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Revisions to Technical Specification Bases Manual
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SSES MANUAL Manual Name:

TSBl Manual

Title:

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

07/09/2010 Procedure Name Rev TEXT LOES 99

Title:

LIST OF EFFECTIVE SECTIONS Issue Date 07/09/2010 Change ID Change Number TEXT TOC

Title:

TABLE OF CONTENTS 19 04/27/2010 TEXT 2.1.1 5

05/06/2009

Title:

SAFETY LIMITS (SLS)

REACTOR CORE SLS TEXT 2.1.2 1

Title:

SAFETY LIMITS (SLS)

REACTOR 10/04/2007 COOLANT SYSTEM (RCS)

PRESSURE S TEXT 3.0 3

08/20/2009

Title:

LIMITING CONDITION FOR OPERATION (LCO)

APPLICABILITY TEXT 3. 1.1

Title:

REACTIVITY TEXT 3.1.2

Title:

REACTIVITY TEXT 3.1.3

Title:

REACTIVITY TEXT 3.1.4

Title:

REACTIVITY TEXT 3.1.5

Title:

REACTIVITY TEXT 3.1.6 1

CONTROL SYSTEMS 04/18/2006 SHUTDOWN MARGIN (SDM) 0 11/15/2002 CONTROL SYSTEMS REACTIVITY ANOMALIES 2

CONTROL SYSTEMS 4

CONTROL SYSTEMS 01/19/2009 CONTROL ROD OPERABILITY 01/30/2009 CONTROL ROD SCRAM TIMES 1

07/06/2005 CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS 2

04/18/2006

Title:

REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL Pagel of 8 Report Date: 07/09/10 Page 1 of

.8 Report Date: 07/09/10

SSES MANUAL Manual Name:

TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.1.7

Title:

REACTIVITY CONTROL TEXT 3.1.8

Title:

REACTIVITY CONTROL TEXT 3.2.1

Title:

POWER DISTRIBUTION 3

04/23/2008 SYSTEMS STANDBY LIQUID CONTROL (SLC)

SYSTEM 3

05/06/2009 SYSTEMS SCRAM DISCHARGE VOLUME (SDV)

VENT AND DRAIN VALVES 2

04/23/2008 LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

TEXT 3.2.2 3

05/06/2009

Title:

POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)

TEXT 3.2.3 2

04/23/2008

Title:

POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)

TEXT 3.3.1.1 4

04/23/2008

Title:

INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS)

INSTRUMENTATION TEXT 3.3.1.2 2

01/19/2009

Title:

INSTRUMENTATION SOURCE RANGE MONITOR (SRM)

INSTRUMENTATION TEXT 3.3.2.1 3

04/23/2008

Title:

INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2

Title:

INSTRUMENTATION TEXT 3.3.3.1

Title:

INSTRUMENTATION 2

04/05/2010 FEEDWATER MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION 8

10/27/2008 POST ACCIDENT MONITORING (PAM)

INSTRUMENTATION TEXT 3.3.3.2 1

04/18/2005

Title:

INSTRUMENTATION REMOTE SHUTDOWN SYSTEM TEXT 3.3.4.1 1

04/23/2008

Title:

INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)

INSTRUMENTATIO9 Page 2 of

.8 Report Date: 07/09/10

SSES MANUAL Manual Name:

TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.3.4.2 0

11/15/2002

Title:

INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP (ATWS-RPT)

INSTRUMENTATION TEXT 3.3.5.1 3

08/20/2009

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 4

04/23/2008

Title:

INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.6.2 3

10/27/2008

Title:

INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION I

TEXT 3.3.7.1 2

10/27/2008

Title:

INSTRUMENTATION CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)

SYSTEM INSTRUMENTATION TEXT 3.3.8.1 2

12/17/2007

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 4

04/27/2010

Title:

REACTOR COOLANT SYSTEM (RCS)

RECIRCULATION LOOPS OPERATING TEXT 3.4.2 2

04/27/2010

Title:

REACTOR COOLANT SYSTEM (RCS)

JET PUMPS TEXT 3.4.3 2

04/23/2008

Title:

REACTOR COOLANT SYSTEM RCS SAFETY RELIEF VALVES S/RVS D

TEXT 3.4.4 0

11/15/2002

Title:

REACTOR COOLANT SYSTEM (RCS)

RCS OPERATIONAL LEAKAGE Page 3 of8 Report Date: 07/09/10

SSES MANUJAL Manual Name:

TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.4.5 1

01/16/2006

Title:

REACTOR COOLANT SYSTEM (RCS)

RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE TEXT 3.4.6 2

08/20/2009

Title:

REACTOR COOLANT SYSTEM (RCS)

RCS LEAKAGE DETECTION INSTRUMENTATION 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 TEXT 3.5.1 2

10/04/2007 SYSTEM (RCS)

RCS SPECIFIC ACTIVITY 1

04/18/2005 SYSTEM (RCS)

RESIDUAL HEAT REMOVAL (RHR)

SHUTDOWN COOLING SYSTEM 0

11/15/2002 SYSTEM (RCS)

RESIDUAL HEAT REMOVAL (RHR)

SHUTDOWN COOLING 3

04/23/2008 SYSTEM (RCS)

RCS PRESSURE AND TEMPERATURE (P/T) LIMITS SYSTEM 0

11/15/2002 SYSTEM (RCS)

REACTOR STEAM DOME PRESSURE 2

01/16/2006

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS)

AND REACTOR CORE ISOLATION SYSTEM ECCS -

OPERATING TEXT 3.5.2 0

11/15/2002

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS)

AND REACTOR CORE ISOLATION SYSTEM ECCS -

SHUTDOWN TEXT 3.5.3 2

07/09/2010

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS)

AND REACTOR CORE ISOLATION SYSTEM RCIC SYSTEM COOLING (RCIC)

COOLING (RCIC)

TEXT 3.6.1.1 3

04/23/2008

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT TEXT 3.6.1.2 1

04/23/2008

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK Page4 of 8 Report Date: 07/09/10 Page 4 of

.8 Report Date: 07/09/10

SSES MANUAL Manual Name:

TSBl Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.1.3

Title:

CONTAINMENT TEXT 3.6.1.4

Title:

CONTAINMENT 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 TEXT 3.6.4.1 9

04/14/2010 SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)

LDCN 3092 1

04/23/2008 SYSTEMS CONTAINMENT PRESSURE 1

10/05/2005 SYSTEMS DRYWELL AIR TEMPERATURE 0

11/15/2002 SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS 2

04/23/2008 SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE 0

11/15/2002 SYSTEMS SUPPRESSION POOL WATER LEVEL 1

01/16/2006 SYSTEMS RESIDUAL HEAT REMOVAL (RHR)

SUPPRESSION POOL COOLING 0

11/15/2002 SYSTEMS RESIDUAL HEAT REMOVAL (RHR)

SUPPRESSION POOL SPRAY 2

06/13/2006 SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS 1

04/18/2005 SYSTEMS DRYWELL AIR FLOW SYSTEM 0

11/15/2002 SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION 7

10/04/2007

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT Page~

of 8

Report Date: 07/09/10 Page 5 of 8

Report Date: 07/09/10

SSES MANUAL Manual Name:

TSBI Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.4.2 3

03/10/2010

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)

TEXT 3.6.4.3 4

09/21/2006

Title:

CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT)

SYSTEM TEXT 3.7.1

Title:

PLANT SYSTEMS ULTIMATE HEAT TEXT 3.7.2

Title:

PLANT SYSTEMS TEXT 3.7.3

Title:

PLANT SYSTEMS TEXT 3.7.4

Title:

PLANT SYSTEMS TEXT 3.7.5

Title:

PLANT SYSTEMS TEXT 3.7.6

Title:

PLANT SYSTEMS TEXT 3.7.7

Title:

PLANT SYSTEMS TEXT 3.7.8

Title:

PLANT SYSTEMS TEXT 3.8.1 4

04/05/2010 RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW)

SYSTEM AND THE SINK (UHS) 2 02/11/2009 EMERGENCY SERVICE WATER (ESW)

SYSTEM 1

01/08/2010 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)

SYSTEM 0

11/15/2002 CONTROL ROOM FLOOR COOLING SYSTEM 1

10/04/2007 MAIN CONDENSER OFFGAS 2

04/23/2008 MAIN TURBINE BYPASS SYSTEM 1

10/04/2007 SPENT FUEL STORAGE POOL WATER LEVEL 0

04/23/2008 6

05/06/2009

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES -

OPERATING TEXT 3.8.2 0

11/15/2002

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES -

SHUTDOWN Pages of 8 Report Date: 07/09/10 Page 6 of 8 Report Date: 07/09/10

SSES MANUAL Manual Name:

TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.8.3

Title:

ELECTRICAL TEXT 3.8.4

Title:

ELECTRICAL TEXT 3.8.5

Title:

ELECTRICAL TEXT 3.8.6

Title:

ELECTRICAL TEXT 3.8.7

Title:

ELECTRICAL TEXT 3.8.8

Title:

ELECTRICAL 2

04/14/2010 POWER SYSTEMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR 3

01/19/2009 POWER SYSTEMS DC SOURCES -

OPERATING 1

12/14/2006 POWER SYSTEMS DC SOURCES -

SHUTDOWN 1

POWER SYSTEMS 12/14/2006 BATTERY CELL PARAMETERS 1

10/05/2005 POWER SYSTEMS DISTRIBUTION SYSTEMS -

OPERATING 0

11/15/2002 POWER SYSTEMS DISTRIBUTION SYSTEMS -

SHUTDOWN TEXT 3.9.1

Title:

REFUELING TEXT 3.9.2

Title:

REFUELING TEXT 3.9.3

Title:

REFUELING TEXT 3.9.4

Title:

REFUELING TEXT 3.9.5

Title:

REFUELING TEXT 3.9.6

Title:

REFUELING OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 0

11/15/2002 REFUELING EQUIPMENT INTERLOCKS 0

11/15/2002 REFUEL POSITION ONE-ROD-OUT INTERLOCK 0

11/15/2002 CONTROL ROD POSITION 0

11/15/2002 CONTROL ROD POSITION INDICATION 0

11/15/2002 CONTROL ROD OPERABILITY -

REFUELING 1

10/04/2007 OPERATIONS REACTOR PRESSURE VESSEL (RPV)

WATER LEVEL Pagel of 8

Report Date: 07/09/10 Page 7 of

.8 Report Date: 07/09/10

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 TEXT 3.9.8 0

11/15/2002

Title:

REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR)

LOW WATER LEVEL TEXT 3.10.1

Title:

SPECIAL TEXT 3.10.2

Title:

SPECIAL TEXT 3.10.3

Title:

SPECIAL TEXT 3.10.4

Title:

SPECIAL TEXT 3.10.5

Title:

SPECIAL TEXT 3.10.6

Title:

SPECIAL TEXT 3.10.7

Title:

SPECIAL TEXT 3.10.8

Title:

SPECIAL OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 1

01/23/2008 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 0

11/15/2002 SINGLE CONTROL ROD WITHDRAWAL -

COLD SHUTDOWN 0

11/15/2002 SINGLE CONTROL ROD DRIVE (CRD)

REMOVAL -

REFUELING 0

11/15/2002 MULTIPLE CONTROL ROD WITHDRAWAL -

REFUELING 1

04/18/2006 CONTROL ROD TESTING -

OPERATING 1

04/12/2006 SHUTDOWN MARGIN (SDM)

TEST -

REFUELING Page~

of 8

Report Date: 07/09/10 Page 8 of 8 Report Date: 07/09/10

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

Section Title Revision TOC Table of Contents 19 B 2.0 SAFETY LIMITS BASES Page B 2.0-1 0

Page TS / B 2.0-2 3

Page TS I B 2.0-3 5

Page TS I B 2.0-4 3

Page TS / B 2.0-5 5

Page TS / B 2.0-6 1

Pages TS / B 2.0-7 through TS / B 2.0-9 1

B 3.0 LCO AND SR APPLICABILITY BASES Page TS / B 3.0-1 1

Pages TS I B 3.0-2 through TS / B 3.0-4 0

Pages TS I B 3.0-5 through TS / B 3.0-7 1

Page TS / B 3.0-8 3

Pages TS I B 3.0-9 through TS / B 3.0-11 2

Page TS I B 3.0-11 a 0

Page TS / B 3.0-12 1

Pages TS / B 3.0-13 through TS I B 3.0-15 2

Pages TS I B 3.0-16 and TS / B 3.0-17 0

B 3.1 REACTIVITY CONTROL BASES Pages B 3.1-1 through B 3.1-4 0

Page TS I B 3.1-5 1

Pages TS / B 3.1-6 and TS / B 3.1-7 2

Pages B 3.1-8 through B 3.1-13 0

Page TS / B 3.1-14 1

Page B 3.1-15 0

Page TS / B 3.1-16 1

Pages B 3.1-17 through B 3.1-19 0

Pages TS / B 3.1-20 and TS / B 3.1-21 1

Page TS / B 3.1-22 0

Page TS / B 3.1-23 1

Page TS / B 3.1-24 0

Pages TS / B 3.1-25 through TS / B 3.1-27 1

Page TS I B 3.1-28 2

Page TS I B 3.1-29 1

Pages B 3.1-30 through B 3.1-33 0

Pages TS / B 3.3-34 through TS / B 3.3-36 1

Pages TS I B 3.1-37 and TS / B 3.1-38 2

Pages TS / B 3.1-39 and TS / B 3.1-40 2

Page TS / B 3.1-40a 0

Pages TS / B 3.1-41 and TS / B 3.1-42 2

SUSQUEHANNA

- UNiT I TSIB LOES-1 Revision 99 SUSQUEHANNA - UNIT 1 TS / B LOES-1 Revision 99

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

Section Title Revision Page TS / B 3.1.43 1

Page TS / B 3.1-44 0

Page TS / B 3.1-45 3

Pages TS / B 3.1-46 through TS I B 3.1-49 1

Page TS / B 3.1-50 0

Page TS I B 3.1-51 3

B 3.2 POWER DISTRIBUTION LIMITS BASES Page TS / B 3.2-1 2

Pages TS / B 3.2-2 and TS / B 3.2-3 3

Pages TS I B 3.2-4 and TS I B 3.2-5 2

Page TS / B 3.2-6 3

Page B 3.2-7 1

Pages TS / B 3.2-8 and TS / B 3.2-9 3

Page TS / B 3.2.10 2

Page TS / B 3.2-11 3

Page TS / B 3.2-12 1

Page TS / B 3.2-13 2

B 3.3 INSTRUMENTATION Pages TS I B 3.3-1 through TS I B 3.3-4 1

Page TS / B 3.3-5 2

Page TS I B 3.3-6 1

Page TS / B 3.3-7 3

Page TS / B 3.3-7a 1

Page TS / B 3.3-8 4

Pages TS / B 3.3-9 through TS I B 3.3-12 3

Pages TS / B 3.3-12a 1

Pages TS / B 3.3-12b and TS / B 3.3-12c 0

Page TS / B 3.3-13 1

Page TS I B 3.3-14 3

Pages TS I B 3.3-15 and TS / B 3.3-16 1

Pages TS I B 3.3-17 and TS / B 3.3-18 4

Page TS I B 3.3-19 1

Pages TS / B 3.3-20 through TS / B 3.3-22 2

Page TS / B 3.3-22a 0

Pages TS / B 3.3-23 and TS / B 3.3-24 2

Pages TS I B 3.3-24a and TS / B 3.3-24b 0

Page TS I B 3.3-25 3

Page TS I B 3.3-26 2

Page TS I B 3.3-27 1

Pages TS I B 3.3-28 through TS I B 3.3-30 3

Page TS / B 3.3-30a 0

SUSQUEHANNA - UNIT I TS I B LOES-2 Revision 99

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

Section Title Revision Page TS / B 3.3-31 4

Page TS / B 3.3-32 5

Pages TS / B 3.3-32a 0

Page TS I B 3.3-32b 1

Page TS / B 3.3-33 5

Page TS / B 3.3-33a 0

Page TS / B 3.3-34 1

Pages TS I B 3.3-35 and TS / B 3.3-36 2

Pages TS / B 3.3-37 and TS ( B 3.3-38 1

Page TS / B 3.3-39 2

Pages TS / B 3.3-40 through TS I B 3.3-43 1

Page TS / B 3.3-44 4

Pages TS / B 3.3-44a and TS / B 3.3-44b 0

Page TS / B 3.3-45 3

Pages TS / B 3.3-45a and TS / B 3.3-45b 0

Page TS / B 3.3-46 3

Pages TS / B 3.3-47 2

Pages TS / B 3.3-48 through TS / B 3.3-51 3

Pages TS / B 3.3-52 and TS / B 3.3-53 2

Page TS I B 3-3-53a 0

Page TS I B 3.3-54 4

Page TS / B 3.3-55 2

Pages TS / B 3.3-56 and TS / B 3.3-57 1

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Page TS / B 3.3-59 1

Page TS / B 3.3-60 0

Page TS / B 3.3-61 1

Pages TS / B 3.3-62 and TS / 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

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Pages TS / B 3.3-70 4

Page TS / B 3.3-71 3

Pages TS / B 3.3-72 and TS / B 3.3-73 2

Page TS / B 3.3-74 3

Page TS / B 3.3-75 2

Page TS / B 3.3-75a 6

Page TS / B 3.3-75b 7

Page TS / B 3.3-75c 5.

SUSQUEHANNA-UNITI TSIB LOES-3 Revision 99 SUSQUEHANNA - UNIT 1 TS / B LOES-3 Revision 99

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

Section Title Revision Pages B 3.3-76 through 3.3-77 0

Page TS I B 3.3-78 1

Pages B 3.3-79 through B 3.3-81 0

Page B 3.3-82 1

Page B 3.3-83 0

Pages B 3.3-84 and B 3.3-85 1

Page B 3.3-86 0

Page B 3.3-87 1

Page B 3.3-88 0

Page B 3.3-89 1

Page TS / B 3.3-90 1

Page B 3.3-91 0

Pages TS / B 3.3-92 through TS I B 3.3-100 1

Pages TS I B 3.3-101 through TS / B 3.3-103 0

Page TS / B 3.3-104 2

Pages TS / B 3.3-105 and TS / B 3.3-106 0

Page TS I B 3.3-107 1

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Page TS / B 3.3-109 1

Pages TS / B 3.3-110 and TS / B 3.3-111 0

Pages TS/B 3.3-112 and TS I B 3.3-112a 1

Pages TS / B 3.3-113 through TS / B 3.3-115 1

Page TS / B 3.3-116 3

Page TS / B 3.3-117 1

Pages TS / B 3.3-118 through TS / B 3.3-122 0

Pages TS / B 3.3-123 and TS / B 3.3-124 1

Page TS / B 3.3-124a 0

Page TS / B 3.3-125 0

Pages TS / B 3.3-126 and TS / B 3.3-127 1

Pages TS / B 3.3-128 through TS/ B 3.3-130 0

Page TS / B 3.3-131 1

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Pages B 3.3-135 through B 3.3-137 0

Page TS / B 3.3-138 1

Pages B 3.3-139 through B 3.3-149 0

Pages TS / B 3.3-150 and TS / B 3.3-151 1

Pages TS / B 3.3-152 through TS / B 3.3-154 2

Page TS / B 3.3-155 1

Pages TS / B 3.3-156 through TS / B 3.3-158 2

Pages TS I B 3.3-159 through TS / B 3.3-162 1

Page TS / B 3.3-163 2

Pages TS / B 3.3-164 and TS / B 3.3-165 1

Pages TS / B 3.3-166 and TS / B 3.3-167 2

SUSQUEHANNA - UNIT 1SUSQUEHANNA

- UNIT 1 TS I B LOES-4 Revision 99 TS I B LOES-4 Revision 99

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

Section Title Revision Pages TS / B 3.3-168 and TS / B 3.3-169 1

Page TS I B 3.3-170 2

Pages TS I B 3.3-171 through TS / B 3.3-177 1

Pages TS / B 3.3-178 through TS / B 3.3-179a 2

Pages TS / B 3.3-179b and TS / B 3.3-179c 0

Page TS / B 3.3-180 1

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Page TS / B 3.3-182 1

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

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TS1 Text LOES.doc 71612010 SUSQUEHANNA - UNIT 1 TS I B LOES-lO Revision 99 SUSQUEHANNA - UNIT I TS I B LOES-1 0 Revision 99

PPL Rev. 2 RCIC System B 3.5.3 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM B 3.5.3 RCIC System BASES BACKGROUND The RCIC System is not part of the ECCS; however, the RCIC System is included with the ECCS section because of their similar functions.

The RCIC System is designed to operate either automatically or manually following reactor pressure vessel (RPV) isolation accompanied by a loss of coolant flow from the feedwater system to provide adequate core cooling and control of the RPV water level. Under these conditions, the High Pressure Coolant Injection (HPCI) and RCIC systems perform similar functions. The RCIC System design requirements ensure that the criteria of Reference I are satisfied.

The RCIC System (Ref. 2) consists of a steam driven turbine pump unit, piping, and valves to provide steam to the turbine, as well as piping and valves to transfer water from the suction source to the core via the feedwater system line, where the coolant is distributed within the RPV through the feedwater sparger. Suction piping is provided from the condensate storage tank (CST) and the suppression pool. Pump suction is normally aligned to the CST to minimize injection of suppression pool water into the RPV. However, if the CST water supply is low, an automatic transfer to the suppression pool water source ensures an adequate suction head for the pump and an uninterrupted water supply for continuous operation of the RCIC System. The steam supply to the turbine is piped from a main steam line upstream of the associated inboard main steam line isolation valve.

The RCIC System is designed to provide core cooling for a wide range of reactor pressures (165 psia to 1225 psia). Upon receipt of an initiation signal, the RCIC turbine accelerates to a specified speed. As the RCIC flow increases, the turbine control valve is automatically adjusted to maintain design flow. Exhaust steam from the RCIC turbine is discharged to the suppression pool. A full flow test line is provided to route water to the CST to allow testing of the RCIC System during normal operation without injecting water into the RPV.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.5-25 Revision 1

PPL Rev. 2 RCIC System B 3.5.3 BASES BACKGROUND (continued)

The RCIC pump is provided with a minimum flow bypass line, which discharges to the suppression pool. The valve in this line automatically opens to prevent pump damage due to overheating when other discharge line valves are closed. To ensure rapid delivery of water to the RPV and to minimize water hammer effects, the RCIC System discharge piping is kept full of water. The RCIC System is normally aligned to the CST. The RCIC discharge line is kept full of water using a "keep fill" system supplied by the condensate transfer system.

APPLICABLE The function of the RCIC System is to respond to transient events by SAFETY providing makeup coolant to the reactor. The RCIC System is not an ANALSES Engineered Safety Feature System and no credit is taken in the safety analyses for RCIC System operation. Based on its contribution to the reduction of overall plant risk, however, the system is included in the Technical Specifications, as required by the NRC Policy Statement (Ref.

4).

LCO The OPERABILITY of the RCIC System provides adequate core cooling such that actuation of any of the low pressure ECCS subsystems is not required in the even of RPV isolation accompanied by a loss of feedwater flow. The RCIC System has sufficient capacity for maintaining RPV inventory during an isolation event.

APPLICABILITY The RCIC System is required to be OPERABLE during MODE 1, and MODES 2 and 3 with reactor steam dome pressure > 150 psig, since RCIC is the primary non-ECCS water source for core cooling when the reactor is isolated and pressurized. In MODES 2 and 3 with reactor steam dome pressure < 150 psig, and in MODES 4 and 5, RCIC is not required to be OPERABLE since the low pressure ECCS injection/spray subsystems can provide sufficient flow to the RPV.

ACTIONS A Note prohibits the application of LCO 3.0.4.b to an inoperable RCIC system. There is an increased risk associated with entering a MODE or other specified condition in the Applicability with an inoperable RCIC system and the provisions of LCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.

(continued)

SUSQUEHANNA-UNIT 1 TS / B 3.5-26 Revision 1

PPL Rev. 2 RCIC System B 3.5.3 BASES ACTIONS A.1 and A.2 (continued)

If the RCIC is inoperable during MODE 1, or MODE 2 or 3 with reactor steam dome pressure > 150 psig, and the HPCI System is verified to be OPERABLE, the RCIC System must be restored to OPERABLE status within 14 days. In this Condition, loss of the RCIC System will not affect the overall plant capability to provide makeup inventory at high reactor pressure since the HPCI System is the only high pressure system assumed to function during a loss of coolant accident (LOCA).

OPERABILITY of HPCI is therefore verified immediately when the RCIC System is inoperable. This may be performed as an administrative check, by examining logs or other information, to determine if HPCI is out of service for maintenance or other reasons. It does not mean it is necessary to perform the Surveillances needed to demonstrate the OPERABILITY of the HPCI System. If the OPERABILITY of the HPCI System cannot be verified, however, Condition B must be immediately entered. For transients and certain abnormal events with no LOCA, RCIC (as opposed to HPCI) is the preferred source of makeup coolant because of its relatively small capacity, which allows easier control of the RPV water level. Therefore, a limited time is allowed to restore the inoperable RCIC to OPERABLE status.

The 14 day Completion Time is based on a reliability study (Ref. 3) that evaluated the impact on ECCS availability, assuming various components and subsystems were taken out of service. The results were used to calculate the average availability of ECCS equipment needed to mitigate the consequences of a LOCA as a function of HPCI and RCIC, the AOTs (i.e., Completion Times) determined for HPCI are also applied to RCIC.

B.1 and B.2 If the RCIC System cannot be restored to OPERABLE status within the associated Completion Time, or if the HPCI System is simultaneously inoperable, the plant must be brought to a condition 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and reactor steam dome pressure reduced to _< 150 psig within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times (continued)

SUSQUEHANNA - UNIT 1 TS / B 3.5-27 Revision 1

PPL Rev. 2 RCIC System B 3.5.3 BASES ACTIONS B.1 and B.2 (continued) are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in a orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.5.3.1 REQUIREMENTS The flow path piping has the potential to develop voids and pockets of entrained air. Maintaining the pump discharge line of the RCIC System full of water ensures that the system will perform properly, injecting its full capacity into the Reactor Coolant System upon demand. This will also prevent a water hammer following an initiation signal. One acceptable method of ensuring the line is full is to vent at the high points. The 31 day Frequency is based on the gradual nature of void buildup in the RCIC piping, the procedural controls governing system operation, and operating experience.

SR 3.5.3.2 Verifying the correct alignment for manual, power operated, and automatic valves in the RCIC flow path provides assurance that the proper flow path will exist for RCIC operation. The SR does not apply to valves that are locked, sealed, or otherwise secured in position since these valves were verified to be in the correct position prior to locking, sealing, or securing.

A valve that receives an initiation signal is allowed to be in a nonaccident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of potentially being mispositioned are in the correct position. This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves. For the RCIC System, this SR also includes the steam flow path for the turbine and the flow controller position.

The 31 day Frequency of this SR was derived from the Inservice Testing Program requirements for performing valve testing at least once every 92 days. The Frequency of (continued)

SUSQUEHANNA - UNIT 1 TS I B 3.5-28 Revision 0

PPL Rev. 2 RCIC System B 3.5.3 BASES SURVEILLANCE SR 3.5.3.2 (continued)

REQUIREMENTS 31 days is further justified because the valves are operated under procedural control and because improper valve position would affect only the RCIC System. This Frequency has been shown to be acceptable through operating experience.

SR 3.5.3.3 and SR 3.5.3.4 The RCIC pump flow rates ensure that the system can maintain reactor coolant inventory during pressurized conditions with the RPV isolated.

The flow tests for the RCIC System are performed at two different pressure ranges such that system capability to provide rated flow is tested both at the higher and lower operating ranges of the system. Additionally, adequate steam flow must be passing through the main turbine or turbine bypass valves to continue to control reactor pressure when the RCIC System diverts steam flow. Reactor steam pressure is considered adequate when Ž_ 920 psig to perform SR 3.5.3.3 and > 150 psig to perform SR 3.5.3.4. However, the requirements of SR 3.5.3.4 are met by a successful performance at any pressure _< 165 psig. Adequate steam flow is represented by at least 1.25 turbine bypass valves open.

Therefore, sufficient time is allowed after adequate pressure and flow are achieved to perform these SRs. Reactor startup is allowed prior to performing the low pressure Surveillance because the reactor pressure is low and the time allowed to satisfactorily perform the Surveillance is short.

The reactor pressure is allowed to be increased to normal operating pressure since it is assumed that the low pressure Surveillance has been satisfactorily completed and there is no indication or reason to believe that RCIC is inoperable. Therefore, these SRs are modified by Notes that state the Surveillances are not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the reactor steam pressure and flow are adequate to perform the test.

The Frequency for SR 3.5.3.3 is determined by the Inservice Testing Program requirements. The 24 month Frequency for SR 3.5.3.4 is based on the need to perform the Surveillance under conditions that apply just prior to or during a startup from a plant outage. Operating experience has shown that these components usually pass the SR when performed at the 24 month Frequency, which is based on the refueling (continued)

SUSQUEHANNA - UNIT 1 TS / B 3.5-29 Revision 1

PPL Rev. 2 RCIC System B 3.5.3 BASES SURVEILLANCE SR 3.5.3.3 and SR 3.5.3.4 (continued)

REQUIREMENTS cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

SR 3.5.3.5 The RCIC System is required to actuate automatically in order to verify its design function satisfactorily. This Surveillance verifies that, with a required system initiation signal (actual or simulated), the automatic initiation logic of the RCIC System will cause the system to operate as designed, including actuation of the system throughout its emergency operating sequence; that is, automatic pump startup and actuation of all automatic valves to their required positions. This test also ensures the RCIC System will automatically restart on an RPV low water level (Level 2) signal received subsequent to an RPV high water level (Level 8) trip and that the suction is automatically transferred from the CST to the suppression pool. The LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.2 overlaps this Surveillance to provide complete testing of the assumed safety function.

The 24 month Frequency is based on the need to perform portions of the

.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 that these components usually pass the SR when performed at the 24 month Frequency, which is based on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

This SR is modified by a Note that excludes vessel injection during the Surveillance. Since all active components are testable and full flow can be demonstrated by recirculation through the test line, coolant injection into the RPV is not required during the Surveillance.

REFERENCES

1.

10 CFR 50, Appendix A, GDC 33.

2.

FSAR, Section 5.4.6.

(continued)

SUSQUEHANNA-UNIT 1 TS / B 3.5-30 Revision 0

PPL Rev. 2 RCIC System B 3.5.3 BASES REFERENCES

3.

Memorandum from R. L. Baer (NRC) to V. Stello, Jr. (NRC),

(continued)

"Recommended Interim Revisions to LCOs for ECCS Components," December 1, 1975.

4.

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

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