ML062980400

Revisions to Technical Specification Bases Unit 1 Manual

ML062980400
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Site:	Susquehanna
Issue date:	10/13/2006
From:	Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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SSES MANTUAL Manual Name: TSBI-

• nual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date: 10/12/2006 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 79 10/12/2006

Title:

LIST OF EFFECTIVE SECTIONS TEXT TOC 12 10/12/2006

Title:

TABLE OF CONTENTS TEXT 2.1.1 2 04/18/2006

Title:

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

Title:

SAFETY LIMITS (SLS) REACTOR COOLANT SYSTEM (RCS) PRESSURE SL TEXT 3.0 2 10/12/2006

Title:

LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY TEXT 3.1.1 1 04118/'2006

Title:

REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)

TEXT 3.1.2

Title:

REACTIVITY CONTROL1ý SYSTEI-S~ REACTIVITY ANOMALIES TEXT 3.1.3 1 07/06/2005

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD OPERABILITY TEXT 3.1.4 3 09/29/2006

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM TIMES TEXT 3.1.5 1 07/06/2005

Title:

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

Title:

REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL Report Date: 10/12/06 Pagel1 Page of of 88 Report Date: 10/12/06

SSES MANUAL Manual Name: TSB--

Manual

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 5 06/13/2006

Title:

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

Title:

INSTRUMENTATION REMOTE SHUTDOWN SYSTEM Pag2 f Rpot Dte 1/1/0 Page 2 of 8 Report Date: 10/12/06

SSES MANUAL Manual Name: TSBI-Eanual

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 (ATWS-RPT) INSTRUMENTATION TEXT 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

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 INSTRUMENTATION TEXT 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

Title:

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: 10/12/06 Page Page33 of of 88 Report Date: 10/12/06

I SSES MANUAL Manual Name: TSB1-Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL 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 2 05/10/2006

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 Report Date: 10/12/06 Page Page44 of of 8 8 Report Date: 10/12/06

SSES MANUAL i Manual Name: TSBI-

.anual

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

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)

TEXT 3.6.1.4 0 11/15/2002

Title:

CONTAINMENT SYSTEMS CONTAINMENT PRESSURE TEXT 3.6.1.5 1 10/05/2005

Title:

CONTAINMENT SYSTEMS DRYWELL AIR 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 2 06/13/2006

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS TEXT 3.6.3.2 1 04/18/2005

Title:

CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM TEXT 3.6.3.3 -* 0 11/15/2002

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION e

Page 5 of 8 Report Date: 10/12/06

SSES MANUAL Manual Name:

Manual

Title:

TSBI7 TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL I

TEXT 3.6.4.1 6 08/08/2006

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT TEXT 3.6.4.2 2 01/03/2005

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)

TEXT 3.6.4.3 4 09/21/2006

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 (CREOASJ 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: 10/12/06 Page 6 of 8 Report Date: 10/12/06

SSES MANUAL Manual Name : TSBIl Manual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.8.3 0 11/15/2002

Title:

ELECTRICAL POWER SYST EMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR TEXT 3.8.4 1 06/13/2006

Title:

ELECTRICAL POWER SYST EMS DC SOURCES - OPERATING TEXT 3.8.5 0 11/15/2002

Title:

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

Title:

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

Title:

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

Title:

ELECTRICAL POWER SYST EMS 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: 10/12/06 Page77 Page of of 88 Report Date: 10/12/06

SSES MANUAL Manual Name: TSB--

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 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: 10/12/06 Page8 Page 8 of of 88 Report Date: 10/12/06

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)

B2.0 SAFETY LIMITS (SLs).................................................................................. B2.0-1 B2.1.1 Reactor C ore S Ls ........................................................................... B2.0-1 B2.1.2 Reactor Coolant System (RCS) Pressure SL ................................. B2.0-7 B3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ........ TS/B3.0-1 83.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ...................... TS/B3.0-10 B3.1 REACTIVITY CONTROL SYSTEMS .................................................... B3.1-1 B3.1.1 Shutdown Margin (SDM) ................................................................ B3.1-1 B3.1.2 Reactivity Anomalies ......................................... B3.1-8 B3.1.3 Control Rod OPERABILITY ............................................................ B3.1-13 B3.1.4 Control Rod Scram Times ........................................................ TS/B3.1-22 B3.1.5 Control Rod Scram Accumulators ............................................ TS/B3.1-29 B3.1.6 Rod Pattern Control .................................................................. TS/B3.1-34 B3.1.7 Standby Liquid Control (SLC) System ............................................ B3.1-39 B3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ................ B3.1-47 B3.2 POWER DISTRIBUTION LIMITS ........................... ....... TS/B3.2-1 B3.2.1 Average Planar Linear Heat Generation Rate (APLHGR) ........ TS/B3.2-1 B3.2.2 Minimum Critical Power Ratio (MCPR) ..................................... TS/B3.2-5 B3.2.3 Linear Heat Generation Rate (LHGR) ....................................... TS/B3.2-10 B3.2.4 Average Power Range Monitor (APRM) Gain and Setpoints ........................................................................... B3.2-14 B3.3 INSTRUMENTATION ................. .................................................... TS/B3.3-1 B3.3.1.1 Reactor Protection System (RPS) Instrumentation ................... TS/B3.3-1 B3.3.1.2 Source Range Monitor (SRM) Instrumentation ............ TS/B3.3-35 B3.3.2.1 Control Rod Block Instrumentation .................... TS/B3.3-44 B3.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrum entation ......................................................................... B3.3-55 B3.3.3.1 Post Accident Monitoring (PAM) Instrumentation ....... *............ TS/B3.3-64 B3.3.3.2 Remote Shutdown System ............................................................. B3.3-76 B3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrum entation ......................................................................... B3.3-81 B3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation .............................. TS/B3.3-92 B3.3.5.1 Emergency Core Cooling System (ECCS)

Instrum entation ......................................................................... B3.3-1 01 B3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrum entation ......................................................................... B3.3-135 B3.3.6.1 Primary Containment Isolation Instrumentation .............................. B3.3-147 B3.3.6.2 Secondary Containment Isolation Instrumentation ................... TS/B3.3-180 B3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)

System Instrumentation ........................................................... B3.3-192 (continued)

SUSQUEHANNA - UNIT 1 TS / B TOC - 1 Revision 12

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)

B3.3 INSTRUMENTATION (continued)

B3.3.8.1 Loss of Power (LOP) Instrumentation ....................................... TS/B3.3-205 B3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring ................................................................................ B 3 .3-2 13 B3.4 REACTOR COOLANT SYSTEM (RCS) ............................................... B3.4-1 B3.4.1 Recirculation Loops Operating ....................................................... B3.4-1 B3.4 .2 Jet P um ps ...................................................................................... B3.4-10 B3.4.3 Safety/Relief Valves (S/RVs) .................................................... TS/B3.4-15 B3.4.4 RCS Operational LEAKAGE ............................................. ............. B3.4-19 B3.4.5 RCS Pressure Isolation Valve (PIV) Leakage ................................. B3.4-24 B3.4.6 RCS Leakage Detection Instrumentation ........................................ B3.4-30 B3.4.7 RCS Specific Activity ...................................................................... B3.4-35 B3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ........................................................... B3.4-39 B3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ........................... B3.4-44 B3.4.10 RCS Pressure and Temperature (P/T) Limits ............................ TS/B3.4-49 B3.4.11 Reactor Steam Dome Pressure ................................................ TS/B3.4-58 B3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM .................................. B3.5-1 B3.5.1 ECCS - O perating ......................................................................... B3.5-1 B3.5.2 ECCS - Shutdown ........................................................................ B3.5-19 B3.5.3 RCIC System . . TS/B3.5-25 B3.6 CONTAINMENT SYSTEMS .......................................................... TS/B3.6-1 B3.6. 1.1 Primary Containment ............................................................... TS/B3.6-1 B3.6.1.2 Primary Containment Air Lock ......................................................... B3.6-7 B3.6.1.3 Primary Containment Isolation Valves (PCIVs) ......................... TS/B3.6-15 B3.6.1.4 Containm ent Pressure .................................................................... B3.6-41 B3.6.1.5 Drywell Air Temperature...... ......... ............ TS/B3.6-44 B3.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers ................ TS/B3.6-47 B3.6.2.1 Suppression Pool Average Temperature ........................................ B3.6-53 B3.6.2.2 Suppression Pool Water Level ....................................................... B3.6-59 B3.6.2.3 Residual Heat Removal (RHR) Suppression Pool C ooling ........................................................................... ...... B3 .6-62 B3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ................ B3.6-66 B3.6.3.1 Not Used .................................................................................. TS/B3.6-70 B3.6.3.2 Drywell Air Flow System ................................................................ B3.6-76 B3.6.3.3 Primary Containment Oxygen Concentration .................................. B3.6-81 B3.6.4.1 Secondary Containment ........................................................... TS/B3.6-84 B3.6.4.2 Secondary Containment Isolation Valves (SCIVs) .................... TS/B3.6-91 B3.6.4.3 Standby Gas Treatment (SGT) System .................................. TS/B3.6-101 (continued)

SUSQUEHANNA - UNIT 1 TS / B TOC - 2 Revision 12

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)

B3.7 PLANT SYSTEMS ........................................................... TS/B3.7-1 B3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ...................................... TS/B3.7-1 B3.7.2 Emergency Service Water (ESW) System ................................ TS/B3.7-7 B3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System ............................................................. TS/B3.7-12 B3.7.4 Control Room Floor Cooling System ........................................ TS/B3.7-19 B3.7.5 Main Condenser Offgas ................................................................. B3.7-24 B3.7.6 Main Turbine Bypass System ................................................... TS/B3.7-27 B3.7.7 Spent Fuel Storage Pool Water Level ........................................... B3.7-31 B3.8 ELECTRICAL POWER SYSTEM ................................................... TS/B3.8-1 B3.8.1 AC Sources - Operating .......................................................... TS/B3.8-1 B3.8.2 AC Sources - Shutdown ................................................................ B3.8-38 B3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ...................................... B3.8-45 B3.8.4 DC Sources - Operating .......................................................... TS/B3.8-54 B3.8.5 DC Sources - Shutdown .............................................. .................. B3.8-66 B3.8.6 Battery Cell Parameters ................................................................. B3.8-71 B3.8.7 Distribution Systems - Operating ................................................... B3.8-78 B3.8.8 Distribution Systems - Shutdown ................................................... B3.8-86 B3.9 REFUELING OPERATIONS .......................................................... TS/B3.9-1 B3.9.1 Refueling Equipment Interlocks ................................................ TS/B3.9-1 B3.9.2 Refuel Position One-Rod-Out Interlock ........................................... B3.9-5 B3.9.3 Control Rod Position .... ........ B3.9-9 B3.9.4 Control Rod Position Indication ...................................................... B3.9-12 B3.9.5 Control Rod OPERABILITY - Refueling ......................................... B3.9-16 B3.9.6 Reactor Pressure Vessel (RPV) Water Level ................................. B3.9-19 B3.9.7 Residual Heat Removal (RHR) - High Water Level....................... B3.9-22 B3.9.8 Residual Heat Removal (RHR) - Low Water Level ......................... B3.9-26 B3.10 SPECIAL OPERATIONS ....... . ........................... TS/B3.10-1 B3.10.1 Inservice Leak and Hydrostatic Testing Operation ................... TS/B3.10-1 B3.10.2 Reactor Mode Switch Interlock Testing .......................................... B3.10-6 B3.10.3 Single Control Rod Withdrawal - Hot Shutdown ............................. B3.10-11 B3.10.4 Single Control Rod Withdrawal- Cold Shutdown ............. B3.10-16 B3.10.5 Single Control Rod Drive (CRD) Removal - Refueling ................... B3.10-21 B3.10.6 Multiple Control Rod Withdrawal - Refueling .................................. B3.10-26 B3.10.7 Control Rod Testing - Operating .................................................... B3.10-29 B3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling ............................. B3.10-33 TSB1 Text TOC 9/20/2006 Revision 12 TS I B TOO -3 SUSQUEHANNA UNIT 1 SUSQUEHANNA-- UNIT 1 TS/BTOC-3 Revision 12

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

Section Title Revision TOC Table of Contents 12 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 4 Pages TS / B 2.0-4 and TS / B 2.0-5 3 Page TS / B 2.0-6 1 Pages B 2.0-7 through B 2.0-9 0 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 Pages TS / B 3.0-8 through TS / B 3.0-9 2 Page TS / B 3.0-10 1 Page TS / B 3.0-11 2 Page TS / B 3.0-1 la 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 Pages B 3.1-15 through B 3.1-21 0 Page TS / B 3.1-22 0 Page TS / B 3.1-23 1 Page TS / B 3.1-24 0 Page TS / B 3.1-25 1 Page TS / B 3.1-26 0 Page 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 B 3.1-39 through B 3.1-44 0 Page TS / B 3.1-45 1 Pages B 3.1-46 and B 3.1-47 0 Pages TS / B 3.1-48 and TS / B 3.1-49 1 Page B 3.1-50 0 Page TS / B 3.1-51 1 SUSQUEHANNA - UNIT 1 TS / B LOES-1 Revision 79

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

Section Title Revision B 3.2 POWER DISTRIBUTION LIMITS BASES Page TS / B 3.2-1 1 Pages TS / B 3.2-2 through TS / B 3.2-6 2

- Page B 3.2-7 0 Pages TS / B 3.2-8 and TS / B 3.2-9 2 Page TS / B 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 1 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 / B 3.3-12c 0 Page TS / B 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 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 Pages TS / B 3.3-25 and TS / B 3.3-26 2 Page TS / B 3.3-27 1 Pages TS / B 3.3-28 through TS / B 3.3-30 3 Page TS / B 3.3-30a 0 Page TS / B 3.3-31 3 Page TS / B 3.3-32 5 Pages TS / B 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 /B 3.3-44 3 Revision 79 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT 1 1 TS B LOES-2 TS I/ B LOES-2 Revision 79

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

Section Title Revision Pages TS / B 3.3-45 through TS / B 3.3-49 2 Page TS / B 3.3-50 3 Page TS / B 3.3-51 2 Pages TS / B 3.3-52 and TS / B 3.3-53 1 Page TS / B 3.3-54 3 Pages B 3.3-55 through B 3.3-63 0 Pages TS / B 3.3-64 and TS / B 3.3-65 2 Page TS / B 3.3-66 4 Page TS / B 3.3-67 3 Page TS / B 3.3-68 4 Page TS / B 3.3-69 5 Pages TS / B 3.3-70 and 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 2 Page TS / B 3.3-75a 5 Page TS / B 3.3-75b 6 Page TS / B 3.3-75c 4 Pages B 3.3-76 through 3.3-77 0 Page TS / B 3.3-78 1 Pages B 3.3-79 through B 3.3-89 0 Page TS / B 3.3-90 1 Page B 3.3-91 0 Pages TS / B 3.3-92 through TS /B 3.3-100 1 Pages B 3.3-101 through B 3.3-103 0 Page TS / B 3.3-104 1 Pages B 3.3-105 and B 3.3-106 .0 Page TS / B 3.3-107 1 Page B 3.3-108 0 Page TS / B 3.3-109 1 Pages B 3.3-110 and B 3.3-111 0 Pages TS / B 3.3-112 and TS / B 3.3-112a 1 Pages TS / B 3.3-113 through TS / B 3.3-115 1 Page TS / B 3.3-116 2 Page TS / B 3.3-117 1 Pages B 3.3-118 through 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 B 3.3-125 0 Pages TS / B 3.3-126 and TS / B 3.3-127 1 Pages B 3.3-128 through B 3.3-130 0 Page TS / B 3.3-131 1 Pages B 3.3-132 through B 3.3-137 0 Revision 79 SUSQUEHANNA - UNIT SUSOUEHANNA -

UNIT I1 TS B LOES-3 TS // B LOES-3 Revision 79

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

Section Title Revision Page TS / B 3.3-138 1 Pages B 3.3-139 through B 3.3-149 0 Pages TS / B 3.3-150 through TS / B 3.3-162 1 Page TS / B 3.3-163 2 Pages TS / B 3.3-164 through TS / B 3.3-177 1 Pages TS / B 3.3-178 and TS / B 3.3-179 2 Pages TS / B 3.3-179a and TS I B 3.3-179b 2 Page TS / B 3.3-179c 0 Page TS / B 3.3-180 1 Page TS / B 3.3-181 2 Pages TS / B 3.3-182 through TS / B 3.3-186 1 Pages TS / B 3.3-187 and TS / B 3.3-188 2 Pages TS / B 3.3-189 through TS / B 3.3-191 1 Pages B 3.3-192 through B 3.3-204 0 Page TS / B 3.3-205 1 Pages B 3.3-206 through B 3.3-219 0 B 3.4 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 and B 3.4-2 0 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 / B 3.4-15 1 Pages TS / B 3.4-16 through TS /B 3.-4-18 2 Pages B 3.4-19 through B 3.4-27 0 Pages TS / B 3.4-28 and TS / B 3.4-29 1 Pages B 3.4-30 and B 3.4-31 .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 / 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 / B 3.4-50 1 Page TS / B 3.4-51 3 Page TS / B 3.4-52 2 Page TS / B 3.4-53 1 Pages TS / B 3.4-54 and TS / B 3.4-55 2 Page TS / B 3.4-56 1 Page TS / B 3.4-57 3 Pages TS / B 3.4-58 through TS / B 3.4-60 1 TS I/ BB LOES-4 Revision 79 SUSQUEHANNA - UNIT SUSQUEHANNA - UNIT I1 TS LOES-4 Revision 79

SUSQUEHANNA STEAM ELECTRIC STATION LIST 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 / B 3.5-4 1 Page TS / B 3.5-5 2 Page TS I B 3.5-6 1 Pages B 3.5-7 through B 3.5-10 0 Page TS / B 3.5-11 1 Page TS / B 3.5-12 0 Page TS / B 3.5-13 1 Pages TS / B 3.5-14 and TS / B 3.5-15 0 Pages TS / B 3.5-16 through TS / B 3.5-18 1 Pages B 3.5-19 through B 3.5-24 0 Page TS / B 3.5-25 1 Pages TS / 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 / B 3.6-1 2 Page TS / B 3.6-1a 3 Pages TS / B 3.6-2 through TS / B 3.6-5 2 Page TS / B 3.6-6 3 Pages TS / B 3.6-6a and TS / B 3.6-6b 2 Page TS / B 3.6-6c 0 Pages B 3.6-7 through B 3.6-14 0 Page TS / B 3.6-15 2 Pages TS / B 3.6-15a and TS / B 3.6-15b 0 Page B 3.6-16 0 Page TS / B 3.6-17 1 Page TS / B 3.6-17a 0 Pages TS / B 3.6-18 and TS / B 3.6-19 0 Page TS / B 3.6-20 1 Page TS / B 3.6-21 2 Page TS / B 3.6-22 1 Page TS / B 3.6-22a 0 Page TS / B 3.6-23 1 Pages TS / B 3.6-24 through TS / B 3.6-25 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 / B 3.6-31 3 Revision 79 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT 1 1 TS / B LOES-5 TS/B LOES-5 Revision 79

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

Section Title Revision Page B 3.6-32 0 Page TS / B 3.6-33 1 Pages B 3.6-34 and B 3.6-35 0 Page TS / B 3.6-36 1 Page B 3.6-37 0 Page TS / B 3.6-38 1 Page B 3.6-39 0 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 / B 3.6-45 1 Page TS / B 3.6-46 2 Pages TS / B 3.6-47 through TS / 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 1 Pages B 3.6-66 through B 3.6-69 0 Pages TS / B 3.6-70 through TS / B 3.6-72 1 Page TS / B 3.6-73 2 Pages TS / B 3.6-74 and TS / B 3.6-75 1 Pages B 3.6-76 and B 3.6-77 0 Page TS / B 3.6-78 1 Pages B 3.6-79 through B 3.3.6-83 0 Page TS / B 3.6-84 3 Page TS / B 3.6-85 2 Page TS / B 3.6-86 4 Page TS / B 3.6-87 through TS / 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 Pages TS I B 3.6-92 through TS / B 3.6-96 1 Page TS / B 3.6-97 2 Pages TS / B 3.6-98 and TS / 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 / B 3.6-104 2 Page TS / B 3.6-105 3 Page TS / B 3.6-106 2 Page TS / B 3.6-107 3 B 3.7 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 / B 3 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 SUSQUEHANNA - UNIT 1 TS / B LOES-6 Revision 79

SUSQUEHANNA STEAM ELECTRIC STATION LIST OFEFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision Page TS / B 3.7-18a 0 Pages TS / B 3.7-19 through TS / B 3.7-23 1 Pages B 3.7-24 through B 3.7-26 0 Pages TS / B 3.7-27 through TS / 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 / 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 / B 3.8-4b 0 Page TS / B 3.8-5 4 Page TS / B 3.8-6 3 Pages TS / B 3.8-7 through TS/B 3.8-8 2 Page TS/B 3.8 4 Page TS / B 3.8-10 3 Pages TS / B 3.8-11 and TS / 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 / B 3.8-22 and TS / B 3.8-23 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 3 Page TS / B 3.8-64 2 Page TS / B 3.8-65 3 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 / B 3.9-4 1 Pages B 3.9-5 through B 3.9-30 0 B 3.10 SPECIAL OPERATIONS BASES Page TS / B 3.10-1 1 Pages B 3.10-2 through B 3.10-31 0 Page TS / 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 1 Page TS / B 3.10-38 2 TSB1 text LOES 9/29/06 SUSQUEHANNA - UNIT 1 TS / B LOES-7 Revision 79

PPL Rev. 2 LCOAPPLICABILITY B3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY BASES LCOs LCO 3.0.1 through LCO 3.0.8 establish the general requirements applicable toI all Specifications and apply at all times, unless otherwise stated.

LCO 3.0.1 LCO 3.0.1 establishes the Applicability statement within each individual Specification as the requirement for when the LCO is required to be met (i.e.,

when the unit is in the MODES or other specified conditions of the Applicability statement of each Specification).

LCO 3.0.2 LCO 3.0.2 establishes that upon discovery of a failure to meet an LCO, the associated-ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered. The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements of an LCO are not met. This Specification establishes that:

a. Completion of the Required Actions within the specified Completion Times-constitutes compliance with a Specification; and

b. Completion of the Required Actions is not required when an LCO is met within the specified Completion Time, unless otherwise specified.

There are two basic types of Required Actions. The first type of Required Action specifies a time limit in which the LCO must be met. This time limit is the Completion Time to restore an inoperable system or component to OPERABLE status or to restore variables to within specified limits. If this type of Required Action is not completed within the specified Completion Time, a shutdown may be required to place the unit in a MODE or condition in which the Specification is not applicable. (Whether stated as a Required Action or not, correction of the entered Condition is an action that may always be considered upon entering (continued)

SUSQUEHANNA - UNIT 1 TS / B 3.0-1 Revision 1

PPL Rev. 2 LCO APPLICABILITY B 3.0 BASES LCO 3.0.2 ACTIONS.) The second type of Required Action specifies the remedial (continued) measures that permit continued operation of the unit that is not further restricted by the Completion Time. In this case, compliance with the Required Actions provides an acceptable level of safety for continued operation.

Completing the Required Actions is not required when an LCO is met or is no longer applicable, unless otherwise stated in the individual Specifications.

The nature of some Required Actions of some Conditions necessitates that, once the Condition is entered, the Required Actions must be completed even though the associated Conditions no longer exist. The individual LCOs ACTIONS specify the Required Actions where this is the case. An example of this is in LCO 3.4.10, "RCS Pressure and Temperature (P/T) Limits."

The Completion Times of the Required Actions are also applicable when a system or component is removed from service intentionally. The reasons for intentionally relying on the ACTIONS include, but are not limited to, performance of Surveillances, preventive maintenance, corrective maintenance, or investigation of operational problems. Entering ACTIONS for these reasons must be done in a manner that does not compromise safety.

Intentional entry into ACTIONS should not be made for operational convenience. Additionally, if intentional entry into actions would result in redundant equipment being inoperable, alternatives should be used instead.

Doing so limits the time both subsystems/divisions of a safety function are inoperable and limits the time conditions exist which may-result in LCO 3.0.3 being entered. Individual Specifications may specify a time limit for performing an SR when equipment is removed from service or bypassed for testing. In this case, the Completion Times of the Required Actions are applicable when this time limit expires; if the equipment remains removed from service or bypassed.

When a change in MODE or other specified condition is required to comply with Required Actions, the unit may enter a MODE or other specified condition in which another Specification becomes applicable. In this case, the Completion Times of the associated Required Actions would apply from the point in time that the new Specification becomes applicable and the ACTIONS Condition(s) are entered.

(continued)

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PPL Rev. 2 LCO APPLICABILITY B 3.0 BASES (continued)

LCO 3.0.3 LCO 3.0.3 establishes the actions that must be implemented when an LCO is not met and:

a. An associated Required Action and Completion Time is not met and no other Condition applies; or

b. The condition of the unit is not specifically addressed by the associated ACTIONS. This means that no combination of Conditions stated in the ACTIONS can be made that exactly corresponds to the actual condition of the unit. Sometimes, possible combinations of Conditions are such that entering LCO 3.0.3 is warranted; in such cases, the ACTIONS specifically state a Condition corresponding to such combinations and also that LCO 3.0.3 be entered immediately.

This Specification delineates the time limits for placing the unit in a safe MODE or other specified condition when operation cannot be maintained within the limits for safe operation as defined by the LCO and its ACTIONS. It is not intended to be used as an operational convenience that permits routine voluntary removal of redundant systems or components from service in lieu of other altematives that would not result in redundant systems or components being inoperable.

Upon entering LCO 3.0.3, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is allowed to prepare for an orderly shutdown before initiating a change in unit operation. This includes time to permit the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower MODES of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the capabilities of the unit, assuming that only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the Reactor Coolant System and the potential for a plant upset that could challenge safety systems under conditions to which this Specification applies. The use and interpretation of specified times to complete the actions of LCO 3.0.3 are consistent with the discussion of Section 1.3, Completion Times.

(continued)

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PPL Rev. 2 LCOAPPLICABILITY B 3.0 BASES LCO 3.0.3 A unit shutdown required in accordance with LCO 3.0.3 may be terminated (continued) and LCO 3.0.3 exited ifany of the following occurs:

a. The LCO is now met.

b. A Condition exists for which the Required Actions have now been performed

c. ACTIONS exist that do not have expired Completion Times. These Completion Times are applicable from the point in time that the Condition is initially entered and not from the time LCO 3.0.3 is exited.

The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the unit to be in MODE 4 when a shutdown is required during MODE 1 operation. If the unit is in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE applies. If a lower MODE is reached in less time than allowed, however, the total allowable time to reach MODE 4, or other applicable MODE, is not reduced. For example, if MODE 2 is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then the time allowed for reaching MODE 3 is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />, because the total time for reaching MODE 3 is not reduced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. Therefore, if remedial measures are completed that would permit a retum to MODE 1, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.

In MODES 1, 2, and 3, LCO 3.0.3 provides actions for Conditions not covered in other Specifications. The requirements of LCO 3.0.3 do not apply in MODES 4 and 5 because the unit is already in the most restrictive Condition required by LCO 3.0.3. The requirements of LCO 3.0.3 do not apply in other specified conditions of the Applicability (unless in MODE 1, 2, or 3) because the ACTIONS of individual Specifications sufficiently define the remedial measures to be taken Exceptions to LCO 3.0.3 are provided in instances where requiring a unit shutdown, in accordance with LCO 3.0.3, would not provide appropriate remedial measures for the associated condition of the unit. An example of this is in LCO 3.7.7, "Spent Fuel Storage Pool Water Level." LCO 3.7.7 has an Applicability of "During movement of irradiated fuel (continued)

SUSQUEHANNA - UNIT 1 TS / B 3.0-4 Revision 0

PPL Rev. 2 LCO APPLICABILITY B 3.0 BASES LCO 3.0.3 assemblies in the spent fuel storage pool." Therefore, this LCO can be (continued) applicable in any or all MODES. If the LCO and the Required Actions of LCO 3.7.7 are not met while in MODE 1, 2, or 3, there is no safety benefit to be gained by placing the unit in a shutdown condition. The Required Action of LCO 3.7.7 of "Suspend movement of irradiated fuel assemblies in the spent fuel storage pool" is the appropriate Required Action to complete in lieu of the actions of LCO 3.0.3. These exceptions are addressed in the individual Specifications.

LCO 3.0.4 LCO 3.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when an LCO is not met. It allows placing the unit in a MODE or other specified condition stated in that Applicability (e.g., the Applicability desired to be entered) when unit conditions are such that the requirements of the LCO would not be met, in accordance with LCO 3.0.4.a, LCO 3.0.4.b, or LCO 3.0.4.c.

LCO 3.0.4.a allows entry into a MODE or other specified condition in the Applicability with the LCO not met when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. Compliance with Required Actions that permit continued operation of the unit for an unlimited period of time in a -MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the MODE change.

Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the Required Actions.

LCO 3.0.4.b allows 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, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate.

The risk assessment may use quantitative, qualitative, or blended approaches, and the risk assessment will be conducted using the plant program, procedures, and criteria in place to implement 10 CFR 50.65(a)(4), which requires that risk impacts of maintenance activities to be assessed and managed. The risk assessment, for the (continued)

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PPL Rev. 2 LCO APPLICABILITY B 3.0 BASES LCO 3.0.4 purposes of LCO 3.0.4 (b), must take into account all inoperable Technical (continued) Specification equipment regardless of whether the equipment is included in the normal 10 CFR 50.65(a)(4) risk assessment scope. The risk assessments will be conducted using the procedures and guidance endorsed by Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants." Regulatory Guide 1.182 endorses the guidance in Section 11 of NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." These documents address general guidance for conduct of the risk assessment, quantitative and qualitative guidelines for establishing risk management actions, and example risk management actions. These include actions to plan and conduct other activities in a manner that controls overall risk, increased risk awareness by shift and management personnel, actions to reduce the duration of the condition, actions to minimize the magnitude of risk increases (establishment of backup success paths or compensatory measures), and determination that the proposed MODE change is acceptable. Consideration should also be given to the probability of completing restoration such that the requirements of the LCO would be met prior to the expiration of ACTIONS Completion Times that would require exiting the Applicability.

LCO 3.0.4.b may be used with single, or multiple systems and components unavailable. NUMARC 93-01 provides guidance relative to consideration of simultaneous unavailability of multiple systems and components.

The results of the risk assessment shall be considered in determining the acceptability of entering the MODE or other specified condition in the Applicability, and any corresponding risk management actions. The LCO 3.0.4.b risk assessments do not have to be documented.

The Technical Specifications allow continued operation with equipment unavailable in MODE 1 for the duration of the Completion Time. Since this is allowable, and since in general the risk impact in that particular MODE bounds the risk of transitioning into and through the applicable MODES or other specified conditions in the Applicability of the LCO, the use of the LCO 3.0.4.b allowance should be generally acceptable, as long as the risk is assessed and managed as stated above. However, there is a small subset of systems and components that have been determined to be more important to risk and use of the LCO 3.0.4.b allowance is prohibited. The LCOs governing these systems and components contain Notes prohibiting the use of LCO 3.0.4.b by stating that LCO 3.0.4.b is not applicable.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.0-6 Revision 1

PPL Rev. 2 LCO.APPLICABILITY B 3.0 BASES LCO 3.0.4 LCO 3.0.4.c allows entry into a MODE or other specified condition in the (continued) Applicability with the LCO not met based on a Note in the Specification which states LCO 3.0.4.c is applicable. These specific allowances permit entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered do not provide for continued operation for an unlimited period of time and a risk assessment has not been performed. This allowance may apply to all the ACTIONS or to a specific Required Action of a Specification. The risk assessments performed to justify the use of LCO 3.0.4.b usually only consider systems and components. For this reason, LCO 3.0.4.c is typically applied to Specifications which describe values and parameters (e.g., [Containment Air Temperature, Containment Pressure, MCPR, Moderator Temperature Coefficient]) and may be applied to other Specifications based on NRC plant-specific approval.

The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.

The provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 to MODE 2 or MODE 3, MODE 2 to MODE 3, and MODE 3 to MODE 4.

Upon entry into a MODE or other specified condition in the Applicability with the LCO not met, LCO 3.0.1 and LCO 3.0.2 require entry into the applicable Conditions and Required Actions until the Condition is resolved, until the LCO is met, or until the unit is not within the Applicability of the Technical Specification.

Surveillances do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by SR 3.0.1. Therefore, utilizing LCO 3.0.4 is not a violation of SR 3.0.1 or (continued)

SUSQUEHANNA - UNIT 1 TS / B 3.0-7 Revision 1

PPL Rev. 2 LCO APPLICABILITY B 3.0 BASES LCO 3.0.4 SR 3.0.4 for any Surveillances that have not been performed on (continued) inoperable equipment. However, SRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected LCO.

LCO 3.0.5 LCO 3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of this Specification is to provide an exception to LCO 3.0.2 (e.g., to not comply with the applicable Required Action(s)) to allow the performance of required testing to demonstrate:

a. The OPERABILITY of the equipment being returned to service; or

b. The OPERABILITY of other equipment.

The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the required testing to demonstrate OPERABILITY. This Specification does not provide time to perform any other preventive or corrective maintenance.

An example of demonstrating the OPERABILITY of the equipment being returned to service is reopening a containment isolation valve that has been closed to comply with Required Actions and must be reopened to perform the required testing.

An example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of required testing on another channel in the other trip system. A similar example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of required testing on another channel in the same trip system.

LCO 3.0.6 LCO 3.0.6 establishes an exception to LCO 3.0.2 for support systems that have an LCO specified in the Technical Specifications (TS). This (continued)

SUSQUEHANNA - UNIT 1 TS / B 3.0-8 Revision 2

PPL Rev. 2 LCO APPLICABILITY B 3.0 BASES LCO 3.0.6 exception is provided because LCO 3.0.2 would require that the Conditions (continued) and Required Actions of the associated inoperable supported system LCO be entered solely due to the inoperability of the support system. This exception is justified because the actions that are required to ensure the plant is maintained in a safe condition are specified in the support system LCOs Required Actions. These Required Actions may include entering the supported system's Conditions and Required Actions or may specify other Required Actions. When a support system is inoperable and there is an LCO specified for it in the TS, the supported system(s) are required to be declared inoperable if determined to be inoperable as a result of the support system inoperability. However, it is not necessary to enter into the supported systems' Conditions and Required Actions unless directed to do so by the support system's Required Actions. The potential confusion and inconsistency of requirements related to the entry into multiple support and supported systems' LCOs' Conditions and Required Actions are eliminated by providing all the actions that are necessary to ensure the plant is maintained in a safe condition in the support system's Required Actions.

However, there are instances where a support system's Required Action may either direct a supported system to be declared inoperable or direct entry into Conditions and Required Actions for the supported system. This may occur immediately or after some specified delay to perform some other Required Action. Regardless of whether it is immediate or after some delay, when a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

Specification 5.5.11, "Safety Function Determination Program (SFDP),"

ensures loss of safety function is detected and appropriate actions are taken.

Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other limitations, remedial actions, or compensatory actions may be identified as a result of the support system inoperability and corresponding exception to entering supported system Conditions and Required Actions. The SFDP implements the requirements of LCO 3.0.6.

Cross division checks to identify a loss of safety function for those support systems that support safety systems are required. The cross division check verifies that the supported systems of the redundant OPERABLE support (continued)

SUSQUEHANNA - UNIT 1 TS / B 3.0-9 Revision 2

PPL Rev. 2 LCO APPLICABILITY B 3.0 BASES LCO 3.0.6 system are OPERABLE, thereby ensuring safety function is retained. If this (continued) evaluation determines that a loss of safety function exists, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

This loss of safety function does not require the assumption of additional single failures or loss of offsite power or concurrent loss of emergency diesel generators. Since operation is being restricted in accordance with the ACTIONS of the support system, any resulting temporary loss of redundancy or single failure protection is taken into account. Similarly, the ACTIONS for inoperable offsite circuit(s) and inoperable diesel generator(s) provide the necessary restriction for cross train inoperabilities. This explicit cross train verification for inoperable AC electrical power sources also acknowledges that supported system(s) are not declared inoperable solely as a result of inoperability of a normal or emergency electrical power source (refer to the definition of OPERABILITY).

When a loss of safety function is determined to exist, and the SFDP requires entry into the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists, consideration must be given to the specific type of function affected. Where a loss of safety function is solely due to a single TS support system (e.g., loss of automatic start due to inoperable instrumentation, or loss of pump suction source due to low tank level) the appropriate LCO is the LCO for the support system. The ACTIONS for a support system LCO adequately addresses the inoperabilities of that system without reliance on entering its supported system LCO. When the loss of function is the result of multiple support systems, the appropriate LCO is the LCO for the supported system.

LCO 3.0.7 There are certain special tests and operations required to be performed at various times over the life of the unit. These special tests and operations are necessary to demonstrate select unit performance characteristics, to perform special maintenance activities, and to perform special evolutions.

Special Operations LCOs in Section 3.10 allow specified TS requirements to be changed to permit performances of these special tests and operations, which otherwise could not be performed if required to comply with the requirements of these TS. Unless otherwise specified, all the other TS requirements remain unchanged. This will ensure all appropriate requirements of the MODE or other specified condition not directly associated with or required to be changed to perform the special test or operation will remain in effect.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.0-10 Revision 1

PPL Rev. 2 LCO APPLICABILITY B 3.0 BASES LCO 3.0.7 The Applicability of a Special Operations LCO represents a condition not (continued) necessarily in compliance with the normal requirements of the TS.

Compliance with Special Operations LCOs is optional. A special operation may be performed either under the provisions of the appropriate Special Operations LCO or under the other applicable TS requirements. If it is desired to perform the special operation under the provisions of the Special Operations LCO, the requirements of the Special Operations LCO shall be followed. When a Special Operations LCO requires another LCO to be met, only the requirements of the LCO statement are required to be met regardless of that LCOs Applicability (i.e., should the requirements of this other LCO not be met, the ACTIONS of the Special Operations LCO apply, not the ACTIONS of the other LCO). However, there are instances where the Special Operations LCO ACTIONS may direct the other LCOs' ACTIONS be met.

The Surveillances of the other LCO are not required to be met, unless specified in the Special Operations LCO. If conditions exist such that the Applicability of any other LCO is met, all the-other LCOs requirements (ACTIONS and SRs) are required to be met concurrent with the requirements of the Special Operations LCO.

LCO 3.0.8 LCO 3.0.8 establishes conditions under which systems are considered to remain capable of performing their intended safety function when associated snubbers are not capable of providing their associated support function(s).

This LCO states that the supported system is not considered to be inoperable solely due to one or more snubbers not capable of performing their associated support function(s). This is appropriate because a limited length of time is allowed for maintenance, testing, or repair of one or more snubbers not capable of performing their associated support function(s) and appropriate compensatory measures of TRO 3.7.8 are followed. The snubber requirements do not meet the criteria in 10 CFR 50.36(c)(2)(ii), and, as such, are appropriate for control within the Technical Requirements Manual.

If the allowed time expires and the snubber(s) are unable to perform their associated support function(s), the affected supported system's LCO(s) must be declared not met and the Conditions and Required Actions entered in accordance with LCO 3.0.2.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.0-11 Revision 2

PPL Rev. 2 LCO APPLICABILITY B 3.0 BASES LCO 3.0.8 LCO 3.0.8.a applies when one or more snubbers are not capable of providing (continued) their associated support function(s) to a single train or subsystem of a multiple train or subsystem supported system or to a single train or subsystem supported system. LCO 3.0.8.a allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore the snubber(s) before declaring the supported system inoperable. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is reasonable based on the low probability of a seismic event concurrent with an event that would require operation of the supported system occurring while the snubber(s) are not capable of performing their associated support function and due to the availability of the redundant train of the supported system.

LCO 3.0.8.b applies when one or more snubbers are not capable of providing their associated support function(s) to more than one train or subsystem of a multiple train or subsystem supported system. LCO 3.0.8.b allows 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to restore the snubber(s) before declaring the supported system inoperable. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Completion Time is reasonable based on the low probability of a seismic event concurrent with an event that would require operation of the supported system occurring while the snubber(s) are not capable of performing their associated support function.

LCO 3.0.8 requires that risk be assessed and managed. Industry and NRC guidance on the implementation of 10 CFR 50.65(a)(4) (the Maintenance Rule) does not address seismic risk. However, use of LCO 3.0.8 should be considered with respect to other plant maintenance activities, and integrated into the existing Maintenance Rule process to the extent possible so that maintenance on any unaffected train or subsystem is properly controlled, and emergent issues are properly addressed. The risk assessment need not be quantified, but may be a qualitative awareness of the vulnerability of systems and components when one or more snubbers are not able to perform their associated support function.

(continued)

SUSQUEHANNA-UNIT 1 TS / B 3.0-11 a Revision 0

PPL Rev. 2 SR Applicability B 3.0 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY BASES SRs SR 3.0.1 through SR 3.0.4 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated.

SR 3.0.1 SR 3.0.1 establishes the requirement that SRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the LCO apply, unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a Surveillance within the specified Frequency, in accordance with SR 3.0.2, constitutes a failure to meet an LCO.

Systems and components are assumed to be OPERABLE when the associated SRs have been met. Nothing in-his Specification, however, is to be construed as implying that systems or components are OPERABLE when:

a. The systems or components are known to be inoperable, although still meeting the SRs; or

b. The requirements of the Surveillance(s) are known to be not met between required Surveillance performances.

Surveillances do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified. The SRs associated with a Special Operations LCO are only applicable when the Special Operations LCO is used as an allowable exception to the requirements of a Specification.

Unplanned events may satisfy the requirements (including applicable acceptance criteria) for a given SR. In this case, the unplanned event may be credited as fulfilling the performance of the SR. This allowance includes those SRs whose performance is normally precluded in a given MODE or other specified condition.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.0-12 Revision 1

PPL Rev. 2 SR Applicability B 3.0 BASES SR 3.0.1 Surveillances, including Surveillances invoked by Required Actions, do not (continued) have to be performed on inoperable equipment because the ACTIONS define the remedial measures that apply. Surveillances have to be met and performed in accordance with SR 3.0.2, prior to returning equipment to OPERABLE status.

Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with SR 3.0.2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the Applicability due to the necessary unit parameters not having been established. In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.

Some examples of this process are:

a. Control Rod Drive maintenance during refueling that requires scram testing at > 800 psi. However, if other appropriate testing is satisfactorily completed and the scram time testing of SR 3.1.4.3 is satisfied, the control rod can be considered OPERABLE. This allows startup to proceed to reach 800 psi to perform other necessary testing.

b. High pressure coolant injection (HPCI) maintenance during shutdown that requires system functional tests at a specified pressure. Provided other appropriate testing is satisfactorily completed, startup can proceed with HPCI considered OPERABLE. This allows operation to reach the specified pressure to complete the necessary post maintenance testing.

SR 3.0.2 SR 3.0.2 establishes the requirements for meeting the specified Frequency for Surveillances and any Required Action with a Completion Time that requires the periodic (continued)

SUSQUEHANNA - UNIT 1 TS / B 3.0-13 Revision 2

PPL Rev. 2 SR Applicability B 3.0 BASES SR 3.0.2 performance of the Required Action on a "once per..." interval.

(continued)

SR 3.0.2 permits a 25% extension of the interval specified in the Frequency.

This extension facilitates Surveillance scheduling and considers plant operating conditions that may not be suitable for conducting the Surveillance (e.g., transient conditions or other ongoing Surveillance or maintenance activities).

The 25% extension does not significantly degrade the reliability that results from performing the Surveillance at its specified Frequency. This is based on the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the SRs. The exceptions to SR 3.0.2 are those Surveillances for which the 25% extension of the interval specified in the Frequency does not apply. These exceptions are stated in the individual Specifications.

As stated in SR 3.0.2, the 25% extension also does not apply to the initial portion of a periodic Completion Time that requires performance on a "once per..." basis. The 25% extension applies to each performance after the initial performance. The initial performance of the Required Action, whether it is a particular Surveillance or some other remedial action, is considered a single action with a single Completion Time. One reason for not allowing the 25%

extension to this Completion Time is that such an action usually verifies that no loss of function-has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an alternative manner.

The provisions of SR 3.0.2 are not intended to be used repeatedly merely as an operational convenience to extend Surveillance intervals (other than those consistent with refueling intervals) or periodic Completion Time intervals beyond those specified.

SR 3.0.3 SR 3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the specified Frequency. A delay (continued)

SUSQUEHANNA - UNIT 1 TS / B 3.0-14 Revision 2

PPL Rev. 2 SR Applicability B 3.0 BASES SR 3.0.3 period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, (continued) whichever is greater, applies from the point in time that it is discovered that the Surveillance has not been performed in accordance with SR 3.0.2, and not at the time that the specified Frequency was not met.

This delay period provides adequate time to complete Surveillances that have been missed. This delay period permits the completion of a Surveillance before complying with Required Actions or other remedial measures that might preclude completion of the Surveillance.

The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in completing the required Surveillance, and the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the requirements.

When a Surveillance with a Frequency based not on the time intervals, but upon specified unit conditions, operating situations, or requirements of regulations (e.g., prior to entering MODE 1 after each fuel loading, or in accordance with 10 CFR 50, Appendix j, as modified by approved exemptions, etc.) is discovered to-not have been. performed when specified, SR 3.0.3 allows for the full delay period of up to the specified Frequency to perform the Surveillance. However, since there is not a time interval specified, the missed Surveillance should be performed at the first reasonable opportunity.

SR 3.0.3 provides a time limit for, and allowances for the performance of Surveillances that become applicable as a consequence of MODE changes imposed by Required Actions.

Failure to comply with specified Frequencies for SRs is expected to be an infrequent occurrence. Use of the delay period established by SR 3.0.3 is a flexibility which is not intended to be used as an operational convenience to extend Surveillance intervals. While up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the limit of the specified Frequency is provided to perform the missed Surveillance, it is expected that the missed Surveillance will be performed at the first reasonable opportunity.

The determination of the first reasonable opportunity should include consideration of the impact on plant risk (from delaying the Surveillance as well as any plant configuration changes required or shutting the plant down to perform the Surveillance) and impact on any analysis assumptions, in addition to unit conditions, planning, availability of personnel, and the time required to perform the Surveillance. The risk impact should be managed through the program in place to (continued)

SUSQUEHANNA - UNIT 1 TS / B 3.0-15 Revision 2

PPL Rev. 2 SR Applicability B 3.0 BASES SR 3.0.3 implement 10 CFR 50.65(a)(4) and its implementation guidance, NRC (continued) Regulatory Guide 1.182, "Assessing and Managing Risk before Maintenance Activities at Nuclear Power Plants." This Regulatory Guide addresses consideration of temporary and aggregate risk impacts, determination of risk management action thresholds, and risk management action up to and including plant shutdown. The missed Surveillance should be treated as an emergent condition as discussed in the Regulatory Guide. The risk evaluation may use quantitative, qualitative, or blended methods. The degree of depth and rigor of the evaluation should be commensurate with the importance of the component. Missed Surveillances for important components should be analyzed quantitatively. If the results of the risk evaluation determine the risk increase is significant, this evaluation should be used to determine the safest course of action. All missed Surveillances will be placed in the Corrective Action Program.

If a Surveillance is not completed within the allowed delay period, then the equipment is considered inoperable or the variable is considered outside the specified limits and the Completion Times of the Required Actions for the applicable LCO Conditions begin immediately upon expiration of the delay period. If a Surveillance is failed within the delay period, then the equipment is inoperable, or the variable is outside the specified limits and the Completion Times of the Required Actions for-the applicable .LCO Conditions begin immediately upon the failure of the Surveillance.

Completion of the Surveillance within the delay period allowed by this Specification, or within the Completion Time of the ACTIONS, restores compliance with SR 3.0.1.

SR 3.0.4 SR 3.0.4 establishes the requirement that all applicable SRs must be met before entry into a MODE or other specified condition in the Applicability.

This Specification ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit. The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.

A provision is included to allow entry into a MODE or other specified condition in the Applicability when an LCO is not met due to Surveillance not being met in accordance with LCO 3.0.4.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.0-16 Revision 0

PPL Rev. 2 SR Applicability B 3.0 BASES SR 3.0.4 However, in certain circumstances, failing to meet an SR will not result in (continued) SR 3.0.4 restricting a MODE change or other specified condition change.

When a system, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated SR(s) are not required to be performed, per SR 3.0.1, which states that Surveillances do not have to be performed on inoperable equipment. When equipment is inoperable, SR 3.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed. Therefore, failing to perform the Surveillance(s) within the specified Frequency does not result in an SR 3.0.4 restriction to changing MODES or other specified conditions of the Applicability. However, since the LCO is not met in this instance, LCO 3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes. SR 3.0.4 does not restrict changing MODES or other specified conditions of the Applicability when a Surveillance has not been performed within the specified Frequency, provided the requirement to declare the LCO not met has been delayed in accordance with SR 3.0.3.

The provisions of SR 3.0.4 shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of SR 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 to MODE 2 or MODE 3, MODE 2 to MODE 3, and MODE 3 to MODE 4.

The precise requirements for performance of SRs are specified such that exceptions to SR 3.0.4 are not necessary. The specific time frames and conditions necessary for meeting the SRs are specified in the Frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition(s) specified in a Surveillance procedure require entry into the MODE or other specified condition in the Applicability of the associated LCO prior to the performance or completion of a Surveillance. A Surveillance that could not be performed until after entering the LCOs Applicability, would have its Frequency specified such that it is not "due" until the specific conditions needed are met.

Alternately, the Surveillance may be stated in the form of a Note, as not required (to be met or performed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of SRs' annotation is found in Section 1.4, Frequency.

SUSQUEHANNA - UNIT 1 TS / B 3.0-17 Revision 0

Oct. 13, 2006 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2006-44318 USER INFORMATION:

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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.

TSB2 - TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 10/01/2006 ADD MANUAL TABLE OF CONTENTS DATE: 10/12/2006 CATEGORY: DOCUMENTS TYPE: TSB2

Oct. 13, 2006 Page 2 of 2 ID: TEXT 3.0 REMOVE: REV:1 ADD: REV: 2 CATEGORY: DOCUMENTS TYPE: TSB2 ID: TEXT LOES REMOVE: REV:76 ADD: REV: 77 CATEGORY: DOCUMENTS TYPE: TSB2 ID: TEXT TOC REMOVE: REV:9 ADD: REV: 10 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 FOR ASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 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 MANUTAL

• , Manual Name: TSB2-Wnual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL Table Of Contents Issue Date: 10/12/2006 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 77 10/12/2006

Title:

LIST OF EFFECTIVE SECTIONS TEXT TOC 10 10/12/2006

Title:

TABLE OF CONTENTS TEXT 2.1.1 1 10/27/2004

Title:

SAFETY LIMITS (SLS) REACTOR CORE SLS TEXT 2.1.2 0 11/18/2002

Title:

SAFETY LIMITS (SLS) REACTOR COOLANT SYSTEM (RCS) PRESSURE SL TEXT 3.0 2 10/12/2006 \

• Title: LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY TEXT 3.1.1 1 0 3t/24,,200b5

Title:

REACTIVITY CONTROL SYSTEMS SHUTDOVWNi MARGIN (SDM)

TEXT 3.1.2 0 11/18/2002

Title:

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

Title:

REACTIVITY CONTTROL SYSTEMS CONTROL ROD OPERABILITY TEXT 3.1.4 .. 3 09/29/2006

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM TIMES TEXT 3.1.5 1 07/06/2005

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS TEXT 3.1.6 2 03/24/2005

Title:

REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL Report Date: 10/12/06 Pagel1 Page of of 8 8 Report Date: 10/12/06

SSES MANUTAL Manual Namen: TSB2"-

Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUATi,'f TEXT 3.1.7 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 2 10/05/2005

Title:

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

TEXT 3.2.2 1 03/24/2005

Title:

POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)

TEXT 3.2.3 0 11/18/2002

Title:

POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE LHGR TEXT 3.2.4 1 - 07/06/2005

Title:

POWER DISTRIBUTION LIMITS AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS TEXT 3.3.1.1 2 07/06/2005

Title:

INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 0 11/18/2002

Title:

INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.1.3 0 11/22/2004

Title:

OPRM INSTRUMENTATION TEXT 3.3.2.1 1 02/17/2005

Title:

INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 0 11/18/2002

Title:

INSTRUMENTATION FEEDWATER - MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 3 06/13/2006

Title:

INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Pag2 f Rpot Dte 1/1/0 Page 2 of 8 Report Date: 10/12/06

SSES MANUAL

• Mainual Name: TSB2-anual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.3.3.2 1 04/18/2005

Title:

INSTRUMENTATION REMOTE SHUTDOWN SYSTEM TEXT 3.3.4.1 0 11/18/2002

Title:

INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATION TEXT 3.3.4.2 0 11/18/2002

Title:

INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP (ATWS-RPT) INSTRUMENTATION TEXT 3.3.5.1 3 07/06/2005

Title:

INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION TEXT 3.3.5.2 0 11/18/2002

Title:

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

Title:

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

Title:

INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.7.1 0 11/18/2002

Title:

INSTRUMENTATION CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM INSTRUMENTATION TEXT 3.3.8.1 2 03/31/2006

Title:

INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATION TEXT 3.3.8.2 0 11/18/2002

Title:

INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING TEXT 3.4.1 2 11/22/2004

Title:

REACTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATING TEXT 3.4.2 0 11/18/2002

Title:

REACTOR COOLANT SYSTEM (RCS) JET PUMPS 8

Page 3 of 8 Report Date: 10/12/06

SSES MANUAL Manual Name: TSB2-Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.4.3 1 01/16/2006

Title:

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

TEXT 3.4.4 0 11/18/2002

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 11/18/2002

Title:

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

- COLD SHUTDOWN TEXT 3.4.10 2 05/10/2006

Title:

REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS TEXT 3.4.11 0 11/18/2002

Title:

REACTOR COOLANT SYSTEM (RCS) REACTOR STEAM DOME PRESSURE TEXT 3.5.1 3 01/16/2006

Title:

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

SYSTEM ECCS - OPERATING TEXT 3.5.2 0 11/18/2002

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 Pag4 o 8ReprtDat: 0/1/0 Page 4 of 8 Report Date: 10/12/06

SSES MANITAL

", Manual Name: TSB2--

• anual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.6.1.1 0 11/18/2002

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT TEXT 3.6.1.2 0 11/18/2002

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK TEXT 3.6.1.3 3 12/08/2005

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)

TEXT 3.6.1.4 0 11/18/2002

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 . 11/18/2002

Title:

CONTAINMENT SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS TEXT 3.6.2.1 0 11/18/2002

Title:

CONTAINMENT SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE TEXT 3.6.2.2 0 11/18/2002

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 11/18/2002

Title:

CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY TEXT 3.6.3.1 2 06/13/2006

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS TEXT 3.6.3.2 1 04/18/2005

Title:

CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM P

Page 5 of 8 Report Date: 10/12/06

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Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.6.3.3 0 11/18/2002

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION TEXT 3.6.4.1 6 08/08/2006

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT TEXT 3.6.4.2 2 01/03/2005

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)

TEXT 3.6.4.3 4 09/21/2006

Title:

CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEM TEXT 3.7'1 0 11/18/2002

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 11/18/2002

Title:

PLANT SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM TEXT 3.7.4 0 11/18/2002

Title:

PLANT SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM TEXT 3.7.5 0 11/18/2002

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 11/18/2002

Title:

PLANT SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL TEXT 3.8.1 - 4 04/18/2006

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES - OPERATING Report Date: 10/12/06 Page6 Page 6 of of 8 8 Report Date: 10/12/06

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Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.8.2 0 11/18/2002

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES - SHUTDOWN TEXT 3.8.3 0 11/18/2002

Title:

ELECTRICAL POWER SYSTEMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR TEXT 3.8.4 1 06/13/2006

Title:

ELECTRICAL POWER SYSTEMS DC SOURCES - OPERATING TEXT 3.8.5 .0 11/18/2002

Title:

ELECTRICAL POWER SYST EMS DC SOURCES - SHUTDOWN TEXT 3.8.6 0 11/18/2002

Title:

ELECTRICAL POWER SYST EMS BATTERY CELL PARAMETERS TEXT 3.8.7 3 - 03/31/2006

Title:

ELECTRICAL POWER SYST 'EMS DISTRIBUTION SYSTEMS - OPERATING TEXT 3.8.8 0 11/18/2002

Title:

ELECTRICAL POWER SYST'EMS DISTRIBUTION SYSTEMS - SHUTDOWN TEXT 3.9.1 0 11/18/2002

Title:

REFUELING OPERATIONS REFUELING EQUIPMENT INTERLOCKS TEXT 3.9.2 0 11/18/2002

Title:

REFUELING OPERATIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK TEXT 3.9.3 0 11/18/2002

Title:

REFUELING OPERATIONS CONTROL ROD POSITION TEXT 3.9.4 0 11/18/2002

Title:

REFUELING OPERATIONS CONTROL ROD POSITION INDICATION TEXT 3.9.5 0 11/18/2002

Title:

REFUELING OPERATIONS CONTROL ROD OPERABILITY - REFUELING Report Date: 10/12/06 Page77 Page of of 88 Report Date: 10/12/06

SSES MANUAL Manual Name: TSB2-Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.9.6 0 11/18/2002

Title:

REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVEL TEXT 3.9.7 0 11/18/2002

Title:

REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) - HIGH WATER LEVEL TEXT 3.9.8 0 11/18/2002

Title:

REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) - LOW WATER LEVEL TEXT 3.10.1 0 11/18/2002

Title:

SPECIAL OPERATIONS INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION TEXT 3.10.2 0 11/18/2002

Title:

SPECIAL OPERATIONS REACTOR MODE SWITCH INTERLOCK TESTING TEXT 3.10.3 0 - 11/18/2002

Title:

SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - HOT SHUTDOWN TEXT 3.10.4 0 11/18/2002

Title:

SPECIAL OPERATIONS SINGLE CONTROL.ROD WITHDRAWAL - COLD SHUTDOWN TEXT 3.10.5 0 11/18/2002

Title:

SPECIAL OPERATIONS SINGLE CONTROL ROD DRIVE (CRD) REMOVAL REFUELING TEXT 3.10.6 0 11/18/2002

Title:

SPECIAL OPERATIONS MULTIPLE CONTROL ROD WITHDRAWAL - REFUELING TEXT 3.10.7 1 03/24/2005

Title:

SPECIAL OPERATIONS CONTROL ROD TESTING - OPERATING TEXT 3.10.8 1 03/24/2005

Title:

SPECIAL OPERATIONS SHUTDOWN MARGIN (SDM) TEST - REFUELING Report Date: 10/12/06 PageS8 Page of of 88 Report Date: 10/12/06

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)

B2.0 SAFETY LIM ITS (SLs) ............................................................................ TS/B2.0-1 B2.1.1 Reactor Core SLs ..................................................................... TS/B2.0-1 B2.1.2 Reactor Coolant System (RCS) Pressure SL ................ ...... B2.0-6 B3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ........ TS/B3.0-1 B3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ...................... TS/B3.0-10 B3.1 REACTIVITY CONTROL SYSTEMS .................................................... B3.1-1 B3.1.1 Shutdow n Margin (SDM ) ................................................................ B3.1-1 B3.1.2 Reactivity Anomalies ................................ B3.1-8 B3.1.3 Control Rod OPERABILITY ....................................... B3.1-13 B3.1.4 Control Rod Scram Times ......................................... TS/B3.1-22 B3.1.5 Control Rod Scram Accumulators ............................ ....... .... TS/B3.1-29 B3.1.6 Rod Pattern Control .............................. .......... ................. ..... TS/B3.1-34 B3.1.7 Standby Liquid Control (SLC) System .................... B3.1-39 B3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ................ B3.1-47 B3.2 POWER DISTRIBUTION LIMITS ............ . . TS/B3.2-1 B3.2.1 Average Planar Linear Heat Generation Rate,(APLHGR) ........ TS/B3.2-1 B3.2.2 Minimum Critical Power Ratio (MCPR) .................................. TS/B3.2-5 B3.2.3 Linear Heat Generation Rate (LHGR),................................ TS/B3.2-10 B3.2.4 Average Power Range Monitor (APRM) Gain and Setpoints ......... I............ ......................................... TS/B3.2-14 B3.3 INSTRUMENTATION........ ................ TS/B3.3-1 B3.3.1.1 Reactor ProtectiornSystem (RPS) Instrumentation ................... TS/B3.3-1 B3.3.1.2 Source Range Monitor (SRM) Instrumentation ............ TS/B3.3-35 B3.3.1.-3 Oscillation Power Range Monitor ..................... TS/B3.3-43a B3.3.2.1 Control Rod Block"Instrumentation .................... TS/B3.3-44 B3.3.2.2 Feedwater Main Turbine High Water Level Trip

.Instrumentation ........................ .......... B3.3-55 B3.3.3.1 Post-Accident Monitoring (PAM) Instrumentation TS/B3.3-64 B3.3.3.2 Remote Shutdown System ............................................................. B3.3-76 B3.3.4.1 .... End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrum entation ......................................................................... B3.3-81 B3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation .................................. B3.3-92 B3.3.5.1 Emergency Core Cooling System (ECCS)

Instrum entation ................................................................... TSIB3.3-1 01 B3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrum entation ......................................................................... B3.3-135 B3.3.6.1 Primary Containment Isolation Instrumentation .............................. B3.3-147 B3.3.6.2 Secondary Containment Isolation Instrumentation ................... TS/B3.3-180 B3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)

System Instrum entation ............................................................ B3.3-192 (continued)

SUSQUEHANNA - UNIT 2 TS / B TOC - 1 Revision 10

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)

B3.3 INSTRUMENTATION (continued)

B3.3.8.1 Loss of Power (LOP) Instrumentation...................................... TSIB3.3-206 B3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring ................................................................................ B 3.3-2 14 B3.4 REACTOR COOLANT SYSTEM (RCS) ......................................... TS/B3.4-1 B3.4.1 Recirculation Loops Operating ................................................. TS/B3.4-1 B3.4.2 Jet P um ps ...................................................................................... B3.4-10 B3.4.3 Safety/Relief Valves (S/RVs) ........................ TS/B3.4-15 B3.4.4 RCS Operational LEAKAGE ........................... B3.4-19 B3.4.5 RCS Pressure Isolation Valve (PIV) Leakage ................................ B3.4-24 B3.4.6 RCS Leakage Detection Instrumentation ........................................ B3.4-30 B3.4.7 RCS Specific Activity ...................................................................... B3.4-35 B3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ........................................................... B3.4-39 B3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ...................................... *.................. B3.4-44 B3.4.10 RCS Pressure and Temperature (P/T) Limits ............................ TS/B3.4-49 B3.4.11 Reactor Steam Dome Pressure TS/B3.4-58 B3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ............................ TS/B3.5-1 B3.5.1 ECCS - O perating ................................................................... TS/B3.5-1 B3.5.2 ECCS - Shutdown ......................................................................... B3.5-19 B3.5.3 RC IC System .......................................................................... TS/B3.5-25 B3.6 CONTAINMENT SYSTEMS ........................... TS/B3.6-1 B3.6.1.-1 Primary Containment ............................. TS/B3.6-1 B3.6.1.2 Primary Containment Air Lock ........................................................ B3.6-7 B3.6.1.3 Primary Containment Isolation Valves (PCIVs) ............ TS/B3.6-15 B3.6.1.4 Containment Pressure ............................... B3.6-40 B3.6.1.5 Drywell Air Temperature ............... . ............ TS/B3.6-43 B3.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers ................ TS/B3.6-46 B3.6.2.1 Suppression Pool Average Temperature ........................................ B3.6-52 B3.6.2.2 Suppression Pool Water Level ....................................................... B3.6-58 B3.6.2.3 Residual Heat Removal (RHR) Suppression Pool C oo ling ..................................................................................... B 3 .6-6 1 B3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ................ B3.6-65 B3.6.3.1 Not Used ................................................................................. TS/B3.6-69 B3.6.3.2 Drywell Air Flow System ................................................................. B3.6-75 B3.6.3.3 Primary Containment Oxygen Concentration .................................. B3.6-80 B3.6.4.1 Secondary Containment ........................................................... TS/B3.6-83 B3.6.4.2 Secondary Containment Isolation Valves (SCIVs) .................... TS/B3.6-90 B3.6.4.3 Standby Gas Treatment (SGT) System ................. TS/B3.6-100 (continued)

SUSQUEHANNA - UNIT 2 TS / B TOC - 2 Revision 10

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)

B3.7 PLANT SYSTEMS ......................................................................... TS/B3.7-1 B3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ...................................... TS/B3.7-1 B3.7.2 Emergency Service Water (ESW) System ................................ TS/B3.7-7 B3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System ............................................................. TS/B3.7-12 B3.7.4 Control Room Floor Cooling System ........................................ TS/B3.7-19 B3.7.5 Main Condenser Offgas ................................................................. B3.7-24 B3.7.6 Main Turbine Bypass System ................................................... TS/B3.7-27 B3.7.7 Spent Fuel Storage Pool Water Level ............................................ B3.7-31 B3.8 ELECTRICAL POWER SYSTEM ......................................................... B3.8-1 B3.8.1 AC Sources - Operating .............................. B3.8-1 B3.8.2 AC Sources - Shutdown ................................................................ B3.8-39 B3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ...................................... B3.8-47 B3.8.4 DC Sources - Operating .......................................................... TS/B3.8-56 B3.8.5 DC Sources - Shutdown .............................. B3.8-70 B3.8.6 Battery Cell Parameters ................................................................. B3.8-77 B3.8.7 Distribution Systems - Operating ................................................... B3.8-84 B3.8.8 Distribution Systems - Shutdown ................................................... B3.8-94 B3.9 REFUELING OPERATIONS .......................................................... TS/B3.9-1 B3.9.1 Refueling Equipment Interlocks ................................................ TS/B3.9-1 B3.9.2 Refuel Position One-Rod-Out Interlock ........................................... B3.9-5 B3.9.3 Control Rod Position ...................................................................... B3.9-9 B3.9.4 Control Rod Position Indication ...................................................... B3.9-12 B3.9.5 Control Rod OPERABILITY - Refueling .......................................... B3.9-16 B3.9.6 Reactor Pressure Vessel (RPV) Water Level ................................. B3.9-19 B3.9.7 Residual Heat Removal (RHR) - High Water Level ....................... B3.9-22 B3.9.8 Residual Heat Removal (RHR) - Low Water Level ......................... B3.9-26 83.10 SPECIAL OPERATIONS ............................................................... TS/B3.10-1 B3.10.1 Inservice Leak and Hydrostatic Testing Operation ................... TS/B3.10-1 83.10.2 Reactor Mode Switch Interlock Testing .......................................... B3.10-6 B3.10.3 Single Control Rod Withdrawal - Hot Shutdown ............................. B3.10-11 B3.10.4 Single Control Rod Withdrawal - Cold Shutdown ........................... B3.10-16 B3.10.5 Single Control Rod Drive (CRD) Removal - Refueling ................... B3.10-21 B3.10.6 Multiple Control Rod Withdrawal - Refueling ................ B3.10-26 B3.10.7 Control Rod Testing - Operating ..................................................... B3.10-30 B3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling ............................. B3.10-34 TSB2 TOC.doc 9/20/2006 SUSQUEHANNA - UNIT 2 TS / B TOC - 3 Revision 10

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

Section Title Revision TOC Table of Contents 10 B 2.0 SAFETY LIMITS BASES

- Page TS/B2.0-1 1 Page TS / B 2.0-2 2 Page TS / B 2.0-3 3 Page TS / B 2.0-4 4 Page TS / B 2.0-5 1 Pages B 2.0-6 through B 2.0-8 0 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 Pages TS / B 3.0-8 through TS / B 3.0-9 2 Page TS / B 3.0-10 1 Page 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 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 / 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 Pages B 3.1-15 through B 3.1-21 0 Page TS / B 3.1-22 0 Page TS / B 3.1-23 1 Page TS / B 3.1-24 0 Page TS / B 3.1-25 1 Page TS / B 3.1-26 0 Page TS / B 3.1-27 1 Page TS / B 3.1-28 2 Page TS / 3.1-29 1 Pages B 3.1-30 through B 3.1-33 0 Pages TS / B 3.1.34 through TS / B 3.1-36 1 Pages TS / B 3.1-37 and TS / B 3.1-38 2 Pages B 3.1-39 through B 3.1-44 0 Page TS / B 3.1-45 1 Pages B 3.1-46 and B 3.1-47 0 Pages TS / B 3.1-48 and TS / B 3.1-49 1 Page B 3.1-50 0 Page TS / B 3.1-51 1 SUSQUEHANNA - UNIT 2 TS / B LOES-1 Revision 77

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

Section Title Revision B 3.2 POWER DISTRIBUTION LIMITS BASES Pages TS / B 3.2-1 and TS / B 3.2-2 1

- Page TS / B 3.2-3 3 Page TS / B 3.2-4 1 Pages TS / B 3.2-5 and TS / B 3.2-6 3 Page TS / B 3.2-7 2 Pages TS / B 3.2-8 and TS / B 3.2-9 3 Pages TS / B 3.2-10 through TS / B 3.2-17 1 Page TS / 3.2-18 2 Page TS / 3.2-19 1 B 3.3 INSTRUMENTATION Pages TS / B 3.3-1 through TS / B 3.3-4 1 Page TS / B 3.3 2 Page TS / B 3.3-6 1 Pages TS / B 3.3-7 through TS / B 3.3-12 2 Page TS / B 3.3-13 1 Page TS / B 3.3-14 2 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 2 Pages TS / B 3.3-19 through TS / B 3.3-27 1 Pages TS / B 3.3-28 through TS / B 3.3-30 2 Page TS / B 3.3-31 1 Page TS / B 3.3-32 3 Page TS / B 3.3-33 2 Pages TS / B 3.3-34 through TS / B 3.3-43 1 Pages TS / B 3.3-43a though TS / B 3.3-43i 0 Pages TS / B 3.3-44 through TS / B 3.3-54 2 Pages B 3.3-55 through B 3.3-63 0 Pages TS / B 3.3-64 and TS / B 3.3-65 2 Page TS / B 3.3-66 4 Page TS / B 3.3-67 3 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 / 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 Pages B 3.3-75a through TS / B 3.3-75c 4 Pages B 3.3-76 and TS / B 3.3-77 0 Page TS / B 3.3-78 1 Pages B 3.3-79 through B 3.3-91 0 Pages TS / B 3.3-92 through TS / B 3.3-103 1 Revision 77 UNIT 2 TS I B LOES-2 SUSQUEHANNA - UNIT SUSQUEHANNA -

2 TS / B LOES-2 Revision 77

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

Section Title Revision Page TS / B 3.3-104 2 Pages TS / B 3.3-105 and TS / B 3.3-106 1 Page TS / B 3.3-107 2 Page TS / B 3.3-108 1 Page TS / B 3.3-109 2 Pages TS / B 3.3-110 through TS /B 3.3-112 1 Page TS / B 3.3-113 2 Page TS / B 3.3-114 1 Page TS / B 3.3-115 through TS / B 3.3-118 2 Pages TS / B 3.3-119 through TS / B 3.3-120 1 Pages TS / B 3.3-121 and TS / B 3.3-122 2 Page TS / B 3.3-123 1 Page TS / B 3.3-124 2 Page TS / B 3.3-124a 0 Page TS / B 3.3-125 1 Page TS / B 3.3-126 2 Page TS / B 3.3-127 3 Page TS / B 3.3-128 2 Pages TS / B 3.3-129 through TS / B 3.3-131 1 Page TS / B 3.3-132 2 Pages TS /B 3.3-133 and TS/B 3.3-134 1 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 through TS / B 3.3-162 1 Page TS / B 3.3-163 2 Pages TS / B 3.3-164 through TS /B 3.3-177 1 Page TS / B 3.3-178 2 Page TS / B 3.3-179 3 Page TS / B 3.3-179a 2 Page TS / B 3.3-180 1 Page TS / B 3.3-181 2 Pages TS / B 3.3-182 through TS / B 3.3-186 1 Pages TS / B 3.3-187 and TS /B 3.3-188 2 Pages TS / B 3.3-189 through TS / B 3.3-191 1 Pages B 3.3-192 through B 3.3-205 0 Page TS / B 3.3-206 1 Pages B 3.3-207 through B 3.3-209 0 Pages TS / B 3.3-210 through TS / B 3.3-213 1 Pages B 3.3-214 through B 3.3-220 0 B 3.4 REACTOR COOLANT SYSTEM BASES Pages TS / B 3.4-1 and TS / B 3.4-2 1 Pages TS / B 3.4-3 through TS / B 3.4-9 3 Revision 77 TS/B LOES-3 SUSQUEHANNA-- UNIT SUSQUEHANNA UNIT 22 TS / B LOES-3 Revision 77

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

Section Title Revision Pages B 3.4-10 through B 3.4-14 0 Page TS / B 3.4-15 1 Pages TS / B 3.4-16 through TS / B 3.4-18 2 Pages B 3.4-19 through B 3.4-27 0 Pages TS / B 3.4-28 and TS / B 3.4-29 1 Pages B 3.4-30 through B 3.3-31 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 / B 3.4-41 1 Pages B 3.4-42 through B 3.4-48 0 Page TS / B 3.4-49 3 Pages TS / B 3.4-50 through TS / B 3.4-52 2 Page TS / B 3.4-53 1 Pages TS / B 3.4-54 and TS / B 3.4-55 2 Page TS / B 3.4-56 1 Page TS / B 3.4-57 2 Pages TS / B 3.4-58 through TS / B 3.4-60 1 B 3.5 ECCS AND RCIC BASES Pages TS / B 3.5-1 and TS / B 3.5-2 1 Pages TS / B 3.5-3 through TS / B 3.5-6 2 Pages TS / B 3.5-7 through TS /B 3.5-10 1 Pages TS / B 3.5-11 and TS / B 3.5-12 2 Pages TS / B 3.6-13 and TS / B 3.5-14 1 Pages TS / B 3.5-15 and TS / B.3.5-16 2 Page TS / B 3.5-17 3 Page TS / B 3.5-18 1 Pages B 3.5-19 through B 3.5-24 0 Pages TS / B 3.5-25 through 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 / B 3.6-1 2 Page TS / B 3.6-1a 3 Pages TS / B 3.6-2 through TS / B 3.6-5 2 Page TS / B 3.6-6 3 Pages TS / B 3.6-6a and TS / B 3.6-6b Page TS / B 3.6-6c 0 Pages B 3.6-7 through B 3.6-14 0 Page TS / B 3.6-15 3 Pages TS / B 3.6-15a and TS / B 3.6-15b 0 Revision 77 TS/B LOES-4 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT 22 TS / B LOES-4 Revision 77

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

Section Title Revision Page TS / B 3.6-16 1 Page TS / B 3.6-17 2 Page TS / B 3.6-17a 0 Pages TS / B 3.6-18 and TS / B 3.6-19 1 Page TS / B 3.6-20 2 Page TS / B 3.6-21 3 Pages TS / B 3.6-21a and TS / B 3.6-21b 0 Pages TS / B 3.6-22 and TS / B 3.6-23 2 Pages TS / B 3.6-24 and TS / B 3.6-25 1 Page TS / B 3.6-26 2 Page TS / B 3.6-27 3 Page TS / B 3.6-28 6 Page TS / B 3.6-29 3 Page TS / B 3.6-29a 0 Page TS / B 3.6-30 2 Page TS / B 3.6-31 3 Page TS / B 3.6-32 1 Page TS / B 3.6-33 2 Page TS / B 3.6-34 1 Pages TS / B 3.6-35 through TS / B 3.6-37 2 Page TS / B 3.6-38 1 Page TS / B 3.6-39 - 5 Pages B 3.6-40 through B 3.6-42 0 Pages TS / B 3.6-43 and TS / B 3.6-44 1 Page TS / B 3.6-45 2 Pages TS / B 3.6-46 through TS / B 3.6-50 1 Page TS / B 3.6-51 2 Pages B 3.6-52 through B 3.6-62 0 Pages TS / B 3.6-63 and TS / B 3.6-64 1 Pages B 3.6-65 through B 3.6-68 0 Pages B 3.6-69 through B 3.6-71 1 Page TS / B 3.6-72 2 Pages TS / B 3.6-73 through TS / B 3.6-74 1 Pages B 3.6-75 and B 3.6-76 0 Page TS / B 3.6-77 1 Pages B 3.6-78 through B 3.6-82 0 Page TS / B 3.6-83 3 Page TS / B 3.6-84 2 Page TS / B 3.6-85 4 Page TS'/ B 3.6-86 through TS / B 3.6-87a 2 Page TS / B 3.6-88 3 Page TS / B 3.6-89 2 Page TS / B 3.3-90 3 Pages TS / B 3.6-91 through TS / B 3.6-95 1 Revision 77 TS/BLOES-5 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT 22 TS / B LOES-5 Revision 77

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

Section Title Revision Page TS / B 3.6-96 2 Pages TS / B 3.6-97 and TS / B 3.6-98 1 Page TS / B 3.6-99 2 Page TS / B 3.6-99a 0 Pages TS / B 3.6-100 and TS / B 3.6-101 1 Pages TS / B 3.6-102 and TS / B 3.6-103 2 Page TS / B 3.6-104 3 Page TS / B 3.6-105 2 Page TS / B 3.6-106 3 B 3.7 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 / B 3.7-6b and TS / B 3.7-6c 0 Page TS / B 3.7-7 2 Page TS / B 3.7-8 1 Pages B 3.7-9 through B 3.7-11 0 Pages TS / 8 3.7-12 and TS / B 3.7-13 1 Pages TS / B 3.7-14 through TS / B 3.7-18 2 Page TS / B 3.7-18a 0 Pages TS / B 3.7-19 through TS / B 3.7-26 1 Pages B 3.7-24 through B 3.7-26 0 Pages TS / B 3.7-27 through TS / B 3.7-29 2 Page TS / B 3.7-30 1 Pages B 3.7-31 through B 3.7-33 0 B 3.8 ELECTRICAL POWER SYSTEMS BASES Pages B 3.8-1 through B 3.8-3 0 Page TS / B 3.8-4 1 Pages TS / B 3.8-4a and TS / B 3.8-4b 0 Pages TS / B 3.8-5 and Page TS / B 3.8-6 1 Pages B 3.8-7 and B 3.8-8 0 Page TS / B 3.8-9 2 Pages TS / B 3.8-10 and TS / B 3.8-11 1 Pages B 3.8-12 through B 3.8-18 0 Page TS / B 3.8-19 1 Pages B 3.8-20 through B 3.8-22 0 Page TS / B 3.8-23 1 Page B 3.8-24 0 Pages TS / B 3.8-25 and TS / B 3.8-26 1 Pages B 3.8-27 through B 3.8-37 0 Revision 77 TS / B LOES-6 SUSQUEHANNA-UNIT2 SUSQUEHANNA - UNIT 2 TS / B LOES-6 Revision 77

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

Section Title Revision Page TS / B 3.8-38 1 Pages TS / B 3.8-39 through TS / B 3.8-55 0 Pages TS / B 3.8-56 through TS / B 3.8-64 1 Page TS / B 3.8-65 2 Page TS / B 3.8-66 3 Pages TS / B 3.8-67 and TS I B 3.8-68 2 Page TS / B 3.8-69 3 Pages B 3.8-70 through B 3.8-85 0 Page TS / B 3.8-86 1 Page TS / B 3.8-87 2 Pages TS / B 3.8-88 through TS / B 3.8-93 1 Pages B 3.8-94 through B 3.8-99 0 B 3.9 REFUELING OPERATIONS BASES Pages TS / B 3.9-1 and TS / B 3.9-2 1 Page TS / B 3.9-2a 1 Pages TS / B 3.9-3 and TS / B 3.9-4 1 Pages B 3.9-5 through B 3.9-30 0 B 3.10 SPECIAL OPERATIONS BASES Page TS / B 3.10-1 1 Pages B 3.10-2 through B 3.10-32 0 Page-TS / B 3.10-33 2 Pages B 3.10-34 through B 3.10-38 0 Page TS I B 3.10-39 2 TSB2 Text LOES.doc 9/29/2006 Revision 77 TS I B LOES-7 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT 22 TS / B LOES-7 Revision 77

PPL Rev. 2 LCO Applicability B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY BASES LCOs LCO 3.0.1 through LCO 3.0.8 establish the general requirements applicable to I all Specifications and apply at all times', unless otherwise stated.

LCO 3.0.1 LCO 3.0.1 establishes the Applicability statement within each individual Specification as the requirement for when the LCO is required to be met (i.e.,

when the unit is in the MODES or other specified conditions of the Applicability statement of each Specification).

LCO 3.0.2 LCO 3.0.2 establishes that upon discovery of a failure to meet an LCO, the associated ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered. The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements of an LCO are not met. This Specification establishes that:

a. Completion of the Required Actions within the specified Completion Times constitutes compliance with a Specification; and

b. Completion of the Required Actions is not required when.an LCO is met within the specified Completion Time, unless otherwise specified.

There are two basic types of Required Actions. The first type of Required Action specifies a time limit in which the LCO must be met. This time limit is the Completion Time to restore an inoperable system or component to OPERABLE status or to restore variables to within specified limits. If this type of Required Action is not completed within the specified Completion Time, a shutdown may be required to place the unit in a MODE or condition in which the Specification is not applicable. (Whether stated as a Required Action or not, correction of the entered Condition is an action that may always be considered upon entering (continued)

SUSQUEHANNA - UNIT 2 TS / B 3.0-1 Revision 1

PPL Rev. 2 LCO Applicability B 3.0 BASES LCO 3.0.2 ACTIONS.) The second type of Required Action specifies the remedial (continued) measures that permit continued operation of the unit that is not further restricted by the Completion Time. In this case, compliance with the Required Actions provides an acceptable level of safety for continued operation.

Completing the Required Actions is not required when an LCO is met or is no longer applicable, unless otherwise stated in the individual Specifications.

The nature of some Required Actions of some Conditions necessitates that, once the Condition is entered, the Required Actions must be completed even though the associated Conditions no longer exist. The individual LCO's ACTIONS specify the Required Actions where this is the case. An example of this is in LCO 3.4.10, "RCS Pressure and Temperature (PIT) Limits."

The Completion Times of the Required Actions are also applicable when a system or component is removed from service intentionally. The reasons for intentionally relying on the ACTIONS include, but are not limited to, performance of Surveillances, preventive maintenance, corrective maintenance, or investigation of operational problems. Entering ACTIONS for these reasons must be done in a manner that does not compromise safety.

Intentional entry into ACTIONS should not be made for operational convenience. Additionally, if intentional entry into actions would result in redundant equipment being inoperable, altematives should be used instead.

Doing so limits the time both subsystems/divisions of a safety function are inoperable and limits the time other conditions exist which may result in LCO 3.0.3 being entered. Individual Specifications may specify a time limit for performing an SR when equipment is removed from service or bypassed for testing. In this case, the Completion Times of the Required Actions are applicable when this time limit expires, if the equipment remains removed from service or bypassed.

When a change in MODE or other specified condition is required to comply with Required Actions, the unit may enter a MODE or other specified condition in which another Specification becomes applicable. In this case, the Completion Times of the associated Required Actions would apply from the point in time that the new Specification becomes applicable and the ACTIONS Condition(s) are entered.

(continued)

SUSQUEHANNA-UNIT2 TS / B 3.0-2 Revision 0

PPL Rev. 2 LCO Applicability B 3.0 BASES (continued)

LCO 3.0.3 LCO 3.0.3 establishes the actions that must be implemented when an LCO is not met and:

a. An associated Required Action and Completion Time is not met and no other Condition applies; or

b. The condition of the unit is not specifically addressed by the associated ACTIONS. This means that no combination of Conditions stated in the ACTIONS can be made that exactly corresponds to the actual condition of the unit. Sometimes, possible combinations of Conditions are such that entering LCO 3.0.3 is warranted; in such cases, the ACTIONS specifically state a Condition corresponding to such combinations and also that LCO 3.0.3 be entered immediately.

This Specification delineates the time limits for placing the unit in a safe MODE or other specified condition when operation cannot be maintained within the limits for safe operation as defined by the LCO and its ACTIONS. It is not intended to be used as an operational convenience that permits routine voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

Upon entering LCO 3.0.3, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is allowed to prepare for an orderly shutdown before ihitiating a change in unit operation. This includes time to permit the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower MODES of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the capabilities of the unit, assuming that only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the Reactor Coolant System and the potential for a plant upset that could challenge safety systems under conditions to which this Specification applies. The use and interpretation of specified times to complete the actions of LCO 3.0.3 are consistent with the discussion of Section 1.3, Completion Times.

(continued)

SUSQUEHANNA - UNIT 2 TS / B 3.0-3 Revision 0

PPL Rev. 2 LCO Applicability B 3.0 BASES LCO 3.0.3 A unit shutdown required in accordance with LCO 3.0.3 may be terminated (continued) and LCO 3.0.3 exited if any of the following occurs:

a. The LCO is now met.

b. A Condition exists for which the Required Actions have now been performed.

c. ACTIONS exist that do not have expired Completion Times. These Completion Times are applicable from the point in time that the Condition is initially entered and not from the time LCO 3.0.3 is exited.

The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the unit to be in MODE 4 when a shutdown is required during MODE 1 operation. If the unit is in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE applies. If a lower MODE is reached in less time than allowed, however, the total allowable time to reach MODE 4, or other applicable MODE, is not reduced. For example, if MODE 2 is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then the time allowed for reaching MODE 3 is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />, because the total time for reaching MODE 3 is not reduced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. Therefore, if remedial measures are completed that would permit a return to MODE 1, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.

In MODES 1, 2, and 3, LCO 3.0.3 provides actions for Conditions not covered in other Specifications. The requirements of LCO 3.0.3 do not apply in MODES 4 and 5 because the unit is already in the most restrictive Condition required by LCO 3.0.3. The requirements of LCO 3.0.3 do not apply in other specified conditions of the Applicability (unless in MODE 1, 2, or 3) because the ACTIONS of individual Specifications sufficiently define the remedial measures to be taken.

Exceptions to LCO 3.0.3 are provided in instances where requiring a unit shutdown, in accordance with LCO 3.0.3, would not provide appropriate remedial measures for the associated condition of the unit. An example of this is in LCO 3.7.7, "Spent Fuel Storage Pool Water Level." LCO 3.7.7 has an Applicability of "During movement of irradiated fuel (continued)

SUSQUEHANNA - UNIT 2 TS / B 3.0-4 Revision 0

PPL Rev. 2 LCO Applicability B 3.0 BASES LCO 3.0.3 assemblies in the spent fuel storage pool." Therefore, this LCO can be (continued) applicable in any or all MODES. If the LCO and the Required Actions of LCO 3.7.7 are not met while in MODE 1, 2, or 3, there is no safety benefit to be gained by placing the unit in a shutdown condition. The Required Action of LCO 3.7.7 of "Suspend movement of irradiated fuel assemblies in the spent fuel storage pool" is the appropriate Required Action to complete in lieu of the actions of LCO 3.0.3. These exceptions are addressed in the individual Specifications.

LCO 3.0.4 LCO 3.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when an LCO is not met. It allows placing the unit in a MODE or other specified condition stated in that Applicability (e.g., the Applicability desired to be entered) when unit conditions are such that the requirements of the LCO would not be met, in accordance with LCO 3.0.4.a, LCO 3.0.4.b, or LCO 3.0.4.c.

LCO 3.0.4.a allows entry into a MODE or other specified condition in the Applicability with the LCO not met when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. Compliance with Required Actions that permit continued operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the MODE change.

Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance With the provisions of the Required Actions.

LCO 3.0.4.b allows 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, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate.

The risk assessment may use quantitative, qualitative, or blended approaches, and the risk assessment will be conducted using the plant program, procedures, and criteria in place to implement 10 CFR 50.65(a)(4), which requires that risk impacts of maintenance activities to be assessed and managed. The risk assessment, for the (continued)

SUSQUEHANNA - UNIT 2 TS / B 3.0-5 Revision 1

PPL Rev. 2 LCO Applicability B 3.0 BASES LCO 3.0.4 purposes of LCO 3.0.4 (b), must take into account all inoperable Technical (continued) Specification equipment regardless of whether the equipment is included in the normal 10 CFR 50.65(a)(4) risk assessment scope. The risk assessments will be conducted using the procedures and guidance endorsed by Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants." Regulatory Guide 1.182 endorses the guidance in Section 11 of NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." These documents address general guidance for conduct of the risk assessment, quantitative and qualitative guidelines for establishing risk management actions, and example risk management actions. These include actions to plan and conduct other activities in a manner that controls overall risk, increased risk awareness by shift and management personnel, actions to reduce the duration of the condition, actions to minimize the magnitude of risk increases (establishment of backup success paths or compensatory measures), and determination that the proposed MODE change is acceptable. Consideration should also be given to the probability of completing restoration such that the requirements of the LCO would be met prior to the expiration of ACTIONS Completion Times that would require exiting the Applicability.

LCO 3.0.4.b may be used with single, or multiple systems and components unavailable. NUMARC 93-01 provides guidance relative to consideration of simultaneous unavailability of multiple systems and components.

The results of the risk assessment shall be considered in determining the acceptability of entering the MODE or other specified condition in the Applicability, and any corresponding risk management actions. The LCO 3.0.4.b risk assessments do not have to be documented.

The Technical Specifications allow continued operation with equipment unavailable in MODE 1 for the duration of the Completion Time. Since this is allowable, and since in general the risk impact in that particular MODE bounds the risk of transitioning into and through the applicable MODES or other specified conditions in the Applicability of the LCO, the use of the LCO 3.0.4.b allowance should be generally acceptable, as long as the risk is assessed and managed as stated above. However, there is a small subset of systems and components that have been determined to be more important to risk and use of the LCO 3.0.4.b allowance is prohibited. The LCOs governing these systems and components contain Notes prohibiting the use of LCO 3.0.4.b by stating that LCO 3.0.4.b is not applicable.

(continued)

SUSQUEHANNA - UNIT 2 TS / B 3.0-6 Revision 1

PPL Rev. 2 LCO Applicability B 3.0 BASES LCO 3.0.4 LCO 3.0.4.c allows entry into a MODE or other specified condition in the (continued) Applicability with the LCO not met based on a Note in the Specification which states LCO 3.0.4.c is applicable. These specific allowances permit entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered do not provide for continued operation for an unlimited period of time and a risk assessment has not been performed. This allowance may apply to all the ACTIONS or to a specific Required Action of a Specification. The risk assessments performed to justify the use of LCO 3.0.4.b usually only consider systems and components. For this reason, LCO 3.0.4.c is typically applied to Specifications which describe values and parameters (e.g., [Containment Air Temperature, Containment Pressure, MCPR, Moderator Temperature Coefficient]) and may be applied to other Specifications based on NRC plant-specific approval.

The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.

The provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 to MODE 2 or MODE 3, MODE 2 to MODE 3, and MODE 3 to MODE 4.

Upon entry into a MODE or other specified condition in the Applicability with the LCO not met, LCO 3.0.1 and LCO 3.0.2 require entry into the applicable Conditions and Required Actions until the Condition is resolved, until the LCO is met, or until the unit is not within the Applicability of the Technical Specification.

Surveillances do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by SR 3.0.1. Therefore, utilizing LCO 3.0.4 is not a violation of SR 3.0.1 or (continued)

SUSQUEHANNA - UNIT 2 TS / B 3.0-7 Revision 1

PPL Rev. 2 LCO Applicability B 3.0 BASES LCO 3.0.4 SR 3.0.4 for any Surveillances that have not been performed on (continued) inoperable equipment. However, SRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected LCO.

LCO 3.0.5 LCO 3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of this Specification is to provide an exception to LCO 3.0.2 (e.g., to not comply with the applicable Required Action(s)) to allow the performance of required testing to demonstrate:

a. The OPERABILITY of the equipment being returned to service; or

b. The OPERABILITY of other equipment.

The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the required testing to demonstrate OPERABILITY. This Specification does not provide time to perform any other preventive or corrective maintenance.

An example of demonstrating the OPERABILITY of the equipment being returned to service is reopening a containment isolation valve that has been closed to comply with Required Actions and must be reopened to perform the required testing.

An example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of required testing on another channel in the other trip system. A similar example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of required testing on another channel in the same trip system.

LCO 3.0.6 LCO 3.0.6 establishes an exception to LCO 3.0.2 for support systems that have an LCO specified in the Technical Specifications (TS). This (continued)

SUSQUEHANNA - UNIT 2 TS / B 3.0-8 Revision 2

PPL Rev. 2 LCO Applicability B 3.0 BASES LCO 3.0.6 exception is provided because LCO 3.0.2 would require that the Conditions (continued) and Required Actions of the associated inoperable supported system LCO be entered solely due to the inoperability of the support system. This exception is justified because the actions that are required to ensure the plant is maintained in a safe condition are specified in the support system LCO's Required Actions. These Required Actions may include entering the supported system's Conditions and Required Actions or may specify other Required Actions. When a support system is inoperable and there is an LCO specified for it in the TS, the supported system(s) are required to be declared inoperable if determined to be inoperable as a result of the support system inoperability. However, it is not necessary to enter into the supported systems' Conditions and Required Actions unless directed to do so by the support system's Required Actions. The potential confusion and inconsistency of requirements related to the entry into multiple support and supported systems' LCOs' Conditions and Required Actions are eliminated by providing all the actions that are necessary to ensure the plant is maintained in a safe condition in the support system's Required Actions.

However, there are instances where a support system's Required Action may either direct a supported system to be declared inoperable or direct entry into Conditions and Required Actions for the supported system. This may occur immediately or after some specified delay to perform some other Required Action. Regardless of whether it is immediate or after some delay, when a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

Specification 5.5.11, "Safety Function Determination Program (SFDP),"

ensures loss of safety function is detected and appropriate actions are taken.

Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other limitations, remedial actions, or compensatory actions may be identified as a result of the support system inoperability and corresponding exception to entering supported system Conditions and Required Actions. The SFDP implements the requirements of LCO 3.0.6.

Cross division checks to identify a loss of safety function for those support systems that support safety systems are required. The cross division check verifies that the supported systems of the redundant OPERABLE support (continued)

SUSQUEHANNA-UNIT2 TS / B 3.0-9 Revision 2

PPL Rev. 2 LCO Applicability B 3.0 BASES LCO 3.0.6 system are OPERABLE, thereby ensuring safety function is retained. If this (continued evaluation determines that a loss of safety function exists, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

This loss of safety function does not require the assumption of additional single failures or loss of offsite power or concurrent loss of emergency diesel generators. Since operation is being restricted in accordance with the ACTIONS of the support system, any resulting temporary loss of redundancy or single failure protection is taken into account Similarly, the ACTIONS for inoperable offsite circuit(s) and inoperable diesel generator(s) provide the necessary restriction for cross train inoperabilities. This explicit cross train verification for inoperable AC electrical power sources also acknowledges that supported-system(s) are not declared inoperable solely as a result of inoperability of a normal or emergency electrical power source (refer to the definition of OPERABILITY).

When a loss of safety function is determined to exist, and the SFDP requires entry into the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists, consideration must be given to the specific type of function affected. Where a loss of safety function is solely due to a single TS support system (e.g., loss of automatic start due to inoperable instrumentation, or loss of pump suction source due to lowtank level) the appropriate LCO is the LCO for the support system. The ACTIONS for a support system LCO adequately addresses the inoperabilities of that system without reliance on entering its supported system LCO. When the loss of function is the result of multiple support systems, the appropriate LCO is the LCO for the supported system.

LCO 3.0.7 There are certain special tests and operations required to be performed at various times over the life of the unit. These special tests and operations are necessary to demonstrate select unit performance characteristics, to perform special maintenance activities, and to perform special evolutions. Special Operations LCOs in Section 3.10 allow specified TS requirements to be changed to permit performances of these special tests and operations, which otherwise could not be performed if required to comply with the requirements of these TS. Unless otherwise specified, all the other TS requirements remain unchanged. This will ensure all appropriate requirements of the MODE or other specified condition not directly associated with or required to be changed to perform the special test or operation will remain in effect.

(continued)

SUSQUEHANNA - UNIT 2 TS / B 3.0-10 Revision 1

PPL Rev. 2 LCO Applicability B 3.0 BASES LCO 3,0.7 The Applicability of a Special Operations LCO represents a condition not (continued) necessarily in compliance with the normal requirements of the TS.

Compliance with Special Operations LCOs is optional. A special operation may be performed either under the provisions of the appropriate Special Operations LCO or under the other applicable TS requirements. If it is desired to perform the special operation under the provisions of the Special Operations LCO, the requirements of the Special Operations LCO shall be followed. When a Special Operations LCO requires another LCO to be met, only the requirements of the LCO statement are required to be met regardless of that LCO's Applicability (i.e., should the requirements of this other LCO not be met, the ACTIONS of the Special Operations LCO apply, not the ACTIONS of the other LCO). However, there are instances where the Special Operations LCO ACTIONS may direct the other LCOs' ACTIONS be met.

The Surveillances of the other LCO are not required to be met, unless specified in the Special Operations LCO. If conditions exist such that the Applicability of any other LCO is met, all the other LCO's requirements (ACTIONS and SRs) are required to be met concurrent with the requirements of the Special Operations LCO.

LCO 3.0.8 LCO 3.0.8 establishes conditions under which systems are considered to remain capable of performing their intended safety function when associated snubbers are not capable of providing their associated support function(s). This-LCO states that the supported system is not considered to be inoperable solely due to one or more snubbers not capable of performing their associated support function(s). This is appropriate because a limited length of time is allowed for maintenance, testing, or repair of one or more snubbers not capable of performing their associated support function(s) and appropriate compensatory measures of TRO 3.7.8 are followed. The snubber requirements do not meet the criteria in 10 CFR 50.36(c)(2)(ii), and, as such, are appropriate for control within the Technical Requirements Manual.

If the allowed time expires and the snubber(s) are unable to perform their associated support function(s), the affected supported system's LCO(s) must be declared not met and the Conditions and Required Actions entered in accordance with LCO 3.0.2.

(continued)

SUSQUEHANNA-UNIT2 TS / B 3.0-11 Revision 2

PPL Rev. 2 LCO Applicability B3.0 BASES LCO 3.0.8 LCO 3.0.8.a applies when one or more snubbers are not capable of providing (continued) their associated support function(s) to a single train or subsystem of a multiple train or subsystem supported system or to a single train or subsystem supported system. LCO 3.0.8.a allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore the snubber(s) before declaring the supported system inoperable. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is reasonable based on the low probability of a seismic event concurrent with an event that would require operation of the supported system occurring while the snubber(s) are not capable of performing their associated support function and due to the availability of the redundant train of the supported system.

LCO 3.0.8.b applies when one or more snubbers are not capable of providing their associated support function(s) to more than one train or subsystem of a multiple train or subsystem supported system. LCO 3.0.8.b allows 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to restore the snubber(s) before declaring the supported system inoperable. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Completion Time is reasonable based on the low probability of a seismic event concurrent with an event that would require operation of the supported system occurring while the snubber(s) are not capable of performing their associated support function.

LCO 3.0.8 requires that risk be assessed and managed. Industry and NRC guidance on the implementation of 10 CFR 50.65(a)(4) (the Maintenance Rule) does not address seismic risk. However, use of LCO 3.0.8 should be considered with respect to other plant maintenance activities, and integrated into the existing Maintenance Rule process to the extent possible so that maintenance on any unaffected train or subsystem is properly controlled, and emergent issues are properly addressed. The risk assessment need not be quantified, but may be a qualitative awareness of the vulnerability of systems and components when one or more snubbers are not able to perform their associated support function.

(continued)

SUSQUEHANNA - UNIT 2 TS / B 3.0-11a Revision 0

PPL Rev. 2 SR Applicability B 3.0 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY BASES SRs SR 3.0.1 through SR 3.0.4 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated.

SR 3.0.1 SR 3.0.1 establishes the requirement that SRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the LCO apply, unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a Surveillance within the specified Frequency, in accordance with SR 3.0.2, constitutes a failure to meet an LCO.

Systems and components are assumed to be OPERABLE when the associated SRs have been met. Nothing in-this Specification, however, is to be construed as implying that systems or components are OPERABLE when:

a. The systems or components are known to be inoperable, although still meeting the SRs; or

b. The requirements of the Surveillance(s) are known to be not met between required Surveillance performances.

Surveillances do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified. The SRs associated with a Special Operations LCO are only applicable when the Special Operations LCO is used as an allowable exception to the requirements of a Specification.

Unplanned events may satisfy the requirements (including applicable acceptance criteria) for a given SR. In this case, the unplanned event may be credited as fulfilling the performance of the SR. This allowance includes those SRs whose performance is normally precluded in a given MODE or other specified condition.

(continued)

SUSQUEHANNA - UNIT 2 TS / B 3.0-12 Revision 1

PPL Rev. 2 SR Applicability B 3.0 BASES SR 3.0.1 Surveillances, including Surveillances invoked by Required Actions, do not (continued) have to be performed on inoperable equipment because the ACTIONS define the remedial measures that apply. Surveillances have to be met and performed in accordance with SR 3.0.2, prior to returning equipment to OPERABLE status.

Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with SR 3.0.2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the Applicability due to the necessary unit parameters not having been established. In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.

Some examples of this process are:

a. Control Rod Drive maintenance during refueling that requires scram testing at > 800 psi. However, if other appropriate testing is satisfactorily completed and the scram time testing of SR 3.1.4.3 is satisfied, the control rod can be considered OPERABLE. This allows startup to proceed to reach 800 psi to perform other necessary testing.

b. High pressure coolant injection (HPCI) maintenance during shutdown that requires system functional tests at a specified pressure. Provided other appropriate testing is satisfactorily completed, startup can proceed with HPCI considered OPERABLE. This allows operation to reach the specified pressure to complete the necessary post maintenance testing.

SR 3.0.2 SR 3.0.2 establishes the requirements for meeting the specified Frequency for Surveillances and any Required Action with a Completion Time that requires the periodic (continued)

SUSQUEHANNA-UNIT2 TS / B 3.0-13 Revision 2

PPL Rev. 2 SR Applicability B 3.0 BASES SR 3.0.2 performance of the Required Action on a "once per..." interval.

(continued)

SR 3.0.2 permits a 25% extension of the interval specified in the Frequency.

This extension facilitates Surveillance scheduling and considers plant operating conditions that may not be suitable for conducting the Surveillance (e.g., transient conditions or other ongoing Surveillance or maintenance activities).

The 25% extension does not significantly degrade the reliability that results from performing the Surveillance at its specified Frequency. This is based on the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the SRs. The exceptions to SR 3.0.2 are those Surveillances for which the 25% extension of the interval specified in the Frequency does not apply. These exceptions are stated in the individual Specifications.

As stated in SR 3.0.2, the 25% extension also does not apply to the initial portion of a periodic Completion Time that requires performance on a "once per..." basis. The 25% extension applies to each performance after the initial performance. The initial performance of the Required Action, whether it is a particular Surveillance or some other remedial action, is considered a single action with a single Completion Time. One reason for not allowing the 25%

extension to this Completion Time is that such an action usually verifies that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an alternative manner.

The provisions of SR 3.0.2 are not intended to be used repeatedly merely as an operational convenience to extend Surveillance intervals (other than those consistent with refueling intervals) or periodic Completion Time intervals beyond those specified.

SR 3.0.3 SR 3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater, applies from the point in time that it is discovered that the Surveillance has not been performed in accordance with SR 3.0.2, and not at the time that the specified Frequency was not met.

(continued)

SUSQUEHANNA - UNIT 2 TS / B 3.0-14 Revision 2

PPL Rev. 2 SR Applicability B 3.0 BASES SR 3.0.3 This delay period provides adequate time to complete Surveillances that have (continued) been missed. This delay period permits the completion of a Surveillance before complying with Required Actions or other remedial measures that might preclude completion of the Surveillance.

The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in completing the required Surveillance, and the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the requirements.

When a Surveillance with a Frequency based not on the time intervals, but upon specified unit conditions, operating situations, or requirements of regulations (e.g., prior to entering MODE 1 after each fuel loading, or in accordance with 10 CFR 50, Appendix j, as modified by approved exemptions, etc.) is discovered to not have been performed when specified, SR 3.0.3 allows for the full delay period of up to the specified Frequency to perform the Surveillance. However, since there is not a time interval specified, the missed Surveillance should be performed at the first reasonable opportunity.

SR 3.0.3 provides a time-limit for, and allowances for the performance of Surveillances that become applicable as a consequence of MODE changes imposed by Required Actions.

Failure to comply with specified Frequencies for SRs is expected to be an infrequent occurrence. Use of the delay period established by SR 3.0.3 is a flexibility which is not intended to be used as an operational convenience to extend Surveillance intervals. While up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the limit of the specified Frequency is provided to perform the missed Surveillance, it is expected that the missed Surveillance will be performed at the first reasonable opportunity.

The determination of the first reasonable opportunity should include consideration of the impact on plant risk (from delaying the Surveillance as well as any plant configuration changes required or shutting the plant down to perform the Surveillance) and impact on any analysis assumptions, in addition to unit conditions, planning, availability of personnel, and the time required to perform the Surveillance. The risk impact should be managed through the program in place to (continued)

SUSQUEHANNA - UNIT 2 TS / B 3.0-15 Revision 2

PPL Rev. 2 SR Applicability B 3.0 BASES SR 3.0.3 implement 10 CFR 50.65(a)(4) and its implementation guidance, NRC (continued) Regulatory Guide 1.182, "Assessing and Managing Risk before Maintenance Activities at Nuclear Power Plants." This Regulatory Guide addresses consideration of temporary and aggregate risk impacts, determination of risk management action thresholds, and risk management action up to and including plant shutdown. The missed Surveillance should be treated as an emergent condition as discussed in the Regulatory Guide. The risk evaluation may use quantitative, qualitative, or blended methods. The degree of depth and rigor of the evaluation should be commensurate with the importance of the component. Missed Surveillances for important components should be analyzed quantitatively. If the results of the risk evaluation determine the risk increase is significant, this evaluation should be used to determine the safest course of action. All missed Surveillances will be placed in the Corrective Action Program.

If a Surveillance is not completed within the-allowed delay period, then the equipment is considered inoperable or the variable is considered outside the specified limits and the Completion Times of the Required Actions for the applicable LCO Conditions begin immediately upon expiration of the delay period. If a Surveillance is failed within the delay period, then the equipment is inoperable, or the variable is outside the specified limits and the Completion Times of the Required Actions for the applicable LCO Conditions begin immediately upon the failure of the Surveillance.

Completion of the Surveillance within the delay period allowed by this Specification, or within the Completion Time of the ACTIONS, restores compliance with SR 3.0.1.

SR 3.0.4 SR 3.0.4 establishes the requirement that all applicable SRs must be met before entry into a MODE or other specified condition in the Applicability.

This Specification ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit. The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.

A provision is included to allow entry into a MODE or other specified condition in the Applicability when an LCO is not met due to Surveillance not being met in accordance with LCO 3.0.4.

(continued)

SUSQUEHANNA - UNIT 2 TS / B 3.0-16 Revision 0

PPL Rev. 2 SR Applicability B 3.0 BASES SR 3.0.4 However, in certain circumstances, failing to meet an SR will not result in (continued) SR 3.0.4 restricting a MODE change or other specified condition change.

When a system, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated SR(s) are not required to be performed, per SR 3.0.1, which states that Surveillances do not have to be performed on inoperable equipment. When equipment is inoperable, SR 3.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed. Therefore, failing to perform the Surveillance(s) within the specified Frequency does not result in an SR 3.0.4 restriction to changing MODES or other specified conditions of the Applicability. However, since the LCO is not met in this instance, LCO 3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes. SR 3.0.4 does not restrict changing MODES or other specified conditions of the Applicability when a Surveillance has not been performed within the specified Frequency, provided the requirement to declare the LCO not met has been delayed in accordance with SR 3.0.3.

The provisions of SR 3.0.4 shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of SR 3,0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 to MODE 2 or MODE 3, MODE 2 to MODE 3, and MODE 3 to MODE 4.

The precise requirements for performance of SRs are specified such that exceptions to SR 3.0.4 are not necessary. The specific time frames and conditions necessary for meeting the SRs are specified in the Frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition(s) specified in a Surveillance procedure require entry into the MODE or other specified condition in the Applicability of the associated LCO prior to the performance or completion of a Surveillance. A Surveillance that could not be performed until after entering the LCOs Applicability, would have its Frequency specified such that it is not "due" until the specific conditions needed are met.

Alternately, the Surveillance may be stated in the form of a Note, as not required (to be met or performed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of SRs' annotation is found in Section 1.4, Frequency.

SUSQUEHANNA - UNIT 2 TS / B 3.0-17 Revision 0

Oct. 13, 2006 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2006-44109 USER INFORMATION:

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TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date: 10/12/2006 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 33 10/12/2006

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LIST OF EFFECTIVE SECTIONS TEXT TOC 9 06/13/2006

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TABLE OF CONTENTS TEXT 1.1 0 11/18/2002

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USE AND APPLICATION DEFINITIONS TEXT 2.1 1 02/04/2005

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PLANT PROGRAMS AND SETPOINTS PLANT PROGRAMS TEXT 2.2 5 03/31/2006

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PLANT PROGRAMS AND SETPOINTS INSTRU TRIP SETPOINT TABLE TEXT 3.0 1 ~0/0 6/2)0 06

Title:

TECHNICAL REQUIREMENT FOR OPEATIO.N (TRO) APPLICABILITY & SURVEILLANCE (TRS)

APPLICABILITY TEXT 3.1.1 o 0 i/18/2002

Title:

REACTIVITY CONTROL S'YSTESMS=NTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATW}S-RI) INSTRUMENTATION TEXT 3.1.2  !. 0 11/18/2002

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REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1.3 3 03/31/2006

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REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 0 11/18/2002

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REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION &

CHECK VALVE TEXT 3.2.1 7 04/26/2006

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CORE OPERATING LIMITS REPORT (COLR)

Report Date: 10/12/06 Page 1 Page 1 of of 15 15 Report Date: 10/12/06

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TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.3.1 0 11/18/2002

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INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 1 04/26/2006

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INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 1 04/26/2006

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INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 2 06/13/2006

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INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0 11/18/2002

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INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK TEXT 3.3.6 2 10/19/2005

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INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 0 11/18/2002

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INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 1 10/22/2003

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INSTRUMENTATION TRM RPS INSTRUMENTATION TEXT 3.3.9 2 03/31/2006

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OPRM INSTRUMENTATION CONFIGURATION TEXT 3.3.10 1. 12/14/2004

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INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1 10/22/2003

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INSTRUMENTATION MVP ISOLATION INSTRUMENTATION TEXT 3.4.1 - 1 04/26/2006

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REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY Report Date: 10/12/06 Page 22 of of 15 15 Report Date: 10/12/06

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TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.4.2 0 11/18/2002

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REACTOR-COOLANT SYSTEM STRUCTURAL INTEGRITY TEXT 3.4.3 0 11/18/2002

Title:

REACTOR COOLANT SYSTEM HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITORS TEXT 3.4.4 1 12/14/2004

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REACTOR COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT 3.4.5 1 04/26/2006

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REACTOR COOLANT SYSTEM REACTOR VESSEL MATERIALS TEXT 3.5.1 1 02/04/2005

Title:

EMERGENCY CORE COOLING AND RCIC ADS MANUAL INHIBIT EXT 3.5.2 0 - 11/18/2002

Title:

EMERGENCY CORE'COOLING AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0 11/18/2002

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EMERGENCY CORE COOLING AND RCIC LONG TERM NITROGEN SUPPLY TO ADS TEXT 3.6.1 0 11/18/2002

Title:

CONTAINMENT VENTING OR PURGING TEXT 3.6.2 0 11/18/2002

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CONTAINMENT SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0 11/18/2002

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CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION TEXT 3.6.4 0 11/18/2002

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CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 -* 0 11/18/2002

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PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN-Pae3 o 5RprtDt:1/20 Page 3 of 15 Report Date: 10/12/06

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TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.2 0 11/18/2002

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PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL TEXT 3.7.3.1 1 04/26/2006

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PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 2 04/26/2006

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PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS TEXT 3.7.3.3 2 08/18/2005

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PLANT SYSTEMS C02 SYSTEMS TEXT 3.7.3.4 1 04/26/2006

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PLANT SYSTEMS HALON SYSTEMS TEXT 3.7.3.5 1 04/26/2006

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PLANT SYSTEMS FIRE HOSE STATIONS TEXT 3.7.3.6 1 04/26/2006

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PLANT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT 3.7.3,7 1 04/26/2006

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PLANT SYSTEMS FIRE RATED ASSEMBLIES TEXT 3.7.3.8 4 09/08/2005

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PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION TEXT 3.7.4 1 04/26/2006

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PLANT SYSTEMS SOLID RADWASTE SYSTEM TEXT 3.7.5.1 0 11/18/2002

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PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT 3.7.5.2 -* 0 11/18/2002

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PLANT SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE Report Date: 10/12/06 4

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TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.5.3 1 04/26/2006

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PLANT SYSTE MS LIQUID H'OLDUP TANKS TEXT 3.7.6 1 03/01/2005

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PLANT SYSTE MS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 0 11/18/2002

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PLANT SYSTE MS MAIN CON DENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING TEXT 3.7.8 3 10/12/2006

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PLANT SYSTE MS SNUBBERS TEXT 3.7.9 1 08/28/2006

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PLANT SYSTE MS CONTROL STRUCTURE HVAC TEXT 3.7.10 1 12/14/2004

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PLANT SYSTE MS SPENT FUEL STORAGE POOLS (SFSPS)

TEXT 3.8.1 1 02/04/2005

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ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT 3.8.2.1 1 12/14/2004

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ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

CONTINUOUS TEXT 3.8.2.2 2 12/14/2004

Title:

ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

AUTOMATIC TEXT 3.8.3 0 11/18/2002

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ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT 3.8.4 0 11/18/2002

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ELECTRICAL POWER 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT 3.8.5 0 11/18/2002

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ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION Pae5oi5RprtDt:1/20 Page 5 of 15 Report Date: 10/12/06

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TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.8.6 0 11/18/2002

Title:

ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.9.1 0 11/18/2002

Title:

REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0 11/18/2002

Title:

REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 0 11/18/2002

Title:

REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 1 04/26/2006

Title:

MISCELLANEOUS SEAL SOURCE CONTAMINATION TEXT 3.10.2 2 08/08/2006

Title:

MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION*

TEXT 3.10.3 1 04/26/2006

Title:

MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

TEXT 3.10.4 1 08/28/2006

Title:

MISCELLANEOUS LEADING EDGE FLOW METER (LEFM)

TEXT 3.11.1.1 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION TEXT 3.11.1.2 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE TEXT 3.11.1.3 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM TEXT 3.11.1.4 1 12/14/2004

Title:

RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION Pag 6of 5 eprt at: 1/1/0 Page 6 of 15 Report Date: 10/12/06

SSES MANUAL

,' Manual Name: TRMI-anual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.1.5 1 12/14/2004

Title:

RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT 3.11.2.1 3 04/26/2006

Title:

RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3.11.2.2 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES TEXT 3.11.2.3 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM TEXT 3.11.2.4 0 11/18/2002

Title:

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3.11.2.5 2 04/26/2006

Title:

RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3.11.2.6 2 12/14/2004

Title:

RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.3 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS TOTAL DOSE TEXT 3.11.4.1 4 08/08/2006

Title:

RADIOACTIVE EFFLUENTS MONITORING PROGRAM TEXT 3.11.4.2 2 04/26/2006

Title:

RADIOACTIVE EFFLUENTS LAND USE CENSUS TEXT 3.11.4.3 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS INTERLABORATORY COMPARISON PROGRAM TEXT 3.12.1 0 11/19/2002

Title:

LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL POOL STORAGE POOL Report Date: 10/12/06 Page 77 Page of of 15 15 Report Date: 10/12/06

SSES MANUAL Manual Name: TRMI- '.

Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.12.2 1 10/12/2006

Title:

LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0 11/19/2002

Title:

LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENT TEXT B3.0 1 01/06/2006

Title:

APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.1.1 .0 11/19/2002

Title:

REACTIVITY CONTROL SYSTEMS BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNI*TE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.1.2 0 11/19/2002

Title:

REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT B3.1.3 3 03/31/2006

Title:

REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT B3.1.4 0 11/19/2002

Title:

REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTAK 'ION AND CHECK VALVE TEXT B3.2.1 0 11/19/2002

Title:

CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR)

TEXT B3.3.1 0 11/19/2002

Title:

INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 0 11/19/2002

Title:

INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 1 02/04/2005

Title:

INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 2 06/13/2006

Title:

INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Report Date: 10/12/06 Page 88 of of 15 15 Report Date: 10/12/06

SSES MANUAL

,Manual Name: TRMT-r ual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.3.5 1 06/13/2006

Title:

INSTRUMENTATION BASES THIS PAGE INTENTIONALLY LEFT BLANK TEXT B3.3.6 3 10/19/2005

Title:

INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION TEXT B3.3.7 0 11/19/2002

Title:

INSTRUMENTATION BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT B3.3.8 1 10/22/2003

Title:

INSTRUMENTATION BASES TRM REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT B3.3.9 2 03/31/2006

Title:

OPRM INSTRUMENTATION 0 - 11/19/2002 TEXTTitle:

B3.3.10 INSTRUMENTATION BASES REACTOR RECIRCULATION PUMP MG SET STOPS TEXT B3.3.11 1 10/22/2003

Title:

INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3.4.1 0 11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY TEXT B3.4.2 0 11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES STRUCTURAL INTEGRITY TEXT B3.4.3 0 11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR TEXT B3.4.4 0 11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT B3.4.5 0 11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS Pae9 o 5RprtDt:1/20 Page 9 of 15 Report Date: 10/12/06

SSES MANUYAL Manual Name: TRMI-Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.5.1 0 11/19/2002

Title:

ECCS AND RCIC BASES ADS MANUAL INHIBIT TEXT B3.5.2 0 11/19/2002

Title:

ECCS AND RCIC BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT B3.5.3 0 11/19/2002

Title:

ECCS AND RCIC BASES LONG TERM NITROGEN SUPPLY TO ADS TEXT B3.6.1 -0 11/19/2002

Title:

CONTAINMENT BASES VENTING OR PURGING TEXT B3.6.2 0 11/19/2002

Title:

CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 0 11/19/2002

Title:

CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION TEXT B3.6.4 1 12/14/2004

Title:

CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT B3.7.1 0 11/19/2002

Title:

PLANT SYSTEMS BASES EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN)

TEXT B3.7.2 0 11/19/2002

Title:

PLANT SYSTEMS BASES ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL TEXT B3.7.3.1 1 04/26/2006

Title:

PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT B3.7.3.2 2 04/26/2006

Title:

PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS TEXT B3.7.3.3 0 11/19/2002

Title:

PLANT SYSTEMS BASES C02 SYSTEMS Pag 1 o 1 Rpor Dte 1/1/0 Page 10 of 15 Report Date: 10/12/06

SSES MANUAL

. .'! Manual Name: TRM--

anual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.3.4 1 04/26/2006

Title:

PLANT SYSTEMS BASES HALON SYSTEMS TEXT B3.7.3.5 1 04/26/2006

Title:

PLANT SYSTEMS BASES FIRE HOSE STATIONS TEXT B3.7.3.6 1 04/26/2006

Title:

PLANT SYSTEMS BASES YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT B3.7.3.7 .0 11/19/2002

Title:

PLANT SYSTEMS BASES FIRE RATED ASSEMBLIES TEXT B3.7.3.8 1 01/12/2004

Title:

PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION

• TEXT B3.7.4 0 11/19/2002

Title:

PLANT SYSTEMS BASES SOLID RADWASTE SYSTEM TEXT B3.7.5.1 0 11/19/2002

Title:

PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT B3.7.5.2 0 11/19/2002

Title:

PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT B3.7.5.3 0 11/19/2002

Title:

PLANT SYSTEMS BASES LIQUID HOLDUP TANKS TEXT B3.7.6 1 03/01/2005

Title:

PLANT SYSTEMS BASES ESSW PUMPHOUSE VENTILATION TEXT B3.7.7 0 11/19/2002

Title:

PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT B3.7.8 -* 2 10/12/2006

Title:

PLANT SYSTEMS BASES SNUBBERS P

Page 11 of 15 Report Date: 10/12/06

SSES MANITAI1 Manual Name: TRMt-Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.9 1 12/14/2004

Title:

PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1 12/14/2004

Title:

PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.8.1 1 02/04/2005

Title:

ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT B3.8.2.1 0 11/19/2002

Title:

ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

CONTINUOUS TEXT B3.8.2.2 1 09/17/2004

Title:

ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

AUTOMATIC TEXT B3.8.3 0 11/19/2002

Title:

ELECTRICAL POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT B3.8.4 0 11/19/2002

Title:

ELECTRICAL POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT B3.8.5 0 11/19/2002

Title:

ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B3.8.6 1 02/04/2005

Title:

ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.9.1 0 11/19/2002

Title:

REFUELING OPERATIONS BASES DECAY TIME TEXT B3.9.2 0 11/19/2002

Title:

REFUELING OPERATIONS BASES COMMUNICATIONS TEXT B3.9.3 - 0 11/19/2002

Title:

REFUELING OPERATIONS BASES REFUELING PLATFORM Report Date: 10/12/06 Page 12 of of 15 15 Report Date: 10/12/06

SSES MANUAL Manual Name: TRY1-Uanual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.10.1 0 11/19/2002

Title:

MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 1 03/31/2006

Title:

MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT B3.10.3 0 11/19/2002

Title:

MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

TEXT B3.10.4 .0 i 11/19/2002

Title:

MISCELLANEOUS BASES LEADING EDGE FLOW METER (LEFM)

TEXT B3.11.1.1 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3.11.1.2 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3.11.1.3 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3.11.1.4 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.1.5 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.11.2.1 1 12/14/2004

Title:

RADIOACTIVE EFFLUENTS BASES DOSE RATE TEXT B3.11.2.2 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES TEXT B3.11.2.3 -* 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATES FORM Page 13 of 15 Report Date: 10/12/06

SSES MANUAL Manual Name: TRl"--

Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.11.2.4 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.11.2.5 3 05/20/2005

Title:

RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3.11.2.6 1 01/27/2004

Title:

RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.3 0 . 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES TOTAL DOSE TEXT B3.11.4.1 2 01/06/2006

Title:

RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3.11.4.2 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES LAND USE CENSUS TEXT B3.11.4.3 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAM TEXT B3.12.1 0 11/19/2002

Title:

LOADS CONTROL PROGRAM BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT B3.12.2 0 11/19/2002

Title:

LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS TEXT B3.12.3 0 11/19/2002

Title:

LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS TEXT 4.1 0 08/31/1998

Title:

ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 -* 0 08/31/1998

Title:

ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION Report Date: 10/12/06 14 Page 14 of of 15 15 Report Date: 10/12/06

SSES MANUAL Manual Name: TRMI--

Sanual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 4.3 08/31/1998

Title:

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION TEXT 4.4 0 08/31/1998

Title:

ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT 4.5 0 08/31/1998

Title:

ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS TEXT 4.6 0 08/31/1998

Title:

ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM TEXT 4.7 0 08/31/1998

Title:

ADMINISTRATIVE CONTROLS TRAINING Report Date: 10/12/06 15 Page 15 of of 15 15 Report Date: 10/12/06

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 33 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date TOC TABLE OF CONTENTS 05/30/2006 1.0 USE AND APPLICATION Pages TRM / 1.0-1 through TRM / 1.0-3 10/04/2002 2.0 PLANT PROGRAMS Page 2.0-1 08/31/1998 Pages TRM / 2.0-2 and TRM / 2.0-3 01/28/2005 Page TRM / 2.0-4 06/25/2002 Page TRM / 2.0-5 04/02/1999 Pages TRM / 2.0-6 and TRM / 2.0-7 03/22/2006 Page TRM / 2.0-8 12/03/2004 Pages TRM / 2.0-9 through TRM / 2.0-11 11/15/2004 Page TRM / 2.0-12 03/22/2006 Pages TRM / 2.0-13 and TRM / 2.0-14 11/15/2004 Page TRM /2.0-15 11/15/2005 3.0 APPLICABILITY Pages TRM / 3.0-1 and TRM / 3.0-2 04/08/1999 Page TRM / 3.0-3 03/15/2002 Page TRM / 3.0-4 11/30/2005 3.1 REACTIVITY CONTROL SYSTEMS Pages 3.1-1 through 3.1-5S 08/31/1998 Pages TRM / 3.1-6 through TRM / 3.1-8 03/22/2006 Pages TRM / 3.1-9 and TRM / 3.1-9a 02/18/1999 Page TRM / 3.1-10 02/18/1999 3.2 CORE OPERATING LIMITS REPORT Page TRM / 3.2-1 07/07/1999 Pages TRM / 3.2-2 through TRM / 3.2-44 03/31/2006 3.3 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 07/16/1999 Page TRM / 3.3-4 03/31/2006 Pages TRM / 3.3-5 and TRM / 3.3-6 08/31/1998 Page TRM / 3.3-7 03/31/2006 Page 3.3-8 08/31/1998 Pages TRM / 3.3-9 and TRM / 3.3-9a 12/17/1998 Page TRM / 3.3-10 05/30/2006 Page TRM / 3.3-11 06/02/2005 Page TRM / 3.3-11 a 05/30/2006 Page TRM / 3.3-12 03/30/2001 Page TRM / 3.3-13 09/13/2005 Page TRM / 3.3-14 12/14/1998 Page TRM / 3.3-15 10/22/2003 Page TRM / 3.3-16 06/27/2001 TRM / LOES-1 EFFECTIVE DATE 10/10/2006 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT I1 TRM / LOES-1 EFFECTIVE DATE 10/10/2006

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 33 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date Pages TRM / 3.3-17 and TRM / 3.3-18 06/14/2002 Pages TRM / 3.3-19 through TRM / 3.3-21 10/22/2003 Page TRM / 3.3-22 03/22/2006 Page TRM / 3.3-22a 11/15/2004 Pages TRM / 3.3-22b through TRM / 3.3-22d 03/22/2006 Page TRM / 3.3-23 12/03/2004 Pages TRM / 3.3-24 and TRM / 3.3-25 05/16/2003 Page TRM / 3.3-26 10/22/2003 3.4 REACTOR COOLANT SYSTEM Page TRM / 3.4-1 03/31/2006 Pages 3.4-2 through 3.4-5 10/23/1009 Pages 3.4-6 through 3.4-11 08/31/1998 Page TRM / 3.4-12 12/03/2004 Page TRM / 3.4-13 03/31/2006 3.5 EMERGENCY CORE COOLING AND RCIC Page TRM / 3.5-1 01/28/2005 Pages 3.5-2 and 3.5-3 08/31/1998 Page TRM / 3.5-4 04/17/2000 Pages 3.5-5 through 3.5-7 08/31/1998 3.6 CONTAINMENT -

Pages 3.6-1 through 3.6-3 08/31/1998 Page TRM / 3.6-4 01/07/2002 Page 3.6-5 08/31/1998 Pages TRM / 3.6-6 through TRM / 3.6-8 12/31/2002 3.7 PLANT SYSTEMS Pages 3.7-1 through 3.7-3 08/31/1998 Pages TRM / 3.7-4 and TRM / 3.7-5 03/31/2006 Pages TRM / 3.7-6 through TRM / 3.7-8 08/02/1999 Page TRM / 3.7-9 03/31/2006 Page TRM / 3.7-10 08/16/2005 Page TRM / 3.7-11 12/29/1999 Pages TRM / 3.7-12 and TRM / 3.7.13 08/02/1999 Page TRM / 3.7-14 08/09/2005 Pages TRM / 3.7-15 and TRM / 3.7-16 08/02/1999 Page TRM / 3.7-17 03/31/2006 Page TRM / 3.7-18 08/02/1999 Page TRM / 3.7-19 03/31/2006 Pages TRM / 3.7-20 through TRM / 3.7-22 08/02/1999 Pages TRM / 3.7-23 and TRM / 3.7-24 03/31/2006 Pages TRM / 3.7-28 and TRM / 3.7-29 08/09/2005 Page TRM./ 3.7-30 08/25/2005 Pages TRM / 3.7-31 and TRM / 3.7-32 11/16/2001 Page TRM / 3.7-33 01/09/2004 TRM / LOES-2 EFFECTIVE DATE 10/10/2006 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT 11 TRM / LOES-2 EFFECTIVE DATE 10/10/2006

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 33 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date Page TRM / 3.7-34 11/16/2001 Page TRM / 3.7-34a 10/05/2002 Page TRM / 3.7-35 03/31/2006 Pages TRM / 3.7-36 and TRM / 3.7-37 02/01/1999 Pages 3.7-38 and 3.7-39 08/31/1998 Page TRM / 3.7-40 03/31/2006 Pages TRM / 3.7-41 and TRM / 3.7-41a 02/14/2005 Pages 3.7-42 and 3.7-43 08/31/1998 Pages TRM / 3.7-44 through TRM 1 3.7-49 10/05/2006 Pages TRM / 3.7-49a and TRM / 3.7-49b 10/05/2006 Page TRM 1 3.7-50 03/09/2001 Page TRM / 3.7-51 08/16/2006 Page TRM / 3.7-52 12/03/2004 Page TRM / 3.7-53 04/15/2003 Page TRM / 3.7 07/29/1999 3.8 ELECTRICAL POWER Page TRM / 3.8-1 04/02/2002 Pages TRM / 3.8-2 through TRM / 3.8-4 01/28/2005 Pages TRM / 3.8-5 and TRM / 3.8-6 04/02/2002 Pages TRM / 3.8-7 through TRM /3.8-10 12/03/2004 Page TRM / 3.8-11 08/10/2004 Page TRM / 3.8-12 12/03/2004 Pages 3.8-13 and 3.8-14 08/31/1998 Pages TRM / 3.8-15 through TRM / 3.8-17 04/02/2002 Page 3.8-18 08/31/1998 Page TRM / 3.8-19 04/02/2002 Page 3.8-20 08/31/1998 Pages TRM / 3.8-21 through TRM / 3.8-23 06/06/1999 Pages 3.8-24 and 3.8-25 08/31/1998 3.9 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 08/31/1998 3.10 MISCELLANEOUS Page TRM / 3.10-1 03/31/2006 Pages 3.10-2 and 3.10-3 08/31/1998 Page TRM / 3.10-4 08/01/2006 Pages TRM / 3.10-5 and TRM / 3.10-6 03/22/2006 Page TRM / 3.10-7 03/31/2006 Page TRM / 3.10-8 08/16/2006 SUSQUEHANNA - UNIT 1 TRM / LOES-3 EFFECTIVE DATE 10/10/2006

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 33 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date 3.11 RADIOACTIVE EFFLUENTS Page TRM / 3.11-1 03/31/2006 Pages 3.11-2 and 3.11-3 08/31/1998 Page TRM / 3.11-4 03/31/2006

- Page 3.11-5 08/31/1998 Page TRM / 3.11-6 03/31/2006 Pages TRM / 3.11-7 through TRM / 3.11-9 08/31/1998 Page TRM / 3.11-10 12/03/2004 Pages 3.11-11 and 3.11-12 08/31/1998 Page 3.11-13 09/011998 Page TRM / 3.11-14 12/03/2004 Pages 3.11-15 and 3.11-16 09/01/1998 Page TRM / 3.11-17 03/31/2006 Page 3.11-18 08131/1998 Page TRM / 3.11-19 08/15/2005 Pages TRM / 3.11-20 and TRM / 3.11-21 03/31/2006 Page TRM / 3.11-22 04/02/2002 Page TRM / 3.11-23 03/31/2006 Page TRM / 3.11-24 05/13/2005 Page 3.11-25 09/01/1998 Pages TRM / 3.11-26 through TRM / 3.11-28 01/21/2004 Page TRM / 3.11 12/03/2004 Pages TRM / 3.11.30 through TRM / 3.11.32 01/21/2004 Page TRM / 3.11-33 03/31/2006 Page 3.11-34 08/31/1998 Page TRM / 3.11-35 03/31/2006 Pages TRM / 3.11-36 through TRM / 3.11-39 11/30/2005 Pages 3.11-40 through 3.11-43 08/31/1998 Page TRM / 3.11-44 08/01/2006 Page TRM / 3.11-45 03/31/2006 Page 3.11-46 08/31/1998 Page TRM / 3.11-47 03/31/2006 3.12 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-3 02/05/1999 Page TRM / 3.12-4 09/30/2006 Page TRM / 3.12-5 02/05/1999 4.0 ADMINISTRATIVE CONTROLS Pages 4.0-1 through 4.0-8 08/31/1998 TRM /LOES-4 EFFECTIVE DATE 10/10/2006 SUSQUEHANNA -

UNIT 1 SUSQUEHANNA - UNIT 1 TRM / LOES-4 EFFECTIVE DATE 10/10/2006

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 33 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date B 3.0 APPLICABILITY BASES Pages B 3.0-1 through B 3.0-10 08/31/1998 Pages TRM / B 3.0-11 and TRM / B 3.0-12 03/15/2002 Pages TRM / B 3.0-13 and TRM / B 3.0-14 11/30/2005

- Page TRM / B 3.0-15 03115/2002 B 3.1 REACTIVITY CONTROL SYSTEMS BASES Pages TRM / B 3.1-1 through TRM / B 3.1-3 07/13/1999 Page B 3.1-4 08/31/1998 Page TRM / B 3.1-5 11/15/2005 Pages TRM / B 3.1-6 and TRM / B 3.1-7 03/22/2006 Page TRM / B 3.1-8 02/18/1999 B 3.2 CORE OPERATING LIMITS BASES Page B 3.2-1 08/31/1998 B 3.3 INSTRUMENTATION BASES Page TRM / B 3.3-1 04/07/2000 Page B 3.3-2 08/31/1998 Pages TRM / B 3.3-3 and TRM / B 3.3-3A 01/31/2005 Pages TRM / B 3.3-4 through TRM / B 3.3-7 05/30/2006 Pages TRM / B 3.3-8 and TRM / B 3.3-9 03/30/2001 Page B 3.3-10 08/31/1998 PagesTRM / B 3.3-11 and TRM / B 3.3-12 09/13/2005 Page TRM / B 3.3-13 12/03/2004 Page TRM / B 3.3-14 06/25/2002 Page TRM / B 3.3-14a 06/14/2002 Page TRM / B 3.3-14b 06/14/2002 Pages TRM / B 3.3-15 and TRM / B 3.3-16 10/22/2003 Page TRM / B 3.3-17 03/22/2006 Pages TRM / B 3.3-17a through TRM / B 3.3-17f 03/22/2006 Pages TRM / B3.3-18 and TRM / B 3.3-19 05/16/2003 Page TRM / B 3.3-20 10/22/2003 Page TRM / B 3.3-21 05/16/2003 B 3.4 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 through B 3.4-4 08/31/1998 Page TRM / B 3.4-5 10/15/1999 Page B 3.4-6 08/31/1998 B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 through B 3.5-5 08/31/1998 B 3.6 CONTAINMENT BASES Page TRM / B 3.6-1 07/26/2001 Page TRM / B 3.6-2 02/01/1999 Page B 3.6-3 08/31/1998 TRM / LOES-5 EFFECTIVE DATE 10/10/2006 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT I1 TRM / LOES-5 EFFECTIVE DATE 10/10/2006

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 33 LIST OFEFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date Page TRM / B 3.6-4 09/23/1999 Page TRM / B 3.6-5 01/07/2002 Page TRM / B 3.6-6 12/03/2004 Pages B.3.6-7 through TRM / B 3.6-11 12/31/2002 B 3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 08/31/1998 Page TRM / B 3.7-3 08/02/1999 Page TRM / B 3.7-4 03/31/2006 Page TRM / B 3.7-5 08/02/1999 Page TRM / B 3.7-6 03/31/2006 Pages TRM / B 3.7-7 and TRM / B 3.7-7a 08/02/1999 Page TRM / B 3.7-8 08/02/1999 Page TRM / B 3.7-9 03/31/2006 Page TRM / B 3.7-10 08/02/1999 Page TRM / B 3.7-10a 03/31/2006 Page TRM / B 3.7-11 08/02/1999 Page TRM / B 3.7-a1 a 03/31/2006 Pages TRM / B 3.7-12 through TRM / B 3.7-14 08/02/1999 Page TRM / B 3.7-14a 08/02/1999 Page TRM / B 3.7-14b 01/09/2004 Pages TRM / B 3.7-15 and TRM / B 3.7-16 02/01/1999 Pages B 3.7-17 through B 3.7-20 08/31/1998 Pages TRM / B 3.7-21 and TRM /B 3-7-21a 02/14/2005 Pages TRM / B 3.7-22 and TRM / B 3.7-23 04/07/2000 Pages TRM / B 3.7-24 through TRM / B 3.7-30 10/05/2006 Pages TRM / B 3.7-30a and TRM / B 3.7-30b 10/05/2006 Page TRM / B 3.7-31 12/03/2004 Page TRM / B 3.7-32 03/09/2001 Page TRM / B 3.7-33 04/15/2003 Page TRM / B 3.7-34 12/03/2004 Page TRM / B 3.7-35 07/05/2000 B 3.8 ELECTRICAL POWER BASES Page TRM / B 3.8-1 04/02/2002 Pages TRM / B 3.8-2 and TRM / B 3.8-2a 01/28/2005 Page TRM / B 3.8-3 04/02/2002 Page TRM / B 3.8-3a 04/02/2002 Page TRM / B 3.8-4 08/10/2004 Page TRM / B 3.8-4a 04/02/2002 Page TRM / B 3.8-5 08/31/1998 Pages TRM / B 3.8-6 through TRM / B 3.8-16 04/02/2002 Page TRM / B 3.8-17 01/28/2005 B.3.9 REFUELING OPERATIONS BASES Pages B 3.9-1 through B 3.9-7 08/31/1998 SUSQUEHANNA - UNIT I TRM / LOES-6 EFFECTIVE DATE 10/10/2006

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 33 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date B 3.10 MISCELLANEOUS BASES Page B 3.10-1 08/31/1998 Pages TRM / B 3.10-2 and TRM / B 3.10-3 03/22/2006 Pages TRM / B 3.10-4 and TRM / B 3.10-5 08/23/1999

- Pages TRM / B 3.10-6 and TRM / B 3.10-7 04/17/2002 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 08/30/1998 Page TRM / B 3.11-10 02/01/1999 Pages TRM/B 3.11-11 and TRM/B 3.11-1 Ia 04/07/2000 Pages TRM/B 3.11-12 and TRM/B 3.11-13 02/01/1999 Page TRM / B 3.11-14 12/03/2004 Page TRM / B 3.11-15 02/01/1999 Pages B 3.11-16 through B 3.11-19 08/30/1998 Page TRM / B 3.11-20 04/02/2002 Page TRM / B 3.11-20a 04/02/2002 Pages TRM / B 3.11-21 through TRM / B 3.11.23a- 05/13/2005 Pages TRM / B 3.11-24 and TRM/B 3.11-25 01/21/2004 Pages B 3.11-26 and B 3.11-27 08/30/1998 Pages TRM / B 3.11-28 and TRM / B 3.11-29 11/30/2005 Page TRM / B 3.11-30 12/03/2004 Pages B 3.7-31 through B 3.7-35 08/30/1998 Page TRM / B 3.11-36 02/12/1999 B.3.12 LOADS CONTROL PROGRAM BASES Pages TRM / B 3.12-1 through TRM / B 3.12-3 02/05/1999 TRM1 text LOES 10/10/2006 TRM / LOES-7 EFFECTIVE DATE 10/10/2006 SUSQUEHANNA - UNIT SUSQUEHANNA - UNIT 1 1 TRM / LOES-7 EFFECTIVE DATE 10/10/2006

Snubbers PPL Rev. a 3.7.8 3.7 Plant Systems 3.7.8 Snubbers TRO 3.7.8 All snubbers shall be OPERABLE APPLICABILITY: When associated supported system(s) are required to be OPERABLE ACTIONS

---

NOTE

1. Separate condition entry is allowed for each snubber.

2. The provisions of TRO 3.0.4 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or moresnubbers A.1.1 Determine the location and the Immediately associated with only one design function of the subsystem of a multiple inoperable snubber(s) subsystem supported (mitigation of seismic or system or associated with a seismic and non-seismic single subsystem loads).

supported system confirmed to be inoperable AND A.1.2 Determine that an OPERABLE Immediately subsystem(s) involving equipment not associated with the inoperable snubber(s) exists to provide makeup and core cooling needed to mitigate a LOOP event.

AND A. 1.3 Determine that the subsystem Immediately supported by the inoperable snubber would remain capable of performing its required safety or support functions for postulated design loads other than seismic loads.

AND (continued)

SUSQUEHANNA - UNIT 1 TRM / 3.7-44 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev...3 3.7.8 CONDITION REQUIRED ACTION COMPLETION TIME NOTE ---

REQUIRED ACTIONS A.1.1 through A. 1.3 must be completed prior to completing REQUIRED ACTION A.1.4.

A.1.4 Enter LCO 3.0.8 immediately AND A.1.5 Replace or restore the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable snubber(s) to OPERABLE status B. One or more snubbers B.1.1 Determine the location and Immediately associated with more than the design function of the one subsystem of a multiple inoperable snubber(s) subsystem supported (mitigation of seismic or system confirmed seismic and non-seismic inoperable, loads).

AND B.1.2 Determine that an Immediately OPERABLE subsystem(s),

involving equipment not associated with the inoperable snubber(s) exists to provide makeup and core cooling needed to mitigate a LOOP event.

AND (continued)

SUSQUEHANNA - UNIT 1 TRM / 3.7-45 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev.a3 3.7.8 CONDITION REQUIRED ACTION COMPLETION TIME B.1.3 Determine that the subsystem Immediately supported by the inoperable snubber would remain capable of performing its required safety or support functions for postulated design loads other than seismic loads.

AND

---

--- NOTE-- --

REQUIRED ACTIONS B.1.1 through B.1.3 must be completed prior to completing REQUIRED ACTION B.1.4.

B.1.4 Enter LCO 3.0.8 Immediately AND B.1.5 Replace or restore the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> inoperable snubber(s) to OPERABLE status C. Required Action and C.1 Declare the supported system Immediately I associated Completion inoperable I Time of Condition A or B not met (continued)

SUSQUEHANNA - UNIT 1 TRM / 3.7-46 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev..32 3.7.8 CONDITION REQUIRED ACTION COMPLETION TIME D. Any snubber selected for D. ---------- NOTE---------- Within the current functional testing either fails This action shall be inspection interval.

to activate or fails to move independent of the Testing due to manufacturer or Requirement for snubbers not design deficiency. meeting the functional test acceptance criteria per TRS 3.7.8.2 All snubbers of the same design subject to the same defect shall be functionally tested E. The snubber service life will E.1 Reevaluate the snubber Prior to exceeding be exceeded prior to the service life snubber service life next scheduled snubber service life review OR E.2 Replace or recondition the Prior to exceeding snubber so as to extend its snubber service life service life beyond the date of the next scheduled service life review TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.7.8.1 Demonstrate each snubber OPERABLE by As directed by Table 3.7.8-1 performance of visual inspection TRS 3.7.8.2 Perform functional test of a representative 24 months sampling of all snubbers per Table 3.7.8-3.

(continued)

SUSQUEHANNA - UNIT 1 TRM / 3.7-47 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev. 3.7.8 TECHNICAL REQUIREMENT SURVEILLANCE (continued)

SURVEILLANCE FREQUENCY TRS 3.7.8.3 -------------- NOTE -----....----------.-.. 24 months Documentation of critical parts replaced so that the maximum service life is not exceeded shall be retained as required by FSAR 17.2-17 Monitor the installation and maintenance records for each snubber to ensure that the service life has not been exceeded and will not be exceeded prior to the next snubber surveillance inspection.

TRS 3.7.8.4 ----------------- NOTE--------------- At the time of the next Snubber tested per this surveillance are in functional test addition to snubbers selected for the sample plan per TRS 3.7.8.2 Test snubbers in locations of snubbers that failed the functional test during the previous test period and test repaired failed snubbers placed in new locations.

TRS 3.7.8.5 An inspection shall be performed of all Within 6 months snubbers attached to sections of systems that of transient have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems.

SUSQUEHANNA - UNIT 1 TRM / 3.7-48 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev.a.3 3.7.8 Table 3.7.8-1 SNUBBER VISUAL INSPECTION INTERVAL Number Of Unacceptable Visually Inspected Snubbers in Previous Inspection Interval Inspection Interval

1. Equal to or less than the applicable May be twice the previous interval but not number in Table 3.7.8-2 Column A greater than 48 months

2. Equal to or less than the applicable Same as the previous interval number in Table 3.7.8-2 Column B but greater than the applicable number in Column A

3. Equal to or greater than the applicable Two-thirds of the previous interval number in Table 3.7.8-2 Column C

4. Less than the applicable number in Equal to the previous interval (1i-1), reduced Table 3.7.8-2 Column C but greater proportionally by a factor that is one-third of than the applicable number in the ratio of the difference between the Column B number of unacceptable snubbers found during the previous interval (N ._)

1 and the number in Column B (NB) to the difference in the numbers in Columns C (Nc) and B,

- or:

I=I_ 3I- 1 (Nil NB SUSQUEHANNA - UNIT 1 TRM / 3.7-49 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev..3- 3.7.8 TABLE 3.7.8-2 NUMBER OF UNACCEPTABLE SNUBBERS PREVIOUS SNUBBER VISUAL INSPECTION INTERVAL Pol5ulation Column A Column B Column C 1 0 0 1 80 0 0 2 100 0 1 4 150 0 3 8 200 2 5 13 300 5 12 25 400 8 18 36 500 12 24 48 750 20 40 78 1,000 or greater 29 56 109

---

.-....--------..............----------.------ NOTES-----------

1.- Interpolation between population or category sizes and the number of unacceptable snubbers is permissible. Use next lower integer for the value of the limit for Columns A, B or C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.

2. The provisions of TRS 3.0.2 are applicable for all inspection intervals up to and including 48 months.

SUSQUEHANNA - UNIT 1 TRM / 3.7-49a EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev.I.3 3.7.8 TABLE 3.7.8-3 FUNCTIONAL TESTING SAMPLE FAILED SNUBBERS REPRESENTATIVE SAMPLING (a)

1. Initial 0 10%

2. Re-Test >0 in initial sample Additional 5 %(b) for each failure

3. Continued Testing >0 In Re-tester or Additional 5% for each failure to Continued Testing 1 0 0 %(b)

Samples (a) Percentage of the total population of each type of snubber (b) An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure and the determine the OPERABILITY of other snubbers, irrespective of type, which may be subject to the same failure mode. The results of this evaluation shall be used. If applicable, in selecting snubbers to be tested. If additional sampling is required due to failure of only one type of snubber, additional samples should be limited to the type of snubber, which has failed the functional testing.

SUSQUEHANNA - UNIT 1 TRM / 3.7-49b EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev-2 B 3.7.8 B 3.7.8 Snubbers BASES TRO All snubbers are required to be OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on non-safety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.

Snubbers are required to be OPERABLE whenever they are considered necessary to support equipment for the systems on which they are installed.

Technical'Specification LCO 3.0.8 has been added to the Technical Specifications to allow snubbers to be inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if the inoperable snubber affects one subsystem or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if it affects multiple subsystems.

The generic NRC Safety Evaluation which approved the use of LCO 3.0.8 requires that certain conditions be met before LCO 3.0.8 can be entered.

TRM 3.7.8 provides guidance on meeting these conditions.

"Type" of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity. For example, mechanical snubbers utilizing the same design features of the 2-kip, and 100-kip capacity manufactured by Company "A" are of the same type. The same design mechanical snubbers manufactured by company "B" for the purposes of this Technical Requirement would be of a different type, as would hydraulic snubbers from either manufacturer.

A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR part 50. The controlled list of plant snubbers is maintained by the ISI Program. The addition or deletion of any snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.

(continued)

SUSQUEHANNA - UNIT 1 TRM / B 3.7-24 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev. 2- B 3.7.8 B 3.7.8 Snubbers BASES TRO The following are examples of conditions that require a snubber to be (continued) declared inoperable:

- Snubber not attached to piping system or support plate,

- Snubber missing,

- Snubber locked in position,

- Snubber excessively bent.

The following are examples of conditions that require an evaluation to confirm whether or not the snubber is inoperable:

- Dent(s) in snubber case,

- Thread engagement not per design,

- Missing bolt(s) on support plate,

- Snubber slightly bent.

As stated in NRC's Safety Evaluation Condition 2, the LCO 3.0.8 require-ment to assess and manage risk is met by licensee programs to comply with the requirements of paragraph (a)(4) of the Maintenance Rule, 10 CFR 50.65, to assess and manage risk resulting from maintenance activities. Since the 10 CFR 50.65(a) (4) guidance, the revised (May 2000)

Section 11 of NUMARC 93-01, does not address seismic risk, licensees must qualitatively integrate the use of LCO 3.0.8 into their 10 CFR 50.65(a) (4) program to assess and manage risk.

As described in the Bases of LCO 3.0.8, "LCO 3.0.8 should be considered with respect to other plant maintenance activities, and integrated into the existing Maintenance Rule process to the extent possible so that maintenance on any unaffected train or subsystem is properly controlled, and emergent issues are properly addressed. The risk assessment need not be quantified, but may be a qualitative awareness of the vulnerability of systems and components when one or more snubbers are not able to perform their associated support function."

(continued)

SUSQUEHANNA - UNIT 1 TRM / B 3.7-25 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev...2 B 3.7.8 B 3.7.8 Snubbers BASES (continued)

ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components and the implementation of LCO 3.0.8. The NRC's 4/27/2005 Safety Evaluation lists the conditions that must be followed to adopt and utilize LCO 3.0.8. The ACTIONS provide the guidance for the implementation of these conditions and therefore the implementation of LCO 3.0.8.

Conditions A and B Condition A applies when one or more snubbers are not capable of providing their associated support function(s) to a single subsystem of a multiple subsystem supported system or to a single subsystem supported system.

Condition B applies when one or more snubbers are not able to perform their associated support function(s) are associated with more than one subsystem of a multiple subsystem supported system.

The wording of these Conditions allow for confirmation of snubber inoperability.- This allows for input from snubber knowledgeable parties to review the condition. The intent'is to obtain this confirmation in an expeditious manner and not delay declaring a snubber or support system inoperable. If confirmation of snubber inoperability is delayed,.thesnubber should be considered inoperable and appropriate actions of this TRO applied.

Required Action A.1.1 or B.1.1 When a snubber is to be rendered incapable of performing its related support function (i.e., nonfunctional) for testing or maintenance or is discovered to not be functional, it must be determined whether any Technical Specification (TS) system(s) require the affected snubber(s) for system OPERABILITY, and whether the plant is in a MODE or specified condition in the Applicability that requires the supported TS system(s) to be OPERABLE.

1. If an analysis determines that the supported TS system(s) do not require the snubber(s) to be functional in order to support the OPERABILITY of the system(s), LCO 3.0.8 is not needed.

2. If the LCO(s) associated with any supported TS system(s) are not currently applicable (i.e., the plant is not in a MODE or other specified condition in the Applicability of the LCO), LCO 3.0.8 is not needed.

(continued)

SUSQUEHANNA - UNIT 1 TRM / B 3.7-26 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev.2- B 3.7.8 B 3.7.8 Snubbers BASES ACTIONS 3. If the supported TS system(s) are inoperable for reasons other than (continued) snubbers, LCO 3.0.8 cannot be used.

LCO 3.0.8 is an allowance, not a requirement. When a snubber is nonfunctional, any supported TS system(s) may be declared inoperable instead of using LCO 3.0.8.

The NRC Safety Evaluation only considered the loss of the ability of a snubber to respond to a seismic event. However, some snubbers have design functions other than response to a seismic event. The inability to perform these non-seismic design functions were not considered or justified. Therefore, when a snubber is to be rendered nonfunctional for testing or maintenance or is discovered to not be functional, the design function of the snubber must be determinedi in order to determine if LCO 3.0.8 may be used.

1. If the design function of the snubber is to react to only seismic loads, LCO 3.0.8 may be applied.

2. If the design function of the snubber includes both seismic loads and non-seismic loads (e.g._, thrust loads, blowdown loads, waterhammer loads, steamhammer loads, LOCA loads, and pipe rupture loads),

any TS systems supported by the nonfunctional snubber must be able to remain OPERABLE if subjected to the non-seismic loads with the snubber removed. If the supported TS system will remain OPERABLE when subjected to non-seismic loads, LCO 3.0.8 may be applied. Otherwise, LCO 3.0.8 may not be applied to TS systems supported by the nonfunctional snubber.

3. If the design function of the snubber includes only non-seismic loads (e.g., thrust loads, blowdown loads, waterhammer loads, steam-hammer loads, LOCA loads, and pipe rupture loads), LCO 3.0.8 cannot be applied to the TS systems supported by the nonfunctional snubber. However, if it can be confirmed that snubber is not needed for OPERABILITY of the TS system, LCO 3.0.8 is not needed.

Note: Snubbers located in the Diesel Generator Buildings only have seismic loads as their design function loads. Snubbers located elsewhere in the plant have both seismic and non-seismic loads as their design function loads.

(continued)

SUSQUEHANNA - UNIT 1 TRM / B 3.7-27 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev..2. B 3.7.8 B 3.7.8 Snubbers BASES ACTIONS Required Action A.1.2 or B.1.2 (continued)

This Required Action ensures that when LCO 3.0.8 is entered there are sufficient OPERABLE subsystems (not associated with the inoperable snubber) to provide makeup and heat removal in the event of a LOOP.

The NRC does not require any other accidents or events such as LOCA, DBA or transients to be accounted for. The subsystems that can be use to meet this condition are:

a. At least one OPERABLE high pressure subsystem (e.g., HPCI or RCIC) and OPERABLE heat removal capability (e.g., suppression pool cooling), or

b. At least one OPERABLE low pressure subsystem (e.g., LPCI or CS) and OPERABLE heat removal capability (e.g., suppression pool cooling or shutdown cooling).

The NRC's Safety Evaluation Condition 1 .(d) is met by these required actions.

Required Action A.1.3 or B.1.3 The NRC's Safety Evaluation requires that subsystem(s) associated with inoperable snubber (s) must be capable of performing their required safety or support function when subjected to the postulated non-seismic design function loads.

NRC's Safety Evaluation also requires that every time LCO 3.0.8 is used for TS systems supported by nonfunctional snubbers whose design loads include non-seismic loads, licensees must be able to produce a record of the design function of the nonfunctional snubber (i.e., seismic vs. non-seismic). This record does not have to be created prior to or following use of LCO 3.0.8, but must be able to be created or produced if requested.

For example, if a system engineer knows from previous experience that a particular snubber is only designed for seismic loads, it is not necessary to collect existing design documents or create design documents or calcula-tions to demonstrate that fact prior to using LCO 3.0.8. However, if asked to demonstrate the design basis of the snubber, the licensee must be able to produce or create appropriate documentation to support that position.

Required Action A.1.4 or B.1.4 Required Action A.1.4 or B.1.4 provide for the entry into LCO 3.0.8 provided the requirements for entry are verified.

(continued)

SUSQUEHANNA - UNIT 1 TRM / B 3.7-28 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev92 B 3.7.8 B 3.7.8 Snubbers BASES ACTIONS Required Action A.1.5 or B.1.5 (continued)

The completion time is consistent with the time used to evaluate the risk of having an inoperable snubber and not declaring the system LCO.

Condition E Snubbers are required to be OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Evaluating their service life and replacing them before the end of their service life ensures that the snubbers will remain OPERABLE.

TRS The TRSs are defined to be performed at the specified Frequency to ensure that the snubbers are maintained OPERABLE. Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the completion of their fabrication or at a subsequent date. Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.

TRS 3.7.8.1 The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Generic Letter 90-09 provides a method for determining the next interval for the visual inspection of snubbers based upon the number of unacceptable snubbers found during the previous inspection, the total population or category size for each snubber type, and the previous inspection interval.

The visual inspection interval for a snubber population shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 3.7.8-1. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 3.7.8-1.

(continued)

SUSQUEHANNA - UNIT 1 TRM / B 3.7-29 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev.2 B 3.7.8 B 3.7.8 Snubbers BASES (continued)

TRS Snubbers may be categorized, based upon their accessibility during power (continued) operation, as accessible or inaccessible, and are inspected on that basis.

The snubber population, for the purpose of visual inspection, is determined either separately or jointly for accessible and inaccessible units. The results of snubber examinations are judged, per Table 3.7.8-2, in accordance with that population. The decision whether to combine the category populations or keep them separate must be documented before any inspection, and that decision shall be used as-the basis upon which to determine the subsequent inspection interval for that category.

The accessibility of each snubber shall be determined and approved by the Plant Operations Review Committee. The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.

Visual inspections shall verify that (1) the snubber has no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component, and to the snubber anchorage are functional.

Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per TRS 3.7.8.2.

A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber. If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.

(continued)

SUSQUEHANNA - UNIT 1 TRM / B 3.7-30 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev.2 B 3.7.8 B 3.7.8 Snubbers BASES TRS TRS 3.7.8.2 (continued)

A representative sample of snubbers shall be tested for each type of snubber. The representative sample selected for the functional test sample plans shall be randomly selected from the snubbers of each type and reviewed before beginning the testing. The review shall ensure as far as practical that they are representative of the various configurations, operating environments, range of size, and capacity of snubbers of each type.

Functional Test Acceptance Criteria The snubber functional test shall verify that:

1) Activation (restraining action) is achieved within the specified range in both tension and compression;

2) Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range;

3) Where required, the force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel; and

4) For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement.

Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.

TRS 3.7.8.3 The maximum expected service life for various seals, springs, and other critical parts shall be determined and established based on engineering information and shall be extended or shortened based on monitored test results and failure history. Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be OPERABLE. The parts replacements shall be documented and the documentation shall be retained in accordance with FSAR 17.2.17.

(continued)

SUSQUEHANNA - UNIT 1 TRM / B 3.7-30a EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev.2 B 3.7.8 B 3.7.8 Snubbers BASES TRS - The service life of a snubber is evaluated via manufacturer input and (continued) information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.

TRS 3.7.8.5 The required inspection consists of the following elements:

1. Perform a visual inspection of all affected snubbers,

2. Verify freedom of motion of mechanical snubbers by manually induced snubber movement, or

3. Verify freedom of motion of mechanical snubbers by evaluation of in-place snubber piston setting, or

4. Verify freedom of motion of mechanical snubbers by stroking the mechanical snubber through its full range of travel.

REFERENCES 1. Generic Letter 90-09 SUSQUEHANNA - UNIT 1 TRM / B 3.7-30b EFFECTIVE DATE 10/05/2006

Heavy Loads Requirements PPL Rev.4 3.12.2 3.12 Loads Control Program 3.12.2 Heavy Loads Requirements TRO 3.1-2.2 The Technical Specification Limiting Conditions of Operation and Technical Requirements for Operation listed in Table 3.12.2-1 shall be met.

APPLICABILITY: During movement of heavy loads in the proximity of irradiated fuel.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The Conditions of A. 1 Suspend movement 6f heavy Immediately TRO 3.12.2 are not met. loads in the proximity of irradiated fuel.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.12.2.1 Administratively verify that all requirements of Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to TRO are met. commencing movement of heavy loads AND Every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter SUSQUEHANNA - UNIT 1 TRM / 3.12-3 EFFECTIVE DATE 2/05/1999

Heavy Loads Requirements PPL Rev. 3.12.2 TABLE 3.12.2-1 TRO 3.12.2 REQUIREMENTS

a. LCO 3.3.6.2(a)

b. LCO 3.3.7.1(b)

c. LCO 3.6.4.1(c)

d. LCO 3.6.4.2(c)

e. LCO 3 .6.4. 3(d)

f. LCO 3.7.3(d)

g. LCO 3.7.7(")

h. LCO 3.8.2

i. LCO 3.8.5

j. LCO 3.8.8

k. LCO 3.9.6 I. TRO 3.3.4(0

m. TRO 3.7.1

n. TRO 3.9. 1 (9

o. TRO 3.11.2.6(h)

(a) Functions 3, 4, 5, 6, and 8.

(b) Functions 3, 4, 5, 6, 8, and 9.

(c) Zone III only.

(d) Minimum of one train OPERABLE.

(e) Only required for movement of heavy load in the proximity of irradiated fuel in the spent fuel storage pool.

() Function 4 from Table 3.3.4-1.

(g) Only required for movement of heavy load in the proximity of irradiated fuel in the Reactor Pressure Vessel with the Steam Separator removed.

(h) Function 3 from Table 3.11.2.6-1.

SUSQUEHANNA - UNIT 1 TRM / 3.12-4 EFFECTIVE DATE 09/30/2006

Oct. 13, 2006 Page 1 of 3 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2006-44178 USER INFORMATION:

GERLACH*ROSE M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:

TO: GERLACH*ROSE M 10/13/2006 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.

TRM2 - TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 09/26/2006 ADD MANUAL TABLE OF CONTENTS DATE: 10/12/2006 CATEGORY: DOCUMENTS TYPE: TRM2

Oct. 13, 2006 Page 2 of 3 ID: TEXT 3.12.2 REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.2.1 REMOVE: REV:4 ADD: REV: 5 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.7.8 REMOVE: REV:4 ADD: REV: 5 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT B3.7.8 REMOVE: REV:1 ADD: REV: 2 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT LOES REMOVE: REV:26 ADD: REV: 28 REMOVE: REV:27 ADD: REV: 27

Oct. 13, 2006 Page 3 of 3 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 FOR ASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 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 Y Manual Name: TRM2-

• lnual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents Issue Date: 10/12/2006 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 28 10/12/2006

Title:

LIST OF EFFECTIVE SE:CTIONS TEXT TOC 8 06/13/2006

Title:

TABLE OF CONTENTS TEXT 1.1 0 11/19/2002

Title:

USE AND APPLICATION DEFINITIONS TEXT 2.1 1 02/04/2005

Title:

PLANT PROGRAMS AND SETPOINTS PLANT PROGRAMS TEXT2. 5 11/22/2005 PLANT PROGRAMS AND SETPOINTS INSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 1 01/06/2006

Title:

APPLICABILITY TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT 3.1.1 0 11/19/2002

Title:

REACTIVITY CONTROL-SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT 3.1.2 0 11/19/2002

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1.3 2 11/22/2005

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 0 11/19/2002

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT 3.2.1 5 10/12/2006

Title:

CORE OPERATING LIMITS CORE OPERATING LIMITS REPORT (COLR)

Report Date: 10/12/06 Page Page 1 of 15 15 Report Date: 10/12/06

SSES MANUJAL Manual Name : TRM2-- y Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.3.1 0 11/19/2002

Title:

INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 1 04/26/2006

Title:

INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 1 04/26/2006

Title:

INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 2 06/13/2006

Title:

INSTRUMENTATION TRM POST-ACCIDENTMONITORING INSTRUMENTATION TEXT 3.3.5 0 11/19/2002

Title:

INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK TEXT 3.3.6 2 - 10/19/2005

Title:

INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 0 11/19/2002

Title:

INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 1 10/22/2003

Title:

INSTRUMENTATION TRM RPS INSTRUMENTATION TEXT 3.3.9 1 11/22/2004

Title:

INSTRUMENTATION LPRM UPSCALE ALARM INSTRUMENTATION TEXT 3.3.10 1 12/14/2004

Title:

INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1 10/22/2003

Title:

INSTRUMENTATION MVP ISOLATION INSTRUMENTATION TEXT 3.4.1 1 04/26/2006

Title:

REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY Report Date: 10/12/06 Page 2 Page of of 15 15 Report Date: 10/12/06

& SSES MANUAL N Manual Name-: TRM2-E ual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.4.2 0 11/19/2002

Title:

REACTOR-COOLANT SYSTEM STRUCTURAL INTEGRITY TEXT 3.4.3 0 11/19/2002

Title:

REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM (RCS)

TEXT 3.4.4 1 12/14/2004

Title:

REACTOR COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT 3.4.5 1 04/26/2006

Title:

REACTOR COOLANT SYSTEM REACTOR VESSEL MATERIALS TEXT 3.5.1 1 02/04/2005

Title:

ECCS AND RCIC ADS MANUAL INHIBIT EXT 3.5.2 0 - 11/19/2002

Title:

ECCS AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0 11/19/2002

Title:

ECCS AND RCIC LONG TERM NITROGEN SUPPLY TO ADS TEXT 3.6.1 0 11/19/2002

Title:

CONTAINMENT VENTING OR PURGING TEXT 3.6.2 0 11/19/2002

Title:

CONTAINMENT SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0 11/19/2002

Title:

CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION TEXT 3.6.4 0 11/19/2002

Title:

CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 0 11/19/2002

Title:

PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN-P Page 3 of 15 Report Date: 10/12/06

SSES MANUAL~

Manual Name: TRM2- 4 Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7.2 0 11/19/2002

Title:

PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL TEXT 3.7.3.1 1 04/26/2006

Title:

PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 2 04/26/2006

Title:

PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS TEXT 3.7.3.3 2 08/18/2005

Title:

PLANT SYSTEMS C02 SYSTEMS TEXT 3.7.3.4 1 04/26/2006

Title:

PLANT SYSTEMS HALON SYSTEMS TEXT 3.7.3.5 1 -04/26/2006

Title:

PLANT SYSTEMS FIRE HOSE STATIONS TEXT 3.7.3.6 1 04/26/2006

Title:

PLANT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT 3.7.3.7 1 04/26/2006

Title:

PLANT SYSTEMS FIRE RATED ASSEMBLIES TEXT 3.7.3.8 5 01/06/2006

Title:

PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION TEXT 3.7.4 1 04/26/2006

Title:

PLANT SYSTEMS SOLID RADWASTE SYSTEM TEXT 3.7.5.1 0 11/19/2002

Title:

PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT 3.7.5.2 - 0 11/19/2002

Title:

PLANT SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE Report Date: 10/12/06 Page 44 Page of of 15 15 Report Date: 10/12/06

SSES MANUAL

,'Manual Name: TRM2---

.anual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7.5.3 1 04/26/2006

Title:

PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 1 03/01/2005

Title:

PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 0 11/19/2002

Title:

PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT 3.7.8 5 10/12/2006

Title:

PLANT SYSTEMS SNUBBERS TEXT 3.7.9 1 08/28/2006

Title:

PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 37.10 1 - 12/14/2004

Title:

PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)

TEXT 3.8.1 2 02/04/2005

Title:

ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT 3.8.2.1 1 12/14/2004

Title:

ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

CONTINUOUS TEXT 3.8.2.2 2 12/14/2004

Title:

ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

AUTOMATIC TEXT 3.8.3 0 11/19/2002

Title:

ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT 3.8.4 1 02/04/2005

Title:

ELECTRICAL POWER 24 VDC ELECTRICAL SUBSYSTEM TEXT 3.8.5 0 11/19/2002

Title:

ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION Report Date: 10/12/06 Page 55 of of 15 15 Report Date: 10/12/06

SSES MANUAL Manual Name: TRM2 ,

Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.8.6 0 11/19/2002

Title:

ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.9.1 0 11/19/2002

Title:

REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0 11/19/2002

Title:

REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 0 11/19/2002

Title:

REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 1 04/26/2006

Title:

MISCELLANEOUS SEALED SOURCE CONTAMINATION TEXT 3.10.2 0 - 11/19/2002

Title:

MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 1 04/26/2006

Title:

MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (iSFSI)

TEXT 3.10.4 1 08/28/2006

Title:

MISCELLANEOUS LEADING EDGE FLOW METER (LEFM)

TEXT 3.11.1.1 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION TEXT 3.11.1.2 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE TEXT 3.11.1.3 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM TEXT 3.11.1.4 -* 1 12/14/2004

Title:

RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION Pag 6of 5 eprt at: 1/1/0 Page 6 of 15 Report Date: 10/12/06

SSES MANUAL Eanual

? Manual Name: TRM2-

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.11.1.5 1 12/14/2004

Title:

RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT 3.11.2.1 3 04/26/2006

Title:

RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3.11.2.2 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES TEXT 3.11.2.3 .1 . 04/26/2006

Title:

RADIOACTIVE EFFLUENTS DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM TEXT 3.11.2.4 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3.11.2.5 2 04/26/2006

Title:

RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3.11.2.6 2 12/14/2004

Title:

RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.3 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS TOTAL DOSE TEXT 3.11.4.1 3 04/26/2006

Title:

RADIOACTIVE EFFLUENTS MONITORING PROGRAM TEXT 3.11.4.2 2 04/26/2006

Title:

RADIOACTIVE EFFLUENTS LAND USE CENSUS TEXT 3.11.4.3 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS INTERLABORATORY COMPARISON PROGRAM TEXT 3.12.1 0 11/19/2002

Title:

LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL STORAGE POOL -

Report Date: 10/12/06 Page 7 of of 15 15 Report Date: 10/12/06

SSES MANUAL Manual Name: TRM2-Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.12.2 1 10/12/2006

Title:

LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0 11/19/2002

Title:

LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENTS TEXT B3.0 1 01/06/2006

Title:

APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.1.1 0 11/19/2002

Title:

REACTIVITY CONTROL SYSTEM BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.1.2 0 11/19/2002

Title:

REACTIVITY CONTROL SYSTEM BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT B3.1.3 2 11/22/2005

Title:

REACTIVITY CONTROL SYSTEM BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT B3.1.4 0 11/19/2002

Title:

REACTIVITY CONTROL SYSTEM BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.1 0 11/19/2002

Title:

CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR)

TEXT B3.3.1 0 11/19/2002

Title:

INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 0 11/19/2002

Title:

INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 1 02/04/2005

Title:

INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 2 06/13/2006

Title:

INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Pag 8 of 5 eprt at: 1/1/0 Page 8 of 15 Report Date: 10/12/06

QSSES MANUAL

,,Manual Name: TRM2-Sanual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.3.5 1 06/13/2006

Title:

INSTRUMENTATION BASES THIS PAGE INTENTIONALLY LEFT BLANK TEXT B3.3.6 3 10/19/2005

Title:

INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION TEXT B3.3.7 0 11/19/2002

Title:

INSTRUMENTATION BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT B3.3.8 1 10/22/2003

Title:

INSTRUMENTATION BASES TRM RPS INSTRUMENTATION TEXT B3.3.9 1 11/22/2004

Title:

INSTRUMENTATION BASES LPRM UPSCALE ALARM INSTRUMENTATION TEXT B3.3.10 0 11/19/2002

Title:

INSTRUMENTATION BASES REACTOR RECIRCULATION PUMP MG SET STOPS TEXT B3.3.11 1 10/22/2003

Title:

INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3.4.1 0 11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY TEXT B3.4.2 0 11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES STRUCTURAL INTEGRITY TEXT B3.4.3 0 11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR TEXT B3.4.4 0 11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT B3.4.5 0 11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS Report Date: 10/12/06 Page 9 Page 9 of of 15 15 Report Date: 10/12/06

SSES MANUAL Manual Name: TRM2--

Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.5.1 0 11/19/2002

Title:

ECCS ANE RCIC BASES ADS MANUAL INHIBIT TEXT B3.5.2 0 11/19/2002

Title:

ECCS AND RCIC BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT B3.5.3 0 11/19/2002

Title:

ECCS AND RCIC BASES LONG TERM NITROGEN SUPPLY TO ADS TEXT B3.6.1 0 11/19/2002

Title:

CONTAINMENT BASES VENTING OR PURGING TEXT B3.6.2 0 11/19/2002

Title:

CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 0 11/19/2002

Title:

CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION TEXT B3.6.4 1 12/14/2004

Title:

CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT B3.7.1 0 11/19/2002

Title:

PLANT SYSTEMS BASES EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN)

TEXT B3.7.2 0 11/19/2002

Title:

PLANT SYSTEMS BASES ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL TEXT B3.7.3.1 1 04/26/2006

Title:

PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT B3.7.3.2 2 04/26/2006

Title:

PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS TEXT B3.7.3.3 - 0 11/19/2002

Title:

PLANT SYSTEMS BASES C02 SYSTEMS 0

Page 10 of 15 Report Date: 10/12/06

SSES MANUAL Manual Name: TRM2

• anual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.3.4 1 04/26/2006

Title:

PLANT SYSTEMS BASES HALON SYSTEMS TEXT B3.7.3.5 1 04/26/2006

Title:

PLANT SYSTEMS BASES FIRE HOSE STATIONS TEXT B3.7.3.6 1 04/26/2006

Title:

PLANT SYSTEMS BASES YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT B3.7.3.7 0 11/19/2002

Title:

PLANT SYSTEMS BASES FIRE RATED ASSEMBLIES TEXT B3.7.3.8 1 01/12/2004

Title:

PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION TEXT B3.7.4 0 11/19/2002

Title:

PLANT SYSTEMS BASES SOLID RADWASTE SYSTEM TEXT B3.7.5.1 0 11/19/2002

Title:

PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT B3.7.5.2 0 11/19/2002

Title:

PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT B3.7.5.3 0 11/19/2002

Title:

PLANT SYSTEMS BASES LIQUID HOLDUP TANKS TEXT B3.7.6 1 03/01/2005

Title:

PLANT SYSTEMS BASES ESSW PUMPHOUSE VENTILATION TEXT B3.7.7 0 11/19/2002

Title:

PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT B3.7.8 2 10/12/2006

Title:

PLANT SYSTEMS BASES SNUBBERS Report Date: 10/12/06 Page 11 Page of of 15 15 Report Date: 10/12/06

SSES M4ANUTAL Manual Name: TRM2-Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.9 1 12/14/2004

Title:

PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1 12/14/2004

Title:

PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.8.1 1 02/04/2005

Title:

ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT B3.8.2.1 0 11/19/2002

Title:

ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

CONTINUOUS TEXT B3.8.2.2 1 09/17/2004

Title:

ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

AUTOMATIC TEXT B3.8.3 0 - 11/19/2002

Title:

ELECTRICAL POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT B3.8.4 0 11/19/2002

Title:

ELECTRICAL POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT B3.8.5 0 11/19/2002

Title:

ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B3.8.6 1 02/04/2005

Title:

ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.9.1 0 11/19/2002

Title:

REFUELING OPERATIONS BASES DECAY TIME TEXT B3.9.2 0 11/19/2002

Title:

REFUELING OPERATIONS BASES COMMUNICATIONS TEXT B3.9.3 -* 0 11/19/2002

Title:

REFUELING OPERATIONS BASES REFUELING PLATFORM Report Date: 10/12/06 Page 12 Page 12 of of 15 15 Report Date: 10/12/06

SSES MANUJMJ d Manual Name: TRM--

Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.10.1 0 11/19/2002

Title:

MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 0 11/19/2002

Title:

MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT B3.10.3 0 11/19/2002

Title:

MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

TEXT B3.10.4 .0 - 11/19/2002

Title:

MISCELLANEOUS BASES LEADING EDGE FLOW METER (LEFM)

TEXT B3.11.1.1 0 11/19/2002

Title:

RADIOACTIVE EFFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3.11.1.2 0 11/19/2002

Title:

RADIOACTIVE EF FLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3.11.1.3 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3.11.1.4 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.1.5 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.11.2.1 1 12/14/2004

Title:

RADIOACTIVE EFFLUENTS BASES DOSE RATE TEXT B3.11.2.2 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES TEXT B3.11.2.3 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN hk PARTICULATES FORM Report Date: 10/12/06 Page 13 Page 13 of of 15 15 Report Date: 10/12/06

SSES MANUAL Manual Name: TRM2-Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.11.2.4 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.11.2.5 3 05/20/2005

Title:

RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3.11.2.6 1 01/27/2004

Title:

RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.3 0 - 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES TOTAL DOSE TEXT B3.11.4.1 2 01/06/2006

Title:

RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3.11.4.2 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES LAND USE CENSUS TEXT B3.11.4.3 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAM TEXT B3.12.1 0 11/19/2002

Title:

LOADS CONTROL PROGRAM BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT B3.12.2 0 11/19/2002

Title:

LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS TEXT B3.12.3 0 11/19/2002

Title:

LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS TEXT 4.1 0 09/27/2003

Title:

ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 -* 0 09/27/2003

Title:

ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION Report Date: 10/12/06 14 Page 14 of of 15 15 Report Date: 10/12/06

SSES MANUAL 4 Manual Name: TRM2-anual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 4.3 09/27/2003

Title:

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION TEXT 4.4 0 09/27/2003

Title:

ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT 4.5 0 09/27/2003

Title:

ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS TEXT 4.6 0 09/27/2003

Title:

ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM TEXT 4.7 0 09/27/2003

Title:

ADMINISTRATIVE CONTROLS TRAINING Report Date: 10/12/06 15 Page 15 of of 15 15 Report Date: 10/12/06

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 28 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date TOC TABLE OF CONTENTS 05/30/2006 1.0 USE AND APPLICATION Page TRM /1.0-1 08/31/1998

- Page TRM /1.0-2 10/04/2002 Page TRM / 1.0-3 08/31/1998 2.0 PLANT PROGRAMS Page 2.0-1 08/31/1998 Pages TRM / 2.0-2 and TRM 2.0-3 01/28/2005 Page TRM / 2.0-4 06/25/2002 Page TRM / 2.0-5 04/12/1999 Pages TRM / 2.0-6 and TRM / 2.0-7 11/15/2004 Page TRM / 2.0-8 12/03/2004 Pages TRM / 2.0-9-through TRM / 2.0-11 11/15/2004 Pages TRM / 2.0-12 through TRM / 2.0-15 11/15/2005 3.0 APPLICABILITY Pages TRM / 3.0-1 and TRM / 3.0-2 04/08/1999 Page TRM / 3.0-3 03/15/2002 Page TRM / 3.0-4 11/30/2005 3.1 REACTIVITY CONTROL SYSTEMS Pages 3.1-1 through 3.1-6 08/31/1998 Pages TRM / 3.1-7 and TRM 3.1-8 11/15/2005 Pages TRM / 3.1-9 and TRM /.3.1-9a 02/18/1999 Page TRM /3. -10 .. 02/18/1999 3.2 CORE OPERATING LIMITS REPORT Page 3,2-1,\ 08/31/1998 Pages TRM / 3.2-2 through TRM / 3.2-39 10/05/2006 3.3 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 07/16/1999

'Page TRM / 3.3-4 03/31/2006 Pages 3.3-5 and 3.3-6 08/31/1998 Page TRM 3.3-7 03/31/2006 Page 3.3-8 08/31/1998 Pages TRM / 3.3-9 and TRM / 3.3-9a 12/17/1998 Page TRM / 3.3-10 05/30/2006 Page TRM / 3.3-11 06/02/2005 Page TRM / 3.3-11 a 05/30/2006 Page TRM / 3.3-12 03/30/2001 Page TRM / 3.3-13 09/13/2005 Page TRM / 3.3-14 12/14/1998 Page TRM / 3.3-15 10/22/2003 SUSQUEHANNA - UNIT 2 TRM / LOES-1 EFFECTIVE DATE 10/10/2006

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 28 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date Page TRM / 3.3-16 06/27/2001 Pages TRM / 3.3-17 and TRM / 3.3-18 06/14/2002 Pages TRM / 3.3-19 and TRM / 3.3-20 10/22/2003 Page TRM / 3.3-21 11/15/2004 Pages TRM /3.3-21a through TRM / 3.3-21d 11/15/2004 Page TRM / 3.3-22 12/03/2004 Pages TRM / 3.3-23 and TRM / 3.3-24 05/16/2003 Page TRM / 3.3-25 10/22/2003 3.4 REACTOR COOLANT SYSTEM Page TRM / 3.4-1 03/31/2006 Pages 3.4-2 through 3.4-5 10/23/1998 Pages 3.4-6 through 3.4-11 08/31/1998 Page TRM / 3.4-12 12/03/2004 Page TRM / 3.4 03/31/2006 3.5 EMERGENCY CORE COOLING AND RCIC Page TRM / 3.5-1 01/28/2005 Pages 3.5-2 and 3.5-3 08/31/1998 Page TRM / 3.5-4 04/17/2000 Pages 3.5-5 through 3.5-7 08/31/1998 3.6 CONTAINMENT Pages 3.6-1 through 3.6-4 08/31/1998 Page TRM / 3.6-5 01/07/2002 Page 3.6-6 08/31/1998 Pages TRM / 3.6-7 through TRM / 3.6-9 12/31/2002 3.7 PLANT SYSTEMS Pages TRM / 3.7-1 and TRM / 3.7-2 07/29/1999 Page 3.7-3 08/31/1998 Pages TRM / 3.7-4 and TRM / 3.7-5 03/31/2006 Pages TRM / 3.7-6 through TRM / 3.7-8 08/02/1999 Page TRM / 3.7-9 03/31/2006 Page TRM / 3.7-10 08/16/2005 Page TRM / 3.7-11 01/21/2000 Pages TRM / 3.7-12 and TRM / 3.7-13 08/02/1999 Page TRM / 3.7-14 08/09/2005 Pages TRM / 3.7-15 and TRM / 3.7-16 08/02/1999 Page TRM / 3.7-17 03/31/2006 Page TRM / 3.7-18 08/02/1999 Page TRM / 3.7-19 03/31/2006 Pages TRM / 3.7-20 through TRM / 3.7-22 08/02/1999 Pages TRM / 3.7-23 and TRM / 3.7-24 03/31/2006 Pages TRM / 3.7-25 through TRM / 3.7-27 08/02/1999 Page TRM / 3.7-28 08/09/2005 SUSQUEHANNA - UNIT 2 TRM / LOES-2 EFFECTIVE DATE 10/10/2006

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 28 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date Page TRM / 3.7-29 11/16/2001 Page TRM / 3.7-30 11/30/2005 Page TRM / 3.7-31 11/16/2001 Page TRM / 3.7-32 01/09/2004 Page TRM / 3.7-33 10/05/2002 Page TRM / 3.7-34 03/31/2006 Pages TRM / 3.7-35 and TRM / 3.7-36 02/01/1999 Pages 3.7-37 through 3.7-38 08/31/1998 Page TRM / 3.7-39 03/31/2006 Pages TRM / 3.7-40 and TRM / 3.7-40a 02/14/2005 Pages 3.7-41 and 3.7-42 08/31/1998 Pages TRM / 3.7-43 through TRM / 3.7-48 10/05/2006 Pages TRM / 3.7-48a and TRM / 3.7-48b 10/05/2006 Page TRM / 3.7-49 03/09/2001 Page TRM / 3.7-50 08/16/2006 Page TRM / 3.7-51 12/03/2004 Page TRM / 3.7-52 04/15/2003 Page TRM / 3.7-53 07/29/1999 3.8 ELECTRICAL POWER Page TRM / 3.8-1 04/02/2002 Pages TRM / 3.8-2 and TRM / 3.8-3 01/28/2005 Page TRM / 3.8-4 01/31/2005 Pages TRM / 3.8-5 and TRM / 3.8-6 04/02/2002 Pages TRM / 3.8-7 through TRM / 3.8-10 12/03/2004 Page TRM / 3.8-11 08/10/2004 Page TRM / 3.8-12 12/03/2004 Pages 3.8-13 and 3.8-14 08/31/1998 Page TRM / 3.8-15 01/28/2005 Pages TRM / 3.8-16 and TRM / 3.8-17 04/02/2002 Page 3.8-18 02/01/1999 Page TRM / 3.8-19 04/02/2002 Page TRM / 3.8-20 02/01/1999 Pages TRM / 3.8-21 through TRM / 3.8-23 06/06/1999 Pages 3.8-24 and 3.8-25 08/31/1998 3.9 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 08/31/1998 3.10 MISCELLANEOUS Page TRM / 3.10-1 03/31/2006 Pages 3.10-2 through 3.10-4 08/30/1998 Page TRM / 3.10-5 03/08/2003 Page TRM / 3.10-6 06/05/2002 Page TRM / 3.10-7 03/31/2006 Page TRM / 3.10-8 08/16/2006 TRM I LOES-3 EFFECTIVE DATE 10/10/2006 SUSQUEHANNA-UNIT2 SUSQUEHANNA - UNIT 2 TRM / LOES-3 EFFECTIVE DATE 10/1012006

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 28 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date 3.11 RADIOACTIVE EFFLUENTS Page TRM / 3.11-1 03/31/2006 Pages 3.11-2 through 3.11-3 08/31/1998 Page TRM / 3.11-4 03/31/2006 Page 3.11-5 08/31/1998 Page TRM / 3.11-6 03/31/2006 Pages 3.11-7 through 3.11-9 08/31/1998 Page TRM / 3.11-10 12/03/2004 Pages 3.11-11 and 3.11-12 08/31/1998 Page 3.11-13 09/01/1998 Page TRM / 3.11-14 12/03/1004 Pages 3.11-15 and 3.11-16 09/01/1998 Page TRM / 3.11-17 03/31/2006 Page 3.11-18 08/31/1998 Page TRM / 3.11-19 08/15/2005 Pages TRM / 3.11-20 and TRM / 3.11-21 03/31/2006 Page TRM / 3.11-22 04/02/2002 Page TRM / 3.11-23 03/31/2006 Page TRM / 3.11-24 05/13/2005 Page 3.11-25 09/01/1998 Pages TRM / 3.11-26-through TRM / 3.11-28 01/21/2004 Page TRM / 3.11-29 12/03/2004 Pages TRM 3.11-30 through TRM / 3.11-32 01/21/2004 Page TRM / 3.11-33 03/31/2006 Page 3.11-34 08/31/1998 Page TRM / 3.11-35 03/31/2006 Pages TRM / 3.11-36 through TRM / 3.11-39 11/30/2005 Pages 3.11-40 through 3.11-44 08/31/1998 Page TRM / 3.11-45 03/31/2006 Page 3.11-46 08/31/1998 Page TRM / 3.11-47 03/31/2006 3.12 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-3 02/05/1999 Page TRM / 3.12-4 09/30/2006 Page TRM / 3.12-5 02/05/1999 4.0 ADMINISTRATIVE CONTROLS Pages 4.0-1 through 4.0-8 08/31/1998 TRM /LOES-4 EFFECTIVE DATE 10/10/2006 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT 22 TRM / LOES-4 EFFECTIVE DATE 10/10/2006

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 28 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date B 3.0 APPLICABILITY BASES Pages B 3.0-1 through B 3.0-10 08/31/1998 Pages TRM / B 3.0-11 and TRM / B 3.0-12 03/15/2002 Pages TRM / B 3.0-13 and TRM / B 3.0-14 11/30/2005

- Page TRM / B 3.0-15 03/15/2002 B 3.1 REACTIVITY CONTROL SYSTEMS BASES Pages TRM / B 3.1-1 through TRM / B 3.1-3 07/13/1999 Page B 3.1-4 08/31/1998 Pages TRM / B 3.1-5 through TRM / B 3.1-7 11/15/2005 Page TRM / B 3.1-8 02/18/1999 B 3.2 CORE OPERATING LIMITS BASES Page B 3.2-1 08/31/1998 B 3.3 INSTRUMENTATION BASES Page TRM / B 3.3-1 04/07/2000 Page B 3.3-2 08/31/1998 Pages TRM / B 3.3-3 and TRM / B 3.3-3A 01/31/2005 Pages TRM / B 3.3-4 through TRM / B 3.3-7 05/30/2006 Pages TRM / B 3.3-8 and TRM / B 3.3-9 03/30/2001 Page B 3.3-10 08/31/1998 Pages TRM / B 3.3-11 and TRM / B 3.3-12 09/13/2005 Page TRM / B 3.3-13 12/03/2004 Page TRM / B 3.3-14 06/25/2002 Page TRM / B 3.3-14a 06/14/2002 Page TRM / B 3.3-14b 06/14/2002 Page TRM / B 3.3-15 10/22/2003 Page TRM / B 3.3-16 10/22/2003 Page TRM / B 3.3-17 10/22/2003 Pages TRM / B 3.3-18 and TRM / B 3.3-19 11/15/2004 Pages TRM / B 3.3-19a through TRM / B 3.3.19e 11/15/2004 Pages TRM / B 3.3-20 and TRM / B 3.3-21 05/16/2003 Page TRM / B3.3-22 10/22/2003 Page TRM / B3.3-23 05/16/2003 B 3.4 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 through B 3.4-4 08/31/1998 Page TRM / B 3.4-5 10/15/1999 Page B 3.4-6 08/31/1998 B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 through B 3.5-5 08/31/1998 B 3.6 CONTAINMENT BASES Page TRM / B 3.6-1 07/26/2001 Page TRM / B 3.6-2 02/01/1999 Page B 3.6-3 08/31/1998 TRM I LOES-5 EFFECTIVE DATE 10/10/2006 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT 22 TRM / LOES-5 EFFECTIVE DATE 10/10/2006

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 28 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date Page TRM / B 3.6-4 09/23/1999 Page TRM / B 3.6-5 01/07/2002 Page TRM / B 3.6-6 12/03/2004 Pages TRM / B 3.6-7 through TRM / B 3.6-11 12/31/2002 B 3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 08/31/1998 Page TRM / B 3.7-3 08/02/1999 Page TRM / B 3.7-4 03/31/2006 Page TRM / B 3.7-5 08/02/1999 Pages TRM / B 3.7-6 and TRM / B 3.7-6a 03/31/2006 Pages TRM / B 3.7-7 and TRM / B 3.7-7a 08/02/1999 Page TRM / B 3.7-8 08/02/1999 Page TRM / B 3.7-9 03/31/2006 Page TRM / B 3.7-10 08/02/1999 Pages TRM / B 3.7-1 Oa through TRM / B 3.7-11 a 03/31/2006 Pages TRM / B 3.7-12 through TRM / B 3.7-14 08/02/1999 Pages TRM / B 3.7-14a and TRM / B 3.7-14b 01/09/2004 Pages TRM / B 3.7-15 and TRM / B 3.7-16 02/01/1999 Pages B 3.7-17 through B 3.7-20 08/31/1998 Pages TRM / B 3.7-21 and TRM / B3.7-21a 02/14/2005 Pages TRM / B 3.7-22 and TRM / B 3.7-23 04/07/2000 Pages TRM / B 3.7-24 through TRM / B 3.7-30 10/05/2006 Pages TRM / B 3.7-30a and TRM / B3.7-30b 10/05/2006 Page TRM / B 3.7-31 12/03/2004 Page TRM / B 3.7-32 03/09/2001 Page TRM / B 3.7-33 04/15/2003 Page TRM / B 3.7-34 12/03/2004 Page TRM / B 3.7-35 07/05/2000 B 3.8 ELECTRICAL POWER BASES Page TRM / B 3.8-1 04/02/2002 Pages TRM / B 3.8-2 and TRM / B 3.8-2a 01/28/2005 Page TRM / B 3.8-3 04/02/2002 Page TRM / B 3.8-3a 04/02/2002 Page TRM / B 3.8-4 04/02/2002 Page TRM / B 3.8-4a 08/10/2004 Page TRM / B 3.8-5 08/31/1998 Pages TRM / B 3.8-6 through TRM / B 3.8-16 04/02/2002 Page TRM / B 3.8-17 01/28/2005 SUSQUEHANNA - UNIT 2 TRM / LOES-6 EFFECTIVE DATE 10/10/2006

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 28 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date B.3.9 REFUELING OPERATIONS BASES Pages B 3.9-1 and B 3.9-2 08/31/1998 Pages B 3.9-3 through B 3.9-7 10/23/1998 B 3.10 MISCELLANEOUS BASES Pages B 3.10-1 through B 3.10-2 08/31/1998 Page TRM / B 3.10-3 03/08/2003 Pages TRM / B 3.10-4 and TRM / B 3.10-5 08/23/1999 Pages TRM / B 3.10-6 and TRM / 3.10-7 04/17/2002 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 08/31/1998 Page TRM / B 3.11-10 02/01/1999 Pages TRM/B 3.11-11 and TRM/B 3.11-1 la 04/07/2000 Pages TRM/B 3.11-12 and TRM/B 3.11-13 02/01/1999 Page TRM / B 3.11-14 12/03/2004 Page TRM / B 3.11-15 02/01/1999 Pages B 3.11-16 through B 3.11-19 08/31/1998 Page TRM / B 3.11-20 04/02/2002 Page TRM / B 3.11-20a 04/02/2002 Pages TRM / B 3.11-21 through TRM / B 3.11-23a 05/13/2005 Pages TRM / B 3.11-24 and TRM / B 3.11-25 01/21/2004 Pages B 3.11-26 through B 3.11-27 08/31/1998 Pages TRM / B 3.11-28 and TRM / B 3.11-29 11/30/2005 Page TRM / B 3.11-30 12/03/2004 Pages B 3.11-31 through B 3.11-35 08/31/1998 Page TRM / B 3.11-36 02/12/1999 B.3.12 LOADS CONTROL PROGRAM BASES Pages TRM / B 3.12-1 through TRM / B 3.12-3 02/05/1999 TRM2 text LOES.doc 10/06/2006 SUSQUEHANNA - UNIT 2 TRM / LOES-7 EFFECTIVE DATE 10/10/2006

Snubbers PPL Rev..5_ 3.7.8 3.7 Plant Systems 3.7.8 Snubbers TRO 3.7.8 All snubbers shall be OPERABLE APPLICABILITY: When associated supported system(s) are required to be OPERABLE ACTIONS

---

NOTE -- -------- - ------------------

1. Separate condition entry is allowed for each snubber.

2. The provisions of TRO 3.0.4 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more snubbers A.1.1 Determine the location and the Immediately associated with only one design function of the subsystem of a multiple inoperable snubber(s) subsystem supported (mitigation of seismic or system or associated with a seismic and non-seismic single subsystem supported loads).

system confirmed to be inoperable AND A.1.2 Determine that an OPERABLE Immediately subsystem(s) involving equipment not associated With the inoperable snubber(s) exists to provide makeup and core cooling needed to mitigate a LOOP event.

AND A. 1.3 Determine that the subsystem Immediately supported by the inoperable snubber would remain capable of performing its required safety or support functions for postulated design loads other than seismic loads.

AND (continued)

SUSQUEHANNA - UNIT 2 TRM / 3.7-43 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev..S 3.7.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

...----------. NOTE--------

REQUIRED ACTIONS A.1.1 through A.1.3 must be completed prior to completing REQUIRED ACTION A.1.4.

A.1.4 Enter LCO 3.0.8 Immediately AND A.1.5 Replace or restore the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable snubber(s) to OPERABLE status B. One or more snubbers B.1.1 Determine the location and Immediately associated with more than the design function of the one subsystem of a multiple inoperable snubber(s) subsystem supported (mitigation of seismic or system confirmed seismic and non-seismic inoperable, loads).

AND B. 1.2 Determine that an Immediately OPERABLE subsystem(s),

involving equipment not associated with the inoperable snubber(s) exists to provide makeup and core cooling needed to mitigate a LOOP event.

AND (continued)

SUSQUEHANNA - UNIT 2 TRM / 3.7-44 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev-5 3.7.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.1.3 Determine that the subsystem Immediately supported by the inoperable snubber would remain capable of performing its required safety or support functions for postulated design loads other than seismic loads.

AND

-- - -- NOTE -....... .

REQUIRED ACTIONS B.1.1 through B.1.3 must be completed prior to completing REQUIRED ACTION B.1.4.

B.1.4 Enter LCO 3.0.8 Immediately AND B.1.5 Replace or restore the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> inoperable snubber(s) to OPERABLE status C. Required Action and C.1 Declare the supported system Immediately associated Completion inoperable Time of Condition A or B not met (continued)

SUSQUEHANNA - UNIT 2 TRM / 3.7-45 EFFECTIVE DATE 10/05/2006 0

Snubbers PPL Rev.5_ 3.7.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Any snubber selected for D. ---------- NOTE ---------- Within the current functional testing either fails This action shall be inspection interval.

to activate or fails to move independent of the Testing due to manufacturer or Requirement for snubbers not design deficiency. meeting the functional test acceptance criteria per TRS 3.7.8.2 All snubbers of the same design subject to the same defect shall be functionally tested E. The snubber service life will E.1 Reevaluate the snubber Prior to exceeding be exceeded prior to the service life snubber service life next scheduled snubber service life review OR E.2 Replace or recondition the Prior to exceeding snubber so as to extend its snubber service life service life beyond the date of the next scheduled service life review TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.7.8.1 Demonstrate each snubber OPERABLE by As directed by performance of visual inspection Table 3.7.8-1 TRS 3.7.8.2 Perform functional test of a representative 24 months sampling of all snubbers per Table 3.7.8-3.

(continued)

SUSQUEHANNA - UNIT 2 TRM / 3.7-46 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev.5 3.7.8 TECHNICAL REQUIREMENT SURVEILLANCE (continued)

SURVEILLANCE FREQUENCY TRS 3.7.8.3 ----------- ------ NOTE ----------- 24 months Documentation of critical parts replaced so that the maximum service life is not exceeded shall be retained as required by FSAR 17.2.17.

Monitor the installation and maintenance records for each snubber to ensure that the service life has not been exceeded and will not be exceeded prior to the next snubber surveillance inspection.

TRS 3.7.8.4 --- T-------E-------------

.------- At the time of the Snubbers tested per this surveillance are in-addition next functional to snubbers selected for the sample plan per test.

TRS 3.7.8.2.

Test snubbers in locations of snubbers that failed the functional test during the previous test period.

TRS 3.7.8.5 An inspection shall be performed of all snubbers As necessary attached to sections of systems that have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems within.

SUSQUEHANNA - UNIT 2 TRM / 3.7-47 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev..5- 3.7.8 Table 3.7.8-1 SNUBBER VISUAL INSPECTION INTERVAL Number Of Unacceptable Visually Inspected Inspection Interval Snubbers in Previous Inspection Interval

1. Equal to or less than the applicable May be twice the previous interval but not number in Table 3.7.8-2 Column A greater than 48 months

2. Equal to or less than the applicable Same as the previous interval number in Table 3.7.8-2 Column B but greater than the applicable number in Column A

3. Equal to or greater than the applicable Two-thirds of the previous interval number in Table 3.7.8-2 Column C

4. Less than the applicable number in Table Equal to the previous interval (1.41), reduced 3.7.8-2 Column C but greater than the proportionally by a factor that is one-third of applicable number in Column B the ratio of the difference between the number of unacceptable snubbers found during the previous interval (N.1) and the number in Column B (NB) to the difference in the numbers in Columns C (Nc) and B, or:

NBI SUSQUEHANNA - UNIT 2 TRM / 3.7-48 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev. .5- 3.7.8 TABLE 3.7.8-2 NUMBER OF UNACCEPTABLE SNUBBERS PREVIOUS SNUBBER VISUAL INSPECTION INTERVAL Population Column A Column B Column C 1 0 0 1 80 0 0 2 100 0 1 4 150 0 3 8 200 2 5 13 300 5 12 25 400 8 18 36 500 12 24 48 750 20 40 78 1,000 or greater 29 56 109

-- ------------- -------------- NOTES----

1. -Interpolation between population or category sizes and the number of unacceptable snubbers is permissible. Use next lower integer for the value of-the limit for Columns A, B or C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.

2. The provisions of TRS 3.0.2 are applicable for all inspection intervals up to and including 48 months.

SUSQUEHANNA - UNIT 2 TRM / 3.7-48a EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev..5_ 3.7.8 TABLE 3.7.8-3 REPRESENTATIVE SAMPLING SAMPLE FAILED SNUBBERS REPRESENTATIVE SAMPLING (a)

1. Initial 0 10%

2. Re-Test >0 in initial sample Additional 5%(b) for each failure

3. Continued Testing >0 In Re-test or Continued Additional 5% for each failure to Testing Samples 100%(b)

(a) Percentage of the total population of each type of snubber (b) An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure and to determine the OPERABILITY of other snubbers, irrespective of type, which may be subject to the same failure mode. The results of this evaluation shall be used, if applicable, in selecting snubbers to be tested. If additional sampling is required due to failure of only one type of snubber, additional samples should be limited to the type of snubber, which has failed the functional testing.

SUSQUEHANNA - UNIT 2 TRM / 3.7-48b EFFECTIVE DATE 10/05/2006

Core Operating Limits Report (COLR)

PPL Rev. 5 3.2.1 3.2 Core Operating Limits Report (COLR) 3.2.1 Core Operating Limits Report (COLR)

TRO 3.2.1 The Core Operating Limits specified in the attached COLR shall be met.

APPLICABILITY: Specified in the referenced Technical Specifications.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core Operating Limits not A.1 Perform action(s) Specified in referenced met. described in referenced Technical Technical Specification. Specifications.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY

........................-- ------------------NOTE --------------------- --------. N/A No associated Surveillances. Surveillances are implemented in the applibable Technical Specifications.

SUSQUEHANNA - UNIT 2 3.2-1 EFFECTIVE DATE 8/31/1998

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 1 of 38 Susquehanna SES Unit 2 Cycle 13A CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering October 2006 pp, SUSQUEHANNA UNIT 2 TRM/3.2- 2 EFFECTIVE DATE 10/05/2006

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 2 of 38 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev. Affected No. Sections DescriptionlPurpose of Revision 0 ALL Issuance of this COLR is in support of Unit 2 Cycle 13A operation.

FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 2 TRM/3.2-3 EFFECTIVE DATE 10/05/2006

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 3 of 38 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 13A CORE OPERATING LIMITS REPORT Table of Contents 1.0 INTRO DUCTIO N..................................................................................................... 4 2.0 D EFIN IT IO NS ..................... .................................................................................... 5 3.0 SHUTDOWN MARGIN ............................................................................................ 6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ........... 7

. 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) ..................................................... 9 6.0 LINEAR HEAT GENERATION RATE (LHGR) ............................ 21 7.0 AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS ............ 24 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION ..................................... 27 9.0 POWER / FLOW MAP ........................................................................................... 34 10.0 O PRM SETPO INTS ............................................................................................... 36 11.0 R EFER EN C ES ............................................................................................................ 37 SUSQUEHANNA UNIT 2 TRM/3.2-4 EFFECTIVE DATE 10/05/2006

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 4 of 38

1.0 INTRODUCTION

This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 13A is prepared in accordance with the requirements of Susquehanna Unit 2, Technical Specification 5.6.5. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits, APRM setpoints, and OPRM setpoints presented herein Were developed using NRC-approved methods and are established such that all applicable limits of the plant safety analysis are met.

SUSQUEHANNA UNIT 2 TRM/3.2-5 EFFECTIVE DATE 10/05/2006

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 5 of 38 2.0 DEFINITIONS Terms used in this COLR but not defined in Section 1.0 of the Technical Specifications or Section 1.1 of the Technical Requirements Manual are provided below.

2.1 The AVERAGE BUNDLE EXPOSURE shall be equal to the total energy p)roduced by the bundle divided by the total initial weight of uranium in the fuel bundle.

2.2 The AVERAGE PLANAR EXPOSURE at a specified height shall be equal to the total energy produced per unit length at the specified height divided by the total initial weight of uranium per unit length at that height.

2.3 The FRACTION OF LIMITING POWER DENSITY (FLPD) shall be the LHGR existing at a given height divided by the applicable LHGR for APRM Setpoint Limit for that bundle type.

2.4 The FRACTION OF RATED THERMAL POWER (FRTP) shall be the measured THERMAL POWER divided by the RATED THERMAL POWER.

2.5 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR limit for the applicable fuel bundle type.

2.6 MFLCPR is the ratio of the applicable MCPR operating limit for the applicable fuel bundle type divided by the MCPR calculated by the core monitoring system for each fuel bundle.

2.7 MAPRAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLGHR limit for the applicable fuel bundle type.

2.8 FDLRC is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR for APRM Setpoint Limit for the applicable fuel bundle type.

2.9 OPRM is the Oscillation Power Range Monitor. The Oscillation Power Range Monitor (OPRM) will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR safety limit is not violated.

2.10 Np is the OPRM setpoint for the number of consecutive confirmations of oscillation half-cycles that will be considered evidence of a stability related power oscillation.

2.11 Sp is the OPRM trip setpoint for the peak to average OPRM signal.

2.12 Fp is the core flow, in Mlbm / hr, below which the OPRM RPS trip is activated.

SUSQUEHANNA UNIT 2 TRM/3.2-6 EFFECTIVE DATE 10/05/2006

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 6 of 38 3.0 SHUTDOWN MARGIN 3.1 Technical Specification Reference Technical Specification 3.1.1 3.2 Description The SHUTDOWN MARGIN shall be equal to or greater than:

a) 0.38% Ak/k with the highest worth rod analytically determined OR b) 0.28% Ak/k with the highest worth rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and poison burnup, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, "R". The adder, "R", is the difference between the calculated value of maximum core reactivity (that is, minimum SDM) during the operating cycle and the calculated BOC core reactivity. If the value of "R" is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOC measured -value is required.

The SHUTDOWN MARGIN limits provided in 3.2a and 3.2b are applicable in MODES 1, 2, 3, 4, and 5. This includes core shuffling.

SUSQUEHANNA UNIT 2 TRM/3.2-7 EFFECTIVE DATE 10/05/2006

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 7 of 38 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 Technical Specification Reference Technical Specification 3.2.1 4.2 -Description The APLHGRs for ATRIUMTM-10 fuel shall not exceed the limit shown in Figure 4.2-1.

The APLHGR limits in Figure 4.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable in Two Loop operation.

The APLHGR limits for Single Loop operation are provided in Section 8.0.

SUSQUEHANNA UNIT 2 TRM/3.2-8 EFFECTIVE DATE 10/05/2006

0 c/A SSES UNIT 2 CYCLE 13A V) 16 . . . . . . . a a la. a a.a

. a........ .

c:

-H REFERENCE T.S. 3.:2.1 14

. ... .... a.. a. a a a a... a .a ... a.. . .. . . . . . . .

• a a a aa a.a . . . . . .

o~

a a 0.0,12.5,.... 15000,12.5- ---- a

~12 -

.. i=i... i**I. I. I............I . iI.....

...... I. ..

. .. Iii .i o- a" a a a a a a a a a a a . a a a aa a

,' .. ',.. .2 ' .SIR

~. . .3F R. NE...T. ". , :1, 0.2 10 0) a a a' a 00125a a a a.. a..a..,15a0aa0012a5a . . .,

0) . . . . . . . . . . . . . . a. a..., . . . . ..... a. ,

a a a

> *I aIaIaIaIaIaIa a* a a a. a a a

a ai a a a a a o a i a a a a l i , a a a ai i i

, , a , . a a a a a a a a l a , ,

8-

-nl

--  : :::  ::: :::  ::::  :::  :::  ::: :67000,6.9 0 CD r

.. . ... .a.a....a a "

.. a.a.a.

CD)

CD CD 4-40000 50000 60000 70000 CD 0 10000 20000 30000 0,$ Average Planar Exposure (MWD/MTU) cc <

CD' Z o0 07 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS 0

AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION 6k OD)

ATRIUMTM-10 FUEL FIGURE 4.2-1

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 9 of 38 5.0 MINIMUM CRITICAL POWER RATIO (MCPRI 5.1 Technical Specification Reference Technical Specification 3.2.2, 3.7.6, and 3.3.4.1 5.2 Description The MCPR limit is specified as a function of core power, core flow, average scram insertion time per Section 5.3 and plant equipment operability status. The MCPR limits for all fuel types (ATRIUMTM-1 0) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.

a) EOC-RPT and Main Turbine Bypass Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOC b) Main Turbine Bypass Inoperable I EOC-RPT Operable Figure 5.2-3: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-4: Power-Dependent MCPR value determined from BOC to EOC c) EOC-RPT Inoperable I Main Turbine Bypass Operable Figure 5.2-5: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOC to EOC The MCPR limits in Figures 5.2-1 through 5.2-6 are valid for Two Loop operation.

The MCPR limits for Single Loop operation are provided in Section 8.0.

SUSOUEHANNA UNIT 2 TRM/3.2- 10 EFFECTIVE DATE 10/05/2006

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 10 of 38 5.3 Average Scram Time Fraction If the average measured scram times are greater than the Realistic Scram times listed in Table 5.3-1 then the MCPR operating limits corresponding to the Maximum Allowable Average Scram Insertion Time must be implemented.

Determining MCPR operating limits based on interpolation between scram insertion times is not permitted. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.

SUSQUEHANNA UNIT 2 TRM/3.2-11 EFFECTIVE DATE 10/05/2006

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 11 of 38 EOC-RPT and Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-12 EFFECTIVE DATE 10/05/2006

SSES UNIT 2 cYCLE 13A

,CD 2.1 cz m

2.0 1.

1.9 1.8 4-E1.7 r-"

N')

1.6 CD

.0 01 o.O1.5 0-1.4 08,1.36) m m

1.3

-n m

CD 1.2 CD CD 1.1 70 80 90 100 110 30 40 50 60

-uDo Total Core Flow (MLB/HR) cc < z (D '

L0 6

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 0) 0 EOC-RPT AND MAIN TURBINE BYPASS OPERABLE 0) 0 0*

TWO LOOP OPERATION (BOC TO EOC) co FIGURE 5.2-1

VI) SSES UNIT 2 CYCLE 13A V,) 3.0 mr 2.9 2.8 2.7 2.6 2.5 9)4 24-

~2.3 Co ~2.2 N)

CD CL2.1 a2.0 1.9 1.8 1.7 m 1.6 1.5 C-)

1.4 (100,1.36) 1.3 60 70 80 90 10C 20 30 40 50 00 Core Power (% RATED)

CD Z

._. 0 -

MCPR OPERATING LIMIT VERSUS CORE POWER o00 EOC-RPT AND MAIN TURBINE BYPASS OPERABLE CO 0 TWO LOOP OPERATION (BOC TO EOC) 00 0)

FIGURE 5.2-2

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 14 of 38 Main Turbine Bypass Inoperable I EOC-RPT Operable SUSQUEHANNA UNIT 2 TRM/3.2-15 EFFECTIVE DATE 10/05/2006

(I)

SSES UNIT 2 CYCLE 13A 2.3 l I

EGEND

_-H 2.2 URVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.1 4. 4 URVE B: REALISTIC AVERAGE SCRAM INSERTION TIME N) 2.0 -I E 1.9 -(30,1.87)-

4. 1 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 USED IN DETERMINING MFLCPR K

V

-K Im..

I c')

d 1.8 I

0N) (D 0 __ _~~(U

_[_._Doi_

cnT 1.7

• -ýý A *ý 1.6 B (100,1.54) 4-(80,1.68)

(108,1.54) m m 1.5 C-,)

1.4

REFERENCE:

T.S. 3.7.6 and 3.2.2 m

CD 1.3 I,

60 70 80 90 100 110 30 40 50 CD Total Core Flow (MLB/HR) (D Z MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE / EOC-RPT OPERABLE 0 TWO LOOP OPERATION (BOC TO EOC) o~ 0)

FIGURE 5.2-3

0 SSES UNIT 2 CYCLE 13A C,) 3.0 (25,2.87)

LEGEND 2.9 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM N) 2.8 INSERTION TIME 2.7 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.6 7I (30,2.57)

I I I I I I

-H 2.5 2.4 2.3

_I ill I- II I SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 I I I F

USED IN DETERMINING MFLCPR -0 C~) =2.2 I--

N)

CL 2.1 (D 0 01 2.0 1.9 1.8 m

1.7 (40,1 .73) A-,

m 1.6 (100,1.54)

(80,1.54) 1.5 --

REFERENCE:

T.S.3.7.6 and 3.2.2 C:)

CD 1.4 1.3 60 70 80 90 100 20 30 40 50 I-01)

Core Power (% RATED) (0 <

z"11 CD*

0) 6 MCPR OPERATING LIMIT VERSUS CORE POWER 0 h0 0)

MAIN TURBINE BYPASS INOPERABLE / EOC-RPT OPERABLE 0) co)

TWO LOOP OPERATION (BOC to EOC) co 0)

FIGURE 5.2-4

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 17 of 38 EOC-RPT Inoperable I Main Turbine Bypass Operable SUSOUEHANNA UNIT 2 TRM/3.2-18 EFFECTIVE DATE 10/05/2006

0 SSES UNIT 2 CYCLE 13A c/) 2.3 *1 I P1D LEGEND 2.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM

-H 2.1 I _ _

INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME

-- t .

o) 2.0 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES I______

ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR ____

K 5U 1.8 0U 0

0- 1.7 (3 , .)(30,1.6)____________ ____________________ ____________________ ___________________ ___________________

1.6 P1 n

-T I -I I 4 1.5 I (70,1.44)

(108,1.44)

B L- -I

IREFERENCE:

T.S. 3.3.4.1 and 3.2.21 1~____

i I

i

____________I 1.4 CD)

N-)

C1 CH P7) 1.3 30 40

____________[ 50 60 70 80 90

.~

100 110

-0 3< "

Total Core Flow (MLB/HR) 0(D MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 00 0 0

EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE 0o 0o 4, 6 0

TWO LOOP OPERATION (BOC TO EOC) 00 0)

FIGURE 5.2-5

SSES UNIT 2 CYCLE 13A 3.0 1 1 1 I I I I Q

m 2.9 -

(25,2.81)

V) 4 4-4  %'~JI~ ~ A: MAXIMUM ALLOWABLE AVERAGE SCRAM 2.8 4.

INSERTION TIME 2.7 1~ 4.

B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.6 \-(30,2.57).

I F-4 2.5 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES N)

E 2.4 2.4 I_!211tI ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I j2.3 I

USED IN DETERMINING MFLCPR [ -0

~2.2 CD N) 0)

(Z, 51

~2.0 2 1.9 1.8 m

n1 1.7

-n *A m

1.6 1.5 --

REFERENCE:

T.S. 3.3.4.1 and 3.2.2_--"

CD (100,1.44) 1.4 (80,1A45) m CD 1.3 50 60 70 80 90 100 CD 20 30 40 N) Core Power (% RATED) -A a'p CD (0 m~ 0 -

MCPR OPERATING LIMIT VERSUS CORE POWER (0 EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE 0)

TWO LOOP OPERATION (BOC to EOC) .0, FIGURE 5.2-6

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 20 of 38 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)

Position 45 0.470 0.520 39 0.630 0.860 25 1.500 1.910 5 2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 2 TRM/3.2- 21 EFFECTIVE DATE 10/05/2006

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 21 of 38

. 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3 and 3.7.6 6.2 Description The LHGR limits are specified below as a function of Main Turbine Bypass operability for each fuel type as follows:

Main Turbine Bypass Operable The LHGR for ATRIUMTM-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1.

Main Turbine Bypass- Inoperable The LHGR for ATRIUMTM-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-2.

The LHGR limits in Figures 6.2-1 and 6.2-2 are valid for Two Loop and Single Loop operation.

SUSQUEHANNA UNIT 2 TRM/3.2-22 EFFECTIVE DATE 10/05/2006

c/ 1SSES UNIT 2 CYCLE 13A

(./3 16 - _ _ _

£2

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES T-:

........ -I..................... ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

. 15000,13.4'

REFERENCE:

T.S. 3.2.3 14 0.0,13.4 .. . . . . ..

U .4 . . .... . . ...... USED IN DETERMINING FDLRX El X " 81- . . . . . . . . . . . . . ..

1 i 1 1 (D Ii S 1 li I C~) a) i i i "I , , i i

• IiIii I I

• I I S

• S I ii i i i i i

, S I S I I

• Sl I S I I , I I I I 1 11i

~

ro6 1 . . . . . . ....

a) m o -n

,N CA 0

_1 40000 50000 60000 70000 10000 20000 30000' Ul0 CD ~~Average Planar Exposure (MWD/MTU)SDD CD' z 6

LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE 0 9 MAIN TURBINE BYPASS OPERABLE O 0)

ATRI 0 FUEL FIGURE 6.2-1

0 0 SSES UNIT 2 CYCLE 13A

.cz . . . . . . . . . . .

Cr)

SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS m4

• 5:VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2

....... VALVES

. .76. OR 3.7.6..2 .

~12 .,

E

. 10 001 , ° 1. 0 ................................

014.. Is3a R F R NE....... d 7sI -o I-I S S I S a I S S I S S I S I S S S I S I I S

. .

• SI SI Cl

. . . I .

L ... ...

.4 CD) 000,7.1

-67 CD) 40000 50000 60'000 70000 0 100 00 20000 30000 Average Planar Exposure (MWD/MTU) (0 < So CD

• No c -nl EXPOSURE co

~O 1o 6 LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR Co 0 MAIN TURBINE BYPASS INOPERABLE 0 0 ATRIUMTM-10 FUEL co 0)

FIGURE 6.2-2

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 24 of 38 7.0 AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS 7.1 Technical Specification Reference Technical Specification 3.2.4 and 3.3.1.1 7.2 Description The APRM flow biased simulated thermal power-upscale scram trip setpoint (S) and flow biased neutron flux-upscale control rod block trip setpoint (SRB) shall be established as specified in Table 7.2-1 and Table 7.2-2, including any adjustments per Technical Specification LCO 3.2.4.

Technical Specification LCO 3.2.4 provides an option to adjust the APRM setpoints when MFLPD is greater than FRACTION OF RATED THERMAL POWER (FRTP). The adjustment applies to both the APRM flow biased simulated thermal power-upscale scram trip setpoint and flow biased neutron flux-upscale control rod block trip setpoint for Two Loop and Single Loop operation. The APRM setpoints for Specification 3.2:4 are established in Tables 7.2-1 and 7.2-2.

SUSQUEHANNA UNIT 2 TRMI3.2- 25 EFFECTIVE DATE 10/05/2006

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 25 of 38 Table 7.2-1 APRM Setpoint for Two Loop Operation I

i Trip Setpoint Allowable Value s *_(0.58W + 59%) T S*< (0.58W + 62%) T1 ISRB!!* (0.58W + 50%) T SRB < (0.58W + 53%) T Table 7.2-2 APRM Setpoint for Single Loop Operation s*

SRB < (0.58W+Trip (0.58W 54%)

+ Setpoint 45%)TT S*

SRB (0.58W Allowable

< (0.58W+ 57%)

+ 48%)T1Value T

where: S and SRB are in percent of RATED THERMAL POWER W = Loop recirculation flow as a percentage of the loop recirculation flow which produces a core flow of 100 million lbs/hr T = Lowest value of the ratio of FRTP_ divided by the MFLPD.2 The FLPD is the actual LHGR divided by the applicable LHGR limit for APRM Setpoints. The LHGR limit for APRM setpoints for ATRIUMTM-10 fuel shall be taken from Figure 7.2-1.

The LHGR for APRM setpoint limits in Figure 7.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable for both Two and Single Loop operation.

For calculated T-values greater than 1.0, a ratio of 1.0 is used in the above equations.

1 APRM flow biased simulated thermal power-upscale scram allowable value in this table is equal to the value established in Technical Specification 3.3.1.1.

2 For the calculation of T, the value of MFLPD shall be the maximum value of FDLRC.

SUSQUEHANNA UNIT 2 TRM/3.2- 26 EFFECTIVE DATE 10/05/2006

6SSES UNIT 2 CYCLE 13A V) rri 6. o i ,ti

.. . .... .. ...f ft I-. '4 .. . .... ... u . . . .

• z , I .:.. . :..u .*

• REFEREIJCE: T.S. 3.24: . .*u. . . ..

jUSED IN DETERMINING FDLRC 1 . . . ..

.t-rI l I I I ii 10c f ,t t f ,ft, t t , ., , t ,t f t f t f ft , , . ,t f .t n

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. . . . . . . . . .. . . . . . . . . . . .f.. . . . . . . . . .

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v.. .. ,

CD 4-30000 40000 50000 60000 70000 cn0 10000 20000 0C CD

~Average-Planar Exposure (MWDIMTU) 6)

LINEAR HEAT GENERATION RATE LIMIT FOR APRM SETPOINTS VERSUS AVERAGE PLANAR EXPOSURE 0 9)

ATRIUT -10 FUEL UMTM 0 FIGURE 7.2-10 )

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 27 of 38

. 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 Technical Specification Reference Technical Specification 3.2.1, 3.2.2, 3.2.3, 3.2.4, 3.3.4.1, 3.4.1, and 3.7.6 8.2 Description APLHGR The APLHGR limit for ATRIUMTM-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1.

The APLHGR limits in Figure 8.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable in Single Loop operation.

Minimum Critical Power Ratio Limit The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limit for all fuel types (ATRIUMTm-10) shall be the greater of:

a) Flow-Dependent-MCPR value determined from Figure 8.2-2 OR b) The Power-Dependent MCPR value determined from one of the following figures, as appropriate:

Figure 8.2-3: EOC-RPT and Main Turbine Bypass Operable from BOC to EOC Figure 8.2-4 : Main Turbine Bypass Inoperable / EOC-RPT Operable from BOC to EOC Figure 8.2-5: EOC-RPT Inoperable I Main Turbine Bypass Operable from BOC to EOC The MCPR limits in Figures 8.2-2 through 8.2-5 are valid only for Single Loop operation.

Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0.

SUSQUEHANNA UNIT 2 TRM/3.2-28 EFFECTIVE DATE 10/05/2006

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 28 of 38 Average Power Range Monitor (APRM) Gain And Setpoints APRM setpoints and the LHGR limit for APRM setpoints for Single Loop operation are defined in Section 7.0.

SUSOUEHANNA UNIT 2 TRM/3.2-29 EFFECTIVE DATE 10/05/2006

(I) SSES UNIT 2 CYCLE 13A 16 m

a a I i T- a a

a a a a * . a a a a aao a

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. . . . . . a.. .. i o al l l i , , a

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40000 50000 60000 70000 0 10000 20000 30000' 70 m<-

Average Planar Exposure (MWD/MTU) W(D r-Co, 0-VERSUS AVERAGE PLANAR EXPOSURE 6 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT to SINGLE LOOP OPERATION Cl) o~ a0 ATRIUMTM-10 FUEL FIGURE 8.2-1

0 SSES UNIT 2 CYCLE 13A

.CD 2.8 m EGEND 2.7 URVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 771 INSERTION TIME CIURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.6 M) 2.5 USED IN DETERMINING MFLCPR

-u 2.4

a. (D 0 (30,2.33) I I 51 B3 4. 4 4. (108,2.33)

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L2.3 m 2.2 n

m f-n m

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REFERENCE:

T.S. 3.4.1 and 3.2.2 m __

-- _ _ _ _ _ ~I _

2.0 80 90 100 110 30 40 50 60 70 CD

-u (D 01 CDJ m Total Core Flow (MLB/HR) 0 N) 0+1 6n-MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW co 0

SINGLE LOOP OPERATION (BOC to EOC) 0 C0 0 FIGURE 8.2-2 0)

0 V1)

SSES UNIT 2 CYCLE 13A 3.5 I.I III mC LEGEND 3.4 (25,3.27) CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM rH 3.3 Al INSERTION TIME 3.2 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.1

• ~ ~(30,2.99)IIII

(,9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 3.0 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 E 2.9 USED IN.DETERMINING MFLCPR oc 2.8 -0

\- 2.7 (D

0 01 M 2.6 2.5 2.4 (A B. (100,2.33) 2.3 (36.6,2.33) m m 2.2 m 2.1 CD)

"-J

REFERENCE:

T.S. 3,4.1 and 3.2.2j-2.0 c:) 1.9 60 70 80 90 100 20 30 40 50 -0 m -0 CD Core Power (% RATED) CDIr

01) (D 071 MCPR OPERATING LIMIT VERSUS CORE POWER 2, 0 0)

EOC-RPT AND MAIN TURBINE BYPASS OPERABLE 0o 0 SINGLE LOOP OPERATION (BOC to EOC) co 0 0)

FIGURE 8.2-3

SSES UNIT 2 CYCLE 13A 3.5 m

3.4 3.3 3.2 3.1 3.0 E 2.9

--A o 2.8 "13

-u r'-

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ir 2.6 O.

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• 2.5 2.4 (100,2.33) m 2.3 m 2.2 m 2.1 2.0 CD) m 1.9 60 70 80 90 100 20 30 40 50 Core Power (% RATED) 0 Dr cm <

MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE co0 SINGLE LOOP OPERATION (BOC to EOC) 0o 0)

FIGURE 8.2-4

0 V) SSES UNIT 2 CYCLE 13A 3.5 I I 3.4 ¶ t I-IL.~'Jr~P4u V~)

3.3 .(25,3.27) ,: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME  !

3.2 3.1 zizzi (30,2.99) r ii 3: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0-

-1 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 K

p2.9

-Hi i r

USED IN DETERMINING MFLCPR I I-CL (D

0. 01

~2.5 2.4 -A B (100,2.33) 2.3 (36.6,2.33) 2.2 Fn 2.1 CD 2.0

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.2 CD 1.9 60 70 80 90 100 m 20 30 40 50 Core Power (% RATED)

CD -Z 0 _

MCPR OPERATING LIMIT VERSUS CORE POWER WA 6

EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE cia 0 SINGLE LOOP OPERATION (BOC to EOC) 00 0)

FIGURE 8.2-5

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 34 of 38 O 9.0 POWER / FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.3 9.2 -Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and I of the Power / Flow map, Figure 9.1.

If the OPRM Instrumentation is OPERABLE per TS 3.3.1.3, Region I of the Power / Flow map is considered an immediate exit region.

If the OPRM Instrumentation is inoperable per TS 3.3.1.3, Region I of the Power I Flow map is considered an immediate scram region.

Region II of the Power / Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation.

SUSOUEHANNA UNIT 2 TRM/3.2-35 EFFECTIVE DATE 10/05/2006

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 35 of 38 120 , , , , . . . . . , .

• 120

Purpose:

L'- L--I~~- UNIT 2

.,L*,J[__ - POWERIFLOWMAP 110 100% Rod Line - 110 Initial /Date: /

APRM Rod Block RE Trip Setpolnt REGION 100 STABILITY REGION I IF OPRM INOPERABLE IMMEDIATE SCRAM L12LF- 100 lAW ON.278-002 IF OPRM OPERABLE IMMEDIATE EXIT lAW ON-278-002 U JýiR m STABILITY REGION IU ipi T 77,III 90 IMMEDIATELY EXIT lAW ON-278-002 90 RESTRICTED REGION -I-L (As defined In Attachment G to NDAP-1A.0338)

I I I I [RodLine 80 1I J jo

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70-

- 1- - 4 LV L 111 I I . .

- 70

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T' T -I-!- - - r- T -1 20 I*L*L I 20

~.Two Pumnp :4 I30%~oSpe.------ F,-'1 L.L -1.

SIJ L I 10 J~I f 10 (0

0 10 20 30 40 50 60 70 80 90 100 110 Total Core Flow (Mlbmlhr)

(for SLO <75% Pump Speed Use Form GO-200-009-2)

Figure 9.1 SSES Unit 2 Cycle 13A Power / Flow Map SUSOUEHANNA UNIT 2 TRM/3.2- 36 EFFECTIVE DATE 10/05/2006

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 36 of 38 10.0 OPRM SETPOINTS 10.1 Technical Specification Reference Technical Specification 3.3.1.3 10.2 -Description Setpoints for the OPRM Instrumentation are established that will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR Safety limit is not violated. The setpoints are described in Section 1.0 and are listed below:

Sp = 1.11

= 14 S 65 Mlbm / hr SUSQUEHANNA UNIT 2 TRM/3.2-37 EFFECTIVE DATE 10/05/2006

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 37 of 38

11.0 REFERENCES

11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

-1. XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984.

2. EMF-2361 (P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model,"

Framatome ANP, May 2001.

3. EMF-2292(P)(A), Revision 0, "ATRIUM TM-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.

4. XN-NF-84-105(P)(A), Volume 1 and Volume 1 Supplements 1 and 2, "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," Exxon Nuclear Company, February 1987.

5. XN-NF-80-19(P)(A), Volume 1 and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983.

6. XN-NF-80-19(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," Exxon Nuclear Company, September 1982.

7. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987.

8. XN-NF-80-19(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, June 1986.

9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc.,

September 1986.

10. ANF-524(P)(A), Revision 2 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors,"

November 1990.

11. NE-092-001A, Revision 1, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993).

SUSQUEHANNA UNIT 2 TRM/3.2-38 EFFECTIVE DATE 10/05/2006

PPL Rev. 5 PL-NF-06-006 Rev. 0 Page 38 of 38

12. ANF-89-98(P)(A) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.

13. ANF-91-048(P)(A), "Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR Evaluation Model," Advanced Nuclear Fuels Corporation, January 1993.

14. EMF-1997(P)(A) Revision 0, "ANFB-10 Critical Power Correlation," Siemens Power Corporation, July 1998; and EMF-1 997(P), Supplement 1(P)(A)

Revision 0, "ANFB-10 Critical Power Correlation : High Local Peaking Results," Siemens Power Corporation, July 1998.

15. Caldon, Inc., "TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM'TM System," Engineering Report - 80P, March 1997.

16. Caldon, Inc., "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFMI T or LEFM CheckPlusTM System,"- Revision 0, Engineering Report ER-160P, May 2000.

17. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A),

"RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model,"

Siemens Power Corporation, February 1998.

18. EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors:- Evaluation and Validation of CASMO-4/Microburn-B2," Siemens Power Corporation, October 1999.

19. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis -

Assessment of STAIF with Input from MICROBURN-B2," Siemens Power Corporation, November 1999.

20. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.

21. ANF-913(P)(A), Volume 1 Revisionl and Volume 1 Supplements 2, 3, and 4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation, August 1990.

22. EMF-1 358(P)(A), Revision 1, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Advanced Nuclear Fuels Corporation, September 1992.

23. EMF-2209(P)(A), Revision 1, "SPCB Critical Power Correlation," Siemens Power Corporation, July 2000.

SUSOUEHANNA UNIT 2 TRM/3.2-39 EFFECTIVE DATE 10/05/2006

Heavy Loads Requirements PPL Rev.l.- 3.12.2 3.12 Loads Control Program 3.12.2 Heavy Loads Requirements TRO 3.12.2 The Technical Specification Limiting Conditions of Operation and Technical Requirements for Operation listed in Table 3.12.2-1 shall be met.

APPLICABILITY: During movement of heavy loads in the proximity of irradiated fuel.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The Conditions of A.1 Suspend movement of Immediately TRO 3.12.2 are not met. heavy loads in the proximity of irradiated fuel.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE - FREQUENCY TRS 3.12.2.1 Administratively verify that all requirements of Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior TRO are met. to commencing movement of heavy loads AND Every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter SUSQUEHANNA - UNIT 2 TRM / 3.12-3 EFFECTIVE DATE 2/05/1999

Heavy Loads Requirements PPL Rev._L 3.12.2 TABLE 3.12.2-1 TRO 3.12.2 REQUIREMENTS

a. LCO 3.3.6.2(a)

b. LCO 3 .3.7.1 .(b)

C. LCO 3.6.4.1(c)

d. LCO 3.6.4.2(c)

e. LCO 3 .6.4. 3 (d)

f. LCO 3.7.3(d)

g. LCO 3.7.7(e)

h. LCO 3.8.2

i. LCO 3.8.5

j. LCO 3.8.8

k. LCO 3.9.6 I. TRO 3.3.4(0

m. TRO 3.7.1

n. TRO 3.9.1(9)

o. TRO 3 .1 1 .2. 6 (h)

(a) Functions 3, 4, 5, 6, and 8.

(b) Functions 3, 4, 5, 6, 8, and 9.

(c) Zone III only.

(d) Minimum of one train OPERABLE.

(e) Only required for movement of heavy load in the proximity of irradiated fuel in the spent fuel storage pool.

0) Function 4 from Table 3.3.4-1.

(g) Only required for movement of heavy load in the proximity of irradiated fuel in the Reactor Pressure Vessel with the Steam Separator removed.

(h) Function 3 from Table 3.11.2.6-1.

SUSQUEHANNA - UNIT 2 TRM / 3.12-4 EFFECTIVE DATE 09/30/2006

Snubbers PPL Rev. 2-._ B 3.7.8 B 3.7.8 Snubbers BASES TRO All snubbers are required to be OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on non-safety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.

Snubbers are required to be OPERABLE whenever they are considered necessary to support equipment for the systems on which they are installed.

Technical Specification LCO 3.0.8 has been added to the Technical Specifications to allow snubbers to be inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if the inoperable snubber affects one subsystem or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if it affects multiple subsystems.

The generic NRC Safety Evaluation which approved the use of LCO 3.0.8 requires that certain conditions be met before LCO 3.0.8 can be entered. TRM 3.7.8 provides guidance on meeting these conditions.

"Type" of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity. For example, mechanical snubbers utilizing the same design features of the 2-kip, and 100-kip capacity manufactured by Company "A" are of the same type. The.

same design mechanical snubbers manufactured by company "B" for the purposes of this Technical Requirement would be of a different type, as would hydraulic snubbers from either manufacturer.

A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR part 50. The controlled list of plant snubbers is maintained in by the ISI Program. The addition or deletion of any snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.

(continued)

SUSQUEHANNA - UNIT 2 TRM I B 3.7-24 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev. 2 B 3.7.8 B 3.7.8 Snubbers BASES TRO The following are examples of conditions that require a snubber to be (continued) declared inoperable:

- Snubber not attached to piping system or support plate,

- Snubber missing,

- Snubber locked in position,

- Snubber excessively bent.

The following are examples of conditions that require an evaluation to confirm whether or not the snubber is inoperable:

- Dent(s) in snubber case,

- Thread engagement not per design,

- Missing bolt(s) on support plate,

- Snubber slightly bent.

As stated in NRC's Safety Evaluation Condition 2, the LCO 3.0.8 requirement to assess and manage risk is met by licensee programs to comply with the requirements of paragraph (a)(4) of the Maintenance Rule, 10 CFR 50.65, to assess and manage risk resulting from maintenance activities. Since the 10 CFR 50.65(a) (4) guidance, the revised (May 2000) Section 11 of NUMARC 93-01, does not address seismic risk, licensees must qualitatively integrate the use of LCO 3.0.8 into their 10 CFR 50.65(a) (4) program to assess and manage risk.

As described in the Bases of LCO 3.0.8, "LCO 3.0.8 should be consid-ered with respect to other plant maintenance activities, and integrated into the existing Maintenance Rule process to the extent possible so that maintenance on any unaffected train or subsystem is properly controlled, and emergent issues are properly addressed. The risk assessment need not be quantified, but may be a qualitative awareness of the vulnerability of systems and components when one or more snubbers are not able to perform their associated support function."

(continued)

SUSQUEHANNA - UNIT 2 TRM / B 3.7-25 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev. 2.__ B 3.7.8 B 3.7.8 Snubbers BASES (continued)

ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components and the implementa-tion of LCO 3.0.8. The NRC's 4/27/2005 Safety Evaluation lists the conditions that must be followed to adopt and utilize LCO 3.0.8.

The ACTIONS provide the guidance for the implementation of these conditions and therefore the implementation of LCO 3.0.8.

Conditions A and B Condition A applies when one or more snubbers are not capable of providing their associated support function(s) to a single subsystem of a multiple subsystem supported system or to a single subsystem supported system.

Condition B applies when one or more snubbers are not able to perform their associated support function(s) are associated with more than one subsystem of a multiple subsystem supported system.

The wording of these Conditions allow for confirmation of snubber inoperability. This allows for input from snubber knowledgeable parties to review the condition. The intent is to obtain this confirmation in an expeditious manner and not delay declaring a snubber or support system inoperable. If confirmation of snubber inoperability is delayed, the snubber should be considered inoperable and appropriate actions of this TRO applied.

Required Action A.1.1 or B.1.1 When a snubber is to be rendered incapable of performing its related support function (i.e., nonfunctional) for testing or maintenance or is discovered to not be functional, it must be determined whether any Technical Specification (TS) system(s) require the affected snubber(s) for system OPERABILITY, and whether the plant is in a MODE or specified condition in the Applicability that requires the supported TS system(s) to be OPERABLE.

1. If an analysis determines that the supported TS system(s) do not require the snubber(s) to be functional in order to support the OPERABILITY of the system(s), LCO 3.0.8 is not needed.

2. If the LCO(s) associated with any supported TS system(s) are not currently applicable (i.e., the plant is not in a MODE or other specified condition in the Applicability of the LCO), LCO 3.0.8 is not needed.

(continued)

SUSQUEHANNA - UNIT 2 TRM / B 3.7-26 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev. 2. B 3.7.8 B 3.7.8 Snubbers BASES ACTIONS 3. If the supported TS system(s) are inoperable for reasons other (continued) than snubbers, LCO 3.0.8 cannot be used.

LCO 3.0.8 is an allowance, not a requirement. When a snubber is nonfunctional, any supported TS system(s) may be declared inoperable instead of using LCO 3.0.8.

The NRC Safety Evaluation only considered the loss of the ability of a snubber to respond to a seismic event. However, some snubbers have design functions other than response to a seismic event. The inability to perform these non-seismic design functions were not considered or justified. Therefore, when a snubber is to be rendered nonfunctional for testing or maintenance or is discovered to not be functional, the design function of the snubber must be determined in order to determine if LCO 3.0.8 may be used.

1. If the design function of the snubber is to react to only seismic loads, LCO 3.0.8 may be applied.

2. If the design function of the snubber includes both seismic loads and non-seismic loads (e.g., thrust loads, blowdown loads, waterhammer loads, steamhammer loads, LOCA loads, and pipe rupture loads), any TS systems supported by the nonfunctional snubber must be able to remain OPERABLE if subjected to the non-seismic loads with the snubber removed. If the supported TS system will remain OPERABLE when subjected to non-seismic loads, LCO 3.0.8 may be applied. Otherwise, LCO 3.0.8 may not be applied to TS systems supported by the nonfunctional snubber.

3. If the design function of the snubber includes only non-seismic loads (e.g., thrust loads, blowdown loads, waterhammer loads, steamhammer loads, LOCA loads, and pipe rupture loads),

LCO 3.0.8 cannot be applied to the TS systems supported by the nonfunctional snubber. However, if it can be confirmed that snubber is not needed for OPERABILITY of the TS system, LCO 3.0.8 is not needed.

Note: Snubbers located in the Diesel Generator Buildings only have seismic loads as their design function loads. Snubbers located else-where in the plant have both seismic and non-seismic loads as their design function loads.

(continued)

SUSQUEHANNA - UNIT 2 TRM / B 3.7-27 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev. Z B 3.7.8 B 3.7.8 Snubbers BASES ACTIONS Required Action A. 1.2 or B. 1.2 (continued)

This Required Action ensures that when LCO 3.0.8 is entered there are sufficient OPERABLE subsystems (not associated with the inoperable snubber) to provide makeup and heat removal in the event of a LOOP.

The NRC does not require any other accidents or events such as LOCA, DBA or transients to be accounted for. The subsystems that can be used to meet this condition are:

a. At least one OPERABLE high pressure subsystem (e.g., HPCI or RCIC) and OPERABLE heat removal capability (e.g., suppression pool cooling), or

b. At least one OPERABLE low pressure subsystem (e.g., LPCI or CS) and OPERABLE heat removal -capability (e.g., suppression pool cooling or shutdown cooling).

The NRC's Safety Evaluation Condition 1 .(d) is met by these required actions.

Required Action A.1.3 or B.1.3 The NRC's Safety Evaluation requires that subsystem(s) associated with inoperable snubber (s) must be capable of performing their required safety or support function when subjected to the postulated non-seismic design function loads.

NRC's Safety Evaluation also requires that every time LCO 3.0.8 is used for TS systems supported by nonfunctional snubbers whose design loads include non-seismic loads, licensees must be able to produce a record of the design function of the nonfunctional snubber (i.e., seismic vs. non-seismic). This record does not have to be created prior to or following use of LCO 3.0.8, but must be able to be created or produced if requested. For example, if a system engineer knows from previous experience that a particular snubber is only designed for seismic loads, it is not necessary to collect existing design documents or create design documents or calculations to demonstrate that fact prior to using LCO 3.0.8. However, if asked to demonstrate the design basis of the snubber, the licensee must be able to produce or create appropriate documentation to support that position.

(continued)

SUSQUEHANNA - UNIT 2 TRM / B 3.7-28 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev. 2- B 3.7.8 B 3.7.8 Snubbers BASES ACTIONS Required Action A.1.4 or B.1.4 (continued)

Required Action A.1.4 or B.1.4 provides for the entry into LCO 3.0.8 provided the requirements for entry are verified.

Required Action A.1.5 or B.1.5 The completion time is consistent with the time used to evaluate the risk of having an inoperable snubber and not declaring the system LCO.

Condition E Snubbers are required to be OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Evaluating their service life and replacing them before the end of their service life ensures that the snubbers will remain OPERABLE.

- TRS The TRSs are defined to be performed at the specified Frequency to ensure that the snubbers are maintained OPERABLE. Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, ifapplicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the completion of their fabrication or at a subsequent date.

Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.

TRS 3.7.8.1 The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Generic Letter 90-09 provides a method for determining the next interval for the visual inspection of snubbers based upon the number of unacceptable snubbers found during the previous inspection, the total population or category size for each snubber type, and the previous inspection interval.

(continued)

SUSQUEHANNA - UNIT 2 TRM / B 3.7-29 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev.. 2_ B 3.7.8 B 3.7.8 Snubbers BASES (continued)

TRS The visual inspection interval for a snubber population shall be (continued) determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers are categorized as inaccessible or accessible during reactor operation.

Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 3.7.8-1. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 3.7.8-1.

Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible, and are inspected on that basis. The snubber population, for the purpose of visual inspection, is determined either separately or jointly for accessible and inaccessible units. The results of snubber examinations are judged, per Table 3.7.8-2, in accordance with that population. The decision whether to combine the category populations or keep them separate must be documented before any inspection, and that decision shall be used as the basis upon which to determine the subsequent inspection interval for that category.

The accessibility of each snubber shall be determined and approved by the Plant Operations Review Committee. The determination shall be based upon the-existing radiation levels and the expected time to perform a visual inspection upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g. temperature, atmosphere, location, etc.), and the

-recommendations of Regulatory Guides 8.8 and 8.10.

Visual inspections shall verify that (1) the snubber has no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component, and to the snubber anchorage are functional.

Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined (continued)

SUSQUEHANNA - UNIT 2 TRM / B 3.7-30 EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev.. 2- B 3.7.8 B 3.7.8 Snubbers BASES TRS OPERABLE per TRS 3.7.8.2. A review and evaluation shall be (continued) performed and documented to justify continued operation with an unacceptable snubber. If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.

TRS 3.7.8.2 A representative sample of snubbers shall be tested for each type of snubber. The representative sample selected for the functional test sample plans shall be randomly selected from the snubbers of each type and reviewed before beginning the testing. The review shall ensure as far as practical that they are representative of the various configurations, operating environments, range of size, and capacity of snubbers of each type.

Functional Test Acceptance Criteria The snubber functional test shall verify that:

1. Activation (restraining action) is achieved within the specified range in both tension and compression;

2. Snubber bleed, or release rate where required, is present in-both tension and compression, within the specified range;

3. Where required, the force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel; and

4. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement.

Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.

(continued)

SUSQUEHANNA - UNIT 2 TRM / B 3.7-30a EFFECTIVE DATE 10/05/2006

Snubbers PPL Rev. 2_ B 3.7.8 B 3.7.8 Snubbers BASES TRS TRS 3.7.8.3 (continued)

The maximum expected service life for various seals, springs, and other critical parts shall be determined and established based on engineering information and shall be extended or shortened based on monitored test results and failure history. Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be OPERABLE. The parts replacements shall be documented and the documentation shall be retained in accordance with FSAR 17.2.17.

The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.

These records will provide statistical bases for future consideration of snubber service life.

TRS 3.7.8.5 The required inspection consists of the following elements:

1. Perform a visual inspection of all affected snubbers,

2. Verify freedom of motion of mechanical snubbers by manually induced snubber movement, or

3. Verify freedom of motion of mechanical snubbers by evaluation of in-place snubber piston setting, or

4. Verify freedom of motion of mechanical snubbers by stroking the mechanical snubber through its full range of travel.

REFERENCES 1. Generic Letter 90-09 SUSQUEHANNA - UNIT 2 TRM / B 3.7-30b EFFECTIVE DATE 10/05/2006