRUMENTATION

TEXT 3.3.8.1


TEXT 3.3.8.2

2 07/06/2005

EMERGENCY CORE COOLING SYSTEMW--(ECCS)' -INSTRUMENTATION

.0 11/15/2002.

REACTOR CORE ISOLATION COOLINGi (RCIC) iSYSTEM.dIISTRUMENTATION

1 11/09/200A. -.1

PRIMARY CONTAINMENT ISOLATION .INSTRUMENTATION . -

1 11/.09/2004

SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION.

0 11/15/2002

CONTROL ROOM EMERGENCY OUTSIDE; AIR SUPPLY °(CREOAS) SYSTEM

1 09/02/2004

LOSS OF POWER (LOP) INSTRUMENTATION

0 11/15/2002

Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWERMONITORING

TEXT 3.4.1 3 04/12/2006

Title: REACTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATING

TEXT 3.4.2 0 11/15/2002

Title: REACTOR COOLANT SYSTEM (RCS) JET PUMPS

TEXT 3.4.3 1 01/16/2006

Title: REACTOR COOLANT SYSTEM (RCS) SAFETY/RELIEF VALVES (SZRVS)

Page 3 of 8 Report Date:' 08/08/06

SSES MAL-UAL

Manual Name: TSBI-


TEXT 3.4.4

Title: REACTOR-COOLANT

TEXT 3.4.5

Title: REACTOR COOLANT

0 11/15/2002

SYSTEM (RCS) RCS OPERATIONAL LEAFAGE

1 01/16/2006

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


- HOT SHUTDOWN

TEXT 3.4.9


- COLD-SHUTDOWN

TEXT 3.4.10


TEXT 3.4.11


TEXT 3.5.1

1 04/18/2005

SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM

0

SYSTEM (RCS)

11/15/2002

RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM

2 05/10/2006

SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS

0 11/15/2002

SYSTEM (RCS) REACTOR STEAM DOME PRESSURE

2 01/16/2006

Title: EMERGENCY :CORE COOLING SYSTEMS (ECCS) AND:REACTOR CORE ISOLATIONSYSTEM ECCS - OPERATING

TEXT 3.5.2 0 11/15/2002

Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND'REACTOR CORE ISOLATIONSYSTEM ECCS - SHUTDOWN

TEXT 3.5.3 1 04/18/2005

Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATIONSYSTEM RCIC SYSTEM

TEXT 3.6.1.1 0 11/15/2002

Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT

COOLING (RCIC)

COOLING (RCIC)

COOLING (RCIC)


SSES MIR.!ANUAL

Manual Name: TSB!-

Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1I MANUAL

TEXT 3.6.1.2 0 11/15/2002,

Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK

TEXT 3.6.1.3 3 12/08/2005

Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS).

TEXT 3.6.1.4 0 11/15/2002

Title: CONTAINMENT SYSTEMS CONTAINMENT PRESSURE

TEXT 3.6.1.5 .1 10/05/2005

Title: CONTAINMENT SYSTEMS DRYWELL AIR TEMPEFRTURE

TEXT 3.6.1.6 0 11/15/2002

Title: CONTAINMENT SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS

TEXT 3.6.2.1 0 11/15/2002

~,Title: CONTAINMENT SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE

TEXT 3.6.2.2 0 11/15/2002

Title: CONTAINMENT SYSTEMS SUPPRESSION POOL WATER LEVEL

TEXT 3.6.2.3 1 01/16/2006

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 2 06/13/2006

Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS

TEXT 3.6.3.2 1 04/18/2005

Title: CONTAINMENT SYSTEMS DRYWELL.AIR FLOW SYSTEM

TEXT 3.6.3.3 0 11/15/2002

Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION


SSES *FAIUAL

Manual Name: TSBI-

Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1,MANUAL

TEXT 3.6.4.1 6 08/08/2006

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 3 10/24/2005

Title: CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEM

TEXT 3.7.1

Title: PLANT

ULTIMA

TEXT 3.7.2

Title: PLANT

TEXT 3.7.3

Title: PLANT

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 11/15/2002

SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THE

.TE HEAT SINK (UHS)

1 11/09/2004

SYSTEMS EMERGENCT.-SERVICE WATER (ESW) SYSTEM

0 11/15/20.02

SYSTEMS CONTROL'ROOM EM.ERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM

0 11/15/2002

SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM

0 11/15/2002

SYSTEMS MAIN.-CONDENSER OFFGAS -

1 01/17/2005

SYSTEMS MAIN TURBINE BYPASS SYSTEM

0 11/15/2002

SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL'

4 04/18/2006

Title: ELECTRICAL POWER SYSTEMS AC SOURCES - OPERATING

TEXT 3.8.2 0 11/15/2002

Title: ELECTRICAL POWER SYSTEMS AC SOURCES - SHUTDOWN

Pe 6 of 8R otDe 0/ 0Paq Report Date: 08/08/06

AS SES ,"..MIWAL

.4Manual Name : TSBT-

Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1.MANUAL

TEXT 3.8.3

Title: ELECTRICAL

TEXT 3.8.4

Title: ELECTRICAL

TEXT 3.8.5

Title: ELECTRICAL

TEXT 3.8.6

Title: ELECTRICAL

TEXT 3.8.7

Title: ELECTRICAL

TEXT 3.8.8

J Title: ELECTRICAL

TEXT 3.9.1

Title: REFUELING C

TEXT 3.9.2

Title: REFUELING C

TEXT 3.9.3

Title: REFUELING C

TEXT 3.9.4

Title: REFUELING C

TEXT 3.9.5

Title: REFUELING C

TEXT 3.9.6

Title: REFUELING C

0 11/15/2002

POWER SYSTEMS DIESEL FUEL OIL, LUBE OIL,.AND STARTINGAIR

1

POWER SYSTEMS

0

POWER SYSTEMS

06/13/2006

DC-SOURCES - OPERATING

11/15/2002

DC SOURCES - SHUTDO11N'-*1"

.0 11/15/2002

POWER SYSTEMS BATTERY CELL PARAMETERS, -

1 10/05/2005

POWER SYSTEMS DISTRIBUrION"SYSTE14S', OPERATING

0

POWER SYSTEMS

11/15/2002 -.

DISTRIBUTION'SYSTEMS -:SHUTDOWN':.,

)PERATIONS

)PERATIONS

)PERATIONS

)PERATIONS

)PERATIONS

)PERATIONS

0 11/15/2002

REFUELING EQUIPMENT INTERLOCKS

0 11/15/2002 -

REFUEL POSITION ONELROD-OtLrý'INTERLOCK

0 11/15/2002

CONTROL ROD:POSITION

0 11/15/2002

CONTROL ROD.POSITIONvINDICATION "

0 11/15/2002

CONTROL'ROD.OPERABILITY - REFUELING

0 11/15/2002

REACTOR PRESSURE VESSEL (RPV) WATER`:LEVEL.


Page 7 .of 8 Report Date: 08/08/06

SSES MANUAL

Manual Name : TSBt-


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

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

0 11/15/2002.

INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION

.0 11/15/2002"

REACTOR MODE SWITCH INTERLOCK TESTING

0 11/15/2002

SINGLE CONTROL ROD WITHPRAWAL - HOT SHUTDOWN

0 11/15/2002-

SINGLE CONTROL ROD WITHDRAWAL - COLD SHUTDOWN

0 11/15/2002

SINGLE CONTROL ROD DRIVE (CRD) REMOVAL - REFUELING

0 11/15/2002

MULTIPLE CONTROL ROD WITHDRAWAL - REFUELING

OPERATIONS Q~

OPERATIONS

OPERATIONS

1 04/18/2006';

OPERATIONS CONTROL ROD TESTING - OPERATING

1 04/12/2006

OPERATIONS SHUTDOWN MARGIN (SDM) TEST - REFUELING

Page 8 ;~f>8., Report Date:. 08/08/06

Page 8 Rep6rt'D&te:.08/08/06

SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision

TOC

B 2.0

B 3.0

Table of Contents 10

B 3.1

B 3.2

SAFETY LIMITS BASES- Page B 2.0-1

Page TS / B 2.0-2Page TS / B 2.0-3Pages TS / B 2.0-4 and TS / B 2.0-5Page TS / B 2.0-6Pages B 2.0-7 through B 2.0-9

LCO AND SR APPLICABILITY BASESPages B 3.0-1 through B 3.0-4Pages TS / B 3.0-5 through TS / B 3.0-7Pages TS / B 3.0-8 through TS I B 3.0-9Pages TS / B 3.0-10 through TS / B 3.0-12Pages TS / B 3.0-13 through TS / B 3.0-15Pages TS / B 3.0-16 and TS / B 3.0-17

REACTIVITY CONTROL BASESPages B 3.1-1 through B 3.1-4Page TS / B 3.1-5Pages TS / B 3.1-6 and TS/IB 3.1-7.Pages B 3.1-8 through B 3.1-13Page TS / B 3.1-14 -

Pages B 3.1-15 through B 3.1-22Page TS / B 3.1-23Pages B 3.1-24 through B 3.1-27Page TS / B 3.1-28Page TS / B 3.1-29Pages B 3.1-30 through B 3.1-33Pages TS / B 3.3-34 through TS / B 3.3-36Pages TS / B 3.1-37 and TS / B 3.1-38Pages B 3.1-39 through B 3.1-44Page TS / B 3.1-45Pages B 3.1-46 and B 3.1-47Pages TS / B 3.1-48 and TS / B 3.1-49Page B 3.1-50Page TS / B 3.1-51

POWER DISTRIBUTION LIMITS BASESPage TS / B 3.2-1Pages TS / B 3.2-2 through TS / B 3.2-6

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SUSQUEHANNA STEAM ELECTRIC STATIONUST OF EFFECTIVE.SECTIONS (TECHNICAL SPECIFICATIONS BASES) .'

Section Title

Page B 3.2-7Pages TS / B 3.2-8 and TS I B 3.2-9Page TS / B 3.2.10Page TS / B 3.2-11Page B 3.2-12Page TS / B 3.2-13Pages B 3.2-14 and B 3.2-15Page TS / B 3.2-16Page B 3.2-17Page TS / B 3.2-18

*Page TS / B 3.2-19

Revision ,

021

2020201

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B 3.3 INSTRUMENTATIONPages TS / B 3.3-1 through TS I B 3.3-4Page TS / B 3.3-5Page TS / B 3.3-6Page TS / B 3.3-7Page TS / B 3.3-7aPages TS / B 3.3-8 through TS / B 3.3-12Pages TS / B 3.3-12a through TS I B 3.3-12cPage TS / B 3.3-13

* Page TS / B 3.3-14Pages TS / B 3.3-15 and TS / B 3.3-16Pages TS / B 3.3-17 and.TS / B 3.3-18.Page TS / B 3.3-19Pages TS / B 3.3-20 through TS I B 3.3-22Page TS / B 3.3-22a -

Pages TS / B 3.3-23 and TS / B 3.3-24Pages TS / B 3.3-24a and TS / B 3.3-24bPages TS / B 3.3-25 and TS / B 3.3-26Page TS / B 3.3-27Pages TS / B 3.3-28 throuigh TS I B 3.3-30Page TS / B 3.3-30a - -

Page TS / B 3.3-31Page TS / B 3.3-32Pages TS / B 3.3-32a and TS I B 3.3-32bPage TS I B 3.3-33Page TS / B 3.3-33aPage TS / B 3.3-34Pages TS / B 3.3-35 and TS / B 3.3-36Pages TS / B 3.3-37 through TS / B 3.3-43 !Page TS / B 3.3-44

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


Pages TS / B 3.3-45 through TS I B 3.3-49 ,, 2Page TS / B 3.3-50 3Page TS / B 3.3-51 2Pages TS / B 3.3-52 and TS/ B 3.3-53 -1- IPage TS / B 3.3-54 3Pages B 3.3-55 through B 3.3-63 0Pages TS / B 3.3-64 and TS I B 3.3-65 2Page TS / B 3.3-66 4Page TS / B 3.3-67 3Page TS / B 3.3-68 4Page TS / B 3.3-69 5Pages TS / B 3.3-70 and TS / B 3.3-71 3Pages TS / B 3.3-72 and TS / B 3.3-73 . .2

Page TS / B 3.3-74 3PageTS/B3.3-75 2Page TS / B 3.3-75a 5Page TS / B 3.3-75b 6Page TS / B 3.3-75c 4Pages B 3.3-76 through 3.3-77 - . 0PageTS/B 3.3-78 . • :, . IPages B 3.3-79 through B 3.3-89 , 0Page TS / B 3.3-90 -Page B 3.3-91. . . •.. •.."....- 0Pages TS /B3.3-92 through TS/ B 3.3-100 1Pages B 3.3-101 through B 3.3-103 0Page TS / B 3.3-104 1. -.

Pages B 3.3-105 and B 3.3-106 0PageTS/B3.3-107 1Page B 3.3-108 0PageTS/B3.3-109 1Pages B 3.3-110 and B 3.3-111 0Pages TS / B 3.3-112 and TS /.B 33-112a - IPagesTS/B3.3-113throughTSIB3.3-115 ... " 1PageTS/B3.3-116 .. 2Page TS / B 3.3-117 - I .1 IPages B 3.3-118 through B13.3-122 0Pages TS / B 3.3-123 and TS I B 3.3-124 1Page TS / B 3.3-124a 0Page B 3.3-125 0Pages TS / B 3.3-126 and TS B 3;3-127 1Pages B 3.3-128 through B 3.3-130 .. 0Page TS / B 3.3-131 1Pages B 3.3-132 through B 3.3-137 i 0

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Section Title

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Pages TS / B 3.3-189 through TS / B 3.3-191,Pages B 3.3-192 through B 3.3-204Page TS / B 3.3-205Pages B 3.3-206 through B 3.3-219

Revision,

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B 3.4 REACTOR COOLANT SYSTEM BASES,'--Pages B 3.4-1 and B 3.4-2Pages TS / B 3.4-3 and Page TS / B 3.4-4Pages TS / B 3.4-5 through TS7 B 3.4-9,..pages B 3.4-10 through B 3.4-14Page TS / B 3.4-15 " :PagesTS / B 3.4-16 through TS / B 3.4-18Pages B 3.4-19 through B 3.4-27Pages TS / B 3.4-28 and TS / B 3.4-29Pages B 3.4-30 and B 3.4-31 -Page TS / B 3.4-32Pages B 3.4-33 through B 3.4-36Page TS / B 3.4-37Pages B 3.4-38 through B 3.4-40".Page TS / B 3.4-41Pages B 3.4-42 through B 3.4-48Page TS / B 3.4-49Page TS I B 3.4-50Page TS / B 3.4-51Page TS / B 3.4-52 *-

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SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section, Title Revision

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TSB1 text LOES7113M06

SUSQUEHANNA - UNIT 1 TS.i B.LOES-7 ". " Revon76

PPL Rev. 6Secondary Containment

B 3.6.4.1

B 3.6 CONTAINMENT SYSTEMS

B 3.6.4.1 Secondary Containment

BASES

BACKGROUND The secondary containment structure completely encloses the primarycontainment structure such that a dual-containment design is utilized tolimit the spread of radioactivity to the environment to within limits. Thefunction of the secondary containment is to contain, dilute, and hold upfission products that may leak from primary containment into secondarycontainment following a Design Basis Accident (DBA). In conjunction withoperation of the Standby Gas Treatment (SGT) System and closure ofcertain -valves whose lines penetrate the secondary containment, thesecondary containment is designed to reduce the activity level of thefission products prior to release to the environment and to isolate andcontain fission products that are released during certain operations thattake place inside primary containment, when primary containment is notrequired to be OPERABLE, or that take place outside primary containment(Ref. 1)'

I

The secondary containment is a structure that completely encloses theprimary containment and reactor coolant pressure boundary components.This structure forns a control volume that serves to hold up and dilute the

fission products. It is possible for the pressure in the control volume torise relative to the environmental pressure (e.g., due'to pump and motorheat load additions).

The secondary containment boundary consists of the reactor buildingstructure and associated removable walls and panels, hatches, doors,dampers, sealed penetrations and valves. The secondary containment isdivided into Zone I, Zone II and Zone III, each of which must beOPERABLE depending on plant status and the alignment of theseconhdry containment boundary. Specifically, the Unit I secondarycontainment boundary can be modified to exclude Zone II. Similarly, theUnit 2 secondary containment boundary can be modified to excludeZone I.1.1 Secondary containment may consist of only Zone III when inMODE 4 or 5 during CORE ALTERATIONS, or during handling ofirradiated fuel within the Zone III secondary containment boundary.

(continued)

SUSQUEHANNA - UNIT 1 TS / 8 3.6-84 Revision 3


B 3.6.4.1

BASES

BACKGROUND To prevent ground level exfiltration while allowing the secondary(continued) containment to be designed as a conventional structure, the secondary

containment requires support systems to maintain the control volumepressure at less than the external pressure. Requirements for the safetyrelated systems are specified separately in LCO 3.6.4.2, "SecondaryContainment Isolation Valves (SCIVs)," and LCO 3.6.4.3, "Standby GasTreatment (SGT) System." When one or more zones are excluded fromsecondary containment, the specific requirements for support systems willalso change (e.g., required secondary containment isolation valves).

APPLICABLE There are two principal accidents for which credit is taken for secondarySAFETY containment OPERABILITY. These are a loss of coolant accident (LOCA)ANALYSES (Ref. 2) and a fuel handling accident inside secondary containment

(Ref. 3). The secondary containment performs no active function inresponse to either of these limiting events; however, its leak tightness isrequired to ensure that the release of radioactive materials from theprimary containment is restricted to those leakage paths and associatedleakage rates assumed in the accident analysis and that fission productsentrapped within the secondary containment structure will be treated bythe SGT System prior to discharge to the environment.

Secondary containment satisfies Criterion 3 of the NRC Policy Statement(Ref. 4).

LCO An, OPERABLE secondary containment provides a control volume intowhich fission products that bypass or leak from primary containment, orare released from the reactor coolant pressure boundary componentslocated in secondary containment, can be diluted and processed prior torelease to the environment. For the secondary containment to beconsidered OPERABLE, it must have adequate leak tightness to ensurethatfthe required vacuum can be established and maintained. The leaktigh'tness of secondary containment must also ensure that the release ofradioactive materials to the environment is restricted to those leakagepaths and associated leakage rates assumed in the accident analysis. Forexample, secondary 'containment bypass leakage must be restricted to theleakage rate required by LCO 3.6.1.3. The secondary containmentboundary required to be OPERABLE is dependent on the operating statusof both units, as well as the configuration of walls, doors, hatches, SCIVs,and'available flow paths to the SGT System.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.6-85 Revision 2


B 3.6.4.1

BASES (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 sameoperating 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 in MODE 4 or 5 to ensure a control voluine, except for othersituations for which significant releases of radioactive material can bepostulated, such as during operations with a potential for draining thereactor vessel (OPDRVs), during CORE ALTERATIONS, or duringmovement of irradiated fuel assemblies in the secondary containment.

ACTIONS A.1

If secondary containment is inoperable, it must be restored to OPERABLEstatus within 4 hours. The 4 hour Completion Time provides a period oftime to 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 (requiringsecondary contaihment OPERABILITY) occurring during periods wheresecondary containment is inoperable is minimal.

A temporary (one-time) Completion Time is connected to the CompletionTime Requirements above (4 hours) with an "OR" connector. TheTemporary Completion Time is 48 hours and applies to the replacement ofthe Reactor Building Recirculating Fan Damper Motors. The TemporaryCompletion Time of 48 hours may only be used once, and expires onDecember 31, 2005.

B.1 and B.2

If secondary containment cannot be restored to OPERABLE status withinthe required Completion Time, the plant must be brought to a MODE inwhich the LCO does not apply. To achieve this status, the plant must bebrought to at least MODE 3 within 12 hours and to MODE 4 within36 hours. The allowed Completion Times are reasonable, based onoperating experience, to reach the required plant conditions from fullpower conditions in an orderly manner and without challenging plantsystems.

(continued)



B 3.6.4.1

BASES

ACTIONS 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, thesecondary containment is the only barrier to release of fission products tothe environment. CORE ALTERATIONS and movement of irradiated fuelassemblies must be immediately suspended if the secondary containmentis inoperable.

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 fuelassemblies while in MODE 1, 2, or 3, the fuel movement is independent ofreactor operations. Therefore, in either case, inability to suspendmovement of irradiated fuel assemblies would not be a sufficient reason torequire a reactor thutdown.

SURVEILLANCE SR 3.6.4.1.1REQUIREMENTS

This SR ensures that the secondary containment boundary issufficiently leak tight to preclude exfiltration under expected windconditions.! i Expected wind conditions are defined as sustained windspeeds of less than 6r equal to 16 mph at the 60m meteorologicaltower or less than orqequal to 11 mph at the lOm meteorological towerif the 60m tower wind speed is not available. Changes in indicatedreactor building differential pressure observed during periods of short-term wind speed gusts above these sustained speeds do not bythemselves impact secondary containment integrity. H6wever, ifsecondary containment integrity is known to be compromised, the LCOmust be entered regardless of wind speed.

(continued)



B 3.6.4.1

BASES

SURVEILLANCEREQUIREMENTS

SR 3.6.4.1.1 (continued)

The 24 hour Frequency of this SR was developed based on operatingexperience related to secondary containment vacuum variations during theapplicable MODES and the low probability of a DBA occurring betweensurveillances.

Furthermore, the 24 hour Frequency is considered adequate in view ofother indications available in the control room, including alarms, to alertthe operator 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 one

door in each access opening to secondary containment zones is closed.In some cases (e.g., railroad bay), secondary containment accessopenings are shared such that a secondary containment barrier may havemultiple inner or multiple outer doors. The intent is to maintain thesecondary containment barrier intact, which is achieved by maintainingthe inner or outer portion of the barrier closed at all times. However, allsecondary containment access doors are normally kept closed, exceptwhen the access opening is being used forentry and exit or whenmaintenance is being performed on an access opening.

When the railroad bay door (No. 101) is closed; all Zone land III hatches,removable walls, dampers, and one door in each access openingconnected to the railroad access bay are closed; or, only Zone Iremovable walls and/or" doors are open to the railroad access shaft; or,only Zone III hatches and/or dampers are open to the railroad accessshaft. When the railroad bay door (No. 101) is open; all Zone I and IIIhatches, removable walls, dampers, and one door in each access openingconnected to the railroad access bay are closed. The truck bay hatch isclosed and the truck bay door (No. 102) is closed unless Zone II is isolatedfrom Zones I and III.

(continued)

I

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B 3.6.4.1

BASES


SR 3.6.4.1.2 and SR 3.6.4.1.3 (continued)

When an access opening between required secondary containment zonesis being used for exit and entry, then at least one door (where two doorsare provided) must remain closed. The access openings betweensecondary containment zones which are not provided with two doors areadministratively controlled to maintain secondary containment integrityduring exit and entry. This Surveillance is modified by a Note that allowsaccess openings with a single door (i.e., no airlock) within the secondarycontainment boundary (i.e., between required secondary containmentzones) to be opened for entry and exit. Opening of an access door forentry and exit allows sufficient'administrative control by individualpersonnel making the entries and exits to assure the secondarycontainment function is not degraded. When one of the zones is not azone recquired for secondary containment OPERABILITY, the Noteallowance would not apply.

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 theoperator.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.6-88a Revision 2


B 3.6.4.1

BASES


(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 containmentthat is less than the pressure external to the secondary containmentboundary. This is confirmed by demonstrating that one SGT subsystemwill draw down the secondary containment to > 0.25 inches of vacuumwater gauge in less than or equal to the maximum time allowed. Thiscannot be accomplished if the secondary containment boundary is notintact. SR 3.6.4.1.5 demonstrates that one SGT subsystem can maintain_> 0.25 inches of vacuum water gauge for at least 1 hour at less than or

equal to the maximum flow rate permitted for the secondary containmentconfiguration that is operable. The 1 hour test period allows secondarycontainment to be in thermal equilibrium at steady state conditions. Asnoted, both SR 3.6.4.1.4 and SR 3.6.4.1.5 acceptance limits aredependent upon the secondary containment configuration when testing isbeing performed. The acceptance criteria for the SRs based onsecondary containment configuration is defined as 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)

Zones I, II and III. 5 125 Seconds •4000 CFM(Zones I, II, and III) (From Zones I, II, and III)

Zones I and III. - 117 Seconds •2885 CFM(Zones I and III) (From Zones I and III)

(continued)

I



B 3.6.4.1

BASES


SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)

Only one of the above listed configurations needs to be tested to confirmsecondary containment OPERABILITY.

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 configurationis tested every 60 months. The 60 month Frequency is acceptablebecause operating experience has shown that these components usuallypass the Surveillance and all active components are tested morefrequently. Therefore, these tests are used to ensure secondarycontainment boundary integrity.

Since these SRs are secondary containment tests, they need not beperformed with each SGT subsystem. The SGT subsystems are tested ona STAGGERED TEST BASIS, however, to ensure that in addition to therequirements of LCO 3.6.4.3, either SGT subsystem will perform SR3.6.4.1.4 and SR 3.6.4.1.5. Operating experience has shown thesecomponents usually pass the Surveillance when performed at the24 month Frequency. Therefore, the Frequency was concluded to beacceptable from a 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 F R 39132).

SUSQUEHANNA-UNIT 1 TS / B 3.6-90 Revision 2

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