ML050110114

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Technical Specification Bases Unit 1 Manual
ML050110114
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Site: Susquehanna Talen Energy icon.png
Issue date: 01/04/2005
From:
Susquehanna
To:
Document Control Desk, Office of Nuclear Reactor Regulation
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Text

Jan. 04, 2005 Page 1 of 1 yMANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2005-444 USER INFORMATI

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Nam GERLACH OSE M EMPL#:028401 CA#:0363 Address:

2 Phone#:

4-3 TRANSMITTAL INFORMATION:

TO:

Gik 01/04/2005 LOCATION: m SNRC FROM:

NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)

THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:

TSB1 -

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 12/23/2004 si)D MANUAL TABLE OF CONTENTS DATE: 01/03/2005 KJTEGORY: DOCUMENTS TYPE: TSB1 ID:

TEXT 3.6.4.1 REMOVE:

REV:0 ADD:

REV: 1 CATEGORY:

DOCUMENTS TYPE: TSB1 ID:

TEXT 3.6.4.2 REMOVE:

REV:1 ADD:

REV: 2 CATEGORY: DOCUMENTS TYPE: TSB1 ID:

TEXT LOES REMOVE:

REV:53 ADD:

REV: 54 UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES.

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i;

>40

SSES MANUAL Manual Name: TSB12 anual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date:

01/03/2005 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 54 01/03/2005

Title:

LIST OF EFFECTIVE SECTIONS TEXT TOC 5

11/22/2004

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 N

Title:

SAFETY LIMITS (SLS)

REACTOR COOLANT SYSTEM (RCS)

PRESSURE SL 0

02N Title LIITN CONDITION.FO TEXT 3.0 0

11/15 2002 1

Title:

LIMITING CONDITION FOR OPERATION (L O)APPLICABILITY TEXT 3.1.1 0

  • . 11f/15/2002

Title:

REACTIVITY CONTROL SYSTEMSsSHUTDOWN MARGIN (SDM)

TEXT 3.1.2 k

-0 11/15/2002

Title:

REACTIVITY CONTROL SYSTEMS REACTIVITY ANOMALIES TEXT 3.1.3 0

11/15/2002

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD OPERABILITY TEXT 3.1.4 0

11/15/2002

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD;SCRAM TIMES TEXT 3.1.5 0

11/15/2002

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD-SCRAM ACCUMULATORS TEXT 3.1.6

.0 11/15/2002

Title:

REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL Pagel.

of 8

Report Date: 01/03/05 Pagel 1

  • of 8---

Report Date: 01/03/05

I

-ID 1

-- In-SSES MANUAL Manual Name: TSB1 Y.

Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL, TEXT 3.1.7 0

11/15/2002

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 (APLHGR)

TEXT 3.2.2 0

11/15/2002

Title:

POWER DISTRIBUTION LIMITS.MINIMUM CRITICAL POWER RATIO (MCPR)

TEXT 3.2.3 0

11/15/2002

Title:

POWER DISTRIBUTION LIMITS LINEAR HEAT GF.NERATION.RATE (LHGR)

TEXT 3.2.4 0

11/15/2002.

Title:

POWER DISTRIBUTION LIMITS AVERAGE POWER RANGE MONITOR (APR1)

GAIN AND SETPOINTS' X

TEXT 3.3.1.1 0

11/15/2002

Title:

INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2

Title:

INSTRUMENTATION 0 0 11/15/2002 -

SOURCE RANGE MONITOR (SRM)

INSTRUIMENTATION TEXT 3.3.2.1 0

11/15/2002'

Title:

INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 0

.11/15/2002.-

Title:

INSTRUMENTATION FEEDWATER -

MAIN TURBINE HIGH MATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 0

11/15/2002

Title:

INSTRUMENTATION POST ACCIDENT MONITORING (PAM)

INSrRUMENTATION LDCN 3702 TEXT 3.3.3.2 0

11/15/2002

Title:

INSTRUMENTATION REMOTE SHUTDOWN SYSTEM age Page 2 of 8 Report Date: 01/03/05

SSESJ NAWUAL Manual Name:

TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL, 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'TRA'NSIN'T WITHOUT.:SCRAM RECIRCuLATION-PUMP TRIP' (ATWS-RPT) INSTRUMENTATION' TEXT 3.3.5.1 0

11/15/2002

Title:

INSTRUMENTATION-EMERGENCY. CORE COOLING.SYSTEM

(ECCS) INSTRUMENTATION' TEXT 3.3.5.2 0

11/15/2002

Title:

INSTRUMENTATION REACTOR CORE ISOLATION COOLING '(RCIC) SYSTEM INSTRUMENTATION TEXT 3.3.6.1 1

11/09/2004

Title:

INSTRUMENTATION PRIMARY !CONTAINMENT ISOLATIONINSTRUMENTATION TEXT 3.3.6.2 1

11/09/2004'.

Title:

INSTRUMENTATION SECONDARY CONTAIXMENT ISOLATION INSTRUMENTATION TEXT 3.3.7.1 0

11/15/2002

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

11/1512002

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

11/15/2002

Title:

REACTOR COOLANT SYSTEM-(RCS).-JET PUMPS

' l '.'.

TEXT 3.4.3 0

11/15/2002i

Title:

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

Page3 of 8 Report Date: 01/03/05 Page 3

-of. 8 Report Date: 01/03/05-

SSES MANUAL Manual Name:

TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.4.4

Title:

REACTOR TEXT 3.4.5

Title:

REACTOR 0

11/15/2002 COOLANT SYSTEM (RCS). RCS OPERATIONAL'LEAKAGE 0

11/15/2002:.'.'

COOLANT SYSTEMA(RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE TEXT 3.4.6

Title:

REACTOR COOLANT TEXT 3.4.7

Title:

REACTOR COOLANT TEXT 3.4.8

Title:

REACTOR COOLANT HOT SHUTDOWN TEXT 3.4.9

Title:

REACTOR COOLANT COLD SHUTDOWN TEXT 3.4.10

Title:

REACTOR COOLANT TEXT 3.4.11

Title:

REACTOR COOLANT 0

11/15/2002: -

SYSTEM (RCS) RCS LEAKAGE, DETECTION INSTRUMENTATION 0

11/15/2002Z SYSTEM (RCS)'RCS SPECIFIC: ACTIVITY 0

11/15,20021 SYSTEM (RCS)

RESIDUAL HEAT' REMOVAL (RHR)

SHUTDOWN COOL:

0 11/15/2002 SYSTEM (RCS).'RESIDUAL HEAT:REMOrVAL (RHR) SHUTDOWN COOL:

0 11/15/2002.

SYSTEM (RCS) RCS PRESSURE 'AND.TEMPERATURE:(P/T) LIMITS 0

11/15/2002:

SYSTEM (RCS) REACTOR STEAM DOME PRESSURE rNG SYSTEM rNG SYSTEM-.--

TEXT 3.5.1 0

11/15/2002

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOiI CORE 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 0

11/15/2002

Title:

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

SYSTEM RCIC SYSTEM TEXT 3.6.1.1 0

11/15/2002

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT We 4 of 8 Report Date: 01/03/05 Pag

SSES MANUAL

,Manual Name:

TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL' TEXT 3.6.1.2

Title:

CONTAINMENT TEXT 3.6.1.3

Title:

CONTAINMENT 0

11/15/2002 SYSTEMS PRIMARY COiITAINMENTVAIR LOCK 0

11/15/2002:

SYSTEMS PRIMARY.CONTAhI1JNT ISOLATION VALVES (PCIVS)

LDCN 3092 TEXT 3.6.1.4

Title:

CONTAINMENT 0

11/15/2002 SYSTEMS CONTAINMENT*,PRESSURE C:. -

TEXT 3.6.1.5

Title:

CONTAINMENT TEXT 3.6.1.6

Title:

CONTAINMENT TEXT 3.6.2.1

Title:

CONTAINMENT 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 TEXT 3.6.3.3

Title:

CONTAINMENT 0

11/15/2002 SYSTEMS DRYWELL. AIR TEMPERATURE 0

11/15/2002 SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM-BREAKERS.'.

0 11/15/2002,'

,SYSTEMS SUPPRESSION:.POOL AVERAGE TEMPERATURE 0

11/15/2002 SYSTEMS SUPPRESSION POOL WATER LEVEL 0

11/15/2002 SYSTEMSRESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING 0

li/15/2002 SYSTEMS. RESIDUAL HEAT:REMOVAL.(RHR)

SUPPRESSION POOL SPRAY 0

11/15/2002 SYSTEMS. PRIMARY-CONTAINMENT HYDROGEN RECOMBINERS 0

11/15/2002 SYSTEMS-DRYWELL"AIR.FLOW SYSTEM '

0

.11/15/2002' SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION Pages of

8.

Report Date: 01/03/05 Page 5 of 8,,.

Report-Date: 01/03/05

SSES MANUAL Manual Name:

TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.4.1 1

01/03/2005

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT TEXT 3.6.4.2 2

01/03/2005.

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMLENT.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 SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW)

SYSTEM AND THE ULTIMATE HEAT SINK (UHS)

TEXT 3.7.2 1

11/09/2004

Title:

PLANT SYSTEMS EMERGENCY SERVICE WATER (ESW)

SYSTEM 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 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)

SYSTEM 0

11/15/2002 SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM.'

0 11/15/2002 SYSTEMS.MAIN CONDENSER OFFGAS 0

11/15/2002 SYSTEMS MAIN TURBINE BYPASS SYSTEM 0

11/15/2002 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL 1

10/17/2003

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES -

OPERATING" TEXT 3.8.2 0

11/15/2002

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES -

SHUTDOWN T

Page 6 of 8 R

Report Date: 01/03/05

4

-SSES IANUAL Manual Name:

TSB1 Manual

Title:

TECHNICAL SPECIFICATION.BASESUNIT 1'MANUAL' -

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-z'OPERATING TEXT 3.8.5 0

11/15/2002

Title:

ELECTRICAL POWER SYSTEMS DC SOURCES.

SHUTDOWN A.

X::

TEXT 3.8.6 0

11f15/2002---

Title:

ELECTRICAL POWER SYSTEMS.BATTERYzCELL PARAMETERS TEXT 3.8.7 0

11/15/2002

Title:

ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS'-'OPERATING TEXT 3.8.8 0

11/15/2002 K

Title:

ELECTRICAL POWER. SYSTEMS.DISTRIBUTION SYSTEMS'-

SHUTDOWN.

TEXT 3.9.1 0

11/15/2002

Title:

REFUELING OPERATIONS REFUELING EQUIPNENT INTERLOCKS TEXT 3.9.2 0

11/15/2002

Title:

REFUELING, OPERATIONS REFUEL POSITION: ONE-ROD-OUT INTERLOCK-TEXT 3.9.3

Title:

REFUELING TEXT 3.9.4

Title:

REFUELING TEXT 3.9.5

Title:

REFUELING OPERATIONS OPERATIONS OPERATIONS 0

l1/15/2002 CONTROLROD;POSITION.

0 11/15/2002 CONTROL;ROD POSITION INDICATION'.:;- :

0 11/15/2002 CONTROL ROD OPERABILITY REFUELING TEXT 3.9.6

Title:

REFUELING 0

11/15/2002 OPERATIONS REACTOR PRESSURE VESSEL (RPV)

WATER LEVEL Page7 of 8 Report Date: 01/03/05 Page 7

. of 8 Report Date: 01/03/05

SSES MANUAL Manual Name: TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.9.7 0

11/15/2002

Title:

REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -

HIGH WATER LEVEL I.

TEXT 3.9.8 0

11/15/2002

Title:

REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RMR)

LOW WATER LEVEL TEXT 3.10.1

Title:

SPECIAL TEXT 3.10.2

Title:

SPECIAL TEXT 3.10.3

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 WITHDRAWAL -

HOT.SHUTDOWN TEXT 3.10.4

Title:

SPECIAL 0

11/15/2002..

SINGLE CONTROL ROD WITHDPAW'AL I

OPERATIONS COLD-SHUTDOWN TEXT 3.10.5

Title:

SPECIAL TEXT 3.10.6

Title:

SPECIAL 0

SINGLE 11/15/2002 C O R D D I R

CONTROL ROD DRIVE (CRD) REMOVAL - REFUELING OPERATIONS OPERATIONS 0

11/15/2002 MULTIPLE CONTROL ROD WITHDRAWAL -

REFUELING TEXT 3.10.7

Title:

SPECIAL TEXT 3.10.8

Title:

SPECIAL OPERATIONS OPERATIONS 0

11/15/2002.

CONTROL ROD TESTING -

0 11/15/2002 SHUTDOWN MARGIN (SDM)

OPERATINC TEST -

REFUELING Page8 of 8 Report Date: 01/03/05 Page 8 of 8 Report Date: 01/03/05

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

Section Title TOC Table of Contents B 2.0 SAFETY LIMiTS BASES Page B 2.0 Page TS /B 2.0-2 ~,.:-- -

Page TS /B32.0-3 Pages TS/ B 2.0-4 and TS] B 2.0-5 PageTS/B2.0-6 Pages B 2.0-7 through B 2.0-9 ',

r B 3.0 LCO AND SR APPLICABILITY BASES Pages B 3.0-1 through B3.0-7 1

A,

  • Pages TS/ B 3.0-8 and TS B,3.0-9

-/

Pages B 3.0-10 through B 3.0-12

/

Pages TS / B 3.0-13 through TS / B 3.0-15 B 3.1 REACTIVITY CONTROL:BASES-Pages B 3.1-1 through B 3.1-5,6 Pages TS / B 3.1-6 and TS B 3.1 Pages B 3.1-8 throughB3:1-27 Pages TS/ B,3;1-28 "

J/_

Pages B 3.1-29 through B 3.1-36 r

Pages TS / B 3.1-37

\\ \\I Pages B 3.1-38,ttiBughB 3.1-51.,

B 3.2 POWER DISTRIBUTION LIMITS BASES Page TS fB 3.2-11 Page TSI/ B 3 2-2

-Page TS / B3.--;"'-

Pag6 TS /B 3.2-4 pagesTS 1 B 3.2-5 and TS/ B'3.2 Page B 3.2-7, ages TS / B 3.2-8 through TS I B 3.2-10 Page TS / B 3.2-11,

Page B 3.2-12 PageTS I B 3.2-13 Pages B 3.2-14 and B 3.2-15 Page TS/B3.2-16 Pages B 3.2-17 and B 3.2-18 Page TS/B3.2-19 Revision

,5 0

2 3

2 0

0 1

1

.0 0

.0 1.

2 2

1-0 1

2 2

2 0

2 B 3.3 INSTRUMENTATION Pages TS / B 3.3-1 through TS I B 3.3-10 Page TS / B 3.3 Pages TS / B 3.3-12 through TS I B 3.3-27 Pages TS / B 3.3-28 through TS / B 3.3-31.

Pages TS / B 3.3-32 and TS I B 3:3-33

.kJ..-.

I 2

1 2

3.

.s SUSQUEHANNA - UNIT I TSIBLOES-1 Revision 54 SUSQUEHANNA - UNIT 1 TS / B LOES-1 Revision 54

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

Section Title Revision Pages TS / B 3.3-34 through TS / B 3.3-43 1

Pages TS / B 3.3-43a through TS / B 3.3-43i 0

Pages TS / B 3.3-44 through TS / B 3.3-54 1

Pages B 3.3-55 through' B 3.3-63 0

Pages TS / B 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

Pages TS / B.3.3-71 through TS. B 3.3-75 2

Page TS / B 3.3-75a 4

Pages TS / B 3.3-75b through TS / B 3.3-75c 3

Pages B 3.3-76 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 3.3-1 00 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 TSI B 3.3-109 1

Pages B 3.3-110 and B 3.3-111 0

Pages TS I B 3.3-112 and TS / B 3.3-112a I

Pages B 3.3-113 and B 3.3-114 0

Page TS/ B 3.3-115 1

Page TS / B 3.3-116 2

PageTS/B3.3-117 1

Pages B 3.3-118 through B 3.3-122 0

Pages TS / B 3.3-123 through TS I B 3.3-124 1

Page TS / B 3.3-124a 0

Pages B 3.3-125 and B 3.3-126 0'

Page TS / B 3.3-127 1

Pages B 3.3-128 through B 3.3-130 0

Page TS / B 3.3-131 1

Pages B 3.3-132 through B 3.3-137 0

Page TS / B 3.3-138 1

Pages B 3.3-139 through B 3.3-149 0

Page TS / B 3.3-150 through TS / B 3.3-162 1

Page TS / B 3.3-163 2

Pages TS / B 3.3-164 through TS / B 3.3-177 1

Pages TS / B 3.3-178 and TS I 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 0

Page TS / B 3.3-180 1

Page TS / B 3.3-181 2

SUSQUEHANNA

- UNIT I TS/B LOES-2 Revision 54 SUSQUEHANNA - UNIT 1 TS / B LOES-2 Revision 54

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

Section Title.

Revision Pages TS / B 3.3-182 through TS / B 3.3-186 1

Pages TS B 3.3-187 and TS / B 3.3-188 2

Pages TS / B 3.3-189 through TS / B 3.3-191 1

Pages B 3.3-192 through B 3.3-204 0

Page TS / B 3.3-205 1

Pages B 3.3-206 through B 3.3-219 0

B 3.4 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 and B 3.4-2 0

Page TS / B 3.4-3 and Page TS / B 3.4-4 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

PageTS/B3.4-18 1

Pages B 3.4-19 through B 3.4-28 0

Page TS / B 3.4-29 Pages B 3.4-30 through B 3.4-48 0

Page TS/B3.4-49 2

Page TS / B 3.4-50 1

PageTS/B3.4-51 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 3.460 1

B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 0

Page TS/B3.5-3 2

Pages TS / B 3.5-4 and TS /B 3.5-5 1

Pages B 3.5-6 through B 3.5-10 0

Page TS / B 3.5-11 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 1

Pages B 3.5-26 through B 3.5-31 0

B 3.6 CONTAINMENT SYSTEMS BASES Page TS / B 3.6-1 2

Page TS / B 3.6-1 a 3

Pages TS / B 3.6-2 through TS / B 3.6-5 2

Page TS /B 3.6-6 3

Pages TS /B 3.6-6a and TS /B 3.6-6b 2

Page TS / B 3.6-6c 0

SUSQUEHANNA - UNIT I TS/BLOES-3 Revision 54 SUSQUEHANNA - UNIT 1 TS /B LOES-3 Revision 54

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

Section Title 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 B 3.6-16 Page TS / B 3.6-17 Page TS / B 3.6-17a Pages TS/B 3.6-18 and TS/B3.6-19 Page TS / B 3.6-20 Page TS / B 3.6-21 Page TS / B 3.6-22 Page TS / B 3.6-22a Page TS / B 3.6-23 Pages TS / B 3.6-24 through TS B 3.6-25 Page TS/ B 3.6-26 PageTS/B3.6-27 Page TS / B 3.6-28 Page TS / B 3.6-29 Page TS/B 3.6-30 Page TS/B3.6-31 Pages B 3.6-32 through B 3.6-35 Page TS l B 3.6-36 Page B 3.6-37 Page TS/B 3.6-38 Page B 3.6-39 Page TS / B 3.6-40 Pages B 3.6-41 through B 3.6-43 Pages TS / B 3.6-44 through TS / B 3.6-51 Page TS / B 3.6-52 Pages B 3.6-53 through B 3.6-63 PageTS/B3.6-64 Pages B 3.6-65 through B 3.6-83 Page TS / B 3.6-84 Pages TS / B 3.6-85 and TS / B 3.6-86 Pages TS / B 3.6-87 through TS I B 3.6-88a Page TS I B 3.6-89 Page TS / B 3.6-90 Page TS I B 3.6-91 Pages TS / B 3.6-92 through TS I B 3.6-96 Page TS / B 3.6-97 Pages TS / B 3.6-98 and TS / B 3.6-99 Page TS / B 3.6-100 Pages TS / B 3.6-101 and TS / B 3.6-102 Pages TS / B 3.6-103 through TS / B 3.6-105 Pages TS / B 3.6-106 and TS / B 3.6-107 Revision 0

2 0

0 1

0 0

1° 2

1 0

1 0

0 Corrected 2

5 1

1 3

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SUSQUEHANNA-UNIT 1 TS /B LOES-4 Revision 54

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

Section Title Revision B 3.7 PLANT SYSTEMS BASES Pages TS I B 3.7-1 through TS I B 3.7-6 2

Page TS I B 3.7-6a 2

Pages TS l B 3 3.7-6b and TS / B 3.7-6c 0

Page TS/B3.7-7 2

Pages TS I B 3.7-8 through TS 1 B 3.7-11 1

Pages TS I B 3.7-12 and TS l B 3.7-13 1

Pages TS I B 3.7-14 through TS I B 3.7-18 2

Page TS / B 3.7-18a 0

Pages TS I B 3.7-19 through TS I B 3.7-23 1

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Pages TS I B 3.7-27 through TS I B 3.7-29 3

Page TS I B 3.7-30 1

Pages B 3.7-31 through B 3.7-33 0

B 3.8 ELECTRICAL POWER SYSTEMS BASES Pages TS I B 3.8-1 through TS I B 3.8-4 2

PageTS/B3.8-5 3

Pages TS I B 3.8-6 through TSIB 3.8-8 2

Pages TS I B 3.8-9 and TS I B 3.8-10 3

Pages TS I B 3.8-11 and TS I B 3.8-17 2

Page TS / B 3.8-18 3

Pages TS I B 3.8-19 through TS I B 3.8-21 2

Pages TS I B 3.8-22 and TS B 3.8-23 3

Pages TS I B 3.8-24 through TS I B 3.8-37 2

Pages B 3.8-38 through B 3.8-53 0

Pages TS I B 3.8-54 through TS I B 3.8-61 1

Page TS I B 3.8-62 2

Page TS / B 3.8-63 2

Page TS I B 3.8-64 1

Page TS I B 3.8-65 2

Pages TSIB 3.8-66 through B 3.8-90 0

B 3.9 REFUELING OPERATIONS BASES Pages TS I B 3.9-1 and TS I B 3.9-1a 1

Pages TS I B 3.9-2 through TS / B 3.9-4 1

Pages B 3.9-5 through B 3.9-30 0

B 3.10 SPECIAL OPERATIONS BASES Page TS / B 3.10-1 1

Pages B 3.10-2 through B 3.10-31 0

PageTS/B3.10-32 I

Pages B 3.10-33 through B 3.10-37 0

PageTS/B3.10-38 1

TSB1 twd LOES 12/1504 SUSQUEHANNA

- UNIT I TSIB LOES-5 Revision 54 SUSQUEHANNA - UNIT 1 TS / B LOES-5 Revision 54

I l i PPL Rev. 1 Secondary 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 primary containment structure such that a dual-containment design is utlized to limit the spread of radioactivity to the environment to within limits. The function of the secondary containment is to contain, dilute, and hold up fission products that may leak from primary containment into secondary containment following a Design Basis Accident (DBA). In conjunction with operation of the Standby Gas Treatment (SGT) System and closure of certain valves whose lines penetrate the secondary containment, the secondary containment is designed td reduce the activity level of the fission products prior to 'release to the environment and to isolate and contain fission products that are released during certain operations that take place inside primary containment, when primary containment is not required to be OPERABLE, or that take place outside primary containment (Ref. 1).

I The secondary containment is a structure that completely encloses the primary containment and reactor coolant pressure boundary components.

This structure forms a control volume that serves to hold up and dilute the fission products. It is possible for the pressure in the control volume to rise relative to the environmental pressure (e.g., due to pump and motor heat load additions).

The secondary containment boundary consists of the reactor building structure and associated removable walls and panels, hatches, doors, dampers, sealed penetrations and valves. The secondary containment is divided into Zone I, Zone II and Zone l1l, each of which must be OPERABLE depending on plant status and the alignment of the secondary containment boundary. Specifically, the Unit I secondary containment boundary can be modified to exclude Zone II. Similarly, the Unit 2 secondary containment boundary can be modified to exclude Zone I. Secondary containment may consist of only Zone IlIl when in MODE 4 or 5 during CORE ALTERATIONS, or during handling of irradiated fuel within the Zone IlIl secondary containment boundary.

(continued)

I SUSQUEHANNA-UNIT 1 I TS / B3.684 Revision 3

PPL Rev. 1 Secondary Containment 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 volume pressure at less than the external pressure. Requirements for the safety related systems are specified separately in LCO 3.6.4.2, "Secondary Containment Isolation Valves (SCIVs)," and LCO 3.6.4.3, "Standby Gas' Treatment (SGT) System." When one or more zones are excluded from secondary containment, the specific requirements for support systems will also change (e.g., required secondary containment isolation valves).

APPLICABLE There are two principal accidents for which credit is taken for secondary SAFETY 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 in response to either of these limiting events; however, its leak tightness is required to ensure that the release of radioactive materials from the primary containment is restricted to those leakage paths and associated leakage rates assumed in the accident analysis and that fission products entrapped within the secondary containment structure will be treated by the 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 into which fission products that bypass or leak from primary containment, or are released from the reactor coolant pressure boundary components located in secondary containment, can be diluted and processed prior to release to the environment For the secondary containment to be considered OPERABLE, it must have adequate leak tightness to ensure that the required vacuum can be established and maintained. The leak tightness of secondary containment must also ensure that the release of radioactive materials to the environment is restricted to those leakage paths and associated leakage rates assumed in the accident analysis. For example, secondary containment bypass leakage must be restricted to the leakage rate required by LCO 3.6.1.3. The secondary containment boundary required to be OPERABLE is dependent on the operating status of 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 / B3.6-85 Revision 2

PPL Rev. 1 Secondary Containment B 3.6.4.1 BASES

In MODES 4 and 5, the probability and consequences of the LOCA are reduced 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 volume, except for other situations for which significant releases of radioactive material can be postulated, such as during operations with a potential for draining the reactor vessel (OPDRVs), during CORE ALTERATIONS, or during movement of irradiated fuel assemblies in the secondary containment.

ACTIONS A.I If secondary containment is inoperable, it must be restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time provides a period of

(continued)

SUSQUEHANNA - UNIT 1 TS / B3.6-86 Revision 2 6,

.I

PPL Rev. 1 Secondary Containment B 3.6.4.1 BASES ACTIONS B.1 and B.2 (continued)

If secondary containment cannot be restored to OPERABLE status within the required Completion Time, 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 at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

C.1. C.2. and C.3 Movement of irradiated fuel assemblies in the secondary containment, CORE ALTERATIONS, and OPDRVs can be postulated to cause fission product release to the secondary containment. In such cases, the secondary containment is the only barrier to release of fission products to the environment. CORE ALTERATIONS and movement of irradiated fuel assemblies must be immediately suspended if the secondary containment is inoperable.

Suspension of these activities shall not preclude completing an action that involves moving a component to a safe position. Also, action must be immediately initiated to suspend OPDRVs to minimize the probability of a vessel 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 is not applicable. If moving irradiated fuel assemblies while in MODE 4 or 5, LCO 3.0.3 would not specify any action. If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, in either case, inability to suspend movement of irradiated fuel assemblies would not be a sufficient reason to require a reactor shutdown.

SURVEILLANCE SR 3.6.4.1.1 REQUIREMENTS This SR ensures that the secondary containment boundary is sufficiently leak tight to preclude exfiltration.

(continued)

SUSQUEHANNA - UNIT 1 T S / B 3.6-87 Revision 1

PPL Rev. 1 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE SR 3.6.4.1.1 (continued)

REQUIREMENTS The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency of this SR was developed based on operating experience related to secondary containment vacuum variations during the applicable MODES and the low probability of a DBA occurring between surveillances.

Furthermore, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is considered adequate in view of other indications available in the control room, including alarms, to alert the 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 walls and access doors in each access opening required to be closed are closed ensures that the infiltration of outside air of such a magnitude as to prevent maintaining the desired negative pressure does not occur.

When the railroad bay door (No. 101) is closed; all Zone I and IlIl hatches, removable walls, dampers, and doors connected to the railroad access bay are closed; or, only Zone I removable walls and/or doors are open to the railroad access shaft; or, only Zone IlIl hatches and/or dampers are -

open to the railroad access shaft. When the railroad bay door (No. 101) is open; all Zone I and. I hatches, removable walls, dampers, and doors connected to the railroad access bay are closed. The truck bay hatch is closed and the truck bay door (No. 102) is closed unless Zone II is isolated from Zones I and Ill.

Verifying that all such openings are closed provides adequate assurance that exfiltration from the secondary containment will not occur. In this application, the term "sealed" has no connotation of leak tightness.

Maintaining secondary containment OPERABILITY requires verifying each door in each access opening to the secondary containment zones and each access opening between the secondary containment zones is closed.

When an access opening to secondary containment is being used for exit and entry, then at least one door must remain closed.

(continued)

SUSQUEHANNA-UNIT 1 TS / B3.6-88

-Revision 1

PPL Rev. 1 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE REQUIREMENTS SR 3.6.4.1.2 and SR 3.6.4.1.3 (continued)

When an access opening between secondary containment zones is being used for exit and entry, then at least one door (where two doors are provided) must remain closed. The access openings between secondary containment zones which are not provided with two doors are administratively controlled to maintain secondary containment integrity during exit and entry.

The 31 day Frequency for these SRs has been shown to be adequate, based on operating experience, and is considered adequate in view of the other indications of door and hatch status that are available to the operator.

(continued)

SUSQUEHANNA - UNIT I TS / B3.6-88a Revision 1

I..

PPL Rev. 1 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.6.4.1.4 and SR 3.6.4.1.5 The SGT System exhausts the secondary containment atmosphere to the environment through appropriate treatment equipment. To ensure that all fission products are treated, SR 3.6.4.1.4 verifies that the SGT System will rapidly establish and maintain a pressure in the secondary containment that is less than the pressure external to the secondary containment boundary. This is confirmed by demonstrating that one SGT subsystem will draw down the secondary containment to 2 0.25 inches of vacuum water gauge in less than or equal to the maximum time allowed. This cannot be accomplished if the secondary containment boundary is not intact. SR 3.6.4.1.5 demonstrates that one SGT subsystem can maintain 2 0.25 inches of vacuum water gauge for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at less than or equal to the maximum flow rate permitted for the secondary containment configuration that is operable. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> test period allows secondary containment to be in thermal equilibrium at steady state conditions. As noted, both SR 3.6.4.1.4 and SR 3.6.4.1.5 acceptance limits are dependent upon the secondary containment configuration when testing is being performed. The acceptance criteria for the SRs based on secondary containment configuration is defined as follows:

SECONDARY MAXIMUM DRAWNDOWN TIME(SEC)

MAXIMUM FLOW RATE (CFM)

CONTAINMENT (SR 3.6.4.1.4 (SR 3.6.4.1.5 CONFIGURATION ACCEPTANCE CRITERIA)

ACCEPTANCE CRITERIA)

Three Zone Operation with s15 Seconds s 2885 CFM From Zones I and III Zone II OPERABLE.

(Zones I and III)

(Verify by calculation that one SGT subsystem will maintain 2.25 inches of vacuum water gauge in secondary containment at a flow rate of s 4000 CFM (From Zones I, II, and 1II)).

Three Zone Operation with s 125 Seconds s 4000 CFM Zones I, II and III.

(Zones I, II, and III)

(From Zones I, II, and Ill)

Two Zone Operation with s 117 Seconds s 2885 CFM Unit 2 Shutdown and (Zones I and III)

(From Zones I and III)

Zone II isolated.

(continued)

I I

SUSQUEHANNA - UNIT 1 TS / B 3.6-89 Revision 2

PPL Rev. 1 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE REQUIREMENTS SR 3.6.4.1.4 and SR 3.6.4.1.5 Only one of the above listed configurations needs to be tested to confirm secondary containment OPERABILITY.

A Note also modifies the Frequency for each SR. This Note identifies that each SR must be performed in the most limiting Secondary Containment Configuration every 60 months. The 60 month Frequency is acceptable because operating experience has shown that these components usually pass the Surveillance and all active components are tested more frequently. Therefore, these tests are used to ensure secondary containment boundary integrity.

Since these SRs are secondary containment tests, they need not be performed with each SGT subsystem. The SGT subsystems are tested on a STAGGERED TEST BASIS, however, to ensure that in addition to the requirements of LCO 3.6.4.3, either SGT subsystem will perform SR 3.6.4.1.4 and SR 3.6.4.1.5. 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.

REFERENCES

1. FSAR, Section 6.2.3.
2. FSAR, Section 15.6.
3. FSAR, Section 15.7.4.
4. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).

SUSQUEHANNA - UNIT 1 TS / B3.6-90 Revision 1

z~~

I

. p I

Nl PPL Rev. 2 SCIVs

-B 3.6.4.2 B 3.6 CONTAINMENT SYSTEMS B 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)

BASES BACKGROUND The function of the SCIVs, in combination with other accident mitigation systems, is to limit fission product release during and following postulated Design Basis Accidents (DBAs) (Ref. 1). Secondary containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that fission products that leak from primary containment into secondary containment following a DBA, or that are released during certain operations when primary containment is not required to be OPERABLE or take place outside primary containment, are maintained within the secondary containment boundary.

I The OPERABILITY requirements for SCIVs help ensure that an adequate secondary containment boundary is maintained during and-after an accident by minimizing potential paths to the environment. These isolation devices consist of either passive devices or active (automatic) devices. Manual valves or dampers, de-activated automatic valves or dampers secured in their closed position (including check valves with flow through the valve secured), and blind flanges are considered passive devices.

Automatic SCIVs close on a secondary containment isolation signal to establish a boundary for untreated radioactive material within secondary containment following a DBA or other accidents.

Other non-sealed penetrations which cross a secondary containment boundary are isolated by the use of valves in the closed position or blind flanges.

APPLICABLE SAFETY ANALYSES The SCIVs must be OPERABLE to ensure the secondary containment barrier to fission product releases is established. The principal accidents for which the secondary containment boundary is required are a loss of coolant accident (Ref. 1) and a fuel handling accident inside secondary containment (Ref. 2). The secondary containment performs no active function in response to either of these limiting events, but the boundary (continued)

SUSQUEHANNA - UNIT 1

.. TS / B3.691

.Revision 3

3 1

PPL Rev. 2 SCIVs B 3.6.4.2 BASES APPLICABLE SAFETY ANALYSES (continued) established by SCIVs is required to ensure that leakage from the primary containment is processed by the Standby Gas Treatment (SGT) System before being released to the environment.

Maintaining SCIVs OPERABLE with isolation times within limits ensures that fission products will remain trapped inside secondary containment so that they can be treated by the SGT System prior to discharge to the environment.

SCIVs satisfy Criterion 3 of the NRC Policy Statement (Ref. 3).

LCO SCIVs that form a part of the secondary containment boundary are required to be OPERABLE. Depending on the configuration of the secondary containment only specific SCIVs are required. The SCIV safety function is related to control of offsite radiation releases resulting from DBAs.

The automatic isolation valves are considered OPERABLE when their isolation times are within limits and the valves actuate on an automatic isolation signal. The valves covered by this LCO,- along with their associated stroke times, are listed in Table B 3.6.4.2-1.

The normally closed isolation valves or blind flanges are considered OPERABLE when manual valves are closed or open in accordance with appropriate administrative controls, automatic SCIVs are deactivated and secured in their closed position, or blind flanges are in place. These passive isolation valves or devices are listed in Table B3.6.4.2-2. Penetrations dosed with sealants are considered part of the secondary containment boundary and are not considered penetration flow paths.

APPLICABILITY In MODES 1, 2, and 3, a DBA could lead to a fission product release to the primary containment that leaks to the secondary containment Therefore, the OPERABILITY of SCIVs is required.

In MODES 4 and 5, the probability and consequences of these events are reduced due to pressure and temperature (continued)

SUSQUEHANNA - UNIT 1 TS / B3.6-92 Revision 1

PPL Rev. 2 SCIVs B 3.6.4.2 BASES APPLICABILITY limitations in these MODES. Therefore, maintaining SCIVs OPERABLE is (continued) not required in MODE 4 or 5, except for other situations under which significant radioactive releases can be postulated, such as during operations with a potential for draining the reactor vessel (OPDRVs), during CORE ALTERATIONS, or during movement of irradiated fuel assemblies in the secondary containment. Moving irradiated fuel assemblies in the secondary containment may also occur in MODES 1, 2, and 3.

ACTIONS The ACTIONS are modified by three Notes. The first Note allows penetration flow paths to be unisolated intermittently under administrative controls. These controls consist of stationing a dedicated operator, who is in continuous communication with the control room, at the controls of the isolation device. In this way, the penetration can be rapidly isolated when a need for secondary containment isolation is indicated.

The second Note provides clarification that for the purpose of this LCO separate Condition entry is allowed for each penetration flow path. This is acceptable, since the Required Actions for each Condition provide appropriate compensatory actions for each inoperable SCIV. Complying with the Required Actions may allow for continued operation, and subsequent inoperable SCIVs are governed by subsequent Condition entry and application of associated Required Actions.

The third Note ensures appropriate remedial actions are taken, if necessary, if the affected system(s) are rendered inoperable by an inoperable SCIV.

A.1 and A.2 In the event that there are one or more required penetration flow paths with one required SCIV inoperable, the affected penetration flow path(s) must be isolated. The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a closed and de-activated automatic SCIV, a dosed manual valve, and a blind flange. For penetrations isolated in (continued)

SUSQUEHANNA-UNIT 1 T S/133.693 Revision 1

PPL Rev. 2 SCIVs B 3.6.4.2 BASES ACTIONS A.1 and A.2 (continued) accordance with Required Action A. 1, the device used to isolate the penetration should be the closest available device to secondary containment. The Required Action must be completed within the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time. The specified time period is reasonable considering the time required to isolate the penetration, and the probability of a DBA, which I requires the SCIVs to close, occurring during this short time is very low.

For affected penetrations that have been isolated in accordance with Required Action A.1, the affected penetration must be verified to be isolated on a periodic basis. This is necessary to ensure that secondary containment penetrations required to be isolated following an accident, but no longer capable of being automatically isolated, will be in the isolation position should an event occur. The Completion Time of once per 31 days is appropriate because the valves are operated under administrative controls and the probability of their misalignment is low. This Required Action does not require any testing or device manipulation. Rather, it involves verification that the affected penetration remains isolated.

Condition A is modified by a Note indicating that this Condition is only applicable to those penetration flow paths with two SCIVs. For penetration flow paths with one SCIV, Condition C provides the appropriate Required Actions.

Required Action A.2 is modified by a Note that applies to devices located in high radiation areas and allows them to be verified closed by use of administrative controls. Allowing verification by administrative controls is considered acceptable, since access to these areas is typically restricted.

Therefore, the probability of misalignment, once they have been verified to be in the proper position, is low.

B.1 With two SCIVs in one or more penetration flow paths inoperable, the affected penetration flow path must be isolated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The method of isolation must (continued)

SUSQUEHANNA - UNIT I TS / B 3.6-94 Revision 1

PPL Rev. 2 SCIVs B 3.6.4.2 BASES ACTIONS B.1 (continued) include the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a closed and de-activated automatic valve, a closed manual valve, and a blind flange. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time is reasonable considering the time required to isolate the penetration and the probability of a DBA, which requires the SCIVs to close, occurring during this short time, is very low.

The Condition has been modified by a Note stating that Condition B is only applicable to penetration flow paths with two isolation valves. For penetration flow paths with one SCIV, Condition C provides the appropriate Required Actions.

C.1 and C.2 With one or more required penetration flow paths with one required SCIV inoperable, the inoperable valve must be restored to OPERABLE status or the affected penetration flow path must be isolated. The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a closed and de-activated automatic valve, a closed manual valve, and a blind flange. A check valve may not be used to isolate the affected penetration. Required Action C.1 must be completed within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time. The Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is reasonable considering the relative stability of.the system (hence, reliability) to act as a penetration isolation boundary and the relative importance of supporting secondary containment OPERABILITY during MODES 1, 2, and 3.

In the event the affected penetration flow path is isolated in accordance with Required Action C.1, the affected penetration must be verified to be isolated on a periodic basis. This is necessary to ensure that secondary containment penetrations required to be isolated following an accident are isolated.

The Completion Time of once per 31 days for verifying each affected penetration is isolated is appropriate because the (continued)

SUSQUEHANNA - UNIT 1 TS / B3.695 Revision 1

PPL Rev. 2 SCIVs B 3.6.4.2 BASES ACTIONS C.1 and C.2 (continued) valves are operated under administrative controls and the probability of their misalignment is low.

Condition C is modified by a Note indicating that this Condition is only applicable to penetration flow paths with only one SCIV. For penetration flow paths with two SCIVs, Conditions A and B provide the appropriate Required Actions.

Required Action C.2 is modified by a Note that applies to valves and blind flanges located in high radiation areas and allows them to be verified by use of administrative means. Allowing verification by administrative means is considered acceptable, since access to these areas is typically restricted.

Therefore, the probability of misalignment of these valves, once they have been verified to be in the proper position, is low.

D.1 and D.2 If any Required Action and associated Completion Time cannot be 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 at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

E.1. E.2. and E.3 If any Required Action and associated Completion Time are not met, the plant must be placed in a condition in which the LCO does not apply. If applicable, CORE ALTERATIONS and the movement of irradiated fuel assemblies in the secondary containment must be immediately suspended.

Suspension of these activities shall not preclude completion of movement of a component to a safe position. Also, if applicable, actions must be immediately initiated to suspend OPDRVs in order to minimize the probability of a vessel draindown and the subsequent potential for fission product release. Actions must continue until OPDRVs are suspended.

(continued)

SUSQUEHANNA - UNIT I TS/ B3.6-96 Revision 1

PPL Rev. 2 SCIVs B 3.6.4.2 BASES ACTIONS E.1. E.2. and E.3 (continued)

Required Action E.1 has been modified by a Note stating that LCO 3.0.3 is not applicable. If moving irradiated fuel assemblies while in MODE 4 or 5, LCO 3.0.3 would not specify any action. If moving fuel while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations.

Therefore, in either case, inability to suspend movement of irradiated fuel assemblies would not be a sufficient reason to require a reactor shutdown.

SURVEILLANCE SR 3.6.4.2.1 REQUIREMENTS This SR verifies that each secondary containment manual isolation valve and blind flange that is required to be closed during accident conditions is closed. The SR helps to ensure that post accident leakage of radioactive fluids or gases outside of the secondary containment boundary is within design limits. This SR does not require any testing or valve manipulation.

Rather, it involves verification (typically visual) that those required SCIVs in secondary containment that are capable of being mispositioned are in the correct position.

Since these SCIVs are readily accessible to personnel during normal operation and verification of their position is relatively easy, the 31 day Frequency was chosen to provide added assurance that the SCIVs are in the correct positions.

Two Notes have been added to this SR. The first Note applies to valves and blind flanges located in high radiation areas and allows them to be verified by use of administrative controls. Allowing verification by administrative controls is considered acceptable, since access to these areas is typically restricted during MODES 1, 2, and 3 for ALARA reasons. Therefore, the probability of misalignment of these SCIVs, once they have been verified to be in the proper position, is low.

A second Note has been included to clarify that SCIVs that are open under administrative controls are not required to meet the SR during the time the SCIVs are open.

(continued)

SUSQUEHANNA - UNIT 1 ITS / B3.697 Revision 2

PPL Rev. 2 SCIVs B 3.6.4.2 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.6.4.2.2 SCIVs with maximum isolation times specified in Table B 3.6.2.4-1 are tested every 92 days to verify that the isolation time is within limits to demonstrate OPERABILITY. Automatic SCIVs without maximum isolation times specified in Table B 3.6.4.2-1 are tested under the requirements of SR 3.6.4.2.3. The isolation time test ensures that the SCIV will isolate in a time period less than or equal to that assumed in the safety analyses.

SR 3.6.4.2.3 Verifying that each automatic required SCIV closes on a secondary containment isolation signal is required to prevent leakage of radioactive material from secondary containment following a DBA or other accidents.

This SR ensures that each automatic SCIV will actuate to the isolation position on a secondary containment isolation signal. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.6.2.5 overlaps this SR to provide complete testing of the safety function. 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.

REFERENCES

1. FSAR, Section 6.2.
2.

FSAR, Section 15.

3.

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

SUSQUEHANNA - UNIT 1 TS / B3.6-98 Revision 1

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PPL Rev. 2 SCIVs B 3.6.4.2 Table B 3.6.4.2-1 Secondary Containment Ventilation System Automatic Isolation Dampers (Page 1 of 1)

Maximum Reactor Valve Number Valve Description Type of Valve Isolation Building A

Time Zone (Seconds)

I HD-17586 A&B Supply System Dampers Automatic Isolation Damper 10.0 I

HD-17524 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 10.0 I

HD-I77576A&B Unfiltered Exhaust System Automatic Isolation Damper 10.0 l

II HD-27586 A&B Supply System Dampers Automatic Isolation Damper 10.0 II HD-27524 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 10.0 II HD-27576 A&B Unfiltered Exhaust System Automatic Isolation Damper 10.0 IlIl HD-I7564 A&B Supply System Dampers Automatic Isolation Damper 14.0 III HD-17514 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 6.5 IlIl HD-7502 A&B Unfiltered Exhaust System Automatic Isolation Damper 6.0 Ill HD-27564 A&B Supply System Dampers Automatic Isolation Damper 14.0 IlIl H-27514 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 6.5 III HD-27502 A&B Unfiltered Exhaust System Automatic Isolation Damper 6.0 N/A HD-17534A Zone 3 Airlock 1-606 Automatic Isolation Damper N/A N/A HD-17534B Zone 3 Airlock 1-611 Automatic Isolation Damper N/A N/A HD-17534C Zone 3 Airlock 1-707 Automatic Isolation Damper N/A N/A HD-17534D Zone 3 Airlock 1-803 Automatic Isolation Damper N/A N/A HD-17534E Zone 3 Airlock 1-805 Automatic Isolation Damper N/A N/A HD-17534F Zone 3 Airlock 1-617 Automatic Isolation Damper N/A N/A HD-17534H Zone 3 Airlock 1-618 Automatic Isolation Damper N/A N/A HD-27534A Zone 3 Airlock 11-606 Automatic Isolation Damper NIA N/A HD-27534C Zone 3 Airlock 11-707 Automatic Isolation Damper N/A N/A HD-27534D Zone 3 Airlock 11-803 Automatic Isolation Damper N/A N/A HD-27534E Zone 3 Airlock 11-805 Automatic Isolation Damper N/A N/A HD-27534G Zone 3 Airlock C-806 Automatic Isolation Damper N/A N/A HD-27534H Zone 3 Airlock 11-618 Automatic Isolation Damper N/A NA HD-275341 Zone 3 Airlock 11-609 Automatic Isolation Damper N/A SUSQUEHANNA - UNIT 1 TS / B 3.6-99 Revision I

PPL Rev. 2 SCIVs B 3.6.4.2 Table B 3.6.4.2-2 Secondary Containment Ventilation System Passive Isolation Valves or Devices (Page I of 1)

I DeviceAraEe NDiieir Device Description A

ev Required Position X-28-2-3000 Utility Penetration to Unit I East Stairwell Yardl670 Blind Flanged X-29-2-44 SDHR System to Fuel Pool Cooling Yard/670 Blind Flanged X-29-2-45 SDHR System to Fuel Pool Cooling Yardl67O Blind Flanged X-29-2-46 Temporarv Chiller to RBCW Yardl670 Blind Flanged X-29-2-47 Temporary Chiller to RBCW Yardl670 Blind Flanged X-29-2-48 Utility Penetation to Unit I RR Bay Yard/670 Capped X-33-2-3000 Utility Penetration to Unit 2 East Stairwell Yard/670 Blind Flanged X-28-2-3000 Utility Penetration to Unit I East Stairwell 28670 Blind Flanged X-29-2-48 Utility Penetration to Unit I RR Bay 29/670 Capped X-33-2-3000 Utility Penetration to Unit 2 East Stairwell 331670 Blind Flanged X-29-3-54 Utility Penetration to Unit 1 RBCCW Hx Area.

27/683 Blind Flanged X-29%3-55 Utility Penetration to Unit I RBCCW Hx Area 27/683 Blind Flanged X-29--95 Temporary Chiller to Unit I RBCW 291749 Blind Flanged X-29-5-96 Temporarv Chiller to Unit 1 RBCW 29/749 Blind Flanged X-29-91 Temporary Chiller to Unit 2 RBCW 331749 Blind Flanged X-29-92 Temporary Chiller to Unit 2 RBCW 331749 Blind Flanged X-29-5-97 Utility Penetration from Unit I RR Bay to Unit 2 Elev. 749 33/749 Capped X-27-642 Diamond Plate Cover over Floor Penetration 271779 Installed X-27-6-92 Instrument Tubing Stubs 271179 Capped X-29-7-4 1 Spare ConduK Threaded Plug 291818' Installed X-30-6-72 Instrument Tubing Stubs 30/779'-

Capped X-30-6-1002 Stairwell #214 Rupture Disc 30/779 Installed Intact X-30-6-1003 Airlock 11-609 Rupture Disc 30/779 Installed Intact X-25-6-1008 Airlock 1-606 Rupture Disc 25/779' Installed Intact X-2914-102 Penetration at Door 433 291719' Blind Flange Installed X-294-103 Penetration at Door 433 291719' Blind Flange Installed X-29t4-102 Penetration at Door 433 331719' Blind Flange Installed X-294-103 Penetration at Door 433 331719' Blind Flange Installed 1S2104 N2 Purge lne to Ul Containment Spectacle Flange 29/683' Blind Side Installed 2S2104 N2 Purge Line to U2 Containment Spectacle Flange 34/672 Blind Side Installed XD-17513 Isolation damper for Railroad Bay Zone III HVAC Supply 29/799 Position Is dependent on Railroad Bay alignment XD-17514 Isolation damperfor Railroad BayZone III HVAC Exhaust 291719' Position Is dependent on Railroad

_Bay alignment 187388 RBCW Temp Chiller Discharge Iso Vlv 29/670 Closed Manual Isolation Valve 187389 RBCW Temp Chiller Supply Iso Vlv 29/670 Closed Manual Isolation Valve 187390 RBCW Temp Chiller Supply Drain Vlv 29/670 Closed Manual Isolation Valve 187391 RBCW Temp Chiller Discharge Drain Vlv 29/670 Closed Manual Isolation Valve 110176 SDHR Supply Drain Vlv 29/670 Closed Manual Isolation Vahve 110186 SDHR Discharge Drain VIv 29/670 Closed Manual Isolation Valve 110180 SDHR Supply Vent Vlv 291749 Closed Manual Isolation Valve 110181 SDHR Discharge Fill Vlv 271749 Closed Manual Isolation Valve 110182 SDHR Discharge Vent Vlv 271749 Closed Manual Isolation Valve 110187 SDHR Supply Fill Vlv 29/749 Closed Manual Isolation Valve 210186 SDHR Supply Drain Vlv 33/749 Closed Manual Isolation Valve 210187 SDHR Supply Vent Vlv 33/749 Closed Manual Isolation Valve 210191 SDHR Discharge Vent Vlv 30/749 Closed Manual Isolation Valve 210192 SDHR Discharge Drain Vlv 301749 Closed Manual Isolation Valve 210193 SDHR Discharge Vent Vlv 33/749 Closed Manual Isolation Valve SUSQUEHANNA - UNIT 1

.TS / B 3.6-1 00 Revision 2

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