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Revisions to Technical Specification Bases Unit 1 Manual
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SSES MANTJA-L Manual Name:

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Title:

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

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05/06/2009

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SAFETY LIMITS (SLS)

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Report Date: 08/20/09 SSES MANUAL Manual Name:

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Title:

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

08/20/2009 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 93 08/20/2009

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01/30/2009

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CONTAINMENT SYSTEMS SECONDARY CONTAINMENT Page.5.

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Title:

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09/21/2006

Title:

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Title:

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TSB1 Manual

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TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.4.2 2

01/03/2005

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Title:

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11/15/2002

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Title:

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04/12/2006

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04/12/2006

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SPECIAL OPERATIONS SHUTDOWN MARGIN (SDM) TEST -

REFUELING Page.a of.a Report Date: 08/20/09

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)

B2.0 SA FETY LIM ITS (S Ls)..................................................................................

B2.0-1 B 2.1.1 R eactor C ore S Ls...........................................................................

B2.0-1 B2.1.2 Reactor Coolant System (RCS) Pressure SL...........................

TS/B2.0-7 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 M argin (S DM )................................................................

B3.1-1 B3.1.2 Reactivity Anom alies..................................................................

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 C ontrol..................................................................

TS/B3.1-34 B3.1.7 Standby Liquid Control (SLC) System......................................

TS/B3.1-39 B3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves......... TS/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 B3.3 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.........................................................................

B 3.3-55 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 e ntatio n.........................................................................

B 3.3-8 1 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...................................................................

TS/B3.3-1Q01 B3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrum e ntation.........................................................................

B 3.3-135 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......................................................

TS/B3. 3-192 (continued)

SUSQUEHANNA - UNIT 1 TS / B TOC - 1 Revision 17 TA8LE OF CONTENTS (TECHNICAL SPECIFICATIONS 8ASES) 82.0 82.1.1 82.1.2 83.0 83.0 83.1 83.1.1 83.1.2 83.1.3 83.1.4 83.1.5 83.1.6 83.1.7 83.1.8 83.2 83.2.1 83.2.2 83.2.3 83.3 83.3.1.1 83.3.1.2 83.3.2.1 83.3.2.2 83.3.3.1 83.3.3.2 83.3.4.1 83.3.4.2 83.3.5.1 83.3.5.2 83.3.6.1 83.3.6.2 83.3.7.1 SAFETY LIMITS (SLs).................................................................................. 82.0-1 Reactor Core SLs........................................................................... 82.0-1 Reactor Coolant System (RCS) Pressure SL........................... TS/82.0-7 LIMITING CONDITION FOR OPERATION (LCO) APPLlCA8IL1TY........ TS/83.0-1 SURVEILLANCE REQUIREMENT (SR) APPLlCA81L1TY...................... TS/83.0-10 REACTIVITY CONTROL SySTEMS................................................. ~.. 83.1-1 Shutdown Margin (SDM)................................................................ 83.1-1 Reactivity Anomalies...................................................................... 83.1-8 Control Rod OPERA81L1TY............................................................ 83.1-13 Control Rod Scram Times........................................................ TS/83.1-22 Control Rod Scram Accumulators............................................ TS/83.1-29 Rod Pattern Contro!.................................................................. TS/83.1-34 Standby Liquid Control (SLC) System...................................... TS/83.1-39 Scram Discharge Volume (SDV) Vent and Drain Valves.......... TS/83.1-47 POWER DISTRI8UTION LIMITS................................................... TS/83.2-1 Average Planar Linear Heat Generation Rate (APLHGR)........ TS/83.2-1 Minimum Critical Power Ratio (MCPR)..................................... TS/83.2-5 Linear Heat Generation Rate (LHGR)....................................... TS/83.2-10 INSTRUMENTATION..................................................................... TS/83.3-1 Reactor Protection System (RPS) Instrumentation................... TS/83.3-1 Source Range Monitor (SRM) Instrumentation......................... TS/83.3-35 Control Rod 810ck Instrumentation........................................... TS/83.3-44 Feedwater - Main Turbine High Water Level Trip Instrumentation......................................................................... 83.3-55 Post Accident Monitoring (PAM) Instrumentation..................... TS/83.3-64 Remote Shutdown System............................................................. 83.3-76 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation......................................................................... 83.3-81 Anticipated Transient Without Scram Recirculation Pump Trip (A TWS-RPT) Instrumentation.............................. TS/83.3-92 Emergency Core Cooling System (ECCS)

Instrumentation................................................................... TS/83.3-101 Reactor Core Isolation Cooling (RCIC) System Instrumentation......................................................................... 83.3-135 Primary Containment Isolation Instrumentation.............................. 83.3-147 Secondary Containment Isolation Instrumentation................... TS/83.3-180 Control Room Emergency Outside Air Supply (CREOAS)

System Instrumentation...................................................... TS/83.3-192

( continued)

SUSQUEHANNA - UNIT 1 TS 18 TOC-1 Revision 17

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 M o n ito ring................................................................................

B 3.3-2 13 B3.4 REACTOR COOLANT SYSTEM (RCS)...............................................

B3.4-1 B3.4.1 Recirculation Loops Operating.......................................................

B3.4-1 B 3.4.2 Jet P um ps......................................................................................

B 3.4-10 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..................................

TS/B3.4-30 B3.4.7 RCS Specific Activity................................................................

TS/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 EC C S - O perating.........................................................................

B3.5-1 B3.5.2 ECCS - Shutdown.........................................................................

B3.5-19 B3.5.3 R C 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....................................................................

B3.6-41 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..................................

TS/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 o o lin g.....................................................................................

B 3.6 -6 2 B3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray................ B3.6-66 B 3.6.3.1 N ot U sed..................................................................................

T S /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)

SUSQU EHAN NA - U N IT 1 TS / B TOC - 2 Revision 17 TA8LE OF CONTENTS (TECHNICAL SPECIFICATIONS 8ASES) 83.3 83.3.8.1 83.3.8.2 83.4 83.4.1 83.4.2 83.4.3 83.4.4 83.4.5 83.4.6 83.4.7 83.4.8 83.4.9 83.4.10 83.4.11 83.5 83.5.1 83.5.2 83.5.3 83.6 83.6.1.1 83.6.1.2 83.6.1.3 83.6.1.4 83.6.1.5 83.6.1.6 83.6.2.1 83.6.2.2 83.6.2.3 83.6.2.4 83.6.3.1 83.6.3.2 83.6.3.3 83.6.4.1 83.6.4.2 83.6.4.3 INSTRUMENTATION (continued)

Loss of Power (LOP) Instrumentation....................................... TS/83.3-205 Reactor Protection System (RPS) Electric Power Monitoring................................................................................ 83.3-213 REACTOR COOLANT SYSTEM (RCS)............................................... 83.4-1 Recirculation Loops Operating....................................................... 83.4-1 Jet Pumps...................................................................................... 83.4-10 SafetylRelief Valves (S/RVs).................................................... TS/83.4-15 RCS Operational LEAKAGE.......................................................... 83.4-19 RCS Pressure Isolation Valve (PIV) Leakage................................. 83.4-24 RCS Leakage Detection Instrumentation.................................. TS/83.4-30 RGS Specific Activity................................................................ TS/83.4-35 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown........................................................... 83.4-39 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown......................................................... 83.4-44 RCS Pressure and Temperature (PIT) Limits........................... TS/83.4-49 Reactor Steam Dome Pressure................................................ TS/83.4-58 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM,................................. 83.5-1 EGCS - Operating......................................................................... 83.5-1 EGCS - Shutdown......................................................................... 83.5-19 RCIC System........................................................................... TS/83.5-25 CONTAINMENT SySTEMS........................................................... TS/83.6-1 Primary Containment................................................................ TS/83.6-1 Primary Containment Air Lock........................................................ 83.6-7 Primary Containment Isolation Valves (PCIVs)......................... TS/83.6-15 Containment Pressure.................................................................... 83.6-41 Drywell Air Temperature........................................................... TS/83.6-44 Suppression Chamber-to-Drywell Vacuum 8reakers................ TS/83.6-47 Suppression Pool Average Temperature.................................. TS/83.6-53 Suppression Pool Water Level....................................................... 83.6-59 Residual Heat Removal (RHR) Suppression Pool Cooling..................................................................................... 83.6-62 Residual Heat Removal (RHR) Suppression Pool Spray................ 83.6-66 Not Used.................................................................................. TS/83.6-70 Drywell Air Flow System................................................................. 83.6-76 Primary Containment Oxygen Concentration.................................. 83.6-81 Secondary Containment........................................................... TS/83.6-84 Secondary Containment Isolation Valves (SCIVs).................... TS/83.6-91 Standby Gas Treatment (SGT) System................................... TS/83.6-101 (continued)

SUSQUEHANNA - UNIT 1 TS 1 8 TOC - 2 Revision 17

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 (C REO AS) System.............................................................

TS/B3.7-12 B3.7.4 Control Room Floor Cooling System........................................

TS/B3.7-19 B3.7.5 Main Condenser Offgas...........................................................

TS/B3.7-24 B3.7.6 Main Turbine Bypass System...................................................

TS/B3.7-27 B3.7.7 Spent Fuel Storage Pool Water Level......................................

TS/B3.7-31 B3.7.8 Main Turbine Pressure Regulation System..................

TS/B3.7-34 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................................

TS/B3.8-45 B3.8.4 DC Sources - Operating..........................................................

TS/B3.8-54 B3.8.5 DC Sources - Shutdown..........................................................

TS/B3.8-66 B3.8.6 Battery Cell Parameters...........................................................

TS/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 C ontrol R od 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...........................

TS/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 8/12/09 SUSQUEHANNA -

UNIT 1 TS / B TOC -3 Revision 17 SUSQUEHANNA - UNIT 1 TS / B TOC - 3 Revision 17 TA8LE OF CONTENTS (TECHNICAL SPECIFICATIONS 8ASES) 83.7 83.7.1 83.7.2 83.7.3 83.7.4 83.7.5 83.7.6 83.7.7 83.7.8 83.8 83.8.1 83.8.2 83.8.3 83.8.4 83.8.5 83.8.6 83.8.7 83.8.8 83.9 83.9.1 83.9.2 83.9.3 83.9.4 83.9.5 83.9.6 83.9.7 83.9.8 83.10 83.10.1 83.10.2 83.10.3 83.10.4 83.10.5 83.10.6 83.10.7 83.10.8 TSB1 Text TOe 8/12/09 PLANT SYSTEMS......................................................................... TS/83.7-1 Residual Heat Removal*Service Water (RHRSW) System and the Ultimate Heat Sink (UHS)...................................... TS/83.7-1 Emergency Service Water (ESW) System................................ TS/83.7-7 Control Room Emergency Outside Air Supply (CREOAS) System............................................................. TS/83.7-12 Control Room Floor Cooling System........................................ TS/83. 7-19 Main Condenser Offgas........................................................... TS/83.7-24 Main Turbine 8ypass System................................................... TS/83.7-27 Spent Fuel Storage Pool Water Level...................................... TS/83.7-31 Main Turbine Pressure Regulation System... :.......................... TS/83.7-34 ELECTRICAL POWER SYSTEM................................................... TS/83.8-1 AC Sources - Operating.......................................................... TS/83.8-1 AC Sources - Shutdown................................................................ 83.8-38 Diesel Fuel Oil, Lube Oil, and Starting Air................................ TS/83.8-45 DC Sources - Operating.......................................................... TS/83.8-54 DC Sources - Shutdown.......................................................... TS/83.8-66 8attery Cell Parameters........................................................... TS/83.8-71 Distribution Systems - Operating................................................... 83.8-78 Distribution Systems - Shutdown................................................... 83.8-86 REFUELING OPERATIONS.......................................,.................. TS/83.9-1 Refueling Equipment Interlocks................................................ TS/83.9-1 Refuel Position One-Rod-Out Interlock........................................... 83.9-5 Control Rod Position...................................................................... 83.9-9 Control Rod Position Indication...................................................... 83.9-12 Control Rod OPERA81L1TY - Refueling......................................... 83.9-16 Reactor Pressure Vessel (RPV) Water Level........................... TS/83.9-19 Residual Heat Removal (RHR) - High Water Level........................ 83.9-22 Residual Heat Removal (RHR) - Low Water Level......................... 83.9-26 SPECIAL OPERATIONS............................................................... TS/83.10-1 Inservice Leak and Hydrostatic Testing Operation................... TS/83.10-1 Reactor Mode Switch Interlock Testing.......................................... 83.10-6 Single Control Rod Withdrawal-Hot Shutdown............................. 83.10-11 Single Control Rod Withdrawal - Cold Shutdown........................... 83.10-16 Single Control Rod Drive (CRD) Removal - Refueling................... 83.10-21 Multiple Control Rod Withdrawal - Refueling.................................. 83.10-26 Control Rod Testing - Operating.................................................... 83.10-29 SHUTDOWN MARGIN (SDM) Test-Refueling............................. 83.10-33 SUSQUEHANNA - UNIT 1 TS 1 8 TOC - 3 Revision 17

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Section Title Revision TOC B 2.0 B 3.0 B 3.1 T able of Contents SAFETY LIMITS BASES Page B 2.0-1 Page TS I B 2.0-2 Page TS I B 2.0-3 Page TS I B 2.0-4 Page TS I B 2.0-5 Page TS I B 2.0-6 Pages TS I B 2.0-7 through TS I B 2.0-9 LCO AND SR APPLICABILITY BASES Page TS I B 3.0-1 Pages TS I B 3.0-2 through TS I B 3.0-4 Pages TS I B 3.0-5 through TS I B 3.0-7 Page TS I B 3.0-8 Pages TS I B 3.0-9 through TS I B 3.0-11 Page TS I B 3.0-11a Page TS I B 3.0-12 Pages TS I B 3.0-13 through TS I B 3.0-15 Pages TS I B 3.0-16 and TS I B 3.0-17 REACTIVITY CONTROL BASES Pages B 3.1-1 through B 3.1-4 Page TS I B 3.1-5.

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Section Title Revision B 3.2 B 3.3 Page TS / B 3.1.43 Page TS / B 3.1-44 Page TS / B 3.1-45 Pages TS / B 3.1-46 through TS / B 3.1 ~49 Page TS / B 3.1-50 Page TS / B 3.1-51 POWER DISTRIBUTION LIMITS BASES Page TS / B 3.2-1 Pages TS / B 3.2-2 and TS / B 3.2-3 Pages TS / B 3.2-4 and TS / B 3.2-5 Page TS / B 3.2-6 Page B 3.2-7 Pages TS / B 3.2-8 and TS / B 3.2-9 Page TS / B 3.2.10 Page TS / B 3.2-11 Page TS / B 3.2-12 Page TS / B 3.2-13 INSTRUMENTATION Pages TS / B 3.3-1 through TS / B 3.3-4 Page TS / B 3.3-5 Page TS / B 3.3-6 Page TS / B 3.3-7 Page TS / B 3.3-7a Page TS / B 3.3-8 Pages T8 / B 3.3-9 through TS / B 3.3-12 Pages T8 / B 3.3-12a Pages T8/ B 3.3-12b and TS / B 3.3-12c Page TS / B 3.3-13 Page TS / B 3.3-14 Pages T8 / B 3.3-15 and TS / B 3.3-16 Pages T8/ B 3.3-17 and TS / B 3.3-18 Page TS / B 3.3-19 Pages TS / B 3.3-20 through TS / B 3.3-22 Page TS / B 3.3-22a Pages TS / B 3.3-23 and TS / B 3.3-24 Pages TS / B 3.3-24a and TS / B 3.3-24b Page TS / B 3.3-25 Page TS / B 3.3-26 Page TS / B 3.3-27 Pages TS / B 3.3-28 through TS / B 3.3-30 Page TS / B 3.3-30a SUSQUEHANNA - UNIT 1 TS I B LOES-2 1 o 3

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Section Title Revision B3.4 Page TS / B 3.3-181 Page TS / B 3.3-182 Page TS / B 3.3-183 Page TS / B 3.3-184 Page TS / B 3.3-185 Page TS / B 3.3-186 Pages TS / B 3.3-187 and TS / B 3.3-188 Pages TS / B 3.3-189 through TS / B 3.3-191 Page TS / B 3.3-192 Page TS / B 3.3-193 Pages TS / B 3.3-194 and TS / B 3.3-195 Page TS / B 3.3-196 Pages TS / B 3.3-197 through TS / B 3.3-204 Page TS / B 3.3-205 Pages B 3.3-206 through B 3.3-209 Page TS / B 3.3-210 Pages B 3.3-211 through B 3.3-219 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 and B 3.4-2 Pages TS / B 3.4-3 and Page TS / B 3.4-4 Pages TS / B 3.4-5 through TS / B 3.4-9 Pages B 3.4-10 through B 3.4-12 Page B 3.4-13 Page B 3.4-14 Page TS / B 3.4-15 Pages TS / B 3.4-16 and TS / B 3.4-17 Page TS / B 3.4-18 Pages B 3.4-19 through B 3.4-27 Pages TS / B 3.4-28 and TS / B 3.4-29 Pages TS / B 3.4-30 and TS / B 3.4-31 Pages TS / B 3.4-32 and TS / B 3.4-33 Page TS / B 3.4-34 Pages TS / B 3.4-35 and TS / B 3.4-36 Page TS / B 3.4-37 Page TS / B 3.4-38 Pages B 3.4-39 and B 3.4-40 Page TS / B 3.4-41 Pages B 3.4-42 through B 3.4-48 Page TS / B 3.4-49 Page TS / B 3.4-50 Page TS / B 3.4-51 Page TS / B 3.4-52 Page TS / B 3.4-53 SUSQUEHANNA - UNIT 1 TS I B LOES-5 3

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Section Title Pages TS / B 3.4-54 through TS / B 3.4-56 Page TS / B 3.4-57 Pages TS / B 3.4-58 through TS / B 3.4-60 B 3.5 ECCS AND RCIC BASES B 3.6 Pages B 3.5-1 and B 3.5-2 Page TS / B 3.5-3 Page TS / B 3.5-4 Page TS I B 3.5-5 Page TS I B 3.5-6 Pages B 3.5-7 through B 3.5-10 Page TS I B 3.5-11 Page TS I B 3.5-12 Page TS I B 3.5-13 Pages TS / B 3.5-14 and TS I B 3.5-15 Pages TS / B 3.5-16 through TS / B 3.5-18 Pages B 3.5-19 through B 3.5-24 Page TS / B 3.5-25 Pages TS / B 3.5-26 and TS / B 3.5-27 Pages B 3.5-28 through B 3.5-31 CONTAINMENT SYSTEMS BASES Page TS / B 3.6-1 Page TS I B 3.6-1a Page TS I B 3.6-2 Page TS I B 3.6-3 Page TS / B 3.6-4 Pages TS / B 3.6-5 and TS I B 3.6-6 Pages TS / B 3.6-6a and TS / B 3.6-6b Page TS / B 3.6-6c Pages B 3.6-7 Page B 3.6-8 Pages B 3.6-9 through B 3.6-14 Page TS I B 3.6-15 Page TS I B 3.6-15a Page TS I B 3.6-15b Pages TS / B 3.6-16 and TS / B 3.6-17 Page TS / B 3.6-17a Pages TS / B 3.6-18 and TS / B 3.6-19 Page TS I B 3.6-20 Page TS / B 3.6-21 Page TS / B 3.6-22 Page TS I B 3.6-22a Page TS/ B 3.6-23 SUSQUEHANNA - UNIT 1 TS I B LOES-6 Revision 2

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SUSQUEHANNA

- UNIT I TS I B LOES-7 Revision 93 SUSQUEHANNA - UNIT 1 TS / B LOES-7 Revision 93 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision Pages TS / B 3.6-24 and TS / B 3.6-25 0

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SUSQUEHANNA - UNIT 1 TS I B LOES-7 Revision 93

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

Section Title Revision Pages TS / B 3.6-103 and TS / B 3.6-104 2

Page TS / B 3.6-105 3

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Page TS / B 3.6-107 3

B 3.7 PLANT SYSTEMS BASES Pages TS / B 3.7-1 3

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B 3.8 ELECTRICAL POWER SYSTEMS BASES Page TS / B 3.8-1 3

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SUSQUEHANNA

- UNIT 1 TS / B LOES-8 Revision 93 SUSQUEHANNA - UNIT 1 TS / B LOES-8 Revision 93 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision 8 3.7 8 3.8 Pages TS / 8 3.6-103 and TS /83.6-104 Page TS / 8 3.6-105 Page TS / 8 3.6-106 Page TS / 8 3.6-107 PLANT SYSTEMS 8ASES Pages TS / 8 3.7-1 Page TS / 8 3.7-2 Pages TS /83.7-3 through TS / 8 3.7-5 Page TS / 8 3.7-5a Pages TS / 8 3.7-6 and TS /8 3.7-6a Page TS / 8 3.7-6b Page TS / 8 3.7-6c Page T8 /83.7-7 Page T8 /83.7-8 Pages TS / 8 3.7-9 through TS / 83.7-13 Pages TS / 8 3.7-14 through T8/ 8 3.7-18 Page T8 / 8 3.7-18a Pages TS / 8 3.7-19 through TS / 8 3.7-23 Page T8 /83.7-24 Pages TS / 8 3.7-25 and T8 / 8 3.7-26 Pages TS / 8 3.7-27 through T8 / 8 3.7-29 Page T8 / 8 3.7-30 Page T8 / 8 3.7-31 Page T8 / 8 3.7-32 Page T8 /83.7-33 Pages TS / 8 3.7-34 through T8 /83.7-37 ELECTRICAL POWER SYSTEMS 8ASES Page T8 / 8 3.8-1 Pages TS / 8 3.8-2 and TS / 8 3.8-3 Page T8 / 8 3.8-4 Pages TS / 8 3.8-4a and T8 / 8 3.8-4b.

Page T8 / 8 3.8-5 Page T8 1 8 3.8-6 Pages TS 1 8 3.8-7 through T8/8 3.8-8 Page T8 / 8 3.8-9 Page T8 /83.8-10 Pages TS / 8 3.8-11 and T8 / 8 3.8-17 Page T8 /83.8-18 Pages TS /83.8-19 through T8 / 8 3.8-21 Pages TS 1 8 3.8-22 and T8 1 8 3.8-23 Pages TS 1 8 3.8-24 through T8 / 8 3.8-37 Pages B 3.8-38 through 8 3.8-44 SUSQUEHANNA - UNIT 1 TS I B LOES-8 2

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Section Title Revision Page TS / B 3.8-45 1

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Pages TS / B 3.8-62 and TS I B 3.8-63 5

Page TS / B 3.8-64 4

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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 3.9-18 0

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B 3.10 SPECIAL OPERATIONS BASES Page TS / B 3.10-1 2

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TSB1 Text LOES.doc 8/12/09 SUSQUEHANNA - UNIT 1 TS I B LOES-9 Revision 93 SUSQUEHANNA - UNIT 1 TS I B LOES-9 Revision 93 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Page TS / B 3.8-45 Pages TS / B 3.8-46 through B 3.8-48 Page TS / B 3.8-49 Pages B 3.8-50 through B 3.8-53 Pages TS / B 3.8-54 through TS / B 3.8-57 Pages TS / B 3.8-58 through TS / B 3.8-61 Pages TS / B 3.8-62 and TS / B 3.8-63 Page TS / B 3.8-64 Page TS / B 3.8-65 Pages TS / B 3.8-66 through TS / B 3.8-77 Pages TS / B 3.8-77A through TS / B 3.8-77C Pages B 3.8-78 through B 3.8-80 Page TS / B 3.8-81 Pages B 3.8-82 through B 3.8-90 B 3.9 REFUELING OPERATIONS BASES Pages TS / B 3.9-1 and TS / B 3.9-1a Pages TS / B 3.9-2 through TS / B 3.9-4 Pages B 3.9-5 through B 3.9-18 Pages TS / B 3.9-19 through TS / B 3.9-21 Pages B 3.9-22 through B 3.9-30 B 3.10 SPECIAL OPERATIONS BASES Page TS / B 3.10-1 Pages TS / B 3.10-2 through TS / B 3.10-5 Pages B 3.10-6 through B 3.10-31 Page TS / B 3.10-32 Page B 3.10-33 Page TS / B 3.10-34 Pages B 3.10-35 and B 3.10-36 Page TS / B 3.10-37 Page TS / B 3.10-38 TSB1 Text LOES.doc 8/12/09 SUSQUEHANNA - UNIT 1 TS I B LOES-9 Revision 1

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PPL Rev. 3 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 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. 3.

LCO APPLICABILITY B 3.0 B 3:0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY BASES LCOs LCO 3.0.1 LCO 3.0.2 LCO 3.0.1 through LCO 3.0.8 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated.

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

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

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. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 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)

SUSQUEHANNA - UNIT 1 TS / B 3.0-2 Revision 0 PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.2 (continued)

ACTIONS.) The second type of Required Action specifies the remedial 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 (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, 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)

SUSQUEHANNA - UNIT 1 TS / B 3.0-2 Revision 0

PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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)

SUSQUEHANNA - UNIT 1 TS / B 3.0-3 Revision 0 PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 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 seNice 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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)

SUSQUEHANNA - UNIT 1 TS / B 3.0-3 Revision 0

PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 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 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , then the time allowed for reaching MODE 3 is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months , because the total time for reaching MODE 3 is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months . 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 1 TS / B 3.0-4 Revision 0 PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.3 (continued)

A unit shutdown required in accordance with LCO 3.0.3 may be terminated 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 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , then the time allowed for reaching MODE 3 is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months , because the total time for reaching MODE 3 is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months . 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 I B 3.0-4 Revision 0

PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 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 1 TS / B 3.0-5 Revision 1 PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.3 (continued)

LCO 3.0.4 assemblies in the spent fuel storage pool." Therefore, this LCO can be 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 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 1 TS / B 3.0-5 Revision 1

PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.4 (continued) purposes of LCO 3.0.4 (b), must take into account all inoperable Technical 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. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.4 (continued) purposes of LCO 3.0.4 (b), must take into account all inoperable Technical 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 3.0A.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. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.4 (continued)

LCO 3.0.4.c allows entry into a MODE or other specified condition in the 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. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.4 (continued)

LCO 3.0.4.c allows entry into a MODE or other specified condition in the 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 I B 3.0-7 Revision 1

PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 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 supported systems that have a support system LCO specified in the Technical Specifications (TS).

This (continued)

SUSQUEHANNA - UNIT 1 TS / B 3.0-8 Revision 3 PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.4 (continued)

LCO 3.0.5 LCO 3.0.6 SR 3.0.4 for any Surveillances that have not been performed on 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 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 OPERABI LlTY 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 establishes an exception to LCO 3.0.2 for supported systems that have a support system LCO specified in the Technical Specifications (TS).

This (continued)

SUSQUEHANNA - UNIT 1 TS I B 3.0-8 Revision 3

PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.6 (continued) exception is provided because LCO 3.0.2 would require that the Conditions 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. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.6 (continued) exception is provided because LCO 3.0.2 would require that the Conditions 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 I B 3.0-9 Revision 2

PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 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 ýis 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 address 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 2 PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.6 (continued)

LCO 3.0.7 system are OPERABLE, thereby ensuring safety function is retained. If this 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 address 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.

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 2

PPL Rev. 3 LCO APPLICABILITY B3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.7 (continued)

The Applicability of a Special Operations LCO represents a condition not 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. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.7 (continued)

LCO 3.0.8 The Applicability of a Special Operations LCO represents a condition not necessarily in compliance with the normal requirements of the TS.

Compliance with Special Operations LCOs is optional. A special operation may be perfonned either under the provisions of the appropriate Special Operations LCO or under the other applicable TS requirements. If it is desired to perfonn 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 LeO 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 establishes conditions under which systems are considered to remain capable of perfonning 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 perfonning 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. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.8 (continued)

LCO 3.0.8.a applies when one or more snubbers are not capable of providing 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore the snubber(s) before declaring the supported system inoperable. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to restore the snubber(s) before declaring the supported system inoperable. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 3.0-11la Revision 0 PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LC03.0.8 (continued)

LCO 3.0.8.a applies when one or more snubbers are not capable of providing 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore the snubber(s) before declaring the supported system inoperable. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to restore the snubber(s) before declaring the supported system inoperable. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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/B3.0-11a Revision 0

PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) 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 1 TS / B 3.0-12 Revision 1 PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY BASES SRs SR 3.0.1 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 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 1 TS / B 3.0-12 Revision 1

PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 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. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY SR 3.0.1 (continued)

SR 3.0.2 Surveillances, including Surveillances invoked by Required Actions, do not 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 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 I B 3.0-13 Revision 2

PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 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. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY SR 3.0.2 (continued)

SR 3.0.3 performance of the Required Action on a "once per... " interval.

SR3.0.2 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 altemative 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 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 I B 3.0-14 Revision 2

PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY SR 3.0.3 period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY SR 3.0.3 (continued) period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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.

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, Appendixj, 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 (coniinued)

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

PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY SR 3.0.3 (continued) implement 10 CFR 50.65(a)(4) and its implementation guidance, NRC 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. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY SR 3.0.3 (continued)

SR 3.0.4 implement 10 CFR 50.65(a)(4) and its implementation guidance, NRC 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 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. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY SR 3.0.4 (continued)

However, in certain circumstances, failing to meet an SR will not result in 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 PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY SR 3.0.4 (continued)

However, in certain circumstances, failing to meet an SR will not result in 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 reql:'ired 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

PPL Rev. 3 ECCS Instrumentation B 3.3.5.1 B 3.3 INSTRUMENTATION B 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation BASES BACKGROUND The purpose of the ECCS instrumentation is to initiate appropriate responses from the systems to ensure that the fuel is adequately cooled in the event of a design basis accident or transient.

For most anticipated operational occurrences and Design Basis Accidents (DBAs), a wide range of dependent and independent parameters are monitored.

The ECCS instrumentation actuates core spray (CS), low pressure coolant injection (LPCI), high pressure coolant injection (HPCI), Automatic Depressurization System (ADS), the diesel generators (DGs) and other features described in the DG background. The equipment involved with each of these systems with exception of the DGs and other features, is described in the Bases for LCO 3.5.1, "ECCS-Operating."

Core Spray System The CS System may be initiated by either automatic or manual means.

Automatic initiation occurs for conditions of Reactor Vessel Water Level Low, Low, Low, Level 1 or Drywell Pressure - High concurrent with Reactor Pressure - Low. Each of these diverse variables is monitored by four redundant instruments. The initiation logic for one CS loop is arranged in a one-out-of-two-twice network using level and pressure instruments which will generate a signal when:

(1) both level sensors are tripped, or (2) two high drywell pressure sensors and two low reactor vessel pressure sensors are tripped, or (3) a combination of one channel of level sensor and one of the other channel of high drywell pressure sensor together with its associated low reactor vessel pressure sensor (i.e. Channel A level sensor and Channel C high drywell and low reactor vessel pressure sensor).

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.3-101 Revision 0 B 3.3 B 3.3.5.1 BASES INSTRUMENTATION Emergency Core Cooling System (ECCS) Instrumentation PPL Rev. 3 ECCS Instrumentation B 3.3.

5.1 BACKGROUND

The purpose of the ECCS instrumentation is to initiate appropriate responses from the systems to ensure that the fuel is adequately cooled in the event of a design basis accident or transient.

For most anticipated operational occurrences and Design Basis Accidents (DBAs), a wide range of dependent and independent parameters are monitored.

The ECCS instrumentation actuates core spray (CS), low pressure coolant injection (LPCI), high pressure coolant injection (HPCI), Automatic Depressurization System (ADS), the diesel generators (DGs) and other features described in the DG background. The equipment involved with each of these systems with exception of the DGs and other features, is described in the Bases for LCO 3.5.1, "ECCS-Operating."

Core Spray System The CS System may be initiated by either automatic or manual means.

Automatic initiation occurs for conditions of Reactor Vessel Water Level Low, Low, Low, Level 1 or Drywell Pressure - High concurrent with Reactor Pressure - Low. Each of these diverse variables is monitored by four redundant instruments. The initiation logic for one CS loop is arranged in a one-out-of-two-twice network using level and pressure instruments which will generate a signal when:

(1 )

(2)

(3)

SUSQUEHANNA - UNIT 1 both level sensors are tripped, or two high drywell pressure sensors and two low reactor vessel pressure sensors are tripped, or a combination of one channel of level sensor and one of the other channel of high drywell pressure sensor together with its associated low reactor vessel pressure sensor (i.e. Channel A level sensor and Channel C high drywell and low reactor vessel pressure sensor).

(continued)

TS / B 3.3-101 Revision 0

PPL Rev. 3 ECCS Instrumentation B 3.3.5.1 BASES BACKGROUND Core Spray System (continued)

Once an initiation signal is received by the CS control circuitry, the signal is sealed in until manually reset.

The logic can also be initiated by use of a manual push button (one push button per subsystem). Upon receipt of an initiation signal, the CS pumps are started 15 seconds after initiation signal if normal offsite power is available and 10.5 seconds after diesel generator power is available.

The CS test line isolation valve, which is also a primary containment isolation valve (PCIV), is closed on a CS initiation signal to allow full system flow assumed in the accident analyses and maintain primary containment isolated.

The CS System also monitors the pressure in the reactor to ensure that, before the injection valves open, the reactor pressure has fallen to a value below the CS System's maximum design pressure.. The variable is monitored by four redundant instruments. The instrument outputs are connected to relays whose contacts are arranged in a one-out-of-two taken twice logic.

Low Pressure Coolant Iniection System The LPCI is an operating mode of the Residual Heat Removal (RHR)

System, with two LPCI subsystems. The LPCI subsystems may be initiated by automatic or manual means. Automatic initiation occurs for conditions of Reactor Vessel Water Level Low, Low, Low, Level 1 or Drywell Pressure - High concurrent with Reactor Pressure - Low. Each of these diverse variables is monitored by four instruments in two divisions.

Each division is arranged in a one-out-of-two-twice network using level and pressure instruments which will generate a signal when:

(1) both level sensors are tripped, or (2) two high drywell pressure sensors and two low reactor vessel pressure sensors are tripped, or (3) a combination of one channel level sensor and one of the other channel of high drywell pressure sensor together with its associated low reactor vessel pressure sensor.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.3-102 Revision 0 BASES BACKGROUND Core Spray System (continued)

PPL Rev. 3 ECCS Instrumentation B 3.3.5.1 Once an initiation signal is received by the CS control circuitry, the signal is sealed in until manually reset.

The logic can also be initiated by use of a manual push button (one push button per subsystem). Upon receipt of an initiation signal, the CS pumps are started 15 seconds after initiation signal if normal offsite power is available and 10.5 seconds after diesel generator power is available.

The CS test line isolation valve, which is also a primary containment isolation valve (PCIV), is closed on a CS initiation signal to allow full system flow assumed in the accident analyses and maintain primary containment isolated.

The CS System also monitors the pressure in the reactor to ensure that, before the injection valves open, the reactor pressure has fallen to a value below the CS System's maximum design pressure. The variable is monitored by four redundant instruments. The instrument outputs are connected to relays whose contacts are arranged in a one-out-of-two taken twice logic.

Low Pressure Coolant Injection System The LPCI is an operating mode of the Residual Heat Removal (RHR)

System, with two LPCI subsystems. The LPCI subsystems may be initiated by automatic or manual means. Automatic initiation occurs for conditions of Reactor Vessel Water Level Low, Low, Low, Level 1 or Drywell Pressure - High concurrent with Reactor Pressure - Low. Each of these diverse variables is monitored by four instruments in two divisions.

Each division is arranged in a one-out-of-two-twice network using level and pressure instruments which will generate a signal when:

(1) both level sensors are tripped, or (2) two high drywell pressure sensors and two low reactor vessel pressure sensors are tripped, or (3) a combination of one channel level sensor and one of the other channel of high drywell pressure sensor together with its associated low reactor vessel pressure sensor.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.3-102 Revision 0

PPL Rev. 3 ECCS Instrumentation B 3.3.5.1 BASES BACKGROUND Low Pressure Coolant Iniection System (continued)

(i.e. Channel A level sensor and Channel C high drywell and low reactor vessel pressure sensor.).

The initiation logic is cross connected between divisions (i.e., either start signal will start all four pumps and open both loop's injection valves).

Once an initiation signal is received by the LPCI control circuitry, the signal is sealed in until manually reset. The cross division start signals for the pumps affect both the opposite division's start logic and the pump's 4KV breaker start logic. The cross division start signal to the opposite division's start logic is for improved reliability. The cross division start signals to the pump's 4KV breaker start logic is needed to ensure specific control power failures do not prevent the start of an adequate number of LPCI pumps.

Upon receipt of an initiation signal, all LPCI pumps start after a 3 second time delay when normal AC power is lost and standby diesel generator power is available. If normal power is available, LPCI pumps A and B will start immediately and pumps C and D will start 7.0 seconds after initiation signal to limit loading of the offsite sources.

The RHR test line and spray line are also isolated on a LPCI initiation signal to allow the full system flow assumed in the accident analyses and for those valves which are also PCIVs maintain primary containment isolated.

The LPCI System monitors the pressure in the reactor to ensure that, before an injection valve opens, the reactor pressure has fallen to a value below the LPCI System's maximum design pressure. The variable is monitored by four redundant instruments. The instrument outputs are connected to relays whose contacts are arranged in a one-out-of-two taken twice logic.

Logic is provided to close the recirculation pump discharge valves to ensure that LPCI flow does not bypass the core when it injects into the recirculation lines. The logic consists of an initiation signal (Low reactor water level and high drywell pressure in a one out of two taken twice logic) from both divisions of LPCI instruments and a pressure permissive. The pressure variable is monitored by four redundant instruments.

(continued)

SUSQUEHANNA-UNIT 1 TS / B 3.3-103 Revision 0 BASES BACKGROUND Low Pressure Coolant Injection System (continued)

PPL Rev. 3 ECCS Instrumentation B 3.3.5.1 (i.e. Channel A level sensor and Channel C high drywell and low reactor vessel pressure sensor.).

The initiation logic is cross connected between divisions (i.e., either start Signal will start all four pumps and open both loop's injection valves).

Once an initiation signal is received by the LPCI control circuitry, the Signal is sealed in until manually reset. The cross division start signals for the pumps affect both the opposite division's start logic and the pump's 4KV breaker start logic. The cross division start signal to the opposite division's start logic is for improved reliability. The cross division start signals to the pump's 4KV breaker start logic is needed to ensure specific control power failures do not prevent the start of an adequate number of LPCI pumps.

Upon receipt of an initiation signal, all LPCI pumps start after a 3 second time delay when normal AC power is lost and standby diesel generator power is available. If normal power is available, LPCI pumps A and B will start immediately and pumps C and D will start 7.0 seconds after initiation signal to limit loading of the offsite sources.

The RHR test line and spray line are also isolated on a LPCI initiation signal to allow the full system flow assumed in the accident analyses and for those valves which are also PCIVs maintain primary containment isolated.

The LPCI System monitors the pressure in the reactor to ensure that, before an injection valve opens, the reactor pressure has fallen to a value below the LPCI System's maximum design pressure. The variable is monitored by four redundant instruments. The instrument outputs are connected to relays whose contacts are arranged in a one-out-of-two taken twice logic.

Logic is provided to close the recirculation pump discharge valves to ensure that LPCI flow does not bypass the core when it injects into the recirculation lines. The logic consists of an initiation signal (Low reactor water level and high drywell pressure in a one out of two taken twice logic) from both divisions of LPCI instruments and a pressure permissive. The pressure variable is monitored by four redundant instruments.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.3-103 Revision 0

PPL Rev. 3 ECCS Instrumentation B 3.3.5.1 BASES BACKGROUND Low Pressure Coolant Injection System (continued)

The instrument outputs are connected to relays whose contacts are arranged in a one-out-of-two taken twice logic.

Hiqh Pressure Coolant Iniection System The HPCI System may be initiated by either automatic or manual means.

Automatic initiation occurs for conditions of Reactor Vessel Water Level-Low Low, Level 2 or Drywell Pressure-High. Each of these variables is monitored by four redundant instruments. The instrument. outputs are connected to relays whose contacts are arranged in a one-out-of-two taken twice logic for each Function.

The HPCI System also monitors the water level in the condensate storage tank (CST). HPCI suction is normally maintained on the CST until it transfers to the suppression pool on low CST level or is manually transferred by the operator. Reactor grade water in the CST is the normal source. Upon receipt of a HPCI initiation signal, the CST suction valve is automatically signaled to open (it is normally in the open position) unless the suppression pool suction valve is open. If the water level in the CST falls to the level switch process setpoint value, an automatic suction transfer is initiated. The suppression pool suction valve receives a signal to open and in parallel, the CST suction valve receives a signal to close to complete the transfer. Two level switches are used to detect low water level in the CST. Either switch can cause the suppression pool suction valve to open and the CST suction valve to close.

The HPCI provides makeup water to the reactor until the reactor vessel water level reaches the Reactor Vessel Water Level-High, Level 8 trip, at which time the HPCI turbine trips, which causes the turbine's stop valve, minimum flow valve, the cooling water isolation valve, and the injection valve to close. The logic is two-out-of-two to provide high reliability of the HPCI System.

(continued)

SUSQUEHANNA - UNIT 1 TS / B 3.3-104 Revision 2 BASES BACKGROUND Low Pressure Coolant Injection System (continued)

PPL Rev. 3 ECCS Instrumentation B 3.3.5.1 The instrument outputs are connected to relays whose contacts are arranged in a one-out-of-two taken twice logic.

High Pressure Coolant Injection System The HPCI System may be initiated by either automatic or manual means.

Automatic initiation occurs for conditions of Reactor Vessel Water Level-Low Low, Level 2 or Drywell Pressure-High. Each of these variables is monitored by four redundant instruments. The instrument outputs are connected to relays whose contacts are arranged in a one-out-of-two taken twice logic for each Function.

The HPCI System also monitors the water level in the condensate storage tank (CST). HPCI suction is normally maintained on the CST until it transfers to the suppression pool on low CST level or is manually transferred by the operator. Reactor grade water in the CST is the normal source. Upon receipt of a HPCI initiation signal, the CST suction valve is automatically signaled to open (it is normally in the open position) unless the suppression pool suction valve is open. If the water level in the CST falls to the level switch process setpoint value, an automatic suction transfer is initiated. The suppression pool suction valve receives a signal to open and in parallel, the CST suction valve receives a signal to close to complete the transfer. Two level switches are used to detect low water level in the CST. Either switch can cause the suppression pool suction valve to open and the CST suction valve to close.

The H PCI provides makeup water to the reactor until the reactor vessel water level reaches the Reactor Vessel Water Level-High, Level 8 trip, at which time the HPCI turbine trips, which causes the turbine's stop valve, minimum flow valve, the cooling water isolation valve, and the injection valve to close. The logic is two-out-of-two to provide high reliability of the HPCI System.

( contif1ued)

SUSQUEHANNA - UNIT 1 TS / B 3.3-104 Revision 2

PPL Rev. 3 ECCS Instrumentation B 3.3.5.1 BASES BACKGROUND Higqh Pressure Coolant Injection System (continued)

The HPCI System automatically restarts if a Reactor Vessel Water Level-Low Low, Level 2 signal is subsequently received.

Automatic Depressurization System The ADS may be initiated by either automatic or manual means.

Automatic initiation occurs when signals indicating Reactor Vessel Water Level-Low Low Low, Level 1; Drywell Pressure-High or ADS Drywell Bypass.Actuation Timer; confirmed Reactor Vessel Water Level-Low, Level 3; and CS or LPCI Pump Discharge Pressure-High are all present and the ADS Initiation Timer has timed out. There are two instruments each for Reactor Vessel Water Level-Low Low Low, Level I and Drywell Pressure-High, and one instrument for confirmed Reactor Vessel Water Level-Low, Level 3 in each of the two ADS trip systems. Each of these instruments drives a relay whose contacts form the initiation logic.

Each ADS trip system includes a time delay between satisfying the initiation logic and the actuation of the ADS valves. The ADS Initiation Timer time delay setpoint is chosen to be long enough that the HPCI system has sufficient operating time to recover to a level above Level 1, yet not so long that the LPCI and CS Systems are unable to adequately cool the fuel if the HPCI fails to maintain that level. An alarm in the control room is annunciated when either of the timers is timing. Resetting the ADS initiation signals resets the ADS Initiation Timers. The ADS also monitors the discharge pressures of the four LPCI pumps and the four CS pumps. Each ADS trip system includes two discharge pressure permissive instruments from both CS pumps in the division and from either of the two LPCI pumps in the associated Division (i.e., Division 1 LPCI pumps A or C input to ADS trip system A, and Division 2 LPCI pumps B or D input to ADS trip system B). The signals are used as a permissive for ADS actuation, indicating that there is a source of core coolant available once the ADS has depressurized the vessel. With both CS pumps in a division or one of the LPCI pumps operating sufficient flow is available to permit automatic depressurization.

The ADS logic in each trip system is arranged in two strings. Each string has a contact from each of the following variables: Reactor Vessel Water Level-Low Low. Low, Level 1; Drywell (continued)

SUSQUEHANNA - UNIT 1 TS / B] 3.3-105 Revision 0 BASES BACKGROUND High Pressure Coolant Injection System (continued)

PPL Rev. 3 ECCS Instrumentation B 3.3.5.1 The HPCI System automatically restarts if a Reactor Vessel Water Level-Low Low, Level 2 signal is subsequently received.

Automatic Depressurization System The ADS may be initiated by either automatic or manual means.

Automatic initiation occurs when signals indicating Reactor Vessel Water Level-Low Low Low, Level 1; Drywell Pressure-High or ADS Drywell Bypass'Actuation Timer; confirmed Reactor Vessel Water Level-Low, Level 3; and CS or LPCI Pump Discharge Pressure-High are all present and the ADS Initiation Timer has timed out. There are two instruments each for Reactor Vessel Water Level-Low Low Low, Level 1 and Drywell Pressure-High, and one instrument for confirmed React.or Vessel Water Level-Low, Level 3 in each of the two ADS trip systems. Each of these instruments drives a relay whose contacts form the initiation logic.

Each ADS trip system includes a time delay between satisfying the initiation logic and the actuation of the ADS valves. The ADS Initiation Timer time delay setpoint is chosen to be long enough that the HPCI system has sufficient operating time to recover to a level above Level 1, yet not so long that the LPCI and CS Systems are unable to adequately cool the fuel if the HPCI fails to maintain that level. An alarm in the control room is annunciated when either of the timers is timing. Resetting the ADS initiation signals resets the ADS Initiation Timers. The ADS also monitors the discharge pressures of the four LPCI pumps and the four CS pumps. Each ADS trip system includes two discharge pressure permissive instruments from both CS pumps in the division and from either of the two LPCI pumps in the associated Division (Le., Division 1 LPCI pumps A or C input to ADS trip system A, and Division 2 LPCI pumps B or D input to ADS trip system B). The signals are used as a permissive for ADS actuation, indicating that there is a source of core coolant available once the ADS has depressurized the vessel. With both CS pumps in a division or one of the LPCI pumps operating sufficient flow is available to permit automatic depressurization.

The ADS logic in each trip system is arranged in two strings. Each string has a contact from each of the following variables: Reactor Vessel Water Level-Low Low. Low, Level 1; Drywell (continued)

SUSQUEHANNA - UNIT 1 TS / B 3.3-105 Revision 0

PPL Rev. 3 ECCS Instrumentation B 3.3.5.1 BASES BACKGROUND Automatic Depressurization System (continued)

Pressure-High; or Drywell Pressure Bypass Actuation Timer. One of the two strings in each trip system must also have a confirmed Reactor Vessel Water Level-Low, Level 3. All contacts in both logic strings must close, the ADS initiation timer must time out, and a loop of CS or LPCI pump discharge pressure signal must be present to initiate an ADS trip system.

Either the A or B trip system will cause all the ADS relief valves to open.

Once the Drywell Pressure-High signal, the ADS Drywell Pressure Bypass Actuation Timer, or the ADS initiation signal is present, it is individually sealed in until manually reset.

Manual inhibit switches are provided in the control room for the ADS; however, their function is not required for ADS OPERABILITY (provided ADS is not inhibited when required to be OPERABLE).

Diesel Generators and Other Initiated Features The DGs may be initiated by either automatic or manual means.

Automatic initiation occurs for conditions of Reactor Vessel Water Level-Low Low Low, Level 1 or Drywell Pressure-High. The DGs are also initiated upon loss of voltage signals (Refer to the Bases for LCO 3.3.8.1, "Loss of Power (LOP) Instrumentation," for a discussion of these signals.)

The initiation logic is arranged in a one-out-of-two-twice network using level and pressure instruments which will generate a signal when:

(1) both level sensors are tripped, or (2) both high drywell pressure sensors are tripped, or (3) a combination of one level sensor and one high drywell pressure sensor is tripped.

DGs A and B receive their initiation signal from CS system initiation logic Division I and Division II respectively. DGs C and D receive their initiation signals from either LPCI systems initiation logic Division I or Division II.

The DGs can also be started manually from the control room and locally from the associated DG room. The DG initiation signal is a (continued)

SUSQUEHANNA - UNIT 1 TS / B 3.3-106 Revision 0 BASES BACKGROUND Automatic Depressurization System (continued)

PPL Rev. 3 ECCS Instrumentation B 3.3.5.1 Pressure-High; or Drywell Pressure Bypass Actuation Timer. One of the two strings in each trip system must also have a confirmed Reactor Vessel Water Level-Low, Level 3. All contacts in both logic strings must close, the ADS initiation timer must time out, and a loop of CS or LPCI pump discharge pressure signal must be present to initiate an ADS trip system.