ML061360211

TSB1 - Technical Specification Bases Unit 1 Manual

ML061360211
Person / Time
Site:	Susquehanna
Issue date:	05/04/2006
From:	Susquehanna
To:	Gerlach R Document Control Desk, Office of Nuclear Reactor Regulation
References
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May. 04, 2006 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2006-22295 USER INFORMATION:

GERLACH*ROSE M EMPL#:028401 CA#: 0363 Aodress: NUCSA2 P ione#: 254-3194 I RANSMITTAL INFORMATION:

TO: GERLACH*ROSE M 05/04/2006 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)

THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ON THIS TRANSMITTAL. WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS.

ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.

TSB1 - TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 04/24/2006 ADD MANUAL TABLE OF CONTENTS DATE: 05/03/2006 CATEGORY: DOCUMENTS TYPE: TSB1 i

i I

ii Aoo (

May. 04, 2006 Page 2 of 2 ID: TEXT 3.3.3.1 REMOVE: REV:3 ADD: REV: 4 CATEGORY: DOCUMENTS TYPE: TSB1 ID: TEXT LOES REMOVE: REV:72 ADD: REV: 73 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 FOR ASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.

-, SSES MANUAL Manual Name: TSB+/--

Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date: 05/03/2006 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 73 05/03/2006

Title:

LIST OF EFFECTIVE SECTIONS TEXT TOC 9 04/18/2006

Title:

TABLE OF CONTENTS TEXT 2.1.1 2 04/18/2006

Title:

SAFETY LIMITS (SLS) REACTOR CORE SLS K1 TEXT 2.1.2 0 11/15/2002

Title:

SAFETY LIMITS (SLS) REACTOR COOLANTSYSTEM aRCS) PRESSURE SL TEXT 3.0 1 t4i8/2Op5

Title:

LIMITING CONDITION FOR OPERATION ) APPLICABILITY TEXT 3.1.1 <1 04/18/2006

Title:

REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)

TEXT 3.1.2 '. 0 11/15/2002

Title:

REACTIVITY CONTROL SYSTEMS REACTIVITY ANOMALIES TEXT 3.1.3 1 07/06/2005

Title:

REACTIVIT CONTROL SYSTEMS CONTROL ROD OPERABILITY TEXT 3.1.4 2 04/18/2006

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM TIMES TE-3T 3.1.5 1 07/06/2005

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS TE4T 3.1.6 2 04/18/2006

Title:

REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL Pae of 8ieotDt:0/30 Page 1 of 8 Report Date: 05/03/06

SSES .H.JNAL 2

Manual Name: TSBt-Eanual

Title:

TECHNICAL SPECIFICATION BASES UNIT -1 MANUAL TEXT 3.1.7 1 08/30/2005

Title:

REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM TEXT 3.1.8 1 10/19/2005

Title:

REACTIVITY CONTROL 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 1 04/18/2006

Title:

POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)

TEXT 3.2.3 0 11/15/2002

Title:

POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)

TEXT 3.2.4 2 04/12/2006

Title:

POWER DISTRIBUTION LIMITS AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS TEXT 3.3.1.1 3 04/12/2006

Title:

INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 1 04/12/2006

Title:

INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 2 04/12/2006

Title:

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

Title:

INSTRUMENTATION FEEDWATER - MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 4 05/03/2006

Title:

INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT 3.3.3.2 1 04/18/2005

Title:

INSTRUMENTATION REMOTE SHUTDOWN SYSTEM Report Date: 05/03/06 Page22 Page of of 88 Report Date: 05/03/06

SSES MANUAL" 0 Manual Name: TSB+/-

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 TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP I (ATWS-RPT) INSTRUMENTATION TEX'I 3.3.5.1 2 07/06/2005

Title:

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

Title:

INSTRUMENTATION REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATION TEXT 3.3.6.1 1 11/09/2004

Title:

INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.6.2 1 11/09/2004 V)

Title:

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

Title:

INSTRUMENTATION CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM l 3 INSTRUMENTATION TB 3.3.8.1 1 09/02/2004

Title:

INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATION TEXT 3.3.8.2 0 11/15/2002 title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS): ELECTRIC POWER MONITORING TEXT 3.4.1 3 04/12/2006 title: REACTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATING TEXT 3.4.2 0 11/15/2002 4

itle: REACTOR COOLANT SYSTEM (RCS) JET PUMPS TEXT 3.4.3 1 01/16/2006

Title:

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

Report Date: 05/03/06 Page3 Page 3 , of of 8 8 Report Date: 05/03/06

SSES. NAItA 4.

^.

It Manual Name: TSB+/--

Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL I

TEXT 3.4.4 0 11/15/2002

Title:

REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE TEXT 3.4.5 1 01/16/2006

Title:

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

Title:

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

Title:

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

Title:

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

- HOT SHUTDOWN TEXT 3.4.9 0 11/15/2002

Title:

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

- COLD SHUTDOWN TEXT 3.4.10 1 04/21/2006

Title:

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

Title:

REACTOR COOLANT SYSTEM (RCS) REACTOR STEAM DOME PRESSURE TEXT 3.5.1 2 01/16/2006

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS)'AND REACTOR-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 1 04/18/2005

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 I

k i

E Report Date: 05/03/06

. Page 4 Page 4 of of 8 8 Report Date: 05/03/06

SSES HAWUAL.

m Manual Name: TSBi-Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 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 SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)

IT 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 TEMPERATURE 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 1 04/18/2005

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS TEX{ 3.6.3.2 1 04/18/2005 litle: CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM TEXT 3.6.3.3 0 11/15/2002

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION Report Date: 05/03/06 Pages Page 5 , of of 8 8 Report Date: 05/03/06

SSES MANUAL I J ,

Manual Name: TSB-i Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.4.1 5 03/16/2006

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 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 0 11/15/2002

Title:

PLANT SYSTEMS CONTROL ROOM.EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM TEXT 3.7.4 0 11/15/2002

Title:

PLANT SYSTEMS CONTROL ROOM FLOOR-COOLING SYSTEM' TEXT 3.7.5 0 11/15/2002

Title:

PLANT SYSTEMS MAIN CONDENSER OFFGAS TEXT 3.7.6 1 01/17/2005.

Title:

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

Title:

PLANT SYSTEMS SPENT FUEL.STORAGE POOL WATER LEVEL TEXT 3.8.1 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 Report Date: 05/03/06 Page6 Page 6 of of 88 Report Date: 05/03/06

i SSES MANUAL

' Manual Name: TSBt-Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 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 - OPERATING TEXT 3.8.5 0 11/15/2002

Title:

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

Title:

ELECTRICAL POWER SYSTEMS BATTERY CELL PARAMETERS TEXT 3.8.7 1 10/05/2005

Title:

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

Title:

ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS - SHUTDOWN TEXT 3.9.1 0 11/15/2002 title: REFUELING OPERATIONS REFUELING EQUIPMENT INTERLOCKS TEXT 3.9.2 0 11/15/2002  :

Title:

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

Title:

REFUELING OPERATIONS CONTROL ROD POSITION TEXT 3.9.4 0 11/15/2002

Title:

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

Title:

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

Title:

REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVEL Report Date: 05/03/06 Page7 Page 7-. of of 8 8 Report Date: 05/03/06

SSES MANUAL

• I Manual Name: TSBi-Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Qw TEXT 3.9.7 0 11/15/2002

Title:

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

Title:

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

Title:

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

Title:

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

Title:

SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - HOT SHUTDOWN TEXT 3.10.4 0 11/15/2002

Title:

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

Title:

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

Title:

SPECIAL OPERATIONS MULTIPLE CONTROL ROD WITHDRAWAL - REFUELING TEXT 3.10.7 1 04/18/2006

Title:

SPECIAL OPERATIONS CONTROL ROD TESTING - OPERATING TEXT 3.10.8 1 04/12/2006

Title:

SPECIAL OPERATIONS SHUTDOWN MARGIN (SDM) TEST - REFUELING Report Date: 05/03/06 Page 8 of 8 - - :. Report Date: 05/03/06-,

SUSQUEHANNA STEAM ELECTRIC STATION  :

LST OFEFFECTIVESECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision TOC Table of Contents 9 B 2.0 SAFETY LIMITS BASES Page B 2.0-1,- 0 Page TS/B2.0-2 3 Page TS / B2.0-3 4 Pages TS B 2.0-4 and TS B 2.0-5 3 Page TS B2.0-6 '

Pages B 2.0-7 through B 2.0-9 0 B 3.0 LCO AND SR APPLICABILITY BASES ,  :

Pages B 3.0-1 through B3.0-4 / 0 Pages TS I B 3.0-5 through TS /B 3.0-7 1 Pages TSI B 3.0-8 through TS / B 3.0-9 < 2 Pages TS I B 3.0-10 through TS / B 3.0-12 1 1\

Pages TS I B 3.0-13 through TS / B s4-is ; 2 PagesTS /B3.0-160and1TSIB3d 0 B 3.1 REACTIVITY CONTROL BASES Pages B 3.1-1 through B3,-

( , 0 PageTS/ B 3.1-5 -

Pages TS I B 3.1-6 and% I 1a Pages B3.1-8 throigh , 0 PageTS/ B 3.1-27 1 Pages B 3.-15 through B 3.1-22 0 Page TS I B3 Pages B3.1Z through B 3.1-27 0 Page TF B6A0 28, 2 PageSI B3.1-5 .

PagesB 3.130 through B 3.1-33 0 9Pages$YS1393.3-34 through TS I B3.3.~36 I

- TS BPge B3.1-37 and TS / B 3.1-38 2 EagJs B 31-39 through B 3.1-44 0 Page TS/B 3.1-45. I Pages B 3.1-46 'ard,B 3.1-47 0 Pages TS /B 3.1-48 and TS/B 3.1-49 I Page B 3.1-50 0 Page TS I B 3.1-51 1 B 3.2 POWER DISTRIBUTION LIMITS BASES PageTS/B3.2-1 1 Pages TS / B 3.2-2 through TS I B 3.2-6 2 Revision 73 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT I1 TS B LOES-1 TS I/ B LOES-1 Revision 73

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVESECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision Page B 3.2-7 0 Pages TS B3.2-8 and TS B 3.2-9 2 Page TS 1B 3.2.10 1 Page TS B 3.2-11 2 Page B 3.2-12 0 Page TS /B 3.2-13 2 Pages B 3.2-14 and B 3.2-15 0 Page TS B 3.2-16 2 Page B 3.2-17 0 Page TS B 3.2-18 1 Page TS B 3.2-19 4 B 3.3 INSTRUMENTATION Pages TS /B 3.3-1 through TS B 3.3-4 1 Page TS /B 3.3-5 2 Page TS/B 3.3-6 -

Page TS/B 3.3-7 3 Page TS/B 3.3-7a 0

.Pages TS B 3.3-8 through TS B 3.3-12 3 Pages TS /,B 3.3-12a through TS B3.3-12c 0 Page TS I 3.3-13 1 Page TS/B 3.3-14 3 Pages TS /B 3.3-15 and TS B 3.3-16 1 Pages TS/B 3.3-17 and TS/B 3.3-18 3 Pages TS/B 3.3-19 ' 1 Pages TS /B 3.3-20 through TS B 3.3-22 2 Page TS1 B 3.3-22a 0 Pages TS /-B 3.3-23 and TS B 3.3-24 2 Pages TS /B 3.3-24a and TS / B 3.3-24b 0 Pages TS /B 3.3-25 and TS /B 3.3-26 2 Page TS1B 3.3-27  ;

Pages TS B 3.3-28 through TS B 3.3-30 -3 Page TS/B 3.3-30a 0 Page TS/B 33-31 3 Page TS B 3.3-32 5 Pages TS IB 3.3-32a and TS B 3.3-32b 0 Page TS /B 3.3-33 5 Page TS B 3.3-33a 0 Page TS B 3.3-34 1 Pages TS B 3.3-35 and TS B 3.3-36 2 Pages TS/B 3.3-37 through TS /B 3.3-43 1 Page TS /B3.3-44 3 NTIT IBLE- eiin7 SUQEAN

.SUSQUEHANNA - UNIT 1 TS / B LOES-2 Revision 73

SUSQUEHANNA STEAM ELECTRIC STATION -

LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision Pages TS / B 3.3-45 through TS I B 3.3-49 2 Page TS / B 3.3-50 3 Page TS I B 3.3-51 2 Pages TS I B 3.3-52 and TS I B 3.3-53 1 Page TS I B 3.3-54 3 Pages B 3.3-55 through B 3.3-63 0 Pages TS I B 3.3-64 and TS I B 3.3-65 2 Page TS / B 3.3-66 4 Page TS/ B 3.3-67 3 Pages TS / B 3.3-68 and TS /B 3.3-69 4 Pages TS / B 3.3-70 and TS / B 3.3-71 3 Pages TS /3.3-72 through TS /3.3-75 2 Page TS / B 3.3-75a 5 Page TS B 3.3-75b 6 I Page TS J B 3.3-75c 4 Pages B 3.3-76 through 3.3-77 .0 Page TS B 3.3-78 Pages B 3.3-79 through B 3.3-89 Page TS / B 3.3-90 Page B 3.3-91 1 Pages TS / B 3.3-92 through TS / B 3.3-100 0 Pages B 3.3-101 through B 3.3-103 -1 Page TS l B 3.3-104 0 Pages B 3.3-105 and B 3.3-106 1 Page TS/B3.3-107 01 Page B 3.3-108 O Page TS I B 3.3-109 Pages B 3.3-110 and B 3.3-111 Pages TS 1B 3.3-112 and TS I B 3.3-112a Pages TS /B 3.3-113 through TS I B 3.3-115 Page TS /B3.3-116 2 PageTS1B3.3-117 1 Pages B 3.3-118 through B 3.3-122 0 Pages TS I B 3.3-123 and TS I B 3.3-124 1 Page TS I B 3.3-124a 0 Page B 3.3-125 0 Pages TS I B 3.3-126 and TS /8 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 0o TS/BLOES-3 Revision 73 SUSQUEHANNA UNIT SUSQUEHANNA-, -

UNIT 1I TS /B LOES-3 Revision 73

SUSQUEHANNA STEAM ELECTRIC STATION  :

LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision Page TS I B 3.3-138 1 Pages B3.3-139 through B 3.3-149 0 Pages TS I B 3.3-150 through TS I B 3.3-162 1 Page TS I B 3.3-163 2 Pages TS / B 3.3-164 through TS I B 3.3-177 1 Pages TS / B 3.3-178 and TS / B 3.3-179 2 Pages TS / B 3.3-179a and TS I B 3.3-179b 2 Page TS I B 3.3-179c 0 Page TS I B 3.3-180 1 Page TS / B 3.3-181 2 Pages TS I B 3.3-182 through TS I 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 -

Pages B 3.3-206 through B 3.3-219 0 B 3.4 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 and B3.4-2 0 Pages TS / B 3.4-3 and Page TS / B 3.4-4 4.

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 I B 3.4-15 1 Pages TS I B 3.4-16 through TS I B3.4-18 2 Pages B3.4-19 through B 3.4-27 0 Pages TS B 3.4-28 and TS I B 3.4-29 1 Pages B 3.4-30 and B 3.4 0 Page TS/ B 3.4-32 ' 1 Pages B 3.4-33 through B 3.4-36 0 Page TS / B 3.4-37 1 Pages B 3.4-38 through B 3.4-40 0 Page TS I B 3.4-41 1 Pages B 3.4-42 through B 3.4-48 0 Page TS/ B 3.4-49 3 Page TS B3.4-50 -

Page TS I B 3.4-51 3 Pages TS I B 3.4-52 and TS / B 3.4-53 1 Pages TS I B 3.4-54 and TS I B 3.4-55 2 Page TS / B 3.4-56 1 Page TS / B 3.4-57 3 Pages TS I B 3.4-58 through TS I B 3.4-0 -1 Revision 73 SUSQUEHANNA - UNIT UNIT I1 TS B LOES-4 TS I/ B LOES-4 Revision 73

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

Section Title Revision B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 0 Page TS / B 3.5-3 -2 Page TS I B 3.5-4 1 Page TS / B 3.5-5 ,2 Page TS / B 3.5-6 1 Pages B 3.5-7 through B 3.5-10 0 Page TS I B 3.5-11 1 Page TS B 3.5-12 0 Page TS/ B 3.5-13 1 Page TS I B 3.5-14 and TS / B3.5-15 0 Pages TS I B 3.5-16 through TS I B 3.5-18 1 Pages B 3.5-19 through B 3.5-24 0 Page TS /B3.5-25 1 Pages TS I B 3.5-26 and TS /B 3.5-27 1 Pages B 3.5-28 through B 3.5-31 0 B 3.6 CONTAINMENT SYSTEMS BASES Page TS I B 3.6-1 2 Page TS I B 3.6-1a 3 Pages TS / B 3.6-2 through TS I B3.6-5 2 Page TS I B 3.6-6 3 Pages TS / B 3.6-6a and TS I B 3.6-6b 2 Page TS I B 3.6-6c 0 Pages B 3.6-7 through B 3.6-14 0 Page TS /B 3.6-15 2 Pages TS I B 3.6-15a and TS / B 3.6-15b 0 Page B3.6-16 -0 Page TS /B 3.6-17 1 Page TS I B3.6-17a 0 Pages TS / B 3.6-18 and TS I B 3.6-19 0

-Page TS/ B 3.6-20 1 Page TS /8 3.6-21 2 Page TS /B3.6-22 1 Page TS I B 3.6-22a 0 Page TS /B 3.6-23 1 Pages TS / B3.6-24 through TS / B3.6-25 0 Page TS /B 3.6-26 1 Page TS /B 3.6-27 2 Page TS /B 3.6-28 5 Pages TS /B 3.6-29 and TS /B 3.6-30 1 Page TS / B3.6-31 3 SUSQUEHANNA - UNIT 1 TS / B LOES-5 Revision 73

I SUSQUE1{ANNA STEAM ELECTRIC STATION  : . .

LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision 0

Page B3.6-32 Page TS / B 3.6-33 Pages B 3.6-34 and B 3.6-35 Page TS / B 3.6-36 Page B 3.6-37 ~0 Page TS / B 3.6-38 1 Page B 3.6-39 Page TS / B 3.6-40 4 Pages B 3.6-41 through B 3.6-43 3 Pages TS / B 3.6-44 and TS I B 3.6-45 1 Page TS / B 3.6-46 2' Pages TS / B 3.6-47 through TS I B 3.6-51 1 Page TS / B 3.6-52 2 Pages B 3.6-53 through B 3.6-63 0 Pages TS / B 3.6-64 and TS / B 3.6-65 O Pages B 3.6-66 through B 3.6-72 0 Page TS / B 3.6-73 I Pages B 3.6-74 through B 3.6-77 Page TS / B 3.6-78 Pages B 3.6-79 through B 3.3.6-83 Page TS / B 3.6-84 3 Page TS / B 3.6-85 2 Page TS / B 3.6-86 '3 Page TS / B 3.6-87 1 Pages TS f B 3.6-88 and TS I B 3.6-88a 2 Page TS / B 3.6-89 3 Page TS / B 3.6-90 -2 Page TS / B 3.6-91 3 I Pages TS / B 3.6-92 through TS I B 3.6-96 1 Page TS / B 3.6-97 2 Pages TS / B 3.6-98 and TS I B 3.6-99 1 Page TS / B 3.6-100 2 Pages TS / B 3.6-101 and TS / B 3.6-102 1 Pages TS / B 3.6-103 and TS I B 3.6-104 2 Page TS / B 3.6-105 3 Pages TS I B 3.6-106 and TS I B 3.6-107 2 B3.7 PLANT SYSTEMS BASES Pages TS / B 3.7-1 through TS / B 3.7-6 2 Page TS / B 3.7-6a 2 Pages TS /B3 3.7-6b and TS/ B 3.7-6c 0 Page TS / B 3.7-7 2 Pages TS / B 3.7-8 through TS/ B 3.7-13 1 Pages TS / B 3.7-14 through TS / B 3.7-18 2 LOES-6 Revision 73 SUSQUEHANNA - UNIT SUSQUEHANNA -

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

Section Title Revision Page TS / B 3.7-18a - -0 Pages TS I B 3.7-19 through TS&I B 3.7-23 1 Pages B 3.7-24 through B 3.7-26 0 Pages TS l B 3.7-27 through TS I B 3.7-29 4 Page TS/ B 3.7-30 2 Pages B 3.7-31 through B 3.7-33 0 B 3.8 ELECTRICAL POWER SYSTEMS BASES Pages TS I B 3.8-1 through TS / B 3.8-3 2 Page TS/ B 3.8-4 3 Pages TS/ B 3.8-4a and TS B3.8-4b 0 Page TS / B 3.8-5 4 Page TS /1B3.8-6 3 Pages TS / B 3.8-7 through TS/B 3.8-8 -2 Page TS / B 3.8-9 4 Page TS B 3.8-10 3 Pages TS B 3.8-11 and TS I B 3.8-17 2 Page TS B 3.8-18 3 Pages TS /B 3.8-19 through TS /B 3.8-21 2 Pages TS /B3.8-22 and TS /B3.8-23 3 Pages TS / B 3.8-24 through TS/ B 3.8-37 2 Pages B 3.8-38 through B 3.8-53 0 Pages TS / B 3.8-54 through TS / B 3.8-61 1 Pages TS /B 3.8-62 and TS /B 3.8-63 2 Page TS/ B 3.8-64 Page TS I B 3.8-65 2 Pages B 3.8-66 through B 3.8-80 0 Page TS/ B 3.8-81 1 Pages B 3.8-82 through B 3.8-90 0 B 3.9 REFUELING OPERATIONS BASES Pages TS /B 3.9-1 and TS / B 3.9-1a 1 Pages TS /B 3.9-2 through TS I B 3.9-4 1 Pages B3.9-5 through B3.9-30 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 Page TS I B 3.10-32 2 Page B 3.10-33 0 Page TS /B 3.10-34 1 Pages B 3.10-35 and B 3.10-36 0 Page TS B 3.10-37 -

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I PPL Rev. 4 PAM Instrumentation B 3.3.3.1 B 3.3 INSTRUMENTATION B'3.3.3.1 Post Accident Monitoring (PAM)' Instrumentation BASES BACKGROUND The primary purpose of the PAM instrumentation is to display plant variables that provide information required by the control room operators during accident situations. This information provides the necessary support for the operator to take the manual actions for which no automatic control is provided and that are required for safety systems to accomplish theirsafety functions for Design Basis Events. The instruments that monitor these variables are designated as Type A, Category I, and non-Type A, Category I, in accordance with Regulatory Guide 1.97 (Ref. 1).,

The OPERABILITY of the accident monitoring instrumentation ensures that there is sufficient information available on selected plant parameters to monitor and assess plant status and behavior following an, accident.

This capability is consistent with the recommendations of Reference 1.

APPLICABLE The PAM instrumentation LCO ensures the OPERABILITY of Regulatory SAFETY Guide 1.97, Type A variables so that the control room operating staff can:

ANALYSES Perform the diagnosis specified in the Emergency Operating

. Procedures (EOPs). These variables are restricted to preplanned actions for the primary success path of Design Basis Accidents (DBAs), (e.g., loss of coolant accident (LOCA)), and

. Take the specified, preplanned, manually controlled actions for which no automatic control is provided, which are required for safety systems to accomplish their safety function.

The PAM instrumentation LCO also ensures OPERABILITY of Category I, non-Type A, variables so that the control room operating staff can:

i

. Determine whether systems important to safety are performing their intended functions; (continued)

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.'APPLICABLE V Determine the potential for causing a gross breach of the barriers to SAFETY radioactivity release; ANALYSES (continued)

• Determine whether a gross breach of a barrier has occurred; and l Initiate action necessary to protect the public and for an estimate of the magnitude of any impending threat.

The plant specific Regulatory Guide 1.97 Analysis (Ref. 2 and 3) documents the process that identified Type A and Category I, non-Type A, variables.

Accident monitoring instrumentation that satisfies the definition of Type A in Regulatory Guide 1.97 meets Criterion 3 of the NRC Policy Statement.

-(Ref. 4) Category I, non-Type A, instrumentation is retained in Technical Specifications (TS) because they are intended to assist operators in minimizing the consequences of accidents. Therefore, these Category I variables are important for reducing public risk, LCO LCO 3.3.3.1 requires two OPERABLE channels for all but one Function, to ensure that no single failure prevents the operators from being presented with the information necessary to determine the status of the plant and to bring the plant to, and maintain it in, a safe condition following that accident.

Furthermore, provision of two channels allows a CHANNEL CHECK during the post accident phase to confirm the validity of displayed information.'

The exception to the two channel requirement is primary containment isolation valve (PCIV) position. Inthis case, the important information is the status of the primary containment penetrations. The LCO requires' one position indicator for each active PCIV. This is sufficient to redundantly verify the isolation status of each isolable penetration either via indicated status of the active valve and prior knowledge of passive valve or via system boundary (continued)

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PPL Rev. 4 PAM Instrumentation B 3.3.3.1 BASES LCO status. If a normally active PCIV is known to be closed and deactivated, (continued) position indication is not needed to determine status. Therefore, the position indication for valves in this state is not required to be OPERABLE.

The following list is a discussion of the specified instrument Functions listed in Table 3.3.3.1-1 in the accompanying LCO. Table B 3.3.3.1-1 provides a listing of the instruments that are used to meet the operability requirements for the specific functions.

1. Reactor Steam Dome Pressure Reactor steam dome pressure is a Type A, Category 1, variable provided to support monitoring of Reactor Coolant System (RCS) integrity and to verify operation of the Emergency Core Cooling Systems (ECCS). Two independent pressure channels, consisting of three wide range control room indicators and one wide range control room recorder per channel with a range of 0 psig to 1500 psig, monitor pressure. The wide range recorders are the primary method of indication- available for use by the operators during an accident, therefore, the PAM Specification deals specifically with this portion of the instrument channel.

2. Reactor Vessel Water Level Reactor vessel water level is a Type A, Category 1, variable provided to support monitoring of core cooling and to verify operation of the ECCS.

A combination of three different level instrument ranges, with two independent channels each, monitor Reactor Vessel Water Level. The extended range instrumentation measures from -150 inches to 180 inches and outputs to three control room level indicators per channel.

The wide range instrumentation measures from -150 inches to 60 inches and outputs to one control room recorder and three control room indicators per channel. The fuel zone range instrumentation measures from -310 inches to -110 inches and outputs to a control room recorder (one channel) and a control room indicator (one channel). These three ranges of instruments combine to provide level indication from the bottom of the Core to above the main steam line. The wide range level recorders, the fuel zone level indicator and level recorder, and one inner ring extended range level indicator per channel are the primary method of indication available for use by the operator during an accident, therefore the PAM (continued)

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- PAM Instrumentation B 3.3.3.1 BASES LCO 2. ReactorVessel Water Level (continued)

Specification deals specifically with this portion of the instrument channel.

3. Suppression Chamber Water Level Suppression chamber water level is a Type A, Category 1, variable provided to detect a breach in the reactor coolant pressure boundary (RCPB). This variable is also used to verify and provide long termn surveillance of ECCS function. A combination of two different level instrument ranges, with two independent channels each, monitor Suppression chamber water level. The wide range instrumentation measures from the ECCS suction lines to approximately the top of the chamber and outputs to one control room recorder per channel. The wide range recorders are the primary method of indication available for use by the operator during an accident, therefore the PAM Specification deals specifically with this portion of the instrument channel.

4. Primary Containment Pressure -.

Primary Containment pressure is a Type A, Category 1, variable provided to detect a breach of the RCPB and to verify ECCS functions that operate to maintain RCS integrity. A combination of two different pressure instrument ranges, with two independent channels each, monitor primary containment pressure. The LOCA range measures from -15 psig to 65 psig and outputs to one control room recorder per channel. The accident range measures from 0 psig to 250 psig and outputs to one control room recorder per channel (same recorders as the LOCA range). The recorders (both ranges) are the primary method of indication available for use by the operator during an accident, therefore the PAM Specification deals specifically with this portion of the instrument channel.

5. Primary Containment Hiqh Radiation Primary containment area radiation (high range) is provided to monitor the potential of significant radiation releases (continued)

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PAM Instrumentation B 3.3.3.1 BASES LCO - 5. Primary Containment Hiah Radiation (continued) and to provide release assessment for use by operators in determining the need to invoke site emergency plans. Two independent channels, which output to one control room recorder per channel with a range of 100 to 1Xi08 R/hr, monitor radiation. The PAM Specification deals specifically with this portion of the instrument channel.

6. Primary Containment Isolation Valve (PCIV) Position PCIV position is provided for verification of containment integrity. In the' case of PCIV position, the important information is the isolation status of

-thecontainment penetration. The LCO requires a channel of valve position indication in the control room to be OPERABLE for an active.

PCIV in a containment penetration flow path, i.e., two total channels of, PCIV position indication for a penetration flow path with two active valves.

For containment penetrations with only one active PCIV having control room indication, Note (b) requires a single channel of valve position indication to be OPERABLE. This is sufficient to redundantly verify the isolation status of each isolable penetration via indicated status of the active valve, as applicable, and prior knowledge of passive valve or system boundary status. If a penetration flow path is isolated, position indication for the PCIV(s) in the associated penetration flow path is not needed to determine status. Therefore, the position indication for valves in an isolated penetration flow path is not required to be OPERABLE.

These valves which require position indication are specified in Table B 3.6.1.3-1. Furthermore, the loss of position indication does not necessarily result in the PCIV being inoperable.

The PCIV position PAM instrumentation consists of position switches unique to PCIVs, associated wiring and control room indicating lamps (not necessarily unique to a PCIV) for active PCIVs (check valves and manual valves are not required to have position indication). Therefore, the PAM Specification deals specifically with these instrument channels.

(continued)

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- PAM Instrumentation B 3.3.3.1 BASES LCO (continued) 7. Neutron Flux Wide range neutron flux is a Category I variable provided to verify reactor shutdown. The Neutron Monitoring System Average Power Range Monitors (APRM) provides reliable neutron flux measurement from 0%to 125% of full power. The APRM consists of'four channels each with their own chassis powered with redundant power supplies. The APRM sends signals to the analog isolator module which in turn sends individual APRM signals to the recorders used for post accident monitoring. The PAM function for neutron flux is satisfied by having any 2 channels of APRM provided for post accident monitoring. The PAM Specification deals specifically with this portion of the instrument channel.

The Neutron Monitoring System (NMS) was evaluated against the criteria established in General Electric NEDO-31558A to ensure its acceptability for post-accident monitoring. NEDO-31558A provides alternate criteria for the NMS to meet the post-accident monitoring guidance of Regulatory Guide 1.97. Based on the evaluation, the NMS was found to meet the criteria established in NEDO-31558A. The APRM sub-function of the NMS is used to provide the Neutron Flux monitoring identified in TS 3.3.3.1 (Ref. 5 and 6).

8. Containment Hydrogen and Oxvaen Analyzers' The drywell and suppression chamber hydrogen and oxygen concentrations are Type A, Category 1, variables. Two independent gas analyzers monitor hydrogen and oxygen concentration to detect unsafe combustible gas levels in primary containment. The analyzers are capable of determining hydrogen concentration in the range of 0 to 30%

by volume and oxygen concentration in the range of 0 to 10% by volume, and each provide control room indication and output to a control room recorder. Each gas analyzer must be capable of sampling either the drywell or the suppression chamber. The recorders are the primary method of indication available for use by the operator during an accident, therefore the PAM Specification deals specifically with this portion of the instrument channel. The gas analyzer piping is provided with heat tracing to reduce the buildup of condensation in the system. H202 Analyzers can' be considered OPERABLE for accident monitoring (TS 3.3.3.1) for up to 100 days with their heat tracing INOPERABLE.

(continued)

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PPL Rev. 4 PAM Instrumentation B 3.3.3.1 BASES LCO (continued) 9. Drvwell Atmosphere Temperature Drywell atmosphere temperature is a Category I variable provided to verify RCS and containment integrity and to verify the effectiveness of ECCS actions taken to prevent containment breach. Two independent temperature channels, consisting of two control room recorders per channel with a range of 40 to 440 degrees F, monitor temperature. The PAM'Specification deals specifically with the inner ring temperature recorder portion of the instrument channel. 1

10. Suppression Chamber Water Temperature Suppression Chamber water temperature is a Type A, Category 1, variable provided to detect a condition that could potentially lead to containment breach and to verify the effectiveness of ECCS actions taken to prevent containment breach. The suppression chamber water temperature instrumentation allows operators to detect trends in suppression chamber water temperature in sufficient time to take action to prevent steam quenching vibrations in the suppression pool. Two channels are required to be OPERABLE. Each channel consists of eight sensors of which a minimum of four sensors (one sensor in each quadrant) must be OPERABLE to consider a channel OPERABLE. The outputs for the temperature sensors are displayed on two independent indicators in the control room and recorded on the monitoring units located in the control room on a back panel. The temperature indicators are the primary method of indication available for use by the operator during an accident, therefore the PAM Specification deals specifically Ewith this portion of the instrument channel.

APPLICABILITY The PAM instrumentation LCO is applicable in MODES 1 and 2. These variables are related to the diagnosis and preplanned actions required to mitigate DBAs. The applicable DBAs are assumed to occur in MODES 1 and 2. In MODES 3, 4, and 5, plant conditions are such that the likelihood of an event that would require PAM instrumentation is extremely low; therefore, PAM instrumentation is not required to be OPERABLE in these MODES.

III (continued)

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- PAM Instrumentation

- IB 3.3.3.1 BASES (continued):

ACTIONS A note has been provided to modify the'ACTIONS related to PAM I instrumentation chahhels. VSedtioh 1.3, Completion Times, specifies that once a Condition 'has',been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits, will not result in separate entry into the Condition. Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for inoperable PAM instrumentation channels provide appropriate compensatory measures for separate Functions. As such, a Note has been provided that allows separate Condition entry for each inoperable PAM Function.

A.1 When one or more Functions have one required channel that is inoperable, the required inoperable channel must be restored to OPERABLE status within 30 days. The 30 day Completion Time is based on operating experience and takes into account the remaining OPERABLE channels, the passive nature of the instrument (no critical automatic action is assumed to occur from these instruments), and the low probability of an event requiring PAM instrumentation during this interval.

B. .I If a channel has not been restored to OPERABLE status in 30 days, this Required Action specifies initiation of action in accordance with Specification 5.6.7, which requires a written report to be submitted to the NRC. This report discusses the results of the root cause evaluation of the inoperability and identifies proposed restorative actions.

(continued)

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. PAM Instrumentation B 3.3.3.1 BASES ACTIONS B. 1 (continued)

This action is appropriate in lieu of a shutdown requirement because alternative actions are identified before the written report is submitted to the NRC, and given the likelihood of plant conditions that would require information provided by this instrumentation.

CAI When one or more Functions have two required channels that are inoperable (i.e., two channels inoperable in the same Function), one channel in the Function should be restored to OPERABLE status within 7 days. The Completion Time of 7 days is based on the relatively low probability of an event requiring PAM instrument operation and the availability of alternate means to obtain the required information.

Continuous operation with two required channels inoperable in a Function is not acceptable because the alternate indications may not fully meet all performance qualification requirements applied to the PAM instrumentation. Therefore, requiring restoration of one inoperable channel of the Function limits the risk that the PAM Function will be in a degraded condition should an accident occur.

D.1 This Required Action directs entry into the appropriate Condition referenced in Table 3.3.3.1-1. The applicable Condition referenced in the Table is Function dependent. Each time an inoperable channel has not met any Required Action of Condition C, as applicable, and the associated Completion Time has expired, Condition D is entered for that channel and provides for transfer to the appropriate subsequent Condition.

E.1 For the majority of Functions in Table 3.3.3.1-1, if any Required Action and associated Completion Time of Condition C are not met, the plant must be brought to a MODE in which the LCO 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 />.

The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions

{continued)

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- PAM Instrumentation B 3.3.3.1 BASES ACTIONS E.1 (continued) from full power conditions in an orderly manner and without challenging plant systems.

F.1 Since alternate means of monitoring primary containment area radiation have been developed and tested, the Required Action is not to shut down the plant, but rather to follow the directions of Specification 5.6.7. These alternate means will be temporarily installed if the normal PAM channel cannot be restored to OPERABLE status within the allotted time. The report provided to the NRC should discuss the alternate means used, describe the degree to which the alternate means are equivalent to the installed PAM channels, justify the areas in which they are not equivalent, and provide a schedule for restoring the normal PAM channels.

SURVEILLANCE The following SRs apply to each PAM instrumentation Function in REQUIREMENTS Table 3.3.3.1-1.

SR 3.3.3.1.1 Performance of the CHANNEL CHECK once every 31 days ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel against a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious.

A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria which are determined by the plant staff based on an investigation of a combination of the channel instrument uncertainties, may be used to support this (continued)

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_ - - PAR Instrumentation B 3.3.3.1 BASES SURVEILLANCE SR 3.3.3.1.1 (continued)

REQUIREMENTS parameter comparison and include indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit and does necessarily indicate the channel is Inoperable.

The Frequency of 31 days is based upon plant operating experience, with regard to channel OPERABILITY and drift, which demonstrates that failure of more than one channel of a given Function in any 31 day interval is rare. The CHANNEL CHECK supplements less formal checks of channels during normal operational use of those displays associated with the required channels of this LCO.

SR 3.3.3.1.2 and SR 3.3.3.1.3 A CHANNEL CALIBRATION is performed every 92 days for the containment Hydrogen and Oxygen Analyzers or 24 months for the other Functions except for the PCIV Position Function. The PCIV Position Function is adequately demonstrated by the Remote Position Indication performed in accordance with 5.5.6, "Inservice Testing Program".

CHANNEL CALIBRATION verifies that the channel responds to measured parameter with the necessary range and accuracy, and does not include alarms.

The CHANNEL CALIBRATION for the Containment High Radiation instruments shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/hr and a one point calibration check of the detector below 10 R/hr with an installed or portable gamma source.

The CHANNEL CALIBRATION for the hydrogen analyzers, use a sample gas containing: a) Nominal zero volume percent hydrogen, balance nitrogen and b) Nominal thirty volume percent hydrogen, balance nitrogen.

The Frequency is based on operating experience and for the 24 month Frequency consistency with the industry refueling cycles.

(continued)

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PPL Rev. 4 PAM Instrumentation B 3.3.3.1 BASES REFERENCES 1. Regulatory Guide 1.97 Rev. 2, "Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident," February 6, 1985

2. Nuclear Regulatory Commission Letter A. Schwencer to N. Curtis, Emergency Response Capability, Conformance to R.G. 1.97, Rev. 2, I dated February 6, 1985.

l.

3. PP&L Letter (PLA-2222), N. Curtis to A. Schwencer, dated May 31, 1984.

4. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 32193)

5. NEDO-31558A, BWROG Topical Report, Position on NRC Reg.

Guide 1.97, Revision 3 Requirements for Post Accident Neutron Monitoring System (NMS)..-

,6. Nuclear Regulatory Commission Letter from C. Poslusny to R.G.

Byram dated July 3, 1996.

,i SUSQUEHANNA - UNIT 1 TS / B 3.3-75 Revision 2 1

I PPL Rev. 4 PAM Instrumentation B 3.3.3.1 TABLE B 3.3.3.1-1 Post Accident Instruments (Page 1 of 3)

Instrument/Variable Elemen Transmitter Recorder Indicator

1. Reactor Steam UR-4201A Pl-1 4202A Dome Pressure N/A PT-1 4201A (red)* Pl-14202Al

. Pl-14204A

.UR-4201B PI-14202B (left side)

N/A PT-14201B( PI-14202B1 -(left side)

PI-14204B (left side)

2. Reactor Vessel N4201A LI- (left side)

Water Level N/A LTLI-14201A1 (left side)

(Wide Range) (blue)* LI-I14201A (letside)

LT1401 U-120B LI-14203B (left side)

N/* L-40AN/A 1-I-14201A31 (right side)

L-14201A (right side) 1' (E~xtended

..N/A Range)

LT1403 NIA _ LI- 14203B L-I14201A (right side)~1 (right side)

N/A - T1403.;::NA 1N/A (ul IA Zn oag)

I-14201A1 (right side)

(Extended Range) LI-I42038 (right side)

N/A (Fue LT-14207BZone1 (1B1raigheide UR-15776A N/A

.(Winded Range)

I LT-14202B UR-15776B N

. 0NA T- o 3 1 3 3 . (FuerZone N/A

______ _ a(Wi e )R RanBe)

Nrrw nage e

wA(bluej- R-576 UL-15775A3 fgt ie LT-14202BUR576 N/

N/A (Wide)Rne 3.SprsinLT-15776A UR-1 5776A L- 75 LT-1 57758 UR-I157768A II 75 TS-Prop/3.3/SA33031 A.B1 B I Iv I-SUSQUEHANNA- UNIT 1 TS / B 3.3-75a :Revision 5

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- PAM Instrumentation B 3.3.3.1 I TABLE B 3.3.3.1-1 Post Accident Instruments (Page 2 of 3)

Instrument/Variable Element Transmitter Recorder Indicator

4. Primary -PT-I15709A Containment N/A to 250 i UR-15701A (Dark Blue)* N/A Pressure PT-I 5709B N/A (0 0 UR-1 5701 B (Dark Blue)* N/A PT-15710A N/A (-15 to 65 psig) UR-15701A (Red)* N/A PT-I15710OB N/A (-15 to 65 psig) UR-1 5701 B (Red)* N/A

5. Primary RE-15720A RITS-15720A UR-15776A (Green)* N/A Containment High Radiation H RE-15720B RITS-15720B UR-15776B (Green)* N/A

6. I Position See Technical Specification Bases Table B 3.6.1.3-1 for PCIV that require position indication to be OPERABLE

7. Neutron Flux N/A APRM1 NR-C51-1R603A N/A (red pen)*

N/A APRM-2 NR-C51-I R603B (red pen)* N/A N/A APRM-3 NR-G51-1R603C N/A

____ ____(red pen)*

N/A APRM-4 NR-C51-1R603D N/A

_ _ __ __ _ _ __ _ __ _ _ _ _ _ _(red pen)*

8.CnanetAE-15745A AT74A UR-15701 A (Blue Violet)*N/

Oxygen and AT175 /

Hydrogen Analyzer (Hydrogen) UR-15701A (Violet)*

AE-15745B AlT 15745B UR-15701B (Blue Violet)* N/A (Hydrogen) UR-15701 B (Violet)* _

AE15746A AIT-15746A UR-15701A (Orange)* N/A

_____ =(Oxygen) AIT-15746B UR-15701 B_(Orage)*_N AE176.AIT-15746B UR-15701 B (Orange)* N/A

_ __ _ _ __ __ _ _ _ _ _ _ _ _ _ ( Ox g en) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __I_ _ _ _ _ _ _ _

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. TABLE B 3.3.3.1-1

. Post Accident Instruments -

(Page 3 of 3)

Instrument/ariable Element Transmitter Recorder Indicator

9. Drywell Atmosphere TEI579OA flI579OA UR-15701A (Brown); N/A I Temperature TR-15790A,(point #1) _____

TE-1 5790B TT-1 5790B (poi/A;# I)NA (point NR15790BI

__________TR-15790B

10. Suppression TE-15753 TX-15751 N/A TIAH-15751*

Chamber Water TE-1 5755 TIA-5751 Temperature TE-15757 TE-1 5759 TE-1 5763 TE-I 5765, TE-1 5767

-__ iTE-15769 TE-15752 N/A TIAH-15752*

TE-15754 TI-1 5752 TE-15758 TE-15760 TE-15762 TE-1 5766 TE-1 5768 TE-15770 .  : :_.

• Indicates that the instrument (and associated components in the instrument channel) is considered as instrument channel surveillance acceptance criteria.

~i (1) In the case of the inner ring Indicators for extended range level, it is recommended that LU-14201A and Ll-14201B be used as acceptance criteria, however LI-14201A1, L!-14201B61, LI-14203A, or LI-14203B may be used in their place provided that surveillance requirements are satisfied. Only one set of these instruments needs to be OPERABLE.

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