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SSES MANUJTAL Manual Name:

TSBI Manual

Title:

TECHNICAL SPECIFICATION 'BASES UNIT I MANUAL Table Of Contents Issue Date:

12/10/2013 Procedure Name Rev TEXT LOES 112

Title:

LIST OF EFFECTIVE SECTIONS CN It^L [D Issue Date 12/10/2013 Change ID Change Number TEXT TOC

Title:

TABLE OF CONTENTS 22 03/28/2013 TEXT 2.1.1 5

Title:

SAFETY LIMITS (SLS)

REACTOR TEXT 2.1.2 1

Title:

SAFETY LIMITS (SLS)

REACTOR 05/06/2009 CORE SLS 10/04/2007 COOLANT SYSTEM (RCS)

PRESSURE S TEXT 3.0

Title:

LIMITING CONDITION 3

08/20/2009 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 0

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

01/19/2009 CONTROL SYSTEMS CONTROL ROD OPERABILITY 4

01/30/2009 CONTROL SYSTEMS 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 Page 1 of 8 Report Date: 12/10/13 Page 1 of 8

Report Date: 12/10/13

SSES MANUAL Manual Name:

TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.1.7 3

04/23/2008

Title:

REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC)

SYSTEM TEXT 3.1.8 3

05/06/2009

Title:

REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV)

VENT AND DRAIN VALVES TEXT 3.2.1 2

04/23/2008

Title:

POWER DISTRIBUTION 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 5

07/23/2013

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 2

04/05/2010

Title:

INSTRUMENTATION FEEDWATER MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 9

02/28/2013

Title:

INSTRUMENTATION 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)

INSTRUMENTATIOW Page 2 of

.8 Report Date: 12/10/13

SSES MANUAL Manual Name:

TSBl 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

Title:

INSTRUMENTATION TEXT 3.3.5.2

Title:

INSTRUMENTATION 3

08/20/2009 EMERGENCY CORE COOLING SYSTEM (ECCS)

INSTRUMENTATION 0

11/15/2002 REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM INSTRUMENTATION TEXT 3.3.6.1 5

07/23/2013

Title:

INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.6.2

Title:

INSTRUMENTATION TEXT 3.3.7.1

Title:

INSTRUMENTATION INSTRUMENTATION 4

09/01/2010 SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION 2

10/27/2008 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)

SYSTEM 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

Title:

REACTOR COOLANT 4

04/27/2010 SYSTEM (RCS)

RECIRCULATION LOOPS OPERATING TEXT 3.4.2 3

10/23/2013

Title:

REACTOR COOLANT SYSTEM (RCS)

JET PUMPS TEXT 3.4.3 3

01/13/2012

Title:

REACTOR COOLANT SYSTEM RCS SAFETY RELIEF VALVES S/RVS TEXT 3.4.4

Title:

REACTOR COOLANT 0

11/15/2002 SYSTEM (RCS)

RCS OPERATIONAL LEAKAGE Page~

of 8 Report Date: 12/10/13 Page 3 of 8

Report Date: 12/10/13

SSES MANUTAL Manual Name:

TSBI Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.4.5

Title:

REACTOR COOLANT 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 TEXT 3.5.1 1

01/16/2006 SYSTEM (RCS)

RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE 3

01/25/2011 SYSTEM (RCS)

RCS LEAKAGE DETECTION INSTRUMENTATION 2

10/04/2007 SYSTEM (RCS)

RCS SPECIFIC ACTIVITY 2

03/28/2013 SYSTEM (RCS)

RESIDUAL HEAT REMOVAL (RHR)

SHUTDOWN COOLING SYSTEM 1

03/28/2013 SYSTEM (RCS)

RESIDUAL HEAT REMOVAL (RHR)

SHUTDOWN COOLING 3

04/23/2008 SYSTEM (RCS)

RCS PRESSURE AND TEMPERATURE (P/T) LIMITS 0

11/15/2002 SYSTEM (RCS)

REACTOR STEAM DOME PRESSURE 2

01/16/2006 SYSTEM0

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS)

AND REACTOR SYSTEM ECCS -

OPERATING TEXT 3.5.2 0

11/15/2002

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS)

AND REACTOR SYSTEM ECCS -

SHUTDOWN TEXT 3.5.3 2

07/09/2010

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS)

AND REACTOR SYSTEM RCIC SYSTEM CORE ISOLATION COOLING (RCIC)

CORE ISOLATION COOLING (RCIC)

TEXT 3.6.1.1

Title:

PRIMARY CONTAINMENT 4

11/09/2011 TEXT 3.6.1.2 1

04/23/2008

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK Page4 of 8 Report Date: 12/10/13 Page 4 of 8

Report Date: 12/10/13

SSES MANUAL Manual Name:

TSBI 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

Title:

CONTAINMENT 10 05/23/2012 SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS) 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 1

02/28/2013 SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION 9

12/10/2013 SYSTEMS SECONDARY CONTAINMENT Pages of 8

Report Date: 12/10/13 Page 5 of 8

Report Date: 12/10/13

SSES MANUAL Manual Name:

TSB1 Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.4.2 8

03/28/2013

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 0

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES -

OPERATING TEXT 3.8.2 0

11/15/2002

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES -

SHUTDOWN s

Page~

of 8

Report Date: 12/10/13 Page 6 of

.8 Report Date: 12/10/13

SSES M.ANTAIL Manual Name:

TSBI 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 4

POWER SYSTEMS 3

POWER SYSTEMS 1

POWER SYSTEMS 10/23/2013 DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR 01/19/2009 DC SOURCES -

OPERATING 12/14/2006 DC SOURCES -

SHUTDOWN 1

12/14/2006 POWER SYSTEMS BATTERY CELL PARAMETERS TEXT 3.8.7

Title:

ELECTRICAl TEXT 3.8.8

Title:

ELECTRICAl 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 1

10/05/2005 POWER SYSTEMS DISTRIBUTION SYSTEMS -

OPERATING 0

11/15/2002 POWER SYSTEMS DISTRIBUTION SYSTEMS -

SHUTDOWN 0

11/15/2002 OPERATIONS REFUELING EQUIPMENT INTERLOCKS 1

09/01/2010 OPERATIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK 0

11/15/2002 OPERATIONS CONTROL ROD POSITION 0

11/15/2002 OPERATIONS CONTROL ROD POSITION INDICATION 0

11/15/2002 OPERATIONS CONTROL ROD OPERABILITY -

REFUELING 1

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

WATER LEVEL Page2 of 8 Report Date: 12/10/13 Page 7 of 8

Report Date: 12/10/13

SSES MANUJAL Manual Name:

TSBI 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: 12/10/13 Page 8 of

.8 Report Date: 12/10/13

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

Section Title Revision TOC Table of Contents 22 B 2.0 SAFETY LIMITS BASES Page B 2.0-1 0

Page TS / B 2.0-2 3

Page TS / B 2.0-3 5

Page TS / 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 / B 3.0-2 through TS / B 3.0-4 0

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

Page TS / B 3.0-8 3

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

Page TS / B 3.0-11 a 0

Page TS / B 3.0-12 1

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

Pages TS / 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 / 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

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Page TS / B 3.1-23 1

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

Page TS / B 3.1-28 2

Page TS / 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 / 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 1 TS I B LOES-1 Revision 112 SUSQUEHANNA - UNIT 1 TS / B LOES-1 Revision 112

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 / B 3.1-49 1

Page TS / B 3.1-50 0

Page TS / 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 / B 3.2-4 and TS / 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 / 8 3.2-11 3

Page TS / 8 3.2-12 1

Page TS / B 3.2-13 2

8 3.3 INSTRUMENTATION Pages TS / B 3.3-1 through TS / B 3.3-4 1

Page TS / 8 3.3-5 2

Page TS / 8 3.3-6 1

Page TS / 8 3.3-7 3

Page TS / B 3.3-7a 1

Page TS / 8 3.3-8 5

Pages TS / B 3.3-9 through TS / 8 3.3-12 3

Pages TS / B 3.3-12a I

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

Page TS / B 3.3-13 1

Page TS / 8 3.3-14 3

Pages TS / B 3.3-15 and TS / 8 3.3-16 1

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

Page TS / 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 / B 3.3-24a and TS / B 3.3-24b 0

Page TS / 8 3.3-25 3

Page TS / B 3.3-26 2

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

Page TS / B 3.3-30a 0

SUSQUEHANNA-UNITi TS I B LOES-2 Revision 112 SUSQUEHANNA - UNIT 1 TS / B LOES-2 Revision 112

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 / 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 / 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 / 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

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

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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 6

SUSQUEHANNA - UNIT 1 TSIB LOES-3 Revision 112 SUSQUEHANNA - UNIT 1 TS / B LOES-3 Revision 112

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 / B 3.3-78 1

Pages B 3.3-79 through B 3.3-81 0

Page B 3.3-82 1

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Pages B 3.3-84 and B 3.3-85 1

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Page TS / B 3.3-90 1

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

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Page TS / B 3.3-117 1

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Pages B 3.3-135 through B 3.3-137 0

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Page TS / B 3.3-155 1

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

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

Page TS / B 3.3-163 2

Page TS / B 3.3-164 1

Pages TS / B 3.3-165 through TS / B 3.3-167 2

SUSQUEHANNA

- UNIT 1 TS / B LOES-4 Revision 112 SUSQUEHANNA - UNIT 1 TS / B LOES-4 Revision 112

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIF-ICATIONS BASES)

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

Page TS / B 3.3-170 2

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

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

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TSB1 Text LOES.doc 11/2212013 SUSQUEHANNA

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PPL Rev. 9 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 utilized 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 to 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).

The secondary containment is a stnjcture 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. Certain plant piping systems (e.g., Service Water, RHR Service Water, Emergency Service Water, Feedwater, etc.) penetrate the secondary containment boundary. The intact piping within secondary containment provides a passive barrier which maintains secondary containment requirements. Breaches of these piping systems within secondary containment will be controlled to maintain secondary containment requirements. The secondary containment is divided into Zone I, Zone II and Zone Ill, each of which must be OPERABLE depending on plant status and the alignment of the secondary containment boundary. Specifically, the Unit 1 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 III when in MODE 4 or 5 during CORE ALTERATIONS, or during handling of irradiated fuel within the Zone III secondary containment boundary.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.6-84 Revision 4

PPL Rev. 9 Secondary Containment B 3.6.4.1 BASES BACKGROUND (continued)

To prevent ground level exfiltration -while allowing the secondary 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 SAFETY ANALYSES There are two principal accidents for which credit is taken for secondary containment OPERABILITY. These are a loss of coolant accident (LOCA)

(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 thpse 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 / B 3.6-85 Revision 2

PPL Rev. 9 Secondary Containment B 3.6.4.1 BASES (continued)

APPLICABILITY In MODES 1, 2, and 3, a LOCA could lead to a fission product release to primary containment that leaks to secondary containment. Therefore, secondary containment OPERABILITY is required during the same operating conditions that require primary containment OPERABILITY.

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. 1 If secondary containment is inoperable, it must be restored to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time provides a period of time to correct the problem that is commensurate with the importance of maintaining secondary containment during MODES 1, 2, and 3. This time period also ensures that the probability of an accident (requiring secondary containment OPERABILITY) occurring during periods where secondary containment is inoperable is minimal.

A temporary (one-time) Completion Time is connected to the Completion Time Requirements above (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ) with an "OR" connector. The Temporary Completion Time is 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and applies to the replacement of the Reactor Building Recirculating Fan Damper Motors. The Temporary Completion Time of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months may only be used once, and expires on December 31, 2005.

B.1 and B.2 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . 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.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.6-86 Revision 4

PPL Rev. 9 Secondary Containment B 3.6.4.1 BASES ACTIONS C.1, C.2, and C.3 (continued)

Movement of irradiated fuel assemblies in the secondary containment, CORE ALTERATIONS, and OPDRVs can be postulated to cause 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 under expected wind conditions. Expected wind conditions are defined as sustained wind speeds of less than or equal to 16 mph at the 60m meteorological tower or less than or equal to 11 mph at the 1 Om meteorological tower if the 60m tower wind speed is not available. Changes in indicated reactor building differential pressure observed during periods of short-term wind speed gusts above these sustained speeds do not by themselves impact secondary containment integrity. However, if secondary containment integrity is known to be compromised, the LCO must be entered regardless of wind speed.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.6-87 Revision 2

PPL Rev. 9 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE SR 3.6:4.1.1 (continued)

REQUIREMENTS The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 one access door 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.

Verifying that all such openings are closed also provides adequate assurance that exfiltration from the secondary containment will not occur.

In this application, the term "sealed" has no connotation of leak tightness.

An access opening typically contains one inner and one outer door.

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

In some cases (e.g., railroad bay), secondary containment access openings are shared such that a secondary containment barrier may have multiple inner or multiple outer doors. The intent is to maintain the secondary containment barrier intact, which is achieved by maintaining the inner or outer portion of the barrier closed at all times. However, all secondary containment access doors are normally kept closed, except when the access opening is being used for entry and exit or when maintenance is being performed on an access opening.

When the railroad bay door (No. 101) is closed; all Zone I and III hatches, removable walls, dampers, and one door in each access opening 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 III hatches and/or dampers are open to the railroad access shaft. When the railroad bay door (No. 101) is open; all Zone I and III hatches, removable walls, dampers, and one door in each access opening 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 Il1.

(continued)

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

PPL Rev. 9 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 required 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. This Surveillance is modified by a Note that allows access openings with a single door (i.e., no airlock) within the secondary containment boundary (i.e., between required secondary containment zones) to be opened for entry and exit. Opening of an access door for entry and exit allows sufficient administrative control by individual personnel making the entries and exits to assure the secondary containment function is not degraded. When one of the zones is not a zone required for secondary containment OPERABILITY, the Note allowance would not apply.

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

(continued)

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

PPL Rev. 9 Secondary Containment B 3.6.4.1 BAS ES 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 > 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

> 0.25 inches of vacuum water gauge for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at less than or equal to the maximum flow rate penrnitted for the secondary containment configuration that is operable. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 DRAWDOWN TIME(SEC)

MAXIMUM FLOW RATE (CFM)

CONTAINMENT (SR 3.6.4.1.4 (SR 3.6.4.1.5 TEST CONFIGURATION ACCEPTANCE CRITERIA)

ACCEPTANCE CRITERIA)

Group 1 Zones 1, 11 and III (Unit 1

< 300 Seconds

_4000 CFM Railroad Bay aligned to (Zones 1, 11, and Ill)

(From Zones I, II, and Ill)

Secondary Containment).

Zones I and III (Unit 1

< 300 Seconds

< 2885 CFM Railroad Bay aligned to (Zones I and Il)

(From Zones I and Ill)

Secondary Containment).

Group 2 Zones I, II and III (Unit 1

300 Seconds

3910 CFM Railroad Bay not aligned (Zones 1, 11, and Ill)

(From Zones I, I1, and Ill) to Secondary Containment).

Zones I and III (Unit 1

< 300 Seconds

< 2800 CFM Railroad Bay not aligned (Zones I and III)

(From Zones I and Ill) to Secondary Containment).

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

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.6-89 Revision 5

PPL Rev. 9 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)

REQUIREMENTS A Note also modifies the Frequency for each SR. This Note identifies that each configuration is to be tested every 60 months. Testing each configuration every 60 months assures that the most limiting configuration is tested 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.

The Unit 1 Railroad Bay can be aligned as a No Zone (isolated from secondary containment) or as part of secondary containment (Zone I or Ill). Drawdown testing of the secondary containment shall be performed with the Unit 1 Railroad Bay aligned in the most limiting configuration.

More specifically, secondary containment drawdown testing will be performed with the Unit I Railroad Bay aligned as a No Zone with the Railroad Bay door open or as part of secondary containment., The specific alignment will be selected based on the alignment that provides the least amount of inleakage and drawdown time margin (on a percentage basis) to the acceptance criteria. This could result in one alignment (e.g., No Zone with the Railroad Bay door open) being limiting for one criterion (e.g.,

drawdown time) and the other alignment (e.g., Railroad Bay aligned to secondary containment) being limiting for the other criterion (e.g.,

inleakage). It also could result in one alignment being limiting for both criteria.

Noteethat aligning the Railroad Bay to either Zone I or III is acceptable since either zone is part of secondary containment. It is preferred to align the Railroad Bay to Zone III for testing since Zone III is included in all possible secondary containment isolation alignments. The most limiting Unit 1 Railroad Bay alignment shall be established each Surveillance period (60 month). Subsequent drawdown testing during the same Surveillance period only requires testing of the Unit 1 Railroad Bay in the most limiting configuration. For example, Zone 1, 11, and III Surveillance testing is performed with the Unit 1 Railroad, Bay aligned both as a No Zone with the Railroad Bay door open and as Zone Ill. If the Surveillance testing determined the most limiting configuration occurs with the Unit 1 Railroad Bay aligned as Zone III, then subsequent Zone I and III drawdown testing during the same Surveillance period only needs to be performed with the Unit I Railroad Bay aligned as Zone Il1.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.6-90 Revision 3

PPL Rev. 9 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE REQUIREMENTS SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)

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).

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ML13361A087: Difference between revisions

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