ML092610708
| ML092610708 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/21/2009 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML092610708 (81) | |
Text
Iq IL Sep. 08, 2009 Sep. 08, 2009
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....... M 7l 08/21/2009 08/21/2009 LOCATION:
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SSES SSES MANUALMANTJA-L Manual Name: TSB1 Manual
Title:
Title: TECHNICAL TECHNICAL SPECIFICATION SPECIFICATION BASES UNIT 1 MANUAL MANUAL Table Table Of Contents Contents Issue Date:
Issue Date: 08/20/2009 08/20/2009 Procedure Procedure Name Rev Rev Issue Date Change ID Change Number Change Number TEXT LOES LOES 9393 08/20/2009 08/20/2009
Title:
Title: LIST OF EFFECTIVE EFFECTIVE SECTIONS SECTIONS TEXT TOC 1717 08/20/2009
Title:
Title: TABLETABLE OF CONTENTS CONTENTS TEXT TEXT 2.1.1 5 05/06/2009
\X,
Title:
Title: SAFETY LIMITS (SLS) (SLS) REACTOR REACTOR CORE SLS "N/*
TEXT TEXT 2.1.2 1 10/04/2007,
Title:
SAFETY LIMITS (SLS) REACTOR COOLANTi'-SYSTM-'(RCS) PRESSURE S TEXT 3. 0 TEXT 3.0 33 ,'08/20/2,0009/
Title:
LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY TEXT TEXT 3.1.1 1i 04/18/2006
Title:
REACTIVITY COTROLSYSTE- SHUTDOWN MARGIN (SDM)
TEXT TEXT 3.1.2 'N . 11/15/2002 11/15/2002
Title:
REACTIVITY CONTROL\SYSTEMS REACTIVITY ANOMALIES TEXT 3.1.3 f <"" >... 2 01119/2009 01/19/2009
Title:
REACTIV ITY) CONTROL SYSTEMS CONTROL ROD OPERABILITY
\ /
TEXT 3. 1.4 3.1.4 4 01/30/2009
Title:
Title: REACTIVITY REACTIVITY CONTROL SYSTEMS CONTROL CONTROL ROD SCRAM TIMES TIMES TEXT 3.1.53.1.5 1 07/06/2005 07/06/2005
Title:
Title: REACTIVITY REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS SYSTEMS CONTROL ACCUMULATORS TEXT 3.1.63.1.6 2 04/18/2006 ie
Title:
Title: REACTIVITY REACTIVITY CONTROL SYSTEMS SYSTEMS ROD PATTERN PATTERN CONTROL CONTROL Report Date: 08/20/09 Pagel Page .11 of of .ll88 Report Date: 08/20/09 08/20/09
SSES SSES MANUAL MANUAL Manual Name:
Manual Name: TSB1 TSB1 Manual
Title:
Manual
Title:
TECHNICAL SPECIFICATION TECHNICAL SPECIFICATION BASES BASES UNIT 11 MANUAL MANUAL TEXT 3.1.73.1.7 33 04/23/2008 04/23/2008
Title:
Title: REACTIVITY CONTROL REACTIVITY CONTROL SYSTEMS SYSTEMS STANDBY STANDBY LIQUID CONTROL (SLC) (SLC) SYSTEM SYSTEM 3.1.8 TEXT 3.1.8 33 05/06/2009
Title:
Title: REACTIVITY CONTROL REACTIVITY CONTROL SYSTEMS SYSTEMS SCRAM SCRAM DISCHARGE VOLUME VOLUME (SDV) (SDV) VENT AND DRAIN DRAIN VALVES VALVES
/' "-
/ /~-" "
TEXT 3.2.1 TEXT 3. 2. 1 2 04/23/2008 //. \ -,
- \
Title:
POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR'HEAT. /"~
/Tt e ~" ,W D\ }
GENERATION )
Title:
POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR/HEAT<GENERATION ,/ / ',:, /'
RATE (APLHGR)
(APLHGR)
~.~/)/:~>/
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3.2 2 TEXT 3.2.2
Title:
Title: POWER DISTRIBUTION LIMITS MINIMUM CRITICAL 33 05/06/2009 CRITICAL POWER"RATIO
/\
/'. "/
POWER~RATIO (MCPR)
(MCPR)
\
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3.2.3 TEXT 3.2.3 2 04/2;"l2Q~~<
04/2312008 "',<;)
Title:
Title: POWER DISTRIBUTION LIMITS LINEAR LINEAR HEAT HEAT-GENERATION GENERATION RATE (LHGR) (LHGR)
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TEXT 3.3.1.1 3.3.1.1 44 {/ (~14/~~:,/2008
//o0423/2008
Title:
INSTRUMENTATION
//
REACTOR/-PROTECTIONW Ti tle: INSTRUMENTATION REACTOR/'PROTECTION) SYSTEM
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SYSTEM (RPS) (RPS) INSTRUMENTATION INSTRUMENTATION
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Title:
Ti 3 . 1. 2 INSTRUMENTATIO~Sj),U~~)G~
t1e, INSTRUMENTATION
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-SOURCE RANGE MONITOR C ""\ 01/19/2009 0 1 /19 /2 0 0 9 MONITOR (SRM) (SRM) INSTRUMENTATION INSTRUMENTATION TEXT 3.3.2;11 TEXT 3.3.2.
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Title:
Ti tle: INSTRUMENTATION',CONTROL INSTRUMENTA'lUON\ ROD BLOCKBLOCK INSTRUMENTATION
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TEXT TEXT 3.3.2.2
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Title:
Title:
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INSTRUMENTATION INSTRUMENTATION
)S--' FEEDWATER FEEDWATER MAIN 11 04/23/2008 04/23/2008 MAIN TURBINETURBINE HIGH HIGH WATER WATER LEVEL LEVEL TRIP TRIP INSTRUMENTATION INSTRUMENTATION
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TEXT TEXT 3.3.3.1 3.3.3.1 88 10/27/2008 10/27/2008
Title:
Title: INSTRUMENTATION INSTRUMENTATION POST ACCIDENT ACCIDENT MONITORING MONITORING (PAM) (PAM) INSTRUMENTATION INSTRUMENTATION TEXT TEXT 3.3.3.2 3.3.3.2 11 04/18/2005 04/18/2005
Title:
Title: INSTRUMENTATION INSTRUMENTATION REMOTE REMOTE SHUTDOWN SHUTDOWN SYSTEM TEXT TEXT 3.3.4.1 3.3.4.1 11 04/23/2008 04/23/2008
Title:
Title: INSTRUMENTATION INSTRUMENTATION END END OF OF CYCLECYCLE RECIRCULATION RECIRCULATION PUMP PUMP TRIPTRIP (EOC-RPT)(EOC-RPT) INSTRUMENTATION INSTRUMENTATION Page Page 22. of of .a8 Report Date:
Report Date: 08/20/09 08/20/09
SSES SSES MANUAL MANUAL Manual Name:
Manual Name: TSB1 TSB1 Manual
Title:
Manual
Title:
TECHNICAL TECHNICAL SPECIFICATION SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.3.4.2 o0 11/15/2002
Title:
Title: INSTRUMENTATION ANTICIPATED' TRANSIENT INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT WITHOUT SCRAM RECIRCULATION RECIRCULATION PUMP TRIP PUMP TRIP (ATWS-RPT) INSTRUMENTATION (ATWS-RPT) INSTRUMENTATION TEXT 3.3.5.1 33 08/20/2009
Title:
Title: INSTRUMENTATION EMERGENCY INSTRUMENTATION EMERGENCY CORE COOLING COOLING SYSTEM SYSTEM (ECCS) (ECCS) INSTRUMENTATION
/;~~'\
TEXT 3.3.5.2 3.3.5.2 o0 11/15/2002 11/15/2002 /<'",- ~ ) }
Title:
Title: INSTRUMENTATION REACTOR CORE ISOLATION ISOLATION COOLING/(,F-CIC,), COOLING/`(RCIC,)\ SY'STEM SYSTEM INSTRUMENTATION
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Title:
Title: INSTRUMENTATION PRIMARY INSTRUMENTATION CONTAINMENT ISOLATION PRIMARY CONTAINMENT
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INSTRUMENTATION INSTRUMENTATION / ^/
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TEXT 3,3.8.1 TEXT 3.3.8.1 <~ 2.,,- 2,\ ",",
" 12/17/2007
Title:
INSTRUMENTATION- ,LOSS OF POWER
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Title:
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TEXT 3.3.8.2 /'. ," ""< \ "-"'.) 00 11/15/2002
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Title:
Title: INSTR~,;\A~Z~~~EACTOR INSTRUMENTATIONT REACTOR PROTECTIONPROTECTION SYSTEM (RPS) (RPS) ELECTRIC POWER MONITORING
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TEXT TEXT 3. 3.4.1 4 .1 \ "'0 ) 3 04/12/2006 04/12/2006
Title:
Title: REACTbR~~90LANT REACTOR COOLANT SYSTEM SYSTEM (RCS) RECIRCULATION LOOPS OPERATING (RCS) RECIRCULATION TEXT TEXT 3.4.2 1 04/23/2008 04/23/2008
Title:
Title: REACTOR COOLANT SYSTEM REACTOR SYSTEM (RCS) (RCS) JET PUMPS PUMPS TEXT 3.4.3 2 04/23/2008
Title:
Title: REACTOR REACTOR COOLANT SYSTEM SYSTEM RCS SAFETY RELIEF VALVES S/RVS TEXT 3.4.4 0 11/15/2002
Title:
Title: REACTOR COOLANT SYSTEM REACTOR SYSTEM (RCS) (RCS) RCS OPERATIONAL LEAKAGE LEAKAGE Page .1 3 of ll.
8 Report Date:
Report Date: 08/20/09 08/20/09
SSES MANUAL MANUAL Manual Name: TSB1 TSB1 Manual
Title:
Title: TECHNICAL SPECIFICATION SPECIFICATION BASES UNIT 11 MANUAL MANUAL TEXT 3.4.5 TEXT 3. 4.5 1 01/16/2006
Title:
Title: REACTOR COOLANT SYSTEM (RCS) (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE TEXT 3.4.6 TEXT 2 08/20/2009
Title:
Title: REACTOR COOLANT SYSTEM (RCS) (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION INSTRUMENTATION
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/>0412'3/2008
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Title:
REACTOR COOLANT-SYSTEM COOLANT- -SYSTEM, (RCS)
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Title:
REACTOR (RCS) REACTOR STEAM DOME DOME PRESSURE TEXT 3.5.13. 5.1
(;:,c~';S:,;~
"N h 2 01/16/2006 01/16/2006
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Title:
EMERGENCYX CORE COOLING SYSTEMS EMERGENCY\C0RECOOLING SYSTEMS (ECCS) (ECCS) AND REACTOR REACTOR CORE ISOLATION COOLING COOLING (RCIC)
(RCIC)
/----.,,~ '\ -,~/ /
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/ (" /" ", _ _ ~~J TEXT 3.5.2 !, < \ 0 11/15/2002 TEXT 3.5.2 \ -/ I
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Title:
EMERGENCY
Title:
EMERGEN~¥/CORE CORE COOLING COOLING SYSTEMS SYSTEMS (ECCS) (ECCS) AND REACTOR REACTOR CORE ISOLATION COOLING COOLING (RCIC)
(RCIC)
SYSTEM ECCS SYSTEM ECCS - SHUTDOWN - SHUTDOWN TEXT TEXT 3.5.33.5.3 1 04/18/2005 04/18/2005
Title:
Title: EMERGENCY EMERGENCY CORE CORE COOLING COOLING SYSTEMS SYSTEMS (ECCS) AND REACTOR (ECCS) REACTOR CORE ISOLATION COOLING COOLING (RCIC)
(RCIC)
SYSTEM SYSTEM RCIC SYSTEM TEXT 3.6.1.1 3.6.1.1 33 04/23/2008 04/23/2008
Title:
Title: CONTAINMENT CONTAINMENT SYSTEMS SYSTEMS PRIMARY PRIMARY CONTAINMENT CONTAINMENT TEXT 3.6.1.2 3.6.1.2 11 04/23/2008 04/23/2008
Title:
Title: CONTAINMENT CONTAINMENT SYSTEMS SYSTEMS PRIMARY PRIMARY CONTAINMENT CONTAINMENT AIR LOCK LOCK Report Date: 08/20/09 Page4 Page .4.
Page 4 of of .a
~8 Report Date:
Report Date: 08/20/09 08/20/09
SSES SSES MANUAL MANUAL Manual Name:
Manual TSB1 Manual Manual
Title:
Title: TECHNICAL SPECIFICATION SPECIFICATION BASES UNIT 1 MANUAL MANUAL TEXT 3.
TEXT 6 . 1. 3 3.6.1.3 8 04/23/2008 04/23/2008'
Title:
Title: CONTAINMENT CONTAINMENT SYSTEMS SYSTEMS PRIMARYPRIMARY CONTAINMENTCONTAINMENT ISOLATION ISOLATION VALVES (PCIVS) (PCIVS)
LDCN 3092 TEXT 3.6.1.4 3.6.1.4 11 04/23/2008
Title:
Title: CONTAINMENT SYSTEMS CONTAINMENT CONTAINMENT CONTAINMENT PRESSURE
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Title:
Title: CONTAINMENT CONTAINMENT SYSTEMS SYSTEMS DRYWELLDRYWELL AIR FLOW SYSTEM SYSTEM TEXT TEXT 3.6.3.3 0 11/15/2002 11/15./2002
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Title:
Title: CONTAINMENT CONTAINMENT SYSTEMS PRIMARY CONTAINMENT CONTAINMENT OXYGEN OXYGEN CONCENTRATION CONCENTRATION TEXT TEXT 3.6.4.1 77 10/04/2007
Title:
Title: CONTAINMENT CONTAINMENT SYSTEMS SYSTEMS SECONDARY CONTAINMENT CONTAINMENT Report Date: 08/20/09 Pages Page 5
.5. of ~
of of8 .li Report Date:
Report 08/20/09 08/20/09
SSES MANUAL MANUAL Manual Manual Name: TSB1 TSB1
Title:
Manual
Title:
SPECIFICATION BASES TECHNICAL SPECIFICATION BASES UNIT 11 MANUAL TEXT 3.6.4.2 2 01/03/2005
Title:
Title: CONTAINMENT SYSTEMS CONTAINMENT SYSTEMS SECONDARY CONTAINMENT CONTAINMENT ISOLATION VALVES (SCIVS) (SCIVS)
TEXT 3.6.4.3 44 09/21/2006
Title:
Title: CONTAINMENT SYSTEMS SYSTEMS STANDBY GAS TREATMENT TREATMENT (SGT) (SGT) SYSTEM SYSTEM
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Title: PLANT SYSTEMS SYSTEMS EMERGENCY EMERGENCY SERVICE SERVICE WATER (ESW,) (ESW) SYSTEM SYSTEM
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Title:
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Ti tIe: PLANT PLANT SYSTEMS SYSTEMS CONTROL CONTROL .F-OpM, ROOMFLOOR FLOOR",,(WOLING COOLING SYSTEM
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TEXT 3.7.5 3.7.5 {"':::: J\. '> 10/04/2007 1">10/04/2007
Title:
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Title:
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TEXT 3.7.7 .7N PLANT (r J \f\
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TEXT 3. 7 . 7 1 10/04/2007
Title:
Title: PLANT SYSTEMS SPENT PLANT SYSTEMS SPENT FUEL FUEL STORAGE POOL POOL WATER WATER LEVEL LEVEL TEXT 3.7.8 3.7.8 0 04/23/2008
.04/23/2008
Title:
Title: PLANT PLANT SYSTEMS SYSTEMS TEXT TEXT 3.8.1 3.8.1 6 05/06/2009 05/06/2009
Title:
Title: ELECTRICAL ELECTRICAL POV POWERNER SYSTEMS SYSTEMS AC SOURCES SOURCES - OPERATING OPERATING TEXT 3.8.2 TEXT 3.8.2 0 11/15/2002 11/15/2002
Title:
Title: ELECTRICAL ELECTRICAL POV POWER SYSTEMS AC SOURCES lER SYSTEMS SOURCES - SHUTDOWN SHUTDOWN Report Date: 08/20/09 Page Page56 Page Q of 8 of of8 .a Report Report Date:
Date: 08/20/09 08/20/09
SSES MANUAL MANJAL Manual Name: TSB1 Manual
Title:
Manual
Title:
TECHNICAL SPECIFICATION SPECIFICATION BASES UNIT 11 MANUAL MANUAL
- 3. 8.3 TEXT 3.8.3 1 04/23/2008
Title:
Title: ELECTRICAL POWER SYSTEMS ELECTRICAL SYSTEMS DIESEL FUEL OIL, OIL, LUBE OIL, OIL, AND STARTING STARTING A*IR AIR 3.8.4 TEXT 3.8.4 33 01/19/2009
Title:
Title: ELECTRICAL POWER SYSTEMS SYSTEMS DC SOURCES SOURCES -- OPERATING
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- Page8.a Page ~ of of of .a8 Report Date: 08/20/09 Report Date: 08/20/09
TABLE TA8LE OF CONTENTS CONTENTS (TECHNICAL SPECIFICATIONS SPECIFICATIONS BASES) 8ASES)
- B2.0 82.0 B 2 .1.1 82.1.1 B2.1.2 82.1.2 SA FETY LIM SAFETY ITS (S LIMITS Ls) ..................................................................................
(SLs)
R eactor Core Reactor C ore SLs S Ls ...........................................................................
Reactor Coolant System (RCS) Pressure Pressure SL ...........................
........................... TS/82.0-7 B2.0-1 82.0-1 B2 .0-1 82.0-1 TS/B2.0-7 B3.0 83.0 LIMITING CONDITION FOR OPERATION LIMITING CONDITION OPERATION (LCO) APPLlCA8IL1TY APPLICABILITY ........ ........ TS/83.0-1 TS/B3.0-1 B3.0 83.0 SURVEILLANCE REQUIREMENT SURVEILLANCE REQUIREMENT (SR) APPLICABILITY APPLlCA81L1TY ...................... TS/B3.0-10
...................... TS/83.0-10 B3.1 83.1 REACTIVITY CONTROL SySTEMS REACTIVITY ................................................... ~ .. B3.1-1 SYSTEMS ................................................. 83.1-1 B3.1.1 83.1.1 Shutdow n M Shutdown (S DM ) ................................................................
argin (SDM)
Margin ................................................................ B3.1-1 83.1-1 B3.1.2 83.1.2 Reactivity Anom Anomaliesalies ......................................................................
.................................................................. B3. 1-8 83.1-8 B3.1.3 83.1.3 Control Rod OPERABILITY ............................................................
OPERA81L1TY ............................................................ B3.1-13 83.1-13 B3.1.4 83.1.4 Control Control Rod Scram ........................................................
Scram Times ........................................................ TS/B3.1-22 TS/83.1-22 B3.1.5 83.1.5 Control Rod Scram Accumulators ............................................
Accumulators ............................................ TS/B3.1-29 TS/83.1-29 B3.1.6 83.1.6 Rod Pattern C ontrol ..................................................................
Pattern Contro!.. ................................................................ TS/83.1-34TS/B3.1-34 B3.1.7 83.1.7 ......................................
Standby Liquid Control (SLC) System ...................................... TS/B3.1-39 TS/83.1-39 B3.1.8 83.1.8 Scram Discharge Volume Volume (SDV) Vent and Drain Valves .......... ......... TS/83.1-47 TS/B3.1-47 B3.2 83.2 DISTRIBUTION LIMITS ...................................................
POWER DISTRI8UTION ................................................... TS/B3.2-1 TS/83.2-1 B3.2.1 83.2.1 Average Average Planar Linear Heat Generation Rate (APLHGR) ........
Heat Generation ........ TS/83.2-1 TS/B3.2-1 B3.2.2 83.2.2 Minimum Critical Power Ratio (MCPR) (MCPR) ..................................... TS/B3.2-5
..................................... TS/83.2-5 B3.2.3 83.2.3 Linear Heat Generation Generation Rate (LHGR) ....................................... TS/B3.2-10
....................................... TS/83.2-10 B3.3 83.3 INSTRUMENTATION .....................................................................
INSTRUMENTATION ..................................................................... TS/83.3-1 TS/B3.3-1
- B3.3.1.1 83.3.1.1 B3.3.1.2 83.3.1.2 B3.3.2.1 83.3.2.1 B3.3.2.2 83.3.2.2 B3.3.3.1 83.3.3.1 Reactor Protection Protection System (RPS) Instrumentation Source Range Monitor Control Control Rod Block Monitor (SRM) Instrumentation Feedwater - Main Turbine High Water Feedwater Instrumentation Accident Monitoring Post Accident Monitoring (PAM)
Instrumentation ...................
................... TS/83.3-1 Instrumentation .........................
TS/B3.3-1 TS/B3.3-35
......................... TS/83.3-35 Instrumentation ...........................................
810ck Instrumentation TS/B3.3-44
........................................... TS/83.3-44 Water Level Trip (PAM) Instrumentation Trip
......................................................................... B Instrum entation .........................................................................
Instrumentation .....................
3.3-55 83.3-55
..................... TS/83.3-64 TS/B3.3-64 B3.3.3.2 83.3.3.2 Remote Shutdown .............................................................
Shutdown System ............................................................. B3.3-76 83.3-76 B3.3.4.1 83.3.4.1 Recirculation Pump Trip (EOC-RPT)
End of Cycle Recirculation Instrum e ntatio n .........................................................................
Instrumentation ......................................................................... B 3 .3-8 1 83.3-81 B3.3.4.2 83.3.4.2 Anticipated Transient Without Anticipated Without Scram Recirculation Recirculation Pump Trip (A (ATWS-RPT) Instrumentation ..............................
TWS-RPT) Instrumentation .............................. TS/B3.3-92 TS/83.3-92 B3.3.5.1 83.3.5.1 Emergency Core Cooling System (ECCS)
Emergency Instrum entation ...................................................................
Instrumentation ................................................................... TS/B3.3-1Q01 TS/83.3-101 B3.3.5.2 83.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrum .........................................................................
e ntation .........................................................................
Instrumentation B3.3-135 83.3-135 B3.3.6.1 83.3.6.1 Containment Isolation Instrumentation Primary Containment Instrumentation .............................. B3.3-147
.............................. 83.3-147 B3.3.6.2 83.3.6.2 Secondary Secondary Containment Isolation Instrumentation ...................
Instrumentation ................... TS/83.3-180 TS/B3.3-180 B3.3.7.1 83.3.7.1 Control Emergency Outside Air Supply (CREOAS)
Control Room Emergency System Instrumentation ......................................................
Instrumentation ...................................................... TS/B3. 3-192 TS/83.3-192
- SUSQUEHANNA - UNIT SUSQUEHANNA UNIT 1 TS 18 / B TOC TOC-1 -1
((continued) continued)
Revision 17
TA8LE OF CONTENTS (TECHNICAL SPECIFICATIONS TABLE SPECIFICATIONS 8ASES) BASES)
- B3.3 83.3 B3.3.8.1 83.3.8.1 B3.3.8.2 83.3.8.2 INSTRUMENTATION (continued)
INSTRUMENTATION Instrumentation .......................................
Loss of Power (LOP) Instrumentation Reactor Protection System (RPS) Electric Power Reactor Power Mo n ito ring ................................................................................
Monitoring ................................................................................ 83.3-213 TS/B3.3-205
....................................... TS/83.3-205 B3 .3-2 13 B3.4 83.4 REACTOR REACTOR COOLANT COOLANT SYSTEM ...............................................
SYSTEM (RCS) ............................................... B3.4-1 83.4-1 B3.4.1 83.4.1 Recirculation Loops Operating Recirculation .......................................................
Operating ....................................................... B3.4-1 83.4-1 B 3 .4 .2 83.4.2 P um ps ......................................................................................
Jet Pumps ...................................................................................... B3 .4-10 83.4-10 B3.4.3 83.4.3 SafetylRelief Valves (S/RVs) ....................................................
Safety/Relief .................................................... TS/B3.4-15 TS/83.4-15 B3.4.4 83.4.4 Operational LEAKAGE RCS Operational ..........................................................
LEAKAGE .......................................................... B3.4-19 83.4-19 B3.4.5 83.4.5 RCS Pressure ................................. B3.4-24 Pressure Isolation Valve (PIV) Leakage ................................. 83.4-24 B3.4.6 83.4.6 Leakage Detection Instrumentation RCS Leakage TS/B3.4-30
.................................. TS/83.4-30 Instrumentation ..................................
B3.4.7 83.4.7 RGS RCS Specific ................................................................
Specific Activity ................................................................ TS/B3.4-35 TS/83.4-35 B3.4.8 83.4.8 Residual Heat Removal (RHR) (RHR) ShutdownShutdown Cooling Cooling System - Hot Shutdown ........................................................... B3.4-39 83.4-39 B3.4.9 83.4.9 Residual Heat Removal (RHR) (RHR) ShutdownShutdown Cooling Cooling System - Cold Shutdown .........................................................
......................................................... 83.4-44 B3.4-44 B3.4.10 83.4.10 RCS Pressure and Temperature Temperature (PIT) (P/T) Limits ........................... TS/B3.4-49
........................... TS/83.4-49 B3.4.11 83.4.11 Reactor Steam Dome Pressure Pressure ................................................ TS/B3.4-58
................................................ TS/83.4-58 B3.5 83.5 EMERGENCY EMERGENCY CORE COOLING COOLING SYSTEMS (ECCS) AND REACTOR REACTOR ISOLATION COOLING CORE ISOLATION COOLING (RCIC) SYSTEM ,.................................. B3.5-1
................................. 83.5-1 B3.5.1 83.5.1 EGCS ECC S - Operating .........................................................................
O perating ......................................................................... B3.5-1 83.5-1
- B3.5.2 83.5.2 B3.5.3 83.5.3 B3.6 83.6 B3.6.1.1 83.6.1.1 B3.6.1.2 83.6.1.2 ECCS - Shutdown EGCS R C IC System RCIC CONTAINMENT SySTEMS CONTAINMENT Primary Containment Shutdown .........................................................................
System ...........................................................................
SYSTEMS ...........................................................
Containment.................................................................
............................................................... TS/83.6-1 Containment Air Lock ........................................................
Primary Containment B3.5-19 83.5-19 TS/B3.5-25 TS/83.5-25 TS/B3.6-1 TS/83.6-1 TS/B3.6-1
........................................................ 83.6-7 B3.6-7 B3.6.1.3 83.6.1.3 Containment Isolation Valves (PCIVs) .........................
Primary Containment TS/B3.6-15
......................... TS/83.6-15 B3.6.1.4 83.6.1.4 Containment Pressure Containment ....................................................................
Pressure .................................................................... B3.6-41 83.6-41 B3.6.1.5 83.6.1.5 Drywell Air Temperature ...........................................................
Temperature ........................................................... TS/B3.6-44 TS/83.6-44 B3.6.1.6 83.6.1.6 Chamber-to-Drywell Vacuum 8reakers Suppression Chamber-to-Drywell Suppression Breakers ................ TS/B3.6-47
................ TS/83.6-47 B3.6.2,1 83.6.2.1 Suppression TS/B3.6-53
.................................. TS/83.6-53 Suppression Pool Average Temperature ..................................
B3.6.2.2 83.6.2.2 Suppression .......................................................
Suppression Pool Water Level ....................................................... B3.6-59 83.6-59 B3.6.2.3 83.6.2.3 Residual Heat Removal Removal (RHR) Suppression Suppression Pool C oo lin g .....................................................................................
Cooling ..................................................................................... B 3 .6-6 2 83.6-62 B3.6.2.4 83.6.2.4 Residual Heat Removal Removal (RHR) Suppression Suppression Pool Spray ................ B3.6-66 Spray ................ 83.6-66 B 3.6 .3.1 83.6.3.1 Not Used Not Used ..................................................................................
.................................................................................. T S /B3.6-70 TS/83.6-70 B3.6.3.2 83.6.3.2 Drywell Drywell Air Flow System ................................................................. B3.6-76
................................................................. 83.6-76 B3.6.3.3 83.6.3.3 Primary Containment Containment Oxygen Concentration ...............
Concentration .................................. B3.6-81 83.6-81 B3.6.4.1 83.6.4.1 Secondary Containment ...........................................................
Secondary Containment. .......................................................... TS/83.6-84 TS/B3.6-84 B3.6.4.2 83.6.4.2 Secondary Containment Isolation Secondary Isolation Valves Valves (SCIVs) .................... TS/B3.6-91
.................... TS/83.6-91 B3.6.4.3 83.6.4.3 Standby Gas Treatment TS/B3.6-101
................................... TS/83.6-101 Treatment (SGT) System ...................................
- SUSQUEHANNA SUSQU UNIT 1 EHAN NA - UNIT TS /1 B 8 TOC - 2 (continued)
Revision 17
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS TA8LE SPECIFICATIONS 8ASES) BASES)
- B3.7 83.7 B3.7.1 83.7.1 B3.7.2 83.7.2 PLANT SYSTEMS .........................................................................
Removal Service Water (RHRSW) System Residual Heat Removal*Service and the Ultimate Heat Sink (UHS) ......................................
Emergency Service Emergency TS/B3.7-1 TS/83.7-1
...................................... TS/83.7-1 TS/B3.7-1
................................ TS/83.7-7 Service Water (ESW) System ................................ TS/B3.7-7 B3.7.3 83.7.3 Control Room Emergency Emergency Outside Air Supply Supply (C REO AS) System .............................................................
(CREOAS) ............................................................. TS/B3.7-12 TS/83.7-12 B3.7.4 83.7.4 Control Room Floor Cooling ........................................
Cooling System ........................................ TS/B3.7-19 TS/83. 7-19 B3.7.5 83.7.5 ...........................................................
Main Condenser Offgas ........................................................... TS/B3.7-24 TS/83.7-24 B3.7.6 83.7.6 Main Turbine 8ypass Bypass System ...................................................
................................................... TS/B3.7-27 TS/83.7-27 B3.7.7 83.7.7 Spent Fuel Storage Pool Water Level ......................................
...................................... TS/83.7-31 TS/B3.7-31 B3.7.8 83.7.8 Main Turbine Pressure Regulation System ... .................. TS/B3.7-34
- .......................... TS/83.7-34 B3.8 83.8 ELECTRICAL POWER ELECTRICAL POWER SYSTEM ...................................................
................................................... TS/B3.8-1 TS/83.8-1 B3.8.1 83.8.1 AC Sources - Operating Operating ..........................................................
.......................................................... TS/B3.8-1 TS/83.8-1 B3.8.2 83.8.2 ................................................................
AC Sources - Shutdown ................................................................ B3.8-38 83.8-38 B3.8.3 83.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ................................
................................ TS/83.8-45 TS/B3.8-45 B3.8.4 83.8.4 Sources - Operating ..........................................................
DC Sources .......................................................... TS/B3.8-54 TS/83.8-54 B3.8.5 83.8.5 Sources - Shutdown ..........................................................
DC Sources .......................................................... TS/B3.8-66 TS/83.8-66 B3.8.6 83.8.6 Battery Cell Parameters 8attery Parameters ...........................................................
........................................................... TS/B3.8-71 TS/83.8-71 B3.8.7 83.8.7 Operating ...................................................
Distribution Systems - Operating B3.8-78
................................................... 83.8-78 B3.8.8 83.8.8 Shutdown ....................................................
Distribution Systems - Shutdown B3.8-86
................................................... 83.8-86 B3.9 83.9 REFUELING OPERATIONS REFUELING ..........................................................
OPERATIONS ....................................... TS/B3.9-1
,.................. TS/83.9-1 B3.9.1 83.9.1 Equipment Interlocks ................................................
Refueling Equipment ................................................ TS/B3.9-1 TS/83.9-1 B3.9.2 83.9.2 One-Rod-Out Interlock Refuel Position One-Rod-Out ...................
Interlock........................................... B3.9-5 83.9-5 B3.9.3 83.9.3 C ontrol R Control od Position ......................................................................
Rod ...................................................................... B3.9-9 83.9-9 B3.9.4 83.9.4 Control Rod Position Indication ......................................................
Indication ...................................................... B3.9-12 83.9-12 B3.9.5 83.9.5 Control Rod OPERABILITY-OPERA81L1TY - Refueling Refueling .........................................
......................................... B3.9-16 83.9-16 B3.9.6 83.9.6 Reactor Pressure Pressure Vessel (RPV) Water Level ...................................................... TS/83.9-19 TS/B3.9-19 B3.9.7 83.9.7 Residual Heat Removal (RHR) (RHR) - High Water Level. Level ........................ B3.9-22
....................... 83.9-22 B3.9.8 83.9.8 Residual Heat Removal (RHR) - Low Water Level ........................
Water Level.. ....................... 83.9-26 B3.9-26 B3.10 83.10 OPERATIONS ...............................................................
SPECIAL OPERATIONS ............................................................... TS/B3.10-1 TS/83.10-1 B3.10.1 83.10.1 Inservice Leak and Hydrostatic Hydrostatic Testing Operation Operation ...................
................... TS/83.10-1 TS/B3.10-1 B3.10.2 83.10.2 Reactor Mode Mode Switch Interlock Interlock Testing .......................................... B3.10-6
.......................................... 83.10-6 B3.10.3 83.10.3 Single Control Rod Withdrawal Withdrawal- - Hot Shutdown .............................
............................. 83.10-11 B3.10-11 B3.10.4 83.10.4 Single Control Rod Withdrawal Withdrawal - Cold Shutdown ........................... 83.10-16 Shutdown ........................... B3.10-16 B3.10.5 83.10.5 Single Control Rod Drive (CRD) Removal - Refueling ................... ................... 83.10-21 B3.10-21 B3.10.6 83.10.6 Multiple Control Rod Withdrawal Withdrawal - Refueling .................................. B3.10-26
.................................. 83.10-26 B3.10.7 83.10.7 Control Rod Testing - Operating ....................................................
................................................... B3.10-29 83.10-29 B3.10.8 83.10.8 SHUTDOWN SHUTDOWN MARGINMARGIN (SDM) Test- Test - Refueling ............................. 83.10-33 Refueling ............................. B3.10-33 TSB1 Text TOe TOC 8/12/09
- SUSQUEHANNA SUSQUEHANNA - UNIT 11 SUSQUEHANNA - UNIT TS TS 1
Revision 17 Revision 17 Revision
SUSQUEHANNA STEAM SUSQUEHANNA ELECTRIC STATION STEAM ELECTRIC SECTIONS (TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE SECTIONS SPECIFICATIONS BASES)
Section Title Revision TOC Table T able of Contents 17 B 2.0 B SAFETY SAFETY LIMITS BASES BASES Page BB 2.0-1 o0 Page TS I/ BB 2.0-2 3 Page TS I/ B 2.0-3 5 Page TS I/ B 2.0-4 3 Page TS I/ B 2.0-5 5 Page TS I/ BB 2.0-6 1 Pages TS I/ BB 2.0-7 through TS I/ B B 2.0-9 1 B 3.0 LCO AND SR APPLICABILITY APPLICABILITY BASES BASES Page TS I/ BB 3.0-1 1 Pages TS I/ BB 3.0-2 through TS I/ B B 3.0-4 o0 Pages TS I/ BB 3.0-5 through TS I/ B B 3.0-7 11 Page TS I/ BB 3.0-8 3 Pages TS I/ BB 3.0-9 through TS I/ B B 3.0-11 2 Page TS I/ B 3.0-11a 3.0-1 la o0 Page TS I/ B 3.0-12 1 Pages TS I/ BB 3.0-13 through TS I/ B B 3.0-15 2 Pages TS I/ BB 3.0-16 and TS I/ B B 3.0-17 0o B 3.1 REACTIVITY CONTROL REACTIVITY CONTROL BASES BASES Pages B 3.1-1 through B B 3.1-4 0o Page TS I/ B 3.1-5.
3.1-5. 1 Pages TS I/ BB 3.1-6 and TS I/ B B 3.1-7 2 Pages BB 3.1-8 through B B 3.1-13 3.1-13 0o Page TS I/ B 3.1-14 1 Page BB 3.1-15 0o Page TS I/ B 3.1-16 1 Pages BB 3.1-17 through B B 3.1-19 3.1-19 0o Pages Pages TS /
IBB 3.1-20 and TS I/ BB 3.1-21 1 Page Page TS /B I B 3.1-22 . 0o Page TS /I B B 3.1-23 1 Page TS /I B B 3.1-24 0o Pages Pages TS I/ B 3.1-25 through TS I/ B B 3.1-27 1 Page TS /I B B 3.1-28 2 Page Page TS /I B B 3.1-29 1 Pages Pages BB 3.1-30 through B B 3.1-33 3.1-33 0o Pages Pages TS I/ B 3.3-34 through TS I/ B B 3.3-36 11 Pages Pages TS I/ B 3.1-37 and TS / B 3.1-38 2 Page Page TS /I B B 3.1-39 3.1-39 and TS /I B B 3.1-40 2 Page Page TS /I B B 3.1-40a 3.1-40a 0o Pages Pages TS I/ B 3.1-41 and TS I/ B 3.1-42 2
- SUSQUEHANNA - UNIT SUSQUEHANNA SUSQUEHANNA -
UNIT 1I UNIT TS I// B TS LOES-1 B LOES-1 Revision 93 Revision 93 93
SUSQUEHANNA SUSQUEHANNA STEAM ELECTRIC STATION STEAM ELECTRIC STATION LIST OF OF EFFECTIVE SECTIONS SECTIONS (TECHNICAL SPECIFICATIONS SPECIFICATIONS BASES)
Section Title Revision Revision Page TS / BB 3.1.43 1 Page TS / BB 3.1-44 o0 Page TS / BB 3.1-45 3 Pages TS / BB 3.1-46 3.1-46 through through TS / BB 3.1 3.1-49
~49 1 Page TS / BB 3.1-50 o0 Page TS / BB 3.1-51 33 B 3.2 B POWER DISTRIBUTION POWER DISTRIBUTION LIMITS LIMITS BASES BASES Page TS / BB 3.2-1 2 Pages TS / BB 3.2-2 and TS //BB 3.2-3 3 Pages TS / BB 3.2-4 and TS //BB 3.2-5 2 Page TS / BB 3.2-6 3 Page BB 3.2-7 11 Pages TS / BB 3.2-8 and TS / B 3.2-9 3 Page TS / BB 3.2.10 3.2.10 2 Page TS / BB 3.2-11 3 Page TS / 8B 3.2-12 11 Page TS / BB 3.2-13 2 B 3.3 B INSTRUMENTATION INSTRUMENTATION Pages TS / BB 3.3-1 through TS / 83.3-4 B 3.3-4 1
- Page TS / B Page TS / B Page TS / B Page TS / B Page TS / B Pages TS B 3.3-5 B 3.3-6 B 3.3-7 B 3.3-7a 3.3-7a B 3.3-8 B 3.3-9 through TS / 83.3-12 T8 / B B 3.3-12 2
3 4
3 1
1 Pages TS /
T8 B B 3.3-12a 1 Pages TS T8// B B 3.3-12b 3.3-12b and TS / B B 3.3-12c 0o Page TS / BB 3.3-13 1 Page TS / BB 3.3-14 3 TS / B Pages T8 B 3.3-15 3.3-15 and TS / B 3.3-16 1 TS / B Pages T8/ B 3.3-17 3.3-17 and TS / B 3.3-18 4 Page TS / BB 3.3-19 1 Pages TS / BB 3.3-20 3.3-20 through TS / B B 3.3-22 2 Page TS / BB 3.3-22a 0o Pages TS / BB 3.3-23 3.3-23 and TS / B 3.3-24 2 Pages TS / BB 3.3-24a and TS / B B 3.3-24b 0o Page TS / BB 3.3-25 3 Page TS / BB 3.3-26 2 Page TS / BB 3.3-27 1 1
Pages TS / BB 3.3-28 through TS / B B 3.3-30 3 Page TS / BB 3.3-30a 3.3-30a 0o
- SUSQUEHANNA - UNIT SUSQUEHANNA SUSQUEHANNA -
UNIT 11 UNIT TS/BLOES-2 TS I/ B LOES-2 LOES-2 Revision 93 Revision 9393
SUSQUEHANNA STEAM ELECTRIC SUSQUEHANNA ELECTRIC STATION OF EFFECTIVE SECTIONS LIST OF LIST SPECIFICATIONS BASES)
SECTIONS (TECHNICAL SPECIFICATIONS Section Title Revision Page TS T8 / B B 3.3-31 4 Page TS T8 / B B 3.3-32 5 TS / B Pages T8 B 3.3-32a 0o Page TS B 3.3-32b T8 / B 1 Page TS B 3.3-33 T8 / B 5 Page TS B 3.3-33a T8 / B 0o Page TS B 3.3-34 T8 / B 1 TS / B Pages T8 B 3.3-35 and T8 TS / BB 3.3-36 2 TS / B Pages T8 B 3.3-37 and T8 TS / BB 3.3-38 1 Page TS /
T8 B B 3.3-39 2 Pages T8 TS / B B 3.3-40 through T8TS / BB 3.3-43 1 Page TS /
T8 B B 3.3-44 4 Pages T8 Pages TS / B B 3.3-44a 3.3-44a and T8/
TS / BB 3.3-44b 3.3-44b o0 Page TS T8 / B B 3.3-45 3 Pages T8 TS / B B 3.3-45a and TS T8 / BB 3.3-45b o0 Page T8 Page TS / B B 3.3-46 3.3-46 3 TS / B Pages T8 B 3.3-47 2 TS / B Pages T8 B 3.3-48 through T8TS I/ BB 3.3-51 3 TS / B Pages T8 B 3.3-52 and T8 TS / BB 3.3-53 2 TS / B Page T8 B 3-3-53a o0 TS / B Page T8 B 3.3-54 4 Page B Page B 3.3-55 3.3-55 11
- Page B Page B Page B Page B B 3.3-56 B 3.3-57 B 3.3-58 B 3.3-59 Pages BB 3.3-60 through B Pages T8 TS / B B 3.3-64 and B 3.3-63 TS / BB 3.3-65 T8 o0 o
1 0
o 2
1 0
Page T8 TS / B B 3.3-66 3.3-66 4 TS / B Page T8 B 3.3-67 3.3-67 33 Page T8 TS / B B 3.3-68 3.3-68 4 TS / B Page T8 B 3.3-69 3.3-69 55 TS / B Pages T8 B 3.3-70 4 TS / B Page T8 B 3.3-71 33 TS / B Pages T8 B 3.3-72 and T8 TS / BB 3.3-73 2 TS / B Page T8 B 3.3-74 33 TS / B Page T8 B 3.3-75 2 TS / B Page T8 B 3.3-75a 6 TS / B Page T8 B 3.3-75b 7 Page T8 Page TS / B B 3.3-75c 5 Pages BB 3.3-76 through 3.3-77 o0 Page T8 Page TS / B B 3.3-78 3.3-78 11 Pages BB 3.3-79 through BB 3.3-81 o0 Page BB 3.3-82 1
- SUSQUEHANNA - UNIT SUSQUEHANNA SUSQUEHANNA -
UNIT 11 UNIT B LOES-3 TS //I B TS LOES-3 LOES-3 Revision 93 Revision 93
SUSQUEHANNA SUSQUEHANNA STEAM ELECTRIC ELECTRIC STATION LIST OF SECTIONS (TECHNICAL OF EFFECTIVE SECTIONS SPECIFICATIONS BASES)
(TECHNICAL SPECIFICATIONS Section Title Revision Page B 3.3-83 o0 Pages BB 3.3-84 and B 3.3-85 1 Page B 3.3-86 o0 Page B 3.3-87 11 Page B 3.3-88 o0 Page B 3.3-89 11 Page TS / BB 3.3-90 3.3-90 11 Page B 3.3-91 0o Pages TS / B 3.3-92 through TS / B B 3.3-100.
3.3-100 1 Pages TS / BB 3.3-101 through TS / B B 3.3-103 0o Page TS / BB 3.3-104 2 Pages TS / B 3.3-105 and TS / B B 3.3-106 0o Page TS / BB 3.3-107 1 Page TS / BB 3.3-108 0o Page TS / BB 3.3-109 1 Pages TS / B 3.3-110 and TS /B B 3.3-110 / B 3.3-111 0o Pages TS / BB 3.3-112 and TS / B B 3.3-112a 3.3-112a 1 Pages TS/B 3.3-113 through TS TS/ B 3.3-113 TS/B/ B 3.3-115 1 Page TS / BB 3.3-116 3 Page TS / BB 3.3-117 1 Pages TS / BB 3.3-118 3.3-118 through TS / B B 3.3-122 0o Pages TS / BB 3.3-123 3.3-123 and TS / B B 3.3-124 1
Page TS / BB 3.3-124a 3.3-124a 0o Page TS / BB 3.3-125 0o Pages TS / BB 3.3-126 3.3-126 and TS / B B 3.3-127 11 Pages TS / BB 3.3-128 3.3-128 through TS/ B B 3.3-130 3.3-130 0o Page TS / BB 3.3-131 1 Pages TS / BB 3.3-132 3.3-132 through TS / B B 3.3-134 o0 Pages B 3.3-135 through B B 3.3-137 3.3-137 o0 Page TS / B 3.3-138 1 Pages B 3.3-139 through B B 3.3-149 3.3-149 o 0 Pages TS / BB 3.3-150 3.3-150 and TS / B B 3.3-151 1 Pages TS / BB 3.3-152 3.3-152 through TS/
TS / BB 3.3-154 2 Page TS / B 3.3-155 1 Pages TS / BB 3.3-156 3.3-156 through TS / B B 3.3-158 3.3-158 22 Pages Pages TS / B B 3.3-159 through TS / B B 3.3-162 11 Page TS / B 3.3-163 2 Pages TS / BB 3.3-164 and TS / B 3.3-165 1 Pages TS / BB 3.3-166 and TS / B 3.3-167 2 Pages TS / BB 3.3-168 and TS / B 3.3-169 1 Page TS / B 3.3-170 2 Pages Pages TS / BB 3.3-171 3.3-171 through TS / B B 3.3-177 1 Pages Pages TS / BB 3.3-178 through TS / B B 3.3-179a 2 Pages Pages TS / BB 3.3-179b and TS / B B 3.3-179c 3.3-179c o0 Page TS / B 3.3-180 1
- SUSQUEHANNA - UNIT SUSQUEHANNA -
UNIT 11 UNIT TS II/ B TS B LOES-4 LOES-4 LOES-4 Revision 93 Revision 93 Revision
SUSQUEHANNA STEAM ELECTRIC STATION SUSQUEHANNA OFEFFECTIVE EFFECTIVE SECTIONS SECTIONS (TECHNICAL SPECIFICATIONS SPECIFICATIONS BASES)
LIST OF Section Title Title Revision Page TS // B Page B 3.3-181 33 Page TS // B Page B 3.3-182 1 Page TS // B Page B 3.3-183 2 Page TS // B Page B 3.3-184 1 Page TS // B Page B 3.3-185 33 Page TS // B Page B 3.3-186 1 Pages TS / BB 3.3-187 and TS / BB 3.3-188 Pages 2 Pages TS // BB 3.3-189 through TS / B Pages B 3.3-191 11 Page TS // B Page B 3.3-192 o0 Page TS // B Page B 3.3-193 11 Pages TS // BB 3.3-194 and TS / BB 3.3-195 Pages 3.3-195 o0 Page TS / B B 3.3-196 22 Pages TS / BB 3.3-197 through TS / B B 3.3-204 o0 Page TS // BB 3.3-205 1 Pages BB 3.3-206 through B B 3.3-209 o 0 Page TS // BB 3.3-210 11 Pages BB 3.3-211 through BB 3.3-219 o0 B 3.4 B3.4 REACTOR COOLANT SYSTEM BASES BASES Pages BB 3.4-1 and B B 3.4-2 o0 Pages TS / B B 3.4-3 and Page TS / BB 3.4-4 4 Pages TS TS // BB 3.4-5 3.4-5 through through TS // B B 3.4-9 3.4-9 2
- Pages B Page B Page B Page B 3.4-10 through B 3.4-12 B 3.4-13 3.4-13 B 3.4-14 Page TS TS // B Pages TS / B Pages TS Page TS / B B 3.4-15
/ 3.4-16 and B 3.4-16 B 3.4-18 and TS / B B 3.4-17 2
0o 0o 2
3 2
1 Pages BB 3.4-19 through B 3.4-27 0o Pages TS / B 3.4-28 and TS / B B 3.4-29 1 Pages TS / B 3.4-30 Pages TS / B 3.4-30 and TS / B 3.4-31 B 0o Pages TS / B 3.4-32 Pages TS / B 3.4-32 andand TS / B 3.4-33 B 3.4-33 1 Page TS / B B 3.4-34 0o Pages TS / B 3.4-35 and TS / B B 3.4-36 3.4-36 1 Page TS TS / BB 3.4-37 2 Page TS Page TS / BB 3.4-38 1 Pages BB 3.4-39 3.4-39 and B B 3.4-40 3.4-40 0o Page TS / B Page B 3.4-41 3.4-41 1 Pages BB 3.4-42 through B 3.4-48 0o Page TS Page TS / BB 3.4-49 3 Page TS / B B 3.4-50 1 Page TS TS / B 3.4-51 3.4-51 3 Page TS / B 3.4-52 Page TS / B 3.4-52 2 Page TS / B B 3.4-53 3.4-53 1
- SUSQUEHANNA SUSQUEHANNA - UNIT SUSQUEHANNA - UNIT 1 UNIT 1 TS /
TS TS B LOES-5
/I B LOES-5 LOES-5 Revision 93 Revision 93 93
SUSQUEHANNA STEAM SUSQUEHANNA STEAM ELECTRIC ELECTRIC STATION LIST OF OF EFFECTIVE SECTIONS SECTIONS (TECHNICAL SPECIFICATIONSSPECIFICATIONS BASES)
Section Title Revision Revision Pages TS / BB 3.4-54 through TS / B B 3.4-56 2 Page TS / BB 3.4-57 3 Pages TS / BB 3.4-58 through TS / B B 3.4-60 1 B 3.5 B ECCS AND RCIC BASES BASES Pages B B 3.5-1 and B B 3.5-2 3.5-2 o 0
Page TS / BB 3.5-3 2 Page TS / BB 3.5-4 11 Page TS I/ B B 3.5-5 2 Page TS I/ B B 3.5-6 1 Pages B B 3.5-7 through B 3.5-10 0o Page TS I/ B B 3.5-11 3.5-11 1 Page TS I/ B B 3.5-12 0o Page TS /I B B 3.5-13 1 Pages TS / BB 3.5-14 and TS I/ B B 3.5-15 0o Pages TS / BB 3.5-16 through TS / B B 3.5-18 1 Pages B 3.5-19 through B 3.5-24 0o Page TS / BB 3.5-25 1 Pages TS / BB 3.5-26 and TS / B B 3.5-27 1 Pages B B 3.5-28 through B B 3.5-31 0o B 3.6 B CONTAINMENT SYSTEMSSYSTEMS BASES CONTAINMENT BASES Page TS / BB 3.6-1 2 2
Page TS I/ B B 3.6-1a 3 Page TS I/ B B 3.6-2 4 Page TS I/ B B 3.6-3 3 Page TS / BB 3.6-4 4 Pages TS / BB 3.6-5 and TS I/ B B 3.6-6 3 Pages TS / BB 3.6-6a and TS / B B 3.6-6b 2 Page TS / BB 3.6-6c 0o B 3.6-7 Pages B 0o B 3.6-8 Page B 1 B 3.6-9 through B 3.6-14 Pages B 0o Page TS I/ B B 3.6-15 2 Page TS I/ B B 3.6-15a 0o Page TS I/ B B 3.6-15b 2 Pages TS / BB 3.6-16 and TS / B B 3.6-17 1 Page TS // B Page B 3.6-17a 0o Pages TS / BB 3.6-18 3.6-18 and TS / B B 3.6-19 0o Page TS I/ B B 3.6-20 1 Page TS / BB 3.6-21 2 Page TS / BB 3.6-22 1 Page TS I/ B B 3.6-22a 0o Page TS/
TS / BB 3.6-23 1
- SUSQUEHANNA - UNIT SUSQUEHANNA UNIT 1SUSQUEHANNA TS -
TSUNIT B1LOES-6 II/ B B LOES-6 LOES-6 Revision 93 Revision 93 Revision 93
SUSQUEHANNA SUSQUEHANNA STEAM ELECTRIC ELECTRIC STATION STATION LIST OF LIST OF EFFECTIVE SECTIONS SECTIONS (TECHNICAL SPECIFICATIONS BASES)
SPECIFICATIONS Section Section Title Revision Revision Pages TS / BB 3.6-24 and TS / B 3.6-25 0 Pages TS / BB 3.6-26 and TS / B 3.6-27 2 Page TS / BB 3.6-28 7 Page TS / BB 3.6-29 2 Page TS / BB 3.6-30 1 Page TS / BB 3.6-31 3 Page TS / BB 3.6-32 0 Page TS / BB 3.6-33 1 Pages TS / B 3.6-34 and TS / B 3.6-35 0 Page TS / BB 3.6-36 1 Page TS / BB 3.6-37 0 Page TS / BB 3:6-38 3.6-38 3 Page TS / BB 3.6-39 2 Page TS / BB 3.6-40 6 Page B 3.6-41 1 Pages BB 3.6-42 and B 3.6-43 3 Pages TS / BB 3.6-44 3.6-44 and TS / B 3.6-45 1 Page TS / BB 3.6-46 2 Pages TS / BB 3.6-47 3.6-47 through TS / B B 3.6-51 3.6-51 1 Page TS / BB 3.6-52 2 Pages TS / BB 3.6-53 3.6-53 through TS / B B 3.6-56 0 Page TS / BB 3.6-57 1
Page TS //3.6-58 3.6-58 2 Pages B 3.6-59 through B B 3.6-63 0 Pages TS / BB 3.6-64 3.6-64 and TS / B 3.6-65 1 Pages B 3.6-66 through B B 3.6-69 0 Pages TS / BB 3.6-70 3.6-70 through TS / BB 3.6-72 1 Page TS / BB 3.6-73 2 Pages TS / BB 3.6-74 3.6-74 and TS / B 3.6-75 1 B 3.6-76 and B Pages B B 3.6-77 0 Page TS / B 3.6-78 1 B 3.6-79 through B Pages B B 3.3.6-83 0 Page TS / B 3.6-84 3 Page TS / B 3.6-85 2 Page TS / B 3.6-86 4 Pages Pages TS / BB 3.6-87 through TS / B B:3.6-88a
-3.6-88a 2 Page TS / B 3.6-89 4 Page TS / B 3.6-90 2 Page TS / B 3.6-91 3 Pages Pages TS / BB 3.6-92 through TS / B B 3.6-96 1 Page TS / BB 3.6-97 2 Pages Pages TS / BB 3.6-98 and TS / B B 3.6-99 1 Page TS / B 3.6-100 2 Pages TS / BB 3.6-101 and TS / B 3.6-102 1
- SUSQUEHANNA SUSQUEHANNA - UNIT SUSQUEHANNA - UNIT 1I TS LOES-7 B LOES-7 TS II/ B LOES-7 Revision 93 Revision 93 93
SUSQUEHANNA SUSQUEHANNA STEAM ELECTRIC ELECTRIC STATION LIST OF EFFECTIVE SECTIONS LIST OF SECTIONS (TECHNICAL SPECIFICATIONSSPECIFICATIONS BASES)
Section Title Revision Pages TS / 8 B 3.6-103 3.6-103 and TS /83.6-104
/ B 3.6-104 2 Page TS / 8B 3.6-105 3 Page TS / 8 B 3.6-106 2 Page TS / 8B 3.6-107 3 B 3.7 8 PLANT SYSTEMS BASES PLANT SYSTEMS 8ASES Pages Pages TS / 8 B 3.7-1 3 Page TS / 8B 3.7-2 4 Pages TS //83.7-3 B 3.7-3 through through TS / 8 B 3.7-5 3 Page TS / 8 B 3.7-5a 0o Pages TS / 8 B 3.7-6 3.7-6 and TS //8B 3.7-6a 3.7-6a 2 Page TS / 8 B 3.7-6b 1 Page TS / 8 B 3.7-6c 2 TS //83.7-7 Page T8 B 3.7-7 33 Page T8 TS //83.7-8 B 3.7-8 2 Pages Pages TS / 8 B 3.7-9 3.7-9 through TS / 83.7-13 B 3.7-13 1 Pages Pages TS / 8 B 3.7-14 3.7-14 through TST8// 8 B 3.7-18 2 Page TS T8 / 8B 3.7-18a 0o Pages Pages TS / 8 B 3.7-19 3.7-19 through TS / 8 B 3.7-23 1 Page TS T8 //83.7-24 B 3.7-24 1 Pages Pages TS / 8 B 3.7-25 3.7-25 and T8 TS / 8B 3.7-26 o0 Pages Pages TS / 8 B 3.7-27 3.7-27 through TST8 / B 55 8 3.7-29 Page TS T8 / 8B 3.7-30 2 Page TS T8 / 8B 3.7-31 1 Page TS T8 / 8B 3.7-32 o0 Page TS / B 3.7-33 T8 /83.7-33 1 Pages TS / 8 B 3.7-34 3.7-34 through TS / B 3.7-37 T8 /83.7-37 o0 B 3.8 8 ELECTRICAL POWER SYSTEMS ELECTRICAL SYSTEMS 8ASES BASES Page TS T8 / B 8 3.8-1 33 Pages TS / 8B 3.8-2 and TS / 8B 3.8-3 22 Page TS T8 / B 8 3.8-4 33 Pages TS / 8B 3.8-4a and T8 TS / 8B 3.8-4b . o0 Page TS T8 / B 8 3.8-5 5 Page TS /B T8 1 8 3.8-6 3 Pages TS 1/ 8 B 3.8-7 through T8/8 TS/B 3.8-8 2 Page TS T8 / B 8 3.8-9 44 Page TS / B 3.8-10 T8 /83.8-10 33 Pages TS / 8B 3.8-11 and T8 TS / 8B 3.8-17 2 Page TS / B 3.8-18 T8 /83.8-18 33 Pages TS /83.8-19
/ B 3.8-19 through T8 TS / 8B 3.8-21 2 Pages TS 1 / 8B 3.8-22 and T8 TS 1/ 8B 3.8-23 33 Pages TS 1/ 8 B 3.8-24 through TST8 / 8 B 3.8-37 2 Pages B 3.8-38 through 8B 3.8-44 o0
- SUSQUEHANNA - UNIT SUSQUEHANNA SUSQUEHANNA - UNIT 11 TS //I B TS B LOES-8 LOES-8 LOES-8 Revision 93 Revision 93 Revision 93
SUSQUEHANNA STEAM ELECTRIC STATION SUSQUEHANNA LIST OF OF EFFECTIVE SECTIONSSECTIONS (TECHNICAL SPECIFICATIONS SPECIFICATIONS BASES)
Section Title Revision Page TS / BB 3.8-45 1 Pages TS / B 3.8-46 through B 3.8-48 0 Page TS / BB 3.8-49 1 Pages BB 3.8-50 3.8-50 through B B 3.8-53 0 Pages TS / B 3.8-54 through TS / B B 3.8-57 2 Pages TS / B 3.8-58 through TS / B B 3.8-61 3 Pages TS / B 3.8-62 and TS I/ B B 3.8-63 5 Page TS / BB 3.8-64 3.8-64 4 Page TS / BB 3.8-65 3.8-65 5 Pages TS / B 3.8-66 through through TS / BB 3.8-77 3.8-77 1 Pages TS / B 3.8-77A through TS / B B 3.8-77C 0 Pages BB 3.8-78 3.8-78 through B 3.8-80 0 Page TS / BB 3.8-81 3.8-81 1 Pages BB 3.8-82 3.8-82 through B 3.8-90 0 B 3.9 REFUELING OPERATIONS REFUELING OPERATIONS BASES BASES Pages TS / BB 3.9-1 and TS / B B 3.9-1a 1 Pages TS / BB 3.9-2 through through TS / B B 3.9-4 1 Pages BB 3.9-5 through B B 3.9-18 0 Pages TS / B 3.9-19 through TS / B B 3.9-21 3.9-21 1 Pages BB 3.9-22 3.9-22 through through B 3.9-30 0
- B 3.10 SPECIAL OPERATIONS Pages Pages Page OPERATIONS BASES Page TS / B B
B 3.10-1 3.10-1 3.10-6 Pages B 3.10-6 Page TS / B Page through B 3.10-32 3.10-32 Page B 3.10-33 BASES Pages TS / B 3.10-2 through TS / B B 3.10-31 B 3.10-5 3.10-5 2
1 0
2 0
Page Page TS / B 3.10-34 3.10-34 1 Pages Pages BB 3.10-35 3.10-35 and B 3.10-36 0 Page Page TS / B 3.10-37 3.10-37 1 Page Page TS / B 3.10-38 3.10-38 2 LOES.doc TSB1 Text LOES.doc 8/12/09
- SUSQUEHANNA - UNIT SUSQUEHANNA SUSQUEHANNA -
UNIT 11 UNIT TS I B LOES-9 TS II B B LOES-9 LOES-9 Revision 93 Revision 93 Revision 93
PPL Rev. 3 .
LCO APPLICABILITY APPLICABILITY B 3.0 3.0 B
B 3:0 3.0 LIMITING LIMITING CONDITION OPERATION (LCO) APPLICABILITY CONDITION FOR OPERATION APPLICABILITY BASES BASES LCOs LCO 3.0.1 through LCO 3.0.8 establish the general requirements requirements applicable applicable to to all Specifications Specifications and apply at all times, unless otherwise stated.
LCO 3.0.1 Applicability statement within each individual LCO 3.0.1 establishes the Applicability Specification Specification as the requirement requirement for when the LCO is required to be met (Le., (i.e.,
MODES or other specified conditions of the Applicability when the unit is in the MODES statement statement of each each Specification).
Specification).
LCO 3.0.2 LCO 3.0.2 establishes that uponupon discovery discovery of a failure to meet an LCO, thethe associated associated ACTIONS shall be met. The Completion Time of each Required Required Condition is applicable from the point in time that an Action for an ACTIONS Condition ACTIONS Condition is entered. The Required Actions establish establish those remedial measures that must be taken within specified Completion Times when the when the requirements of an LCO are not met. This Specification Specification establishes that:
establishes that:
- a. Completion Completion of the Required Required Actions within the specified specified Completion Times constitutes compliance with a Specification; Specification; and
- b. Completion Completion of the Required within the specified Required Actions is not required when an LCO is met specified Completion Time, unless otherwise specified.
There are two basic types of Required Actions. The first type of Required 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 OPERABLE status or to restore variables to within specified limits. If Ifthis this type of Required Required Action is not completed completed within the specified specified Completion required to place the unit in Time, a shutdown may be required in a MODE or condition condition in which the Specification Specification is not applicable. (Whether stated as a Required Required Action or not, correction correction of the entered Condition is an action that may always be considered considered upon entering entering
- SUSQUEHANNA - UNIT 1 SUSQUEHANNA TS / B 3.0-1 (continued)
(continued)
Revision 1
PPL Rev. 3 LCO APPLICABILITY APPLICABILITY B 3.0 B 3.0 B 3.0 B LIMITING CONDITION FOR OPERATION LIMITING CONDITION OPERATION (LCO) APPLICABILITY LCO 3.0.2 ACTIONS.) The second type of Required Required Action specifies the remedial (continued) measures measures that permit continued continued operation operation of the unit that is not further further restricted restricted by the Completion Completion Time. In In this case, compliance compliance with the Required provides an acceptable Actions provides acceptable level of safety for continued continued operation.
Completing the Required Actions is not required when an LCO is met or is no Completing no longer longer applicable, unless unless otherwise stated in in the individual Specifications.
The nature of some Required Actions of some Conditions necessitates necessitates that, once the Condition is entered, the Required Actions must be completed completed even though the associated associated Conditions no longer exist. The individual LCOs individual LCOs ACTIONS specify the RequiredRequired Actions where this is the case. An example of this is in LCO 3.4.10, "RCS Pressure Pressure and Temperature Temperature (PIT)(P/T) Limits."
The Completion Times of the Required Required Actions are also applicable when a system or component is removed from service service intentionally.
intentionally. The reasons for intentionally intentionally relying on the ACTIONS include, but are not limited to, performance preventive maintenance, performance of Surveillances, preventive corrective maintenance, corrective maintenance, investigation of operational maintenance, or investigation operational problems. Entering Entering ACTIONS ACTIONS for these reasons reasons must be done done in a manner manner that does not compromise compromise safety.
- Intentional entry into ACTIONS convenience.
ACTIONS should not be made for operational convenience. Additionally, if if intentional intentional entry into actions would result in.
redundant equipment being inoperable, inoperable, alternatives Doing so limits the time both subsystems/divisions inoperable being entered. Individual Individual Specifications alternatives should be used in, used instead.
subsystems/divisions of a safety function are inoperable and limits the time conditions exist which may result in in LCO 3.0.3 Specifications may specify a time limit for performing 3.0.3 performing an SR when equipment equipment is removed from service or bypassed for testing. In In this this case, the Completion case, Completion Times of the Required Required Actions are applicable applicable when this this time limit time expires; if limit expires; the equipment if the eqUipment remains remains removed from service removed from service or bypassed.
When a change in in MODE or other specified specified condition is required to comply with Required Required Actions, the unit may enter a MODE or other specified condition in which another Specification Specification becomes becomes applicable. In In this case, Completion Times of the associated the Completion associated Required Actions would apply from from the point in time that the new Specification becomes new Specification becomes applicable and the the ACTIONS ACTIONS Condition(s) are entered,entered.
- SUSQUEHANNA SUSQUEHANNA - UNIT UNIT 11 TS / B 3.0-2 (continued)
Revision 0
PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION LIMITING CONDITION OPERATION (LCO) (LCO) APPLICABILITY .
LCO 3.0.3 LCO 3.0.3 establishes establishes the actions that must be implemented implemented when an LCO is not met and:
- a. An associated Required Action and Completion Completion Time is not met and no no other Condition applies; or
- b. The condition of the unit is not specifically addressed addressed by the associated ACTIONS. This means that no combination combination of Conditions stated in the the ACTIONS ACTIONS can be made that exactly corresponds to the actual exactly corresponds actual condition condition of the unit. Sometimes, possible combinations combinations of Conditions are such that entering warranted; in such cases, the ACTIONS entering LCO 3.0.3 is warranted; ACTIONS specifically state a Condition corresponding to such combinations and Condition corresponding also that LCO 3.0.3 be entered immediately.
Specification delineates This Specification delineates the time limits for placing the unit in a safe MODE MODE or other specified condition condition when operation cannot be maintained within the the limits for safe operation as defined defined by the LCO and its ACTIONS. ItIt is not intended to be used as an operational convenience that permits routine intended routine voluntary removal of redundant redundant systems or components components from seNice service in lieu of alternatives that would not result in other altematives in redundant systems or components components
- being inoperable.
Upon entering entering LCO 3.0.3, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is allowed to prepare for an orderly shutdown before initiating a change in operator to coordinate in unit operation.
operation. This includes time to permit the coordinate the reduction in in electrical generation dispatcher to ensure the stability and availability generation with the load availability of the electrical the electrical grid. The time time limits specified to reach MODES of operation permit the shutdown to reach lower MODES proceed in a controlled controlled and orderly manner manner that is well within the specified maximum cooldown rate and within the capabilities of the unit, assuming that only the minimum minimum required equipment equipment is OPERABLE. This reduces thermal stresses on components components of the Reactor Coolant System and the potential for a plant upset that could challenge safety systems systems under conditions to which this this Specification applies. The use and interpretation Specification interpretation of specified times to complete complete the actions of LCO 3.0.3 are consistent with the discussion discussion of Section 1.3, Completion Times.
Completion (continued)
(continued)
SUSQUEHANNA SUSQUEHANNA -- UNIT UNIT 1 TS / B 3.0-3 3.0-3 Revision Revision 0
PPL Rev. 3 LCO APPLICABILITY LCO APPLICABILITY B 3.0 3.0
- B 3.0 LIMITING CONDITION LCO 3.0.3 LCO 3.0.3 (continued)
CONDITION FOR OPERATION OPERATION (LCO) APPLICABILITY A unit shutdown required in accordance with LCO 3.0.3 may be terminated A unit shutdown required in accordance with LCO 3.0.3 may be terminated and LCO 3.0.3 exited if 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 performed
- c. ACTIONS ACTIONS exist that do not have expired Completion Times. These These Completion Completion Times are applicable applicable from the point in time that the the Condition is initially entered and not from the time LCO 3.0.3 is exited.
The time limits of Specification Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the unit to be in in MODE 4 when a shutdown is required during MODE 1 operation. If Ifthe unit is in a lower MODE of operation when a shutdown is required, the time limit for in reaching the next lower MODE MODE applies. If If a lower MODE MODE is reached in less time than allowed, however, the total allowable allowable time to reach MODE MODE 4, or other applicable applicable MODE, is not reduced. For example, if if MODE 2 is reached reached in in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then the time allowedallowed for reaching MODE MODE 3 is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />, because because the total time for reaching reaching MODE 3 is not reduced from the allowable allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. Therefore, if if remedial measures measures are completed completed that would would permit a return retum to MODE 1, 1, a penalty penalty is not incurred by having having to reach a lower lower MODE of operation in in less than the total time allowed.
In MODES In MODES 1, 1, 2, and 3, LCO 3.0.33.0.3 provides actions for Conditions not covered in other Specifications.
in other Specifications. The requirements of LCO 3.0.3 3.0.3 do not apply in in MODES MODES 4 and 5 because because the the unit unit is is already already inin the most restrictive Condition Condition required required by LCO 3.0.3. The requirements requirements of LCO 3.0.3 do not apply in in other specified specified conditions of the Applicability Applicability (unless in in MODE 1, 1, 2, or 3) because because the ACTIONS of individual Specifications Specifications sufficiently sufficiently define the remedial measures measures to be taken.
Exceptions to LCO 3.0.3 are provided provided in instances instances where requiring a unit unit shutdown, in accordance accordance with LCO 3.0.3, would not provide provide appropriate appropriate remedial measures measures forfor the the associated condition of the unit. An example of associated condition this is this is in in LCO LCO 3,7.7, 3.7.7, "Spent "Spent Fuel Fuel Storage PoolPool Water Level." LCO Water Level." LCO 3.7.7 has an Applicability of "During movement movement of irradiated fuel irradiated fuel (continued)
(continued)
- SUSQUEHANNA-SUSQUEHANNA - UNIT 1 TS /I B 3.0-4 Revision Revision 0 0
PPL Rev. 3 LCO APPLICABILITY APPLICABILITY B 3.0 3.0 B
B 3.0 LIMITING CONDITION LIMITING CONDITION FOR OPERATION OPERATION (LCO) APPLICABILITY LCO 3.0.3 assemblies assemblies in the spent fuel storage pool." Therefore, this LCO can be be (continued) applicable applicable in any or all MODES. If If the LCO and the Required Required Actions Actions of LCO 3.7.7 are not met while in MODEMODE 1, 2, or 3, there is no safety benefit 1,2, benefit toto be gained by placing the unit in in a shutdown condition. The Required Required Action of LCO 3.7.7 of "Suspend movement movement of irradiated fuel assemblies in in the spent spent fuel storage pool" is the appropriate appropriate Required Action to complete complete in lieu of the the actions actions of LCO 3.0.3. These exceptions exceptions are addressed in in the individual Specifications.
LCO 3.0.4 LCO 3.0.4 establishes limitations MODES or other specified limitations on changes in MODES specified conditions conditions in the Applicability when an LCO is not met. ItIt allows placing the unit in a MODE or other specified specified condition stated in that Applicability Applicability Applicability desired (e.g., the Applicability desired to be entered) entered) when unit conditions conditions are such that the requirements requirements of the LCO would not be met, in accordanceaccordance 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 the condition in the Applicability Applicability with the LCO not met when the associated associated ACTIONS to be be entered entered permit permit continued operation in the MODE MODE or other other specified condition condition in the Applicability for an unlimited period of time. Compliance Compliance with Required Required Actions that permit continued continued operation operation of the unit for an unlimited period of time in a MODE MODE or other specified provides specified condition provides an acceptable acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the MODE MODE change.
Therefore, in such cases, entry MODE or other specified condition in entry into a MODE in the Applicability Applicability may be made in accordance accordance with the provisions of the the Required Actions.
Required LCO 3.0.4.b allows entry into a MODE or other specified condition in the the Applicability with the LCO not met after performance Applicability assessment performance of a risk assessment addressing addressing inoperable inoperable systems and components, consideration consideration of the the determination of the acceptability results, determination acceptability of entering entering the MODEMODE or other specified specified condition condition in the Applicability, and establishment establishment of risk management actions, if appropriate.
management appropriate.
The risk assessment assessment may use quantitative, quantitative, qualitative, or blended approaches, approaches, and the risk assessment assessment will be conducted using the plant plant program, procedures, and criteria in place to implement implement 10 CFR 50.65(a)(4),
50.65(a)(4), which requires that risk impacts of maintenance maintenance activities activities to be assessed and managed. The risk assessment, for the the (continued)
(continued)
- SUSQUEHANNA SUSQUEHANNA -- UNIT 11 TS / B 3.0-5 Revision Revision 1
PPL Rev. 3 LCO APPLICABILITY 3.0 B 3.0 LIMITING CONDITION FOR OPERATION B 3.0 LIMITING OPERATION (LCO) APPLICABILITY APPLICABILITY LCO 3.0.4 purposes purposes of LCO 3.0.4 (b), (b), must take into account all inoperable inoperable Technical (continued) Specification equipment regardless Specification equipment regardless of whether equipment is included whether the equipment included in the normal 10 CFR 50.65(a)(4) risk assessment scope. The risk assessments assessments will be conducted procedures and guidance conducted using the procedures guidance endorsed Regulatory Guide 1.182, endorsed by Regulatory 1.182, "Assessing and Managing Managing Risk Before Maintenance Maintenance Activities Activities at Nuclear Power Plants." Regulatory Guide Guide 1.182 endorses the guidance in Section 11 of NUMARC NUMARC 93-01, 93-01, "Industry Guideline for Monitoring Monitoring the Effectiveness Effectiveness of Maintenance Maintenance at Nuclear Power documents address Power Plants." These documents address general general guidance for conduct of the risk assessment, quantitative quantitative and qualitative qualitative guidelines for establishing management actions, and example risk management establishing risk management management actions. These include include actions actions to plan and conduct other activities activities in aa manner manner that controls overall overall risk, increased risk awareness awareness by shift and and management management personnel, actions to reduce the duration duration of the condition, actions to minimize the magnitude magnitude of risk increases (establishment of backup backup success paths or compensatory measures), and determination compensatory determination that the proposed MODE change is acceptable. ConsiderationConsideration should also be given to the probability probability of completing completing restoration restoration such that thethe requirements requirements of the LCO would be met prior to the expiration of ACTIONS ACTIONS Completion Completion Times that would require exiting the Applicability.
- LCO 3.0.4.b 3.0A.b may be used with single, or multiple systems and components unavailable. NUMARC components unavailable.
consideration consideration of simultaneous components.
NUMARC 93-01 provides guidance simultaneous unavailability The results of the risk assessment guidance relative to unavailability of multiple systems and assessment shall be be considered considered in determining determining the to the acceptability acceptability of entering the MODEMODE or other specified condition in the the Applicability, and any corresponding risk management management actions. The The LCO 3.0.4.b risk assessments assessments do not have to be documented.
documented.
The Technical Specifications Specifications allow continued operation with equipment equipment unavailable unavailable in MODE 1 for the duration Completion Time. Since duration of the Completion Since this is allowable, allowable, and since in general general the risk impact in that particular MODE bounds the risk of transitioning MODE transitioning into and through the applicable applicable MODES or other specified MODES specified conditions conditions in the Applicability Applicability of the LCO, the the use of the LCO 3.0.4.b allowance generally acceptable, as long allowance should be generally long as the risk is assessed and managed managed as stated above. However, there is a small subset of systems and components that have been determined determined to to be more important to risk and use of the LCO 3.0.4.b allowance allowance is prohibited. The LCOs governing these systems and components contain contain Notes prohibiting the use of LCO 3.0.4.b by stating Notes prohibiting stating that LCO 3.0.4.b is not not applicable.
(continued)
(continued)
- SUSQUEHANNA SUSQUEHANNA - UNITUNIT 1 TS / B B 3.0-6 Revision Revision 1
PPL Rev. 3 LCO APPLICABILITY 3.0 B 3.0 B 3.0 LIMITING CONDITION LIMITING CONDITION FOR OPERATION OPERATION (LCO) APPLICABILITY LCO 3.0.4 LCO 3.0.4.c allows entry into a MODE or other specified condition in the the (continued) Applicability with the LCO not met based on a Note in the Specification Applicability Specification which states LCO 3.0.4.c is applicable. These specific allowances allowances permit permit other specified conditions in the Applicability when MODES or other entry into MODES the associated ACTIONS to be entered entered do not provide provide for continued operation for an unlimited period operation assessment has not period of time and a risk assessment been performed. allowance may apply to all the ACTIONS or to aa performed. This allowance specific Required Specification. The risk assessments Required Action of a Specification. assessments performed to justify the use of LCO 3.0.4.b usually only consider systems performed systems and components. For this reason, LCO 3.0.4.c is typically applied to describe values and parameters (e.g., [Containment Specifications which describe Specifications [Containment Air Temperature, Containment Pressure, MCPR, MCPR, Moderator Temperature Moderator Temperature Coefficient]) and may be applied to other Specifications Coefficient]) Specifications based on NRC NRC plant-specific plant-specific approval.
Specification should not be interpreted The provisions of this Specification interpreted as endorsing endorsing the failure to exercise the good practice of restoring systems or good practice components OPERABLE status before components to OPERABLE before entering an associated associated MODE MODE or other specified condition in the Applicability.
specified condition
- The provisions of LCO 3.0.4 shall not prevent changes changes in MODESMODES or other other specified conditions in the Applicability specified Applicability that are required required to comply with ACTIONS. In In addition, the provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified changes Applicability that specified conditions in the Applicability that
. result from any unit shutdown. In In this context, a unit shutdown is defined as a change in MODE or other specified specified condition in the Applicability associated associated with transitioning from MODE 1 to MODE 2 or MODE MODE 3, MODE 2 to MODE 3, and MODE 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 the applicable Required Actions until the Condition is resolved, applicable Conditions and Required until the LCO is met, or until the unit is not within the Applicability Applicability of thethe Technical Specification.
Technical Specification.
Surveillances Surveillances do not have have to be performed performed on the associated inoperable associated inoperable equipment equipment (or on variables outside outside the specified limits), as permitted by permitted by SR 3.0.1.
3.0.1. Therefore, utilizing LCO 3.0.4 is not a violation of SR 3.0.1 or (continued)
- SUSQUEHANNA-UNIT SUSQUEHANNA - UNIT 1 TS /I B 3.0-7 Revision 1
PPL Rev. 3 LCO APPLICABILITY B 3.0 3.0 B 3.0 LIMITING CONDITION FOR OPERATION LIMITING CONDITION OPERATION (LCO) (LCO) APPLICABILITY LCO 3.0.4 SR 3.0.4 for any Surveillances Surveillances that have not been performed performed on (continued) inoperable inoperable equipment. However, SRs must be met to ensure OPERABILITY prior to declaring OPERABILITY declaring the associated equipment OPERABLE associated equipment OPERABLE (or variable within limits) and restoring compliance compliance with the affected affected LCO.
LCO 3.0.5 LCO 3.0.5 establishes establishes the allowance for restoring equipment equipment to service under administrative administrative controls when itit has been removed from service or declared declared inoperable inoperable to comply with ACTIONS. The sole purpose of this Specification Specification is to provide an exception to LCO 3.0.2 (e.g., to not comply with the applicable applicable Required Action(s)) to allow the performance performance of required testing to to demonstrate:
- a. OPERABILITY of the equipment The OPERABILITY equipment being returned returned to service; or
- b. OPERABILITY of other equipment.
The OPERABILITY administrative controls ensure the time the equipment The administrative equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time time absolutely necessary to perform absolutely perform the required required testing to demonstrate demonstrate Specification does not provide time to perform OPERABILITY. This SpeCification perform any other preventive or corrective preventive corrective maintenance.
maintenance.
An example example of demonstrating demonstrating the OPERABILITY OPERABILITY of the equipment equipment being being returned to service is reopening a containment returned containment isolation valve that has been closed to comply with Required Actions Actions and must be reopened to perform the the required testing.
required testing.
An example example of demonstrating demonstrating the OPERABILITY equipment is taking OPERABILITY of other equipment taking an inoperable an inoperable channel channel or or trip trip system system out out of the tripped condition to prevent tripped condition prevent the the trip function from trip from occurring occurring during during the the performance performance of required required testing testing on another channel in in the other trip system. A similar example example of demonstrating demonstrating OPERABILITY the OPERABI LlTY of other equipment equipment is taking an inoperable inoperable channel channel or triptrip system out of the tripped condition to permit the logic to function and indicate indicate appropriate response the appropriate response during the performance performance of required testing on another channel in in the same trip system.
LCO 3.0.6 LCO 3.0.6 establishes establishes an exception exception to LCO 3.0.2 for supported supported systems that have a support system system LCO specified in specified in the Technical Technical Specifications (TS).
Specifications (TS).
This This (continued)
(continued)
- SUSQUEHANNA SUSQUEHANNA -- UNITUNIT 11 TS /I B 3.0-8 Revision 3
PPL Rev. 3 LCO APPLICABILITY 3.0 B 3.0 B 3.0 CONDITION FOR OPERATION LIMITING CONDITION OPERATION (LCO) APPLICABILITY APPLICABILITY LCO 3.0.6 LCO exception is provided provided because LCO 3.0.2 would require that the ConditionsConditions (continued) and Required Required Actions of the associated inoperable supported associated inoperable supported system LCO be entered solely due to the inoperability inoperability of the support system. This This exception is justified because the actions that are required to ensure the the maintained in a safe condition are specified plant is maintained specified in the support system LCOs Required Required Actions. These Required Required Actions may include entering the the supported system's Conditions Required Actions or may specify, other Conditions and Required Required Actions. When a support system is inoperable Required inoperable and there is an LCO specified for itit in the TS, the supported supported system(s) are required to be be inoperable ififdetermined declared inoperable determined to be inoperable inoperable as a result of the support system system inoperability. However, itit is not necessary necessary to enter into thethe supported supported systems' Conditions Required Actions unless directed Conditions and Required directed to dodo so by the support system's Required Actions. The potential potential confusion andand related to the entry into multiple support and inconsistency of requirements related supported supported systems' LCOs' Conditions and Required Actions are eliminated eliminated by providing providing all the actions that are necessary necessary to ensure the plant is is maintained in a safe condition in the support system's Required condition in Required Actions.
However, there are instances instances where a support system's Required Action may either either direct a supported system to be declared inoperable inoperable or direct entry intointo
- Conditions Conditions and Required Action. Regardless support Required Actions for the supported system. This may occur immediately or after some specified Regardless of whether support system's Required specified delay whether it is delay to perform some other Required immediate immediate or after some inoperable or directs entry into Conditions and Required Actions for a inoperable supported supported system, the applicable delay, Required Action directs a supported system to be declared applicable Conditions and Required Actions shall be occur Required when a declared be entered entered in accordance accordance with LCO 3.0.2.
Specification Specification 5.5.11, Determination Program 5.5.11, "Safety Function Determination Program (SFDP),"
ensures ensures loss of safety function safety function is detected and appropriate actions are taken.
Upon entry into LCO 3.0.6, an evaluation shall be made to determine ifif loss of safety fUnction function exists. Additionally, other limitations, remedial actions, or compensatory identified as a result of the support system compensatory actions may be identified inoperability inoperability and corresponding corresponding exception to entering entering supported supported system Conditions and Required Required Actions. The SFDP implements requirements of implements the requirements LCO 3.0.6.
Cross division checks 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 supported systems systems of the redundant redundant OPERABLE OPERABLE support (continued)
(continued)
SUSQUEHANNA SUSQUEHANNA -- UNITUNIT 11 TS I/ B 3.0-9 Revision 2
PPL Rev. 3 LCO APPLICABILITY APPLICABILITY B 3.0 3.0 B
B 3.0 LIMITING B OPERATION (LCO) APPLICABILITY CONDITION FOR OPERATION LIMITING CONDITION LCO 3.0.6 system are OPERABLE, thereby ensuring safety function is retained. IfIfthis this (continued) evaluation determines determines that a loss of safety safety function exists, the appropriate appropriate Conditions and Required Actions of the LCO in which the loss of safety function function exists are required required to be entered.
This loss of safety function does not require the assumptionassumption of additional additional single single failures or loss of offsite power power or concurrent loss of emergency emergency diesel generators. Since operation is being restricted accordance with the restricted in accordance the ACTIONS of the support system, any resulting temporary temporary loss of redundancy or redundancy single failure protection is taken into account. Similarly, the ACTIONS for inoperable inoperable offsite circuit(s) and inoperable inoperable diesel generator(s) provide the provide the necessary necessary restriction for cross train inoperabilities. This explicit cross train verification for inoperable inoperable AC electrical electrical power sources also acknowledges acknowledges that supported system(s) are not declared supported declared inoperable inoperable solely as a result of inoperability inoperability of a normal normal or emergency emergency electrical power source source (refer to the the definition of OPERABILITY).
When a loss of safety function ýis determined to exist, and the SFDP requires is determined requires entry into the appropriate Conditions and Required Required Actions of the LCO in in which the loss of safety function exists, consideration consideration must be given to the specific specific
- type of function affected. Where a loss of safety function single TS support appropriate support system LCO adequately for the support system.
function is solely due to a support system (e.g., loss of automatic start due to inoperable instrumentation, instrumentation, or loss of pump suction source due to low tank level) the appropriate LCO is the LCO adequately address the inoperabilities The inoperable ACTIONS ACTIONS the for inoperabilities of that system without reliance on entering its supported system LCO. When the loss of a
function is the result of multiple support systems, the appropriateappropriate LCO is the the LCO LCO forfor the the supported system.
supported system.
LCO 3.0.7 There There are certain special special tests and operations operations required to be performed at various times over the life of the unit. These These special tests and operations are necessary to demonstrate necessary demonstrate select unit performance performance characteristics, characteristics, to perform special maintenance maintenance activities, and to perform perform special evolutions. Special Operations LCOs in Section 3.10 allow specified TS requirements to be be performances of these special changed to permit performances special tests and operations, which otherwise could not be performed performed if if required to comply with the requirements requirements of these TS. Unless otherwise specified, all the other TS requirements remain unchanged. This will ensure all appropriate requirements of the MODE appropriate requirements MODE or other specified condition not directly associated with or required to be changed to .
directly associated perform the special test or operation operation will remain in in effect.
(continued)
(continued)
SUSQUEHANNA - UNIT SUSQUEHANNA UNIT 1 TS / B 3.0-10 3.0-10 Revision 2
PPL Rev. 3 LCO APPLICABILITY B3.0 B 3.0 B 3.0 LIMITING CONDITION LIMITING CONDITION FOR OPERATION (LCO) (LCO) APPLICABILITY LCO 3.0.7 The Applicability Applicability of a Special Operations Operations LCO represents represents a condition condition not (continued) necessarily in compliance necessarily compliance with the normal requirements requirements of the TS.
Compliance with Special Operations Compliance Operations LCOs is optional. A A special operation may be performed perfonned either under the provisions of the appropriate Special Operations LCO or under Operations under the other applicable applicable TS requirements. If If it it is desired to perform perfonn the special operation provisions of the Special operation under the provisions Operations LCO, the requirements Operations requirements of the Special Special Operations Operations LCO shall be be followed. When a Special Special Operations LCO requires another another LCO to be met, only the requirements of the LCO statement are required to be met regardless regardless of that LCOs Applicability Applicability (i.e., should the requirements of this other LCO not not be met, the ACTIONS of the Special Special Operations LCO apply, not the ACTIONS ACTIONS of the other other LCO). However, there are instances instances where the Special Operations LCO ACTIONS may direct the other LCOs' ACTIONS Operations ACTIONS be met.
The Surveillances of the other LCO are not required to be met, unless unless specified in the Special Operations Special Operations LCO. If If conditions exist such that thethe Applicability of any other LCO LeO is met, all the other LCOs requirements requirements (ACTIONS and SRs) are required to be met concurrent concurrent with the requirements requirements of the Special Special Operations Operations LCO.
- LCO 3.0.8 LCO 3.0.8 establishes conditions conditions under which systems are considered to remain capable of perfonning performing their intended snubbers are not capable capable of providing intended safety function when associated providing their associated solely due to one or more snubbers not capable support function(s). This is appropriate because associated support function(s).
This LCO states that the supported system is not considered to be inoperable inoperable capable of performing their associated because a limited length of time is is allowed for maintenance, maintenance, testing, or repair of one or more snubbers not not capable performing their associated capable of perfonning appropriate associated support function(s) and appropriate compensatory measures compensatory measures of TRO 3.7.8 are followed. The snubber requirements do not meet the criteria requirements criteria in 10 CFR 50.36(c)(2)(ii),
50.36(c)(2)(ii), and, as such, are appropriate appropriate for control within the Technical Requirements Manual.
Technical Requirements If If the allowed allowed time expires and the snubber(s) are unable to perform perform theirtheir associated support associated support function(s), the affected affected supported system's LCO(s) must must be declared declared not met and the Conditions Conditions and Required Required Actions entered entered in in accordance with LCO 3.0.2.
accordance (continued)
SUSQUEHANNA - UNIT SUSQUEHANNA UNIT 1 TS / B 3.0-11 3.0-11 Revision 2
PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0
- B 3.0 LCO 3.0.8 LC03.0.8 (continued)
CONDITION FOR OPERATION (LCO) APPLICABILITY LIMITING CONDITION LIMITING LCO 3.0.8.a applies applies when one or more snubbers snubbers are not capable providing capable of providing associated support function(s) to a single train or subsystem of a multiple their associated multiple train or subsystem supported subsystem supported system or to a single train or subsystem supported system. LCO 3.0.8.a 3.0.8.a allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore the snubber(s) before before declaring the supported system inoperable. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion hour Completion reasonable based Time is reasonable based on the low probability probability of a seismic event concurrent concurrent with an event that would require operation of the supported supported system occurring occurring while the snubber(s) associated support snubber(s} are not capable of performing their associated function and due to the availability of the redundant redundant train of the supported supported system.
LCO 3.0.8.b 3.0.8.b applies when one or more snubbers are not capable of providing providing their associated associated support function(s) to more more than one train or subsystem of a multiple train or subsystem supported supported system. LCO 3.0.8.b allows 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to restore the snubber(s) before declaring declaring the supported system inoperable.
inoperable. The The Completion Time is reasonable based on the low probability of a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Completion seismic event concurrent concurrent with an event that would require operation operation of the the supported supported system occurring occurring while the snubber(s) are not capable capable of performing their associated support function.
- LCO 3.0.8 requires that risk be assessed and managed. Industry and NRC guidance guidance on the implementation implementation of 10 CFR 50.65(a)(4) (the Maintenance Rule) does not address seismic risk. However, use of LCO Maintenance 3.0.8 should be considered considered with respect to other plant maintenance activities, and integrated integrated into the existing extent possible so that maintenance existing Maintenance maintenance on any unaffected (the maintenance Maintenance Rule process to the unaffected train or subsystem LCO the is properly properly controlled, and emergent issues are properly addressed. addressed. The The assessment need risk assessment qualitative need not be quantified, but may be a qualitative awareness of the vulnerability awareness vulnerability of systems and components components when one or or more snubbers are not able to perform their associated support support function.
((continued) continued)
SUSQUEHANNA -- UNIT SUSQUEHANNA UNIT 1 TS / B 3.0-11la TS/B3.0-11a Revision 0 Revision
PPL Rev. 3 LCO APPLICABILITY B 3.0 3.0 B 3.0 B OPERATION (LCO) APPLICABILITY LIMITING CONDITION FOR OPERATION BASES BASES SRs SR 3.0.1 through SR 3.0.4 establish establish the general requirements requirements applicable to all Specifications Specifications and apply at all times, unless otherwise otherwise stated.
SR 3.0.1 SR 3.0.1 establishes the requirement requirement that SRs must be met during the the MODES or other specified conditions conditions in the Applicability Applicability for which the the requirements of the LCO apply, unless otherwise otherwise specified in the individual SRs. This Specification is to ensure ensure that Surveillances Surveillances are performed performed to verify the OPERABILITY OPERABILITY of systems and components, and that variables are within within specified specified limits. Failure to meet a Surveillance Surveillance within the specified specified Frequency, in accordance accordance with SR 3.0.2, constitutes a failure to meet an LCO.
Systems and components components are assumed assumed to be OPERABLE when the the associated associated SRs have been met. Nothing in this Specification, however, is to be construed as implying that systems components are OPERABLE systems or components OPERABLE when:
- a. The systems or components are known to be inoperable, inoperable, although still meeting the SRs; or
- b. The requirements requirements of the Surveillance(s) are known to be not met between required Surveillances other specified performances.
required Surveillance performances.
Surveillances do not havehave to be performed when the unit is in specified condition in a MODE condition for which the requirements of the associated are not applicable, unless otherwise MODE or associated LCO otherwise specified. The SRs associated with a LCO Special Special Operations LCO are only applicable applicable when the Special Operations Operations LCO is used as an allowable exception to the requirements of a Specification.
LCO is used as an allowable exception to the requirements of a Specification.
Unplanned events events may satisfy the requirements (including applicable (including applicable acceptance acceptance criteria) for a given SR. In In this case, the unplanned unplanned event may be be credited as fulfilling the performance performance of the SR. This allowance includes those those SRs whose performance is normally whose performance normally precluded precluded in a given MODE or other specified condition.
(continued)
(continued)
- SUSQUEHANNA- - UNIT 1 SUSQUEHANNA 3.0-12 TS / B 3.0-12 Revision 1
PPL Rev. 3 LCO APPLICABILITY APPLICABILITY 3.0 B 3.0 B 3.0 LIMITING CONDITION LIMITING CONDITION FOR OPERATIONOPERATION (LCO) APPLICABILITY SR 3.0.1 Surveillances invoked Surveillances, including Surveillances invoked by Required Required Actions, do not (continued) have to be performed have performed on inoperable inoperable equipment equipment because because the ACTIONS define ACTIONS define the remedial measures measures that apply. Surveillances Surveillances have to be met and. and performed in performed in accordance accordance with SR 3.0.2, prior to returning equipment to OPERABLE status.
OPERABLE status.
Upon completion completion of maintenance, appropriate post maintenance maintenance testing is is required to declare equipment required equipment OPERABLE. This includes includes ensuring applicable applicable Surveillances are not failed and their most recent performance Surveillances performance is in in accordance with SR 3.0.2. Post maintenance accordance maintenance testing may not be possible in in specified conditions the current MODE or other specified conditions inin the Applicability Applicability due to thethe necessary unit parameters necessary parameters not having been established. In In these situations, equipment may be considered the equipment considered OPERABLE OPERABLE provided provided testing has beenbeen satisfactorily completed satisfactorily completed to the extent possible and the equipment equipment is notnot otherwise believed believed to be incapable incapable of performing its function. This will allowallow operation to proceed operation proceed to a MODE or other specified specified condition where other necessary post maintenance necessary maintenance tests can be completed.
completed.
Some examples of this process are:
- a. Control Rod Drive maintenance maintenance during refueling that requires scram testing at > 800 psi. However, ifif other appropriate satisfied, the control rod can be considered startup to proceed startup appropriate testing is completed and the scram time testing of SR 3.1.4.3 is
. satisfactorily completed considered OPERABLE. This allows proceed to reach 800 psi to perform perform other necessary allows necessary testing.
- b. High pressure coolant injection (HPCI) maintenance maintenance during shutdown that requires system functional tests at a specified specified pressure. Provided other appropriate testing is satisfactorily satisfactorily completed, startup can proceed with HPCI considered OPERABLE. This allows operation to reach the specified specified pressure to complete the necessary necessary post maintenance testing.
SR 3.0.2 SR 3.0.2 establishes establishes the requirements requirements for meeting the specified Frequency for Surveillances and any Required Required Action with a Completion Time that requires the periodic periodic (continued)
(continued)
- SUSQUEHANNA - UNIT 1 SUSQUEHANNA TS /I B 3.0-13 3.0-13 Revision 2
PPL Rev. 3 LCO APPLICABILITY APPLICABILITY B 3.0 3.0 B 3.0 LIMITING CONDITION CONDITION FOR OPERATIONOPERATION (LCO) APPLICABILITY SR 3.0.2 performance of the Required performance Required Action on a "once per..."
per... " interval.
(continued)
SR 3.0.2 permits a 25% extension of the interval SR3.0.2 interval specified inin the Frequency.
Surveillance scheduling and considers plant This extension facilitates Surveillance plant operating conditions that may not be suitable for conducting the SurveillanceSurveillance (e.g., transient conditions or other ongoing Surveillance or maintenance ongoing Surveillance maintenance activities).
The 25% extension extension does not significantly degrade the reliability that results performing the Surveillance at its specified Frequency. This is based on from performing the recognition recognition that the most probable result of any particular particular Surveillance Surveillance being performed verification of conformance performed is the verification conformance with the SRs. The The exceptions exceptions to SR 3.0.2 are those Surveillances Surveillances for which the 25% 25% extension extension of the interval interval specified in the Frequency Frequency does not apply. These exceptions exceptions are stated in in the individual Specifications.
As stated in in SR 3.0.2, the 25% extension also does not apply to the initial portion of a periodic periodic Completion Time that requires performance performance on a "once per..."
per... " basis. The 25% extension applies to each performance after the initial each performance performance.
performance. The initial performance performance of the Required Required Action, whether itit is a
- particular Completion diverse components or accomplishes in an alternative altemative manner.
Time.
remedial action, is considered a single particular Surveillance or some other remedial action with a single Completion One reason reason for not allowing extension to this Completion Time is that such an action usually verifies that no loss of function has occurred occurred by checking checking the status of redundant or accomplishes the function of the inoperable the single 25%
equipment inoperable equipment The provisions of SR 3.0.2 are not intended to be used repeatedly repeatedly merely as as convenience to extend Surveillance an operational convenience Surveillance intervals intervals (other than those consistent with refueling refueling intervals) intervals) or periodic periodic Completion Completion Time intervals intervals beyond those specified.
SR 3.0.3 SR 3.0.3 establishes the flexibility to defer declaring declaring affected affected equipment equipment inoperable or an affected inoperable affected variable outside the specified specified limits when a Surveillance has not been completed within the specified Surveillance specified Frequency. A delay (continued)
(continued)
- SUSQUEHANNA-UNIT SUSQUEHANNA - UNIT 11 TS I/ B 3.0-14 3.0-14 Revision 2 Revision
PPL Rev. 3 LCO APPLICABILITY B 3.0 3.0
- B 3.0 LIMITING SR 3.0.3 LIMITING CONDITION (continued)
CONDITION FOR OPERATION whichever OPERATION (LCO) APPLICABILITY APPLICABILITY period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater, applies from the point in in time that itit is discovered discovered that the the Surveillance has not been performed in accordance Surveillance accordance with SR 3.0.2, and not at the time that the specified Frequency was not met.
specified Frequency adequate time to complete This delay period provides adequate complete Surveillances Surveillances that have have been missed. This delay period permits permits the.completion the completion of a Surveillance Surveillance complying with Required before complying Required Actions or other remedial measures measures that might preclude completion of the Surveillance.
The basis for this delay period includes includes consideration consideration of unit conditions, adequate planning, adequate planning, availability of personnel, the time required required to perform the the Surveillance, the safety significance significance of the delay in in completing completing the required Surveillance, and the recognition that the most probable probable result of any particular Surveillance being performed is the verification of conformance particular conformance with the requirements.
When a Surveillance Surveillance with a Frequency based not on the time intervals, but but upon specified unit conditions, operating operating situations, or requirements requirements of regulations (e.g., prior to entering entering MODE 1 after each fuel loading, or in in
- accordance with 10 CFR 50, Appendixj, accordance exemptions, etc.)etc.) is discovered Appendix j, as modified by approved discovered to not have been performed when specified, SR 3.0.3 allows for the full delay period of up to the specified Frequency perform the Surveillance. However, since there is not a time interval the missed Surveillance should be performed at the first reasonable opportunity.
Frequency to interval specified, reasonable provides a time limit for, and allowances SR 3.0.3 provides allowances for the performance performance of Surveillances that become applicable Surveillances applicable as a consequence consequence of MODE changes MODE changes Required Actions.
imposed by Required Failure to comply with specified Frequencies for SRs is expected specified Frequencies expected to be an infrequent occurrence. Use of the delay period established infrequent established by SR 3.0.3 is a flexibility which is not intended intended to be used used as an operational convenience convenience to extend Surveillance Surveillance intervals. While up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the limit of the specified Frequency is provided to perform Frequency perform the missed Surveillance, itit is expected that the missed Surveillance will be performed performed at the first reasonable reasonable opportunity.
The determination determination of the first reasonable reasonable opportunity should include consideration of the impact on plant risk (from include consideration delaying the Surveillance delaying Surveillance as well as any plant configuration changes changes required or shutting the plant down to perform the Surveillance) and impact impact on any analysis assumptions, in addition to unit conditions, planning, availability availability of of personnel, and the time required to perform the Surveillance. The risk impact should be managed managed through the program in in place to
- SUSQUEHANNA SUSQUEHANNA - UNIT UNIT 1 TS / B 3.0-15 3.0-15 (continued)
(coniinued)
Revision 2
PPL Rev. 3 LCO APPLICABILITY B 3.0 B 3.0 B 3.0 LIMITING LIMITING CONDITION CONDITION FOR OPERATION OPERATION (LCO) (LCO) APPLICABILITY APPLICABILITY SR 3.0.3 implement 10 CFR 50.65(a)(4) and its implementation implementation guidance, NRC NRC (continued) Regulatory Regulatory Guide 1.182, "Assessing and Managing Managing Risk before Maintenance Maintenance Activities Activities at Nuclear Nuclear Power Regulatory Guide Power Plants." This Regulatory addresses Guide addresses consideration of temporary and aggregate consideration aggregate risk impacts, determination determination of risk management action thresholds, and risk management management management action up to and including plant shutdown. The missed including missed Surveillance Surveillance should be treated treated as an emergent condition as discussed in the Regulatory emergent Regulatory Guide. The risk evaluation evaluation may use quantitative, qualitative, qualitative, or blended methods. The degree degree of depth and rigor of the evaluation should be commensurate commensurate with the importance importance of the component. Missed Surveillances important components should be Surveillances for important be analyzed quantitatively. If analyzed If the results of the risk evaluation evaluation determine determine the risk increase is significant, this evaluation should be used to determine increase determine the safest course of action. All missed Surveillances placed in the Corrective Surveillances will be placed Corrective Action Program.
If Surveillance is not completed If a Surveillance completed within the allowed allowed delay period, then the the equipment is considered equipment considered inoperable inoperable or the variable is considered outside the the specified limits and the Completion Times of the Required Required Actions for thethe Conditions begin immediately upon expiration applicable LCO Conditions expiration of the delay period. IfIf a Surveillance is failed within the delay period, then the equipment equipment is
- inoperable, or the variable Times of the Required immediately upon immediately variable is outside the specified limits and the Completion Required Actions for the applicable applicable LCO Conditions begin upon the failure of the Surveillance.
Completion of the Surveillance Surveillance within the delay period allowed by this Specification, or within the Completion Time of the ACTIONS, restores SpeCification, begin this restores compliance with SR 3.0.1.
3.0.1.
SR 3.0.4 SR 3.0.4 establishes the requirement requirement that all applicable SRs must be met met before entry into a MODE or other specified specified condition condition in the Applicability.
This Specification Specification ensures ensures that system and componentcomponent OPERABILITY OPERABILITY requirements and variable variable limits are met before entry into MODES or other specified conditions in the Applicability Applicability for which these these systems and and components ensure safe operationoperation of the unit. The provisions of this this Specification should not be interpreted interpreted as endorsing the failure to exercise exercise the good practice practice of restoring systems or components OPERABLE components to OPERABLE status before entering entering an associated MODE MODE or other specified condition condition in in the Applicability.
A A provision is included to allow entry into a MODE or other specified specified condition Applicability when an LCO is not met due to Surveillance condition in the Applicability Surveillance not being met in accordance accordance with LCO 3.0.4.
(continued)
(continued)
- SUSQUEHANNA - UNIT 1 SUSQUEHANNA TS / B 3.0-16 3.0-16 Revision Revision 0
PPL Rev. 3 LCO APPLICABILITY 3.0 B 3.0 B 3.0 LIMITING CONDITION LIMITING CONDITION FOR OPERATION OPERATION (LCO) APPLICABILITY SR 3.0.4 However, in certain circumstances, circumstances, failing to meet an SR will not result in (continued) SR 3.0.4 restricting a MODE MODE change change or other specified condition change.
When a system, subsystem, division, component, device, or variable is inoperable or outside inoperable outside its specified limits, the associated associated SR(s) are not required to be performed, per SR 3.0.1, 3.0.1, which states that Surveillances Surveillances do do not have to be performed performed on inoperable inoperable equipment. When equipment equipment is inoperable, SR 3.0.4 does not apply to the associated SR(s) since the inoperable, the requirement for the SR(s) to be performed performed is removed. Therefore, failing failing to perform the Surveillance(s) within the specified Frequency does not result in an SR 3.0.4 restriction restriction to changing MODES or other specified changing MODES specified conditions of the Applicability. However, since the LCO is not met in this this instance, LCO 3.0.4 will govern any restrictions restrictions that may (or may not) apply to MODE or other specified specified condition changes. SR 3.0.4 does not not restrict changing MODES or other specified specified conditions of the Applicability when a Surveillance Surveillance has not been performed within the specified Frequency, Frequency, provided the requirement requirement to declare declare the LCO not met has has been delayed .in accordance with SR 3.0.3.
- in accordance The provisions provisions of SR 3.0.4 shall not prevent entry into MODES or other specified conditions in the Applicability Applicability that are required reql:'ired to comply comply with ACTIONS. In In addition, the provisions of SR 3.0.4 shall not prevent prevent changes in MODESMODES or other specified specified conditions in the Applicability that result from any unit shutdown.
shutdown. In In this context, a unit shutdown is defined defined as a change in MODE or other specified condition condition in the Applicability Applicability associated with transitioning from MODE 1 to MODE 2 or MODE 3, MODE 2 to MODE 3, and MODE 3 to MODE MODE 4.
The precise requirements for performance precise requirements performance of SRs are specified specified such that exceptions to SR 3.0.4 are not necessary. The specific time frames and conditions necessary necessary for meeting the SRs are specified in the Frequency, in the Surveillance, or both. This allows performance performance of Surveillances Surveillances when the prerequisite prerequisite condition(s) specified in a Surveillance Surveillance procedure procedure require entry into the MODE or other specified condition in the Applicability of the associated performance or completion of a associated LCO prior to the performance Surveillance. A A Surveillance performed until after Surveillance that could not be performed entering the LCOs Applicability, would have its Frequency Frequency specified specified such that itit is not "due" "due" until the specific specific conditions conditions needed are met.
Alternately, the Surveillance 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 time has been reached. Further discussion of the specific specific formats of SRs' annotation is found in Section 1.4, Frequency.
- SUSQUEHANNA - UNIT 1 SUSQUEHANNA TS / BB 3.0-17 3.0-17 Revision 0
PPL Rev. 3 Instrumentation ECCS Instrumentation B 3.3.5.1 B 3.3 B INSTRUMENTATION INSTRUMENTATION B 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation Emergency Instrumentation BASES BASES BACKGROUND BACKGROUND The purpose purpose of the ECCS instrumentation instrumentation is to initiate appropriate appropriate responses from the systems to ensure that the fuel is adequately adequately cooled in the event of a design design basis accident accident or transient.
anticipated operational For most anticipated operational occurrences occurrences and Design Basis Accidents Accidents (DBAs), a wide range of dependent independent parameters are dependent and independent monitored.
monitored.
The ECCS instrumentation instrumentation actuates actuates core spray (CS), low pressure pressure coolant coolant injection (LPCI), high pressure coolant injection (HPCI), Automatic (HPCI), Automatic Depressurization generators (DGs) and other Depressurization System (ADS), the diesel generators other described in the DG background.
features described background. The equipment equipment involved involved with with each of these systems systems with exception exception of the DGs and other features, is is described in the Bases for LCO 3.5.1, described 3.5.1, "ECCS-Operating."
- Core Spray System The CS System may be initiated by either Automatic either automatic or manual means.
Automatic initiation occurs for conditions conditions of Reactor Low, Low, Low, Level 1 or Drywell Pressure Reactor Reactor Vessel Water Pressure - Low. Each of these diverse variables Reactor Pressure Water Level Pressure - High concurrent with variables is monitored monitored by four redundant instruments. The initiation initiation logic for one CS loop is arranged in a one-out-of-two-twice arranged one-out-of-two-twice network usingusing level and pressure instruments which will generate instruments generate a signal when:
(1))
(1 both level level sensors sensors are tripped, or (2) two high drywell drywell pressure pressure sensors and two low reactor reactor vessel pressure sensors are tripped, or pressure (3) combination of one channel a combination channel of level level sensor and one of the the drywell pressure other channel of high drywell pressure sensor together together with its its associated low reactor vessel pressure sensor (i.e. Channel A A level sensor sensor and Channel C high drywell and low reactor vessel pressure pressure sensor).
- SUSQUEHANNA SUSQUEHANNA - UNIT UNIT 1 TS / B 3.3-101 (continued)
(continued)
Revision 0
PPL Rev. 3 Instrumentation ECCS Instrumentation B
B 3.3.5.1 BASES BASES BACKGROUND BACKGROUND Core Spray System (continued)
Once an initiation initiation signal is received by the CS control circuitry, the signal is sealed in until manually manually reset.
The logic can also be initiated by use of a manualmanual push button (one push subsystem). Upon receipt of an initiation button per subsystem). initiation signal, the CS pumps pumps are started 15 15 seconds after initiation signal ifif normal offsite power power is available and 10.510.5 seconds after diesel generator power is available.
The CS test line isolation valve, which is also a primary containment containment isolation valve (PCIV),
(PCIV), is closed closed on a CS initiation signal to allow full system flow assumed in the accident accident analyses and maintain primary containment isolated.
isolated.
The CS System also monitors the pressure in the reactor to ensure that, before the injection valves open, the reactor pressure pressure has fallen to a value value below the CS System's maximum design pressure.. pressure. The variable variable is monitored by four redundant redundant instruments.
instruments. The instrument instrument outputs are connected to relays whose contacts are arranged in a one-out-of-two one-out-of-two taken twice logic.
Low Pressure Coolant Injection Iniection System The LPCI is an operating mode of the Residual Residual Heat Removal (RHR)
System, with two LPCI subsystems. The LPCI subsystems may be be initiated by automatic or manual means. AutomaticAutomatic initiation occurs occurs for conditions of Reactor Vessel Water Level Low, Low, Low, Level 1 or or Drywell Pressure - High concurrent Drywell concurrent with Reactor Pressure - Low. Each of these diverse variables variables is monitored by four instruments instruments in two divisions.
Each division is arranged arranged in a one-out-of-two-twice one-out-of-two-twice network using level and pressure instruments generate a signal instruments which will generate signal when:
(1)
(1) both level level sensors are tripped, or (2) pressure sensors two high drywell pressure sensors and two low reactor vessel vessel pressure pressure sensors sensors are tripped, oror (3)
(3) aa combination combination of of one one channel channel level sensor and one of the other channel channel of high drywell drywell pressure pressure sensor together with its associated low reactor vessel pressure sensor.
- SUSQUEHANNA SUSQUEHANNA - UNIT 1 TS / B 3.3-102 3.3-102 (continued)
Revision 0 Revision
PPL PPL Rev. 33 Instrumentation ECCS Instrumentation BB 3.3.5.1 3.3.5.1 BASES BASES BACKGROUND BACKGROUND Low Pressure Coolant Injection Low Iniection System (continued)
(i.e. Channel A level (i.e. level sensor and Channel C C high drywell and low reactor vessel pressure sensor.).
The initiation logic is cross connected between divisions (i.e., (i.e., either start signal will start all four pumps and open both loop's injection valves).
Signal Once an initiation signal is received by the LPCI control control circuitry, the signal Signal is sealed in until manually reset.
reset. The cross division start signals for the pumps affect both the opposite division's start logic and the pump's pump's 4KV breaker start logic. The cross division start signal to the opposite opposite division's start logic is for improved reliability. The cross division start start signals to the pump's 4KV breaker breaker start logic is needed needed to ensure specificspecific control power failures do not prevent prevent the start of an adequate 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 generator power is available. IfIf normal power is available, LPCI pumps A and B will start immediately immediately and pumps C and D will start 7.0 seconds initiation seconds after initiation signal to limit loading loading of the offsite sources.
The RHR test line and spray line are also isolated isolated on a LPCI initiation signal to allow the full system flow assumed in the accident accident analyses and for those those valves which are also PCIVs maintain primary primary containment containment isolated.
The LPCI System monitors the pressure pressure in the reactor to ensure that, before an injection injection valve opens, the reactorreactor pressure has fallen to aa value value below below the LPCI System's maximum maximum design design pressure. The variable is monitored monitored by four redundant redundant instruments. The instrument instrument outputs outputs are connected connected to relays whose contacts contacts are arranged in a one-out-of-two arranged a one-out-of-two taken twice logic.
Logic Logic is provided provided to close close the recirculation recirculation pump discharge discharge valves to ensure that LPCI ensure LPCI flow does not bypass bypass the core when it injects into the the recirculation recirculation lines. The logic consists of an initiation signal (Low (Low reactor reactor water water level and highhigh drywell pressure in a one out of two taken twice drywell pressure twice logic) from both both divisions of LPCI instruments instruments and a pressure a pressure permissive. The The pressure pressure variable is monitored monitored by four redundant redundant instruments.
- SUSQUEHANNA- UNIT 1 SUSQUEHANNA - UNIT TS / B 3.3-103 3.3-103 (continued)
(continued)
Revision Revision 0
PPL Rev. 3 ECCS Instrumentation Instrumentation B
B 3.3.5.1 BASES BASES BACKGROUND BACKGROUND Low Pressure Pressure Coolant Coolant Injection Injection System (continued)
The instrument outputs are connected connected to relays whose contacts contacts are arranged in a one-out-of-two one-out-of-two taken twice logic.
Hiqh Iniection System High Pressure Coolant Injection The HPCI System may be initiated initiated by either automatic or manual means.
Automatic initiation Automatic initiation occurs for conditions of Reactor Reactor Vessel Water Level-Low Low, Level 2 or Drywell Pressure-High.
Pressure-High. Each of these variables is monitored by four redundant monitored redundant instruments. The instrument instrument. outputs are connected to relays whose contacts are arranged connected arranged in a one-out-of-two one-out-of-two taken twice logic for each each Function.
The HPCI System also monitors the water level level in the condensate storage storage tank (CST). HPCI suction is normally maintained maintained on the CST until it it transfers to the suppression suppression pool on low CST level or is manually transferred by the operator. Reactor grade water in the CST is the normal transferred source. Upon receipt of a HPCI initiation signal, the CST suction suction valve is automatically automatically signaled to open (it (it is normally normally in the open position) unless unless the suppression suppression pool suction valve is open. If If the water level in the CST falls to the level switch process setpoint setpoint value, an automatic automatic suction suction transfer is initiated. The suppression pool suction valve receives receives a signal to open and in parallel, the CST suction valve receives aa signal to close to complete the transfer. Two level switches are used to detect 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 HPCI PCI provides provides makeup makeup water to the reactor reactor vessel reactor until the reactor water level reaches the Reactor Vessel Water Level-High, Level-High, Level 8 trip, at which time the HPCI turbineturbine trips, which causes causes the turbine's stop valve, minimum flow valve, the cooling water isolation valve, and the injection injection valve to close. The logic is two-out-of-two two-out-of-two to provide high reliability the reliability of the HPCI System.
((continued) contif1ued)
- SUSQUEHANNA SUSQUEHANNA -- UNIT 1 TS / B B 3.3-104 3.3-104 Revision 2 Revision
PPL Rev. 3 ECCS Instrumentation Instrumentation B 3.3.5.1 BASES BASES BACKGROUND BACKGROUND Higqh High Pressure Pressure Coolant Injection Injection System System (continued)
The HPCI System automatically automatically restarts if Reactor Vessel Water if a Reactor Level-Low Level-Low Low, Level 2 signal is subsequently received.
Automatic Automatic Depressurization Depressurization System The ADS may be initiated initiated by either automatic or manual manual means.
Automatic initiation occurs when signals indicating Reactor Reactor Vessel Water Level-Low Level-Low Low Low, Level 1; Drywell Pressure-High Pressure-High or ADS Drywell Bypass.Actuation Timer; confirmed Bypass'Actuation confirmed Reactor Vessel Vessel Water Level-Low, Level 3; and CS or LPCI Pump Discharge Pressure-High are all present Discharge Pressure-High present and the ADS Initiation Initiation Timer has timed out. ThereThere are two instruments instruments each for Reactor Vessel Water Level-LowLevel-Low Low Low, Level 1I and Drywell Pressure-High, Pressure-High, and one instrumentinstrument for confirmed Reactor Vessel Water confirmed React.or Water Level-Low, Level 3 in each of the two ADS trip systems. Each of these instruments instruments drives drives a relay whose contacts contacts form the initiation logic.
Each Each ADS trip system system includes a time delay between satisfying the the initiation logic and the actuation of the ADS valves. The ADS InitiationInitiation Timer time delay setpoint is chosen to be long enough that the HPCI system has sufficient sufficient operating operating time to recover recover to a level above Level 1, yet not so long that the LPCI and CS Systems are unable to adequately adequately cool the fuel ifif the HPCI fails to maintain that level. An alarm in the control annunciated when either of the timers is timing. Resetting room is annunciated the Resetting the ADS initiation signals resets the ADS Initiation Initiation Timers. The ADS also discharge pressures monitors the discharge pressures of the four LPCI pumps and the four CS CS pumps. Each ADS trip system includes two discharge discharge pressure permissive instruments permissive instruments from both CS pumps in the division and from associated Division (i.e.,
either of the two LPCI pumps in the associated (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 depressurized the vessel. With both CS pumps in a division division or one of the LPCI pumps operating operating sufficient sufficient flow flow is available available to permit automatic automatic depressurization.
depressurization.
The ADS logic in each trip system is arranged in two strings. Each string has a contact from each of the following variables:
variables: Reactor Vessel Water Level-Low Level-Low Low. Low, Level 1; Drywell
- SUSQUEHANNA - UNIT 1 SUSQUEHANNA TS / B]
B 3.3-105 3.3-105 (continued)
(continued)
Revision 00 Revision
PPL Rev. 3 ECCS Instrumentation ECCS Instrumentation B 3.3.5.1 3.3.5.1 B
BASES BASES BACKGROUND BACKGROUND Automatic Depressurization System (continued)
Automatic Depressurization Pressure-High; Pressure-High; or Drywell Pressure Bypass Drywell Pressure Bypass Actuation Timer. One of the the two strings in each each trip system must also havehave a confirmed Reactor Vessel 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 pump discharge pressure signal discharge signal must be present present to initiate an ADS trip system.
Either the A or B trip system will cause all the ADS relief valves valves to open.
Once the Drywell Pressure-High Pressure-High signal, the ADS Drywell Pressure Bypass Bypass Actuation Timer, or the ADS initiation signal is present, it is individually individually sealed sealed in until manually manually reset.
Manual inhibit switches Manual switches are provided in the control room for the ADS; however, their function function is not required for ADS OPERABILITY OPERABILITY (provided ADS is not inhibited when required to be OPERABLE).
OPERABLE).
Diesel Generators and Other Initiated Features Features The DGs may be initiated by either automatic or manual means.
Automatic initiation occurs for conditions conditions of Reactor Reactor Vessel Water Level-Water Level-Low Low Low, Level 1 or Drywell Pressure-High.
Pressure-High. The DGs are also initiated upon loss of voltage signals (Refer to the Bases for LCO 3.3.8.1, initiated 3.3.8.1, "Loss of Power (LOP) Instrumentation,"
Instrumentation," for a discussion of these signals.)
The initiation logic is arranged arranged in a one-out-of-two-twice one-out-of-two-twice network network using level and pressure instruments which will generate pressure instruments generate a signal when:
(1) both level sensors 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.
pressure DGs A and B receive their initiation signal from CS system initiation logic logic Division I and Division IIII respectively. DGs C and D receive their initiation initiation signals from either LPCI systems initiation logic Division I or Division II. II.
The DGs DGs can can also be be started started manually from the control manually from control room room andand locally locally from the from the associated associated DGDG room.
room. The The DG DG initiation initiation signal is aa signal is
- SUSQUEHANNA - UNIT SUSQUEHANNA UNIT 1 TS /I B 3.3-106 3.3-106
((continued) continued)
Revision 0 Revision
PPL Rev. 3 ECCS Instrumentation Instrumentation B 3.3.5.1 BASES BASES BACKGROUND BACKGROUND Diesel Generators Generators and Other Initiated FeaturesFeatures (continued) sealed in signal and must be manually manually reset. The DG initiation logic is reset by resetting the associated ECCS initiationinitiation logic. Upon receipt of a loss of coolant accident accident (LOCA)
(LOCA) initiation signal, each DG is automatically automatically started, is ready to load in approximately approximately 10 seconds, and will run in standby conditions (rated voltage and speed, with the DG output output breaker open). The DGs will only energize energize their respective respective Engineered Engineered Safety Feature Feature buses if if a loss of offsite power occurs. (Refer to Bases for LCO 3.3.8.1.).
In In addition to DG initiation, initiation, the ECCS instrumentation instrumentation initiates initiates other design features. Signals from the CS System logic initiate initiate (1) the reset of Emergency Service two Emergency Service Water (ESW) timers, (2) the reset of the the degraded grid timers for the 4kV buses on Unit 1, (3) LOCA load shed degraded schemes, and (4) the trip of Drywell Cooling equipment. Signals from the the LPCI LPCI System logic initiate (1) (1) the reset of two Emergency Emergency Service Service Water Water (ESW) timers, (2) the trip of turbine building chillers, and (3) the trip of reactor building chillers. The ESW pump timer reset feature feature assures the the ESW pumps do not start concurrently concurrently with the CS or LPCI pumps. IfIf one one or both ESW pump timer resets in a division or reactor building/turbine building/turbine building chiller trips are inoperable; inoperable; two offsite circuits with the 4kV buses buses aligned to their normal configuration are required to be OPERABLE. OPERABLE. If If one or both ESW pump timer resets in a division or reactor reactor building/turbine building building/turbine building chiller trips are inoperable; inoperable; the effects on one one offsite circuit have have not been analyzed; and therefore, the offsite circuit is assumed not to be capable capable of accepting the required loads during during certain certain accident events. The ESW pump timer reset is not required in MODES 4 because concurrent and 5 because concurrent pump starts, on a LOCA signal, of the ESW pumps (initiated by the DG start circuitry) with CS or LPCI pumps cannot cannot occur MODES.
occur in these MODES.
(continued)
(continued)
SUSQUEHANNA SUSQUEHANNA - UNIT 1 TS / B 3.3-107 3.3-107 Revision 1
PPL Rev. 3 Instrumentation ECCS Instrumentation B 3.3.5.1 BASES BASES (continued)
APPLICABLE The actions of the ECCS are explicitly assumed in the safety analyses of SAFETY References 11 and 2. The ECCS is initiated References initiated to preserve preserve the integrity of the ANALYSES, fuel cladding by limiting the post LOCA peak cladding temperature to less less LCO, and than the 10 CFR 50.46 limits.
APPLICABILITY APPLICABI LlTY ECCS instrumentation instrumentation satisfies Criterion Criterion 3 of the NRC Policy Statement Statement (Ref. 4). Certain instrumentation instrumentation Functions Functions are retained for other reasonsreasons and are described below in the individual individual Functions discussion.
The OPERABILITY OPERABILITY of the ECCS instrumentation instrumentation is dependent dependent upon the the OPERABILITY OPERABILITY of the individual individual instrumentation instrumentation and channel Functions channel Functions specified 3.3.5.1-1. Each specified in Table 3.3.5.1-1. Each Function must have a required number number of OPERABLE OPERABLE channels, with their setpoints setpoints within the specified Allowable Allowable Values, where appropriate.
appropriate. The actual actual setpoint is calibrated consistent calibrated consistent with applicable methodology assumptions. Each ECCS applicable setpoint methodology ECCS subsystem must also respond respond within its assumed assumed response time.
3.3.5.1-1, footnotes Table 3.3.5.1-1, footnotes (b) and (c), are added added to show that certain certain instrumentation Functions are also required ECCS instrumentation required to be OPERABLE OPERABLE to perform DG initiation and actuation of other Technical perform Technical Specifications Specifications (TS)(TS) function.
- Allowable Values are specified for each ECCS Function specified table. Nominal trip setpoints are specified The nominal setpoints exceed exceed Operation the setpoints are selected Allowable Allowable Value specified in the setpoint selected to ensure between CHANNEL specified in the setpoint calculations.
that the setpoints ensure thatthe setpoints do not CALIBRATIONS.
between CHANNEL CALIBRATIONS.
Operation with a trip setpoint less conservative conservative than the nominal trip trip the not setpoint, but within its Allowable Value, is acceptable. A channel is inoperable inoperable if its actual trip setpoint setpoint isisnot
'not within its required Allowable Allowable Value. Trip setpoints are those predetermined predetermined values of output at which an action should take place. The setpoints are compared compared to the actual process parameter parameter (e.g., reactor reactor vessel water level),
level), and when the the measured measured output value of the process process parameter parameter reaches the setpoint, the the associated device associated device changes state. The analytic limits are derived from the the limiting values of the process parameters parameters obtained from the safety analysis. The Allowable Values are derived from the analytic limits, corrected for calibration, process, and some of the instrument errors. The corrected The trip setpoints are then determined, determined, accounting accounting for the remaining instrument instrument errors (e.g., drift). The trip setpoints setpoints derived in this manner manner
- SUSQUEHANNA SUSQUEHANNA - UNIT 1 TS / B 3.3-108 3.3-108 (continued)
Revision 0 Revision
PPL Rev. 3 Instrumentation ECCS Instrumentation B 3.3.5.1 BASES BASES APPLICABLE APPLICABLE provide adequate adequate protection because instrumentation uncertainties, because instrumentation SAFETY process effects, calibration tolerances, instrument instrument drift, and severe ANALYSES, ANALYSES, environment environment errors (for by 10 CFR 50.49) are accounted for.
LCO, and and APPLICABILITY APPLICABILITY An exception to the methodology methodology described described to derive the Allowable ValueValue (continued) methodology used to determine is the methodology determine the Allowable Allowable Values Values for the ECCS ECCS pump start time delays and HPCI CST Level 1 - Low. These Allowable Allowable Values are based on systemsystem calculations calculations and/or engineering engineering judgement judgement which establishes a conservative limit at which the function should occur.
In general, the individual In individual Functions are required to be OPERABLE OPERABLE in the the MODES or other specified specified conditions conditions that may require ECCS (or DG) initiation to mitigate the consequences consequences of a designdesign basis transient or accident. To ensure reliable reliable ECCS and DG function, a combination of Functions is required to provide primary and secondarysecondary initiation signals.
The specific Applicable Applicable Safety Analyses, LCO, and Applicability discussions Function by Function basis.
discussions are listed below on a Function Core Spray and Low Pressure Pressure Coolant Injection Injection Systems Systems Reactor Vessel Water Level-Low 1.a, 2.a. Reactor Level-Low Low Low, Level Level 1 reactor pressure vessel (RPV) water level indicates Low reactor indicates that the capability to cool the fuel may be threatened. Should RPV water level decrease decrease too far, fuel damage damage could result. The low pressure ECCS and associated DGs are initiated initiated at Level 1 to ensure that core spray and flooding flooding functions are available available to prevent prevent or minimize fuel damage. The Reactor Reactor Vessel Water Level-Low Level-Low Low Low, Level 1 is one of the Functions Functions assumed to be OPERABLE OPERABLE and capablecapable of initiating the ECCS during the the analyzed in References transients analyzed References 2. In Reactor Vessel In addition, the Reactor Vessel Level-Low Low Low, Level 1 Function is directly Water Level-Low directly assumed in thethe analysis of the recirculation line break (Ref. 1). 1). The core cooling function of the ECCS, along with the scram of scram action of the Reactor Protection Protection System (RPS), ensures that the fuel peak cladding temperature temperature remains remains below below the limits of 10 CFR 50.46.
(continued)
(continued)
SUSQUEHANNA -- UNIT 1 SUSQUEHANNA TS / B 3.3-109 3.3-109 Revision 1
PPL Rev. 3 ECCS Instrumentation EGGS Instrumentation B 3.3.5.1 BASES BASES APPLICABLE APPLIGABLE 1.a, 2.a. Reactor Reactor Vessel Water Level-Low Level-Low Low Low, Level 1 SAFETY SAFETY (continued)
ANALYSES, LCO, and LGO, Reactor Reactor Vessel Water Level-LowLevel-Low Low Low, Level 1 signals are initiated initiated APPLICABILITY APPLIGABILITY from four level instruments instruments that sense the difference difference between between the the pressure due to a constant column of water (reference pressure (reference leg) and the the pressure pressure due to the actual water level (variable leg) in the vessel.
The Reactor Vessel Water Level-Low Level-Low Low Low, Level 1 Allowable Value Value is chosen chosen to allow time for the low pressure core flooding systems to activate and provide provide adequate adequate cooling cooling The initiation initiation logic for LPCI LPGI pumps and injection valves is cross connected such that either division's start signal will start all four pumps and open both loop's injection valves. This cross division logic is required in in MODES 1, 1, 2, and 3. In In MODES 4 and 5, redundancy redundancy in the initiation initiation circuitry is not required. Therefore, in MODES 4 and 5 for LPGI, LPCI, only one one division of initiation logic is required.
DGs G C and D D which are initiated from the LPGI LPCI LOCA initiation are cross LOGA initiation connected such that both DGs receive an initiation signal from both Divisions of the LPCI LOCA initiation circuitry. This cross connected LPGI LOGA connected logic logic is only required in MODES MODES 1, 1, 2, and 3. In MODES redundancy in MODES 4 and 5, redundancy in the DG initiation circuitry circuitry is not required. Therefore, in MODES MODES 4 and 5 for DGs G C and D D only one division of EGGS ECCS initiation logic is required.
Four channels of Reactor Vessel Water Level-Low Level-Low Low Low, Level 1 Function are only required to be OPERABLE when the EGGS Function ECCS or DG(s) are required required to be OPERABLE OPERABLE to ensure that no single instrument failure preclude EGGS can preclude ECCS and DG initiation. Refer to LGO LCO 3.5.1 and LGO LCO 3.5.2, "ECCS-Shutdown," for Applicability "EGGS-Shutdown," Applicability Bases for the low pressure EGGS ECCS subsystems; LGO LCO 3.8.1, "AC Sources-Operating";
3.8.1, "AG Sources--Operating"; and LGO LCO 3.8.2, "AC Sources-Shutdown," for Applicability "AG Sources-Shutdown," Applicability Bases for the DGs.
1.b, 2.b. Drywell Pressure-High 1.b,2.b. Pressure-High High pressure in the drywell drywell could indicate indicate a break in the reactor coolant pressure boundary (RCPB). The low pressure EGGS boundary (RGPB). ECCS (provided a concurrent concurrent low reactor pressure pressure signal is
- SUSQUEHANNA SUSQUEHANNA - UNIT 1 TS / B 3.3-110 3.3-110 (continued)
Revision Revision 0
PPL Rev. 3 Instrumentation ECCS Instrumentation B 3.3.5.1
- BASES BASES APPLICABLE APPLICABLE SAFETY Pressure-High (continued) 1.b, 2.b. Drywell Pressure-High ANALYSES, present) and associated associated DGs, without aa concurrent concurrent low reactor pressure pressure LCO, and signal, are initiated upon receipt of the Drywell Pressure-High Pressure-High Function in APPLICABI LlTY APPLICABILITY order order to minimize minimize the possibility possibility of fuel damage. The Drywell Pressure-Pressure-High Function, along with the Reactor Reactor Water Level-Low Level-Low Low Low, Level 1 Function, is directly directly assumed in the analysis of the recirculation recirculation line break (Ref. 1).
1). The core cooling function of the ECCS, along with the the scram action of the RPS, ensures ofthe ensures that the fuel peak cladding temperature temperature remains below the limits of 10 CFR 50.46.
High drywell drywell pressure signals are initiated initiated from four pressure pressure instruments instruments that sense sense drywell pressure. The Allowable Value was selected to be as practical and be indicative of a LOCA inside primary containment.
low as practical The Drywell Pressure-High Pressure-High Function is required to be OPERABLE when the ECCS or DG is required to be OPERABLEOPERABLE in conjunction conjunction with times times when the primary containment containment is required to be OPERABLE. Thus, four channels of the CS and LPCI Drywell Pressure-High Pressure-High Function are required to be OPERABLE OPERABLE in MODES MODES 1, 2, and 3 to ensureensure that no single single instrument failure can preclude preclude ECCS and DG initiation. In In MODES 4 and 5, the Drywell Pressure-High Pressure-High Function is not required, since there is energy in the reactor to pressurize insufficient energy pressurize the primary containment to Drywell. Pressure-High Drywell Pressure-High setpoint. Refer Refer to LCO 3.5.1 for Applicability Bases for the low pressure ECCS subsystems and to LCO 3.8.1 for for Applicability Bases for the DGs.
Applicability Reactor Steam Dome Pressure-Low 1.c, 1.d, 2.c, 2.d Reactor Low reactor reactor steam dome pressure signals are used as permissives permissives for the the low pressure ECCS subsystems. The low reactor reactor pressure permissive is is.
provided to prevent prevent a high drywell pressure condition condition which is not accompanied by low reactor pressure, i.e. a false LOCA Signal, accompanied signal, from disabling two RHR pumps on the other unit. The low reactor steam dome dome pressure permissive permissive also ensures that, prior to opening the injection injection valves of the low pressure ECCS subsystems, the reactor pressure has reactor pressure has fallen to a value below these subsystems' maximum design design pressure. The The Reactor Steam Dome Pressure-Low is one of the Functions assumed to Dome Pressure-Low OPERABLE and capable of permitting be OPERABLE permitting initiation of the ECCS during the the transients transients analyzed Reference 2. In analyzed in Reference In addition, the Reactor Steam Dome Dome Pressure-Low Function Pressure-Low Function is directly assumed in the analysis of the the recirculation line break break (continued)
(continued)
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PPL Rev. 3 ECCS Instrumentation ECCS Instrumentation B 3.3.5.1 BASES BASES APPLICABLE 1.c, 1.d, 2.c, 2.d Reactor Pressure-Low (continued)
Reactor Steam Dome Pressure-Low SAFETY ANALYSES, 1). The core cooling function of the ECCS, along with the scram (Ref. 1).
LCO, and action action of the RPS, ensures ensures that the fuel peak cladding temperaturetemperature APPLICABILITY APPLICABILITY remains below below the limits of 10 CFR 50.46.
The Reactor Reactor Steam Dome Pressure-Low Pressure-Low signals are initiated from four four pressure instruments instruments that sensesense the reactor dome pressure.
The pressure instruments are set to actuate pressure instruments between the Upper and actuate between Lower Allowable Allowable Values on decreasing decreasing reactor dome pressure.
The Upper Allowable Value is low enough enough to ensure that the reactor dome dome pressure has fallen to a value below below the Core Spray and RHR/LPCI maximum design pressures to preclude preclude piping overpressurization.
overpressurization.
The Lower Allowable Value is high enough enough to ensure that the ECCS ECCS prevents the fuel peak cladding injection prevents' cladding temperature temperature from exceeding exceeding the the limits of 10 CFR 50.46.
DGs C and 0 D which are initiated from the LPCI LOCA initiation are cross initiated from' cross connected such that both DGs receive receive an initiation signal from both Divisions of the LPCI LOCA initiation initiation circuitry. This cross connected connected logic logic is only required required in MODES 1, 2, and 3. In In MODES 4 and 5, redundancy in in the DG initiation circuitry is not required. Therefore, required. Therefore, in MODES MODES 4 and 5 for DGs C and 0 D only one division of ECCS initiation logic is required.
Four channels of Reactor Reactor Steam Pressure-Low Function are Steam Dome Pressure-Low are OPERABLE only when the ECCS is required to be required to be OPERABLE be OPERABLE OPERABLE to ensure that no single instrument failure can preclude preclude ECCS initiation. ReferRefer to LCO 3.5.1 and LCO 3.5.2 for ApplicabilityApplicability Bases Bases
.for the low pressure ECCS subsystems.
2.f. Manual 1.e, 2.f. Manual Initiation Initiation The Manual Manual Initiation Initiation push button channels channels introduce signals into the the appropriate appropriate ECCS logic to provide manual initiation capability and are manual initiation redundant to the automatic protective instrumentation.
automatic protective instrumentation. There is one push button for each each of the CS and LPCI subsystems (i.e., two for CS and two for LPCI).
The Manual Manual Initiation Initiation Function Function is not assumed in any accident or transient analyses analyses in the FSAR. However, the Function is
- SUSQUEHANNA - UNIT 1 SUSQUEHANNA TS / B 3.3-112 TS/B3.3-112 1
(continued)
(continued)
Revision Revision 1
PPL Rev. 3 ECCS Instrumentation Instrumentation B 3.3.5.1 BASES BASES APPLICABLE APPLICABLE 1.e, 2.f. Manual Initiation (continued)
SAFETY ANALYSES, ANALYSES, retained for overall redundancy and diversity diversity of the low pressure ECCS ECCS LCO, and function as required by the NRC in the plant licensing basis.
function as required by the NRC in the plant licensing basis.
APPLICABILITY
- SUSQUEHANNA SUSQUEHANNA - UNIT 1 TS / B 3.3-112a 3.3-112a (continued)
Revision 1
PPL Rev. 3 Instrumentation ECCS Instrumentation B 3.3.5.1 BASES BASES APPLICABLE 1.e, 2.f. Manual Manual Initiation (continued)
SAFETY ANALYSES, There There is no Allowable Value for this Function Function since the channels are LCO, and mechanically actuated mechanically actuated based solely on the position of the push buttons.
APPLICABILITY APPLICABI L1TY Each channel of the Manual Initiation Function Manual Initiation Function (one channel channel per subsystem) is required required to be OPERABLE OPERABLE only when the associated associated ECCS ECCS is required to be OPERABLE. Referto Refer to LCO 3.5.1 and LCO 3.5.2 for Applicability Applicability Bases for the low pressure ECCS subsystems.
2.e. Reactor Reactor Steam Dome Pressure-Low (Recirculation Discharge Valve Permissive)
(Recirculation Low reactor steam dome pressure signals are used used as permissives permissives for for recirculation discharge recirculation discharge and bypass valves closure. This ensures that the the LPCI subsystems inject into the properproper RPV location assumed assumed in the the safety analysis. The Reactor Reactor Steam Dome Pressure-Low Pressure-Low is one of the the Functions assumed assumed to be OPERABLE and capable of closing the valves valves during the transients analyzed analyzed in Reference Reference 2. The core cooling cooling function function of the ECCS, along with the scram action of the RPS, ensures ensures that the the fuel peak cladding temperature temperature remains below the limits of 10 10 CFR 50.46.
The Reactor Pressure-Low Function is directly assumed in Reactor Steam Dome Pressure-Low in the analysis analysis of the recirculation recirculation line break (Ref. 1).
1).
The Reactor Reactor Steam Dome Pressure-Low Pressure-Low signals are initiated initiated from four pressure instruments that sense the reactor dome pressure.
The Allowable Value is chosen to ensure that the valves close prior prior to commencement of LPCI injection flow into the core, as assumed in the commencement the safety analysis.
Four channels channels of the Reactor Reactor Steam Steam Dome Pressure-Low Pressure-Low Function are only required to be OPERABLE OPERABLE in MODES MODES 1, 2, and 3 with the associated associated recirculation pump discharge discharge valve open. With the valve(s) closed, the the function instrumentation instrumentation has been performed; thus, the Function Function is notnot required. In MODES 4 and 5, the loop injection locationlocation is not critical since since LPCI injection through the recirculation recirculation loop in either direction direction will still ensure that LPCI flow reaches the core (i.e.,
(Le., there is no significant significant reactor steam reactor steam dome dome back pressure).
back pressure).
- SUSQUEHANNA - UNIT 1 SUSQUEHANNA 3.3-113 TS / B 3.3-113 (continued)
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Revision Revision 1
PPL Rev. 3 ECCS Instrumentation EGGS Instrumentation B 3.3.5.1 BASES BASES APPLICABLE APPLICABLE HPCI System SAFETY ANALYSES, 3.a. Reactor Reactor Vessel Level-Low Low, Level 2 Vessel Water Level-Low LCO, and and APPLICABILITY APPLICABILITY Low RPV water level indicates indicates that the capability to cool the fuel may be be (continued) threatened.
threatened. Should RPV water level decreasedecrease too far, fuel damage could could result. Therefore, the HPCI System is initiated at Level 2 to maintain level above the top of the active fuel. The Reactor Reactor Vessel Water Level-Low Low, Level 2 is one of the Functions assumed assumed to be OPERABLE OPERABLE analyzed analyzed in Reference Reference 2. Additionally, the Reactor Vessel Water Water Level-Low Level-Low Low, Level 2 Function associated associated with HPCI is directly directly assumed in the analysis analysis of the recirculation recirculation line break (Ref. 2). The core cooling function of the the ECCS, along with the scram action of the RPS, ensures that the fuel peak ECGS, temperature remains below the limits of 10 CFR cladding temperature GFR 50.46.
Reactor Vessel Reactor Vessel Water Level-Low Level-Low Low, Level 2 signals are initiated initiated from four level instruments instruments that sense the difference difference between between the pressure due due to a constant column of water (reference leg) and the pressure due to the the actual water level (variable leg) in the vessel.
The HPGI HPCI Reactor Reactor Vessel Water Level-Low Low, Level 2 Allowable Water Level-Low Allowable Value is chosen to be consistent with the Reactor Core Isolation Cooling Cooling (RCIC) System Reactor Vessel Water Level - Low Low, Level 2 Allowable Allowable value.
Four channels of Reactor Reactor Vessel Level-Low Low, Level 2 Vessel Water Level-Low Function are required to be OPERABLE Function OPERABLE only when HPCI is required to be be OPERABLE OPERABLE to ensure ensure that no single instrument instrument failure can preclude preclude HPCI initiation. Refer to LCO 3.5.1 for HPCI Applicability Applicability Bases.
3.b. Drywell Drvwell Pressure-Hiah Pressure-High High pressure in the drywell drywell could indicate indicate a break break in the RCPB. The The HPCI System is initiated upon receipt of the Drywell Pressure-High Function in order to minimize the possibility of fuel damage. The Drywell Pressure-High Function, along with the Reactor Water Level-Low Pressure-High Level-Low Low, Level 2 Function, is directly assumed assumed in the analysis analysis of the recirculation line break (Ref. 1). The core cooling function of the EGGS, ECCS, along with the the scram scram action of the the
- SUSQUEHANNA - UNIT 1 SUSQUEHANNA TS / B 3.3-114 3.3-114 (continued)
(continued)
Revision 1
PPL Rev. 3 ECCS Instrumentation Instrumentation B 3.3.5.1
- BASES BASES APPLICABLE SAFETY 3.b. Drywell Pressure-High (continued)
ANALYSES, RPS, ensures ensures that the fuel peak cladding temperature temperature remains below the the LCO, and limits of 10 10 CFR 50.46.
APPLICABILITY High drywell drywell pressure signals are initiated initiated from four pressure instruments pressure instruments that sense drywell drywell pressure. The Allowable Allowable Value was selected selected to be asas low as possible possible to be indicative of aa LOCA inside inside primary primary containment. .'
Four channels of the Drywell Pressure-High Pressure-High Function Function are required to be be OPERABLE when HPCI is required to be OPERABLE OPERABLE to ensureensure that nono single instrument failure can preclude HPCI initiation. Refer to LCO 3.5.1 for the Applicability Applicability Bases for the HPCI System.
3.c. Reactor 3.c. Reactor Vessel Water Level-High, Level Level 8 High RPV water level indicates indicates that sufficient cooling water inventory exists in the reactor reactor vessel such such that there is no danger to the fuel.
Therefore, Therefore, the Level 8 signal is used to trip the HPCI turbine to preventprevent overflow into the main main steam steam lines (MSLs). The Reactor Reactor Vessel Water Water Level-High, Level 8 Function is not assumed in the accident Level-High, accident and and transient transient analyses. ItIt was retained since it is a potentially potentially significant significant contributor to risk.
Reactor Vessel Water Level-High, Reactor Level-High, Level 8 signals for HPCI are initiated from two level instruments. Both Level 8 signals are required required in order to trip HPCI. This ensures that no single instrument failure can preclude preclude an HPCI initiation or trip. The Reactor Vessel Water Level-High, Level 8 Allowable Value is chosen to prevent prevent flow from the HPCI Systemfrom System from overflowing into the MSLs.
Two channels of Reactor Reactor Vessel Water Level-High, Level 8 Function are required to be OPERABLE OPERABLE only when HPCI is required to be OPERABLE.
Refer to LCO 3.5.1 and LCO 3.5.2 for HPCI Applicability Applicability Bases.
Condensate Storage 3.d. Condensate Storage Tank Level-Low The Condensate Condensate Storage Storage Tank-Low conservatively Tank-Low signal indicates that a conservatively NPSH-available limit is being approached.
calculated NPSH-available
- SUSQUEHANNA- - UNIT SUSQUEHANNA UNIT 1 TS / B 3.3-115 3.3-115 (continued)
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Revision Revision 1
PPL Rev. 3 Instrumentation ECCS Instrumentation B
B 3.3.5.1 BASES APPLICABLE APPLICABLE Condensate Storage 3.d. Condensate Storaqe Tank Level-Low (continued)
SAFETY ANALYSES, Normally Normally the suction valves between between HPCI and the CST are open and, LCO, and and upon receiving a HPCI initiation signal, water for HPCI injection would be be APPLICABILITY taken from the CST. However, if if the water level in the CST falls to the the level switch process process setpoint value, an automatic automatic suction transfer is initiated. The suppression 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. The HPCI suction transfer complete transfer must be initiated prior to CST level dropping dropping below below the technical specification specification allowable allowable value to ensure that an adequate suction head for the pump and an uninterrupted ensure uninterrupted makeup water is available supply of makeup available to the HPCI pump. The Function is implicitly implicitly assumed in the accident and transient transient analyses analyses (which take take credit for HPCI) since the analyses assume that the HPCI suction source source is the suppression pool.
Condensate Storage Condensate Storage Tank Level-Low Level-Low signals are initiated from two level instruments. The logic is arranged such that either either level switch can cause cause the suppression suppression pool suction valves to open and the CST suction valve to to Condensate Storage Tank Level-Low Function close. The Condensate Function Allowable Allowable
- Value is high enough adequate pump suction head enough to ensure adequate head while water is being taken from the CST.
Two channels channels of the Condensate Storage Tank Level-Low FunctionFunction are required to be OPERABLE OPERABLE only when HPCI is required to be OPERABLEOPERABLE to ensure that no single instrument instrument failure can preclude preclude HPCI swap to suppression pool source. Refer to LCO 3.5.1 for HPCI Applicability suppression Bases.
- SUSQUEHANNA -- UNIT 1 SUSQUEHANNA TS / B B 3.3-116 3.3-116
((continued) continued)
Revision 3
PPL Rev. 3 Instrumentation ECCS Instrumentation B 3.3.5.1 BASES APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY APPLICABI LlTY Manual Initiation 3.e. Manual The Manual Manual Initiation push button channel channel introduces the introduces signals into the HPCI logic to provide provide manual initiation initiation capability and is redundant to thethe automatic protective instrumentation.
automatic instrumentation. There is one push button for the the HPCI System.
The Manual Manual Initiation Function is not assumed in any accidentaccident or transient analyses in the FSAR. However, the Function is retained for overall redundancy and diversity diversity of the HPCI function as required required by the NRC in in the plant licensing basis.
\
There There is no Allowable Value for this Function since since the channel channel is mechanically actuated based mechanically based solely on the position of the push button.
One channel of the Manual Initiation Function Function is required to be be OPERABLE only when the HPCI System System is required to be OPERABLE.
Refer to LCO 3.5.1 for HPCI Applicability Applicability Bases.
- SUSQUEHANNA - UNIT 1 SUSQUEHANNA TS /I B 3.3-117 3.3-117 (continued)
(continued)
Revision Revision 1
PPL Rev. 3 ECCS Instrumentation Instrumentation B 3.3.5.1
- BASES BASES APPLICABLE APPLICABLE SAFETY Automatic Dewressurization Depressurization System ANALYSES, 4.a.
4.a, 5.a. Reactor Vessel Water Level-Low Level-Low Low Low, Low. Level 1 LCO, and and APPLICABILITY APPLICABI LlTY Low RPV water level indicates indicates that the capability to cool the fuel may be be (continued) threatened.
threatened. Should RPV water level decreasedecrease too far, fuel damage damage could result. Therefore, ADS receives receives one of the signals necessary necessary for initiation initiation from this Function. The Reactor Vessel Water Level-LowLevel-Low Low Low, Level 1 is one of the Functions Functions assumed to be OPERABLE OPERABLE and capablecapable of initiating the ADS during the accident analyzed analyzed in Reference 1. The The core cooling function of the ECCS, along with the scram scram action of the the RPS, ensures ensures that the fuel peak peak cladding temperature remains below the the limits of 10 10 CFR 50.46.
Reactor Vessel Water Level-Low Level-Low Low Low, Level 1 signals are initiated from four level instruments instruments that sense the difference difference between the the pressure due to a constant column of water (reference leg) and the the pressure due to the actual water level (variable leg) in the vessel. Four Four channels channels of Reactor Reactor Vessel Water Level-Low Level-Low Low Low, Level 1 Function Function are required required to be OPERABLE OPERABLE only when ADS is required to be be OPERABLE OPERABLE to ensure that no single instrument failure can preclude ADS ADS initiation. Two channels input to ADS trip system A, A, while the other two channels channels input to ADS trip system B. B. Refer to LCO 3.5.1 for ADS ADS Applicability Bases.
Applicability The Reactor Reactor Vessel Water Level-Low Level-Low Low Low, Level 1 Allowable Value Value is chosen to allow time for the low pressure core flooding flooding systems to initiate and provide adequate adequate cooling.
4.b. 5.b. Drywell 4.b,5.b. Drvwell Pressure-High Pressure-Hiah High pressure in the drywell drywell could indicate a break in the RCPB.
Therefore, ADS receives receives one of the signals necessary necessary for initiation from this Function in order order to minimize the possibility possibility of fuel damage. The The Drywell Pressure-High is assumed assumed to be OPERABLE OPERABLE and capablecapable of initiating initiating the ADS during the accidents accidents analyzed Reference 2. The core analyzed in Reference cooling function of the ECCS, along with the scram action of the RPS, ensures that the fuel peak cladding temperature temperature remains below limits below the limits of 10 CFR 50.46.
- SUSQUEHANNA SUSQUEHANNA - UNIT 1 TS / B 3.3-118 3.3-118 (continued)
Revision 0 Revision
PPL Rev. 3 ECCS Instrumentation Instrumentation B 3.3.5.1 BASES BASES APPLICABLE 4.b, 5.b. Drywell Pressure-High Pressure-High (continued)
SAFETY ANALYSES, Drywell Pressure-High Pressure-High signals are initiated from four pressure instruments pressure instruments LCO, and that sense sense drywell drywell pressure. The Allowable Value was selectedselected to be as APPLICABILITY APPLICABI LlTY indicative of a LOCA inside primary containment.
low as possible and be indicative Four channels channels of Drywell Pressure-High Pressure-High Function are only required to be be OPERABLE OPERABLE when ADS is required to be OPERABLE OPERABLE to ensure that no no single instrument failure can preclude preclude ADS initiation.
initiation. Two channels input input to ADS trip system A, while the other two channels channels input to ADS triptrip system system B. B. Refer to LCO 3.5.1 for ADS Applicability Applicability Bases.
4.c, 5.c. Automatic Depressurization Depressurization System Initiation TimerTimer The purpose purpose of the Automatic Depressurization System Initiation Timer is Automatic Depressurization to delay depressurization depressurization of the reactor reactor vessel to allow the HPCI System time to maintain reactor vessel water level. Since the rapid rapid depressurization depressurization caused by ADS operation operation is one of the most severe transients transients on the reactor vessel, its occurrence occurrence should should be limited. By delaying initiation of the ADS Function, the operator delaying operator is given the chance to monitor monitor the success or failure of the HPCI System to maintain water level, and then to decide decide whether or not to allow ADS to initiate, to delay initiation initiation further by recycling recycling the timer, or to inhibit initiation permanently.
The Automatic Depressurization Automatic Depressurization System Initiation Timer Function is assumed to be OPERABLE OPERABLE for the accident analyses of Reference Reference 1 that require ECCS initiation and assume failure of the HPCI System.
Depressurization System Initiation Timer relays, There are two Automatic Depressurization one in each of the two ADS trip systems. The Allowable Value for the the Automatic Depressurization Depressurization System System Initiation Initiation Timer is chosen so that there*
there is still time after depressurization depressurization for the low pressure ECCS subsystems subsystems to provide adequate adequate core cooling.
cooling.
Two channels channels of the Automatic Automatic Depressurization Depressurization System Initiation Timer Function Function are only required to be OPERABLE OPERABLE when the ADS is required to OPERABLE to ensure that no single instrument failure can preclude be OPERABLE preclude ADS initiation. (One channel inputs to ADS trip system A, while the other channel
- SUSQUEHANNA - UNIT SUSQUEHANNA UNIT 1 TS / B 3.3-119 3.3-119 (continued)
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Revision 0
PPL Rev. 3 ECCS Instrumentation EC.CS Instrumentation B 3.3.5.1 BASES BASES APPLICABLE APPLICABLE 4.c, 5.c.
4.c, S.c. Automatic Depressurization System Automatic Depressurization System Initiation Initiation Timer (continued)
SAFETY ANALYSES, ANALYSES, inputs to ADS trip system B. B. Refer to LCO 3.5.1 for ADS Applicability LCO, and Bases.
APPLICABILITY APPLICABI LlTY 4.d. S.d.
4.d, 5.d. Reactor Vessel Water Level-Low, Level 3 The Reactor Vessel Water Water Level-Low, Level 3 FunctionFunction is used by the the ADS only as a confirmatory confirmatory low water level signal. ADS receivesreceives one of the signals necessary necessary for initiation from Reactor Reactor Vessel Water Level-Low Low Low, Level 1 signals. In In order to prevent prevent spurious initiation of the the ADS due to spurious Level 1 signals, a Level 3 signal must also be be received received before ADS initiation commences.
Reactor Reactor Vessel Vessel Water Level-Low, Level 3 signals are initiated from two instruments that sense the difference level instruments between the pressure due to a difference between constant column of water (reference (reference leg) and the pressure pressure due to the the actual water level (variable leg) in the vessel. The Allowable Value for Reactor Reactor Vessel Vessel Water Level-Low, Level 3 is selected selected at the RPS Level 3 scram Allowable Allowable Value for convenience. Refer to LCO 3.3.1.1, 3.3.1.1, "Reactor "Reactor
- Protection Protection this Function.
System Two channels of Reactor (RPS) Instrumentation,"
Instrumentation,"
Reactor Vessel Water for the Bases discussion discussion of Water Level-Low, Level 3 Function are required to be OPERABLE only when the ADS is required to be OPERABLE to ensure that no single instrument OPERABLE be preclude ADS instrument failure can preclude of ADS initiation. One channel inputs initiation. inputs to ADS trip system system A, A, while the other channel inputs to ADS trip system B. B. Refer to LCO 3.5.1 for ADS ADS Applicability Applicability Bases.
4.e, 4.f, 4.f, 5.e, S.e, 5.f.
S.f. Core Spray Spray and Low Pressure Iniection Pressure Coolant Injection Pump Discharge Pressure-High Discharge Pressure-High Discharge Pressure-High The Pump Discharge Pressure-High signals from the CS and LPCI LPCI pumps are used as permissives for ADS initiation, indicating indicating that there is aa source of low pressure cooling water available once the ADS has has depressurized depressurized the vessel. Pump Discharge Pressure-High one of the Pressure-High is the Functions assumed Functions assumed to be OPERABLE and capable capable of permitting ADS.
- SUSQUEHANNA SUSQUEHANNA - UNIT UNIT 1 TS I/ B 3.3-120 3.3-120 (continued)
(continued)
Revision 0
PPL Rev. 3 ECCS Instrumentation Instrumentation B
B 3.3.5.1 BASES BASES APPLICABLE APPLICABLE 4.e, 4.f, 5.e, 5.f. Core Spray and Low Pressure Coolant Injection Iniection SAFETY Discharge Pressure-High Pump Discharge Pressure-High (continued)
ANALYSES, LCO, and initiation during the events analyzed in Reference Reference 1 with an assumed APPLICABILITY APPLICABI LlTY HPCI failure. For these events the ADS depressurizes depressurizes the reactor vessel so that the low pressure ECCS can perform perform the core cooling cooling functions.
This core cooling function of the ECCS, along with the scram action of the the RPS, ensures that the fuel peak cladding temperature temperature remains below the the limits of 10 CFR 50.46. Pump discharge pressure signals are initiated from discharge pressure twelve pressure twelve pressure instruments, two on the discharge discharge side of each of the four LPCI'pumps discharge of each of CS pumps. In LPCI'pumps and one on the discharge In order to generate an ADS permissive in one trip system, itit is necessary that only only one LPCI pump or one CS subsystem subsystem indicate indicate the high discharge discharge pressure condition. The Pump Discharge Pressure-High pressure Pressure-High Allowable Allowable Value is less than the pump discharge pressure when the pump is discharge pressure operating in aa full flow mode and high enough to avoid any condition that results in a discharge discharge pressure permissive permissive when the CS and LPCI pumps pumps are aligned for injection injection and the pumps are not running. The actual operating point of this function is not assumed assumed in any transient or accident accident analysis.
- Twelve Twelve channels of Core Spray and Low Pressure Coolant Injection Discharge Pressure-High Discharge Pressure-High Function are only required when the ADS is required to be OPERABLE OPERABLE to ensure that no single instrument failure can preclude ADS initiation.
associated with CS pumps initiation. Two CS channels Injection Pump required to be OPERABLE OPERABLE channels pumps A and C and four LPCI channels associated single Pump with LPCI pumps A and C are required for trip system A. A. Two CS CS channels associated with CS pumps Band B and D D and four LPCI channels channels associated with LPCI pumps Band B and D are required required for trip system B. ReferRefer to LCO 3.5.1 for ADS Applicability Bases.
4.g, 5.g.
4.q, 5.q. Automatic Depressurization Depressurization System System Drvwell Drywell Pressure Bypass Bypass Actuation Timer One of the signals required for ADS initiation is Drywell Pressure-High.
Pressure-High.
However, if if the event requiring ADS initiation occurs occurs outside the drywell (e.g., main steam line break outside outside containment),
containment), a high drywell drywell pressure pressure signal may never never be present. Therefore, the Automatic Depressurization Depressurization System System Drywell Pressure Bypass Actuation
- SUSQUEHANNA SUSQUEHANNA - UNIT 1 TS / B 3.3-121 (continued)
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PPL Rev. 3 ECCS Instrumentation Instrumentation B 3.3.5.1 B
- BASES BASES APPLICABLE APPLICABLE SAFETY 4a. 5.g. Automatic 4.9,5.9. Automatic Depressurization Depressurization System Drywell Pressure Bypass Actuation Timer (continued)
Bypass ANALYSES, LCO, and and Timer is used to bypass the Drywell Pressure-High Pressure-High Function after a APPLICABILITY APPLICABI L1TY certain time period has elapsed.
elapsed. Operation of the Automatic Automatic Depressurization System Drywell Pressure Depressurization Pressure Bypass Actuation Actuation Timer Timer Function is not assumed assumed in any accident analysis. The instrumentation is retained in the TS because because ADS is part of the primary primary success path for for mitigation mitigation of a DBA.
There are four Automatic Depressurization Depressurization System Drywell Dryweli Pressure Pressure Bypass Actuation Timer relays, two in each of the two ADS trip systems.
The Allowable Depressurization System Low Allowable Value for the Automatic Depressurization Low Water Level Actuation Timer is chosen to ensure that there is still time time after depressurization depressurization for the low pressure ECCS subsystems to provide provide adequate core cooling.
adequate cooling.
Four channels channels of the Automatic Depressurization System Drywell Automatic Depressurization Pressure Bypass Actuation Timer Function are required to be OPERABLE OPERABLE only when the ADS is required to be OPERABLEOPERABLE to ensure that no single single instrument instrument failure can preclude preclude ADS initiation. Refer to LCO 3.5.1 for ADS Applicability Bases.
4.h, 5.h. Manual Manual Initiation Initiation Manual Initiation The Manual Initiation push button channels channels introduce introduce signals signals into the ADSADS logic to provide manual initiation capability and are redundant to the the automatic protective instrumentation.
automatic protective instrumentation. There are two push buttons for each each ADS trip system for a total of four.
The Manual Manual Initiation Initiation Function is not assumed in any accident accident or transient transient analyses in the FSAR. However, the Function is retained for overall redundancy redundancy and diversity of the ADS functions as required by the NRC in in the plant licensing licensing basis.
There is no Allowable Value for this Function since the channels channels are mechanically mechanically actuated actuated based solely on the position of the push buttons.
Four channels channels of the ManualManual Initiation Function Function (two channels per trip trip system) are only only
- SUSQUEHANNA SUSQUEHANNA - UNIT 1 TS / B 3.3-122 3.3-122 (continued)
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PPL Rev. 3 Instrumentation ECCS Instrumentation B 3.3.5.1
- BASES BASES APPLICABLE SAFETY 4.h, 5.h. Manual Initiation (continued)
ANALYSES, required to be OPERABLE when the ADS is required to be OPERABLE. OPERABLE.
LCO, and Refer to LCO 3.5.1 for ADS Applicability Applicability Bases.
APPLICABILITY APPLICABI LlTY ACTIONS A Note has been provided to modify the ACTIONS ACTIONS related to ECCS ECCS instrumentation channels. Section 1.3, Completion Completion Times, specifies specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed expressed in the Condition discovered to be Condition discovered be inoperable or not within limits will not result in separate entry into the inoperable the Condition. Section 1.3 also specifies specifies that Required Required Actions of the the Condition continue to apply for each additional additional failure, with Completion Completion Times based on initial entry entry into the Condition. However, the Required Actions for inoperable inoperable ECCS instrumentation instrumentation channels provideprovide appropriate compensatory appropriate compensatory measures measures for separate separate inoperable Condition inoperable entry for each inoperable inoperable ECCS instrumentation instrumentation channel.
A. 1
- Required Action A.1 directs entry into the appropriate Required referenced in Table 3.3.5.1-1.
referenced 3.3.5.1-1. The applicable appropriate Condition applicable Condition referenced table is Function dependent. Each time a channel is discovered inoperable, Condition A is entered for that channel and provides for transfer appropriate subsequent transfer to the appropriate subsequent Condition.
referenced in the discovered the B.1, B.2, and B.3 B.1, Required Actions B.1 B.1 and B.2 are intended intended to ensure that appropriate appropriate actions actions are taken if if multiple, inoperable, untripped channels within the the same Function same Function result in redundant redundant automatic initiation capability being lost lost for the feature(s). Required Action B.1 features features would be those that are initiated by Functions Functions 1.a, 1.b, 1.c, 2.a, 2.b, and 2.c (e.g., low pressure ECCS). The Required Action B.2 system would be HPCI. For Required Required B.1, redundant automatic initiation capability is lost ifif (a)
Action B.1, (a) one one 1 .a, 11.b, Function 1.a, .b, 1.c, 1 .c, 2.a, or 2.b is inoperable inoperable and untripped with only one one offsite source OPERABLE, or (b) one or more Function Function 1.al.a or Function 2.a channels in both divisions are inoperable and untripped, untripped, oror (c) one or more Function 1.b or Function 2.b channels in both divisions divisions are are (continued)
(continued)
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PPL Rev. 3 Instrumentation ECCS Instrumentation B 3.3.5.1 BASES BASES ACTIONS B.1, B.2, and B.3 (continued)
B.1, inoperable and untripped, or (d) one or more Function 1.c or Function 2.c 2.c channels inoperable and untripped.
channels in both divisions are inoperable For (a) above 1 .a, 11.b, above (Function 1.a, .b, 11.c,
.c, 2.a, or 2.b is inoperable inoperable and untripped with only one offsite source OPERABLE), the ESW pump timer source OPERABLE),
receive a reset signal and the Reactor resets may not receive Reactor Building Building chillers, Turbine Building Building chillers and the Drywell Drywell cooling cooling equipment equipment may not not receive a trip signal. Without the reset of the ESW pump timers and without the trip of the Reactor Reactor Building and Turbine Building chillers, the the OPERABLE OPERABLE offsite circuit may not be capable of accepting accepting starts the starts of the concurrently with CS or LPCI pumps. For this situation, both ESW pumps concurrently the OPERABLE OPERABLE offsite circuit and the DG, that would not be capable capable of starting, starting, should be declared inoperable.
inoperable. Actions required by LCO 3.8.1 "AC Sources Operating" or LCO 3.8.2 "AC Sources Sources Shutdown" should should be be taken or disable disable the affected reactor building/turbine building/turbine building chillers and disable disable the affected ESW pumps automatic initiation capability capability and take take the ACTIONS required by LCO 3.7.2 "ESW System".
For the Drywell cooling equipment trip, inoperability inoperability of this feature feature would associated drywell cooling fans be declared inoperable in require that the associated in accordance accordance with LCO 3.6.3.2 "Drywell Air Flow System". System".
With two offsite sources OPERABLE and one Function 1.a, 1.b, 1.c, 2.a, sources OPERABLE or 2.b inoperable inoperable and untripped, sufficient ECCS equipment equipment is available to meet meet the design design basis accident accident analysis.
(c) and (d) above, for each For (b), (c) each Division, since since each inoperable inoperable channel channel would have Required Required Action B.
B.11 applied separately (refer to Note), each inoperable ACTIONS Note), inoperable channel would only require the affected affeCted portion portion of the associated system system of low pressure pressure ECCS, DGs, and associated associated features to be declared declared inoperable. However, since channels channels in both Divisions are inoperable inoperable and untripped, and the CompletionCompletion TimesTimes started concurrently concurrently for the channels in both subsystems, this results in the affected affected portions in the associated associated low pressure pressure ECCS and DGs being concurrently declared inoperable.
concurrently declared For Required Action B.2, redundant automatic initiation capability automatic initiation capability is lost if if two Function 3.a or two Function Function 3.b channels inoperable and are inoperable untripped untripped in the same trip system. In this situation (loss of redundant redundant automatic automatic initiation capability), the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> hour allowance allowance of Required Required Action B.3 is not appropriate appropriate and the feature(s) associated associated with the the inoperable, untripped inoperable, untripped
- SUSQUEHANNA - UNIT 1 SUSQUEHANNA TS / B 3.3-124 (continued)
(continued)
Revision Revision 1
PPL Rev. 3 ECCS Instrumentation Instrumentation B 3.3.5.1 BASES ACTIONS ACTIONS B.1, B.1, B.2, and B.3 (continued) channels must be declared inoperable inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. As noted (Note 1 to Required Required Action B.1), Required Action B.1 is only applicable in MODES MODES 1, 1, 2, and 3. In MODES MODES 4 and 5, the specific initiation time of the low low pressure ECCS is not assumed and the probability of a LOCA is lower.
pressure Thus, a total loss of initiation capability for 24 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> hours (as allowed by Required Required Action B.3) is allowed during MODES MODES 4 and 5. There is no no similar Note provided for Required Action B.2 since HPCI instrumentation instrumentation is not required in MODES 4 and 5; thus, a Note is not necessary. Notes Notes are also provided provided (Note 2 to Required Action B.1 and the Note to Required Required Action B.2) to delineate delineate which Required Action Action is applicable applicable for each Function that requires entryentry into Condition B if an associated Condition B channel channel is inoperable.
inoperable. This ensures that the proper proper loss of initiation capability check is performed.
performed.
The Completion Time is intended intended to allow the operator time to evaluate evaluate and repair any discovered discovered inoperabilities. This Completion Time also also exception to the normal "time zero" for beginning the allowed allows for an exception allowed outage time "clock." For Required Action B.1, B.1, the Completion Completion Time only only
- begins upon discovery discovery that a redundant redundant feature in both Divisions (e.g.,
both CS subsystems) cannot be automatically automatically
- SUSQUEHANNA -- UNIT SUSQUEHANNA UNIT 1 TS / B 3.3-124a 3.3-124a (continued)
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PPL Rev. 3 Instrumentation ECCS Instrumentation B 3.3.5.1 B
BASES BASES ACTIONS B.1, B.2, and B.3 (continued)
B.1, initiated due to inoperable, untripped channels within the same Function Function as described described in the paragraph paragraph above. For Required Action B.2, the the Completion Time only begins upon discovery that the HPCI System cannot be automatically automatically initiated initiated due to two inoperable, inoperable, untripped untripped channels for the associated associated Function in the same trip system. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> hour Completion Time from discoverydiscovery of loss of initiation capability is acceptable because acceptable because it minimizes risk while allowing time for restoration or tripping of channels.
Because of the diversity of sensors available to provide initiation Because initiation signals signals redundancy of the ECCS design, an allowable out of service and the redundancy time service time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> hours has been shown to be acceptable acceptable (Ref. 3) to permitpermit restoration of any inoperable inoperable channel OPERABLE status. IfIf the channel to OPERABLE the inoperable channel inoperable channel cannot be restored to OPERABLE status within the the allowable out of service time, the channel must be placed in the tripped condition per Required Action B.3. Placing the inoperable inoperable channel channel in trip trip would conservatively conservatively compensate compensate for the inoperability, restore capability to accommodate a single failure, and allow operation to continue.
accommodate Alternately, ifif it is not desired to place channel in trip (e.g., as in the place the channel the case where placing the inoperable inoperable channel in trip would result in an initiation), Condition G must be entered initiation), entered and its Required Action taken.
C.1 and C.2C.2 Required Action C.1 is intended intended to ensure that appropriate actions are taken if inoperable channels if multiple, inoperable channels within the same Function result in in redundant automatic automatic initiation capability being lost for the feature(s).
Required Action C.1 features features would be those that are initiated initiated by Functions 1.d, 2.d, and 2.e (Le., (i.e., low pressure ECCS). RedundantRedundant automatic initiation capability automatic initiation capability is lost if if either (a) two or more Function 1.d channels channels are inoperable inoperable such that the trip system loses initiation initiation capability, (b) two or moremore Function 2.d channels are inoperable inoperable in the the same trip system such that the trip system loses initiation capability, or (c) two or more Function 2.e channels are inoperable (c) inoperable affecting affecting LPCI different subsystems.
pumps in different subsystems. In In this situation (loss of redundant redundant automatic automatic initiation initiation
- SUSQUEHANNA SUSQUEHANNA - UNIT 1 TS / BB 3.3-125 3.3-125 (continued)
(continued)
Revision 0
PPL Rev. 3 ECCS Instrumentation Instrumentation B 3.3.5.1 BASES BASES ACTIONS ACTIONS C.1 and C.2 (continued) capability), the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowance allowance of Required Required Action C.2 is not appropriate appropriate and the feature(s) associated with the inoperable inoperable channels must be declared inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Since each inoperable inoperable channel would have each inoperable have Required Action C.1 applied separately (refer to ACTIONS applied separately ACTIONS Note),Note), each inoperable channel would only require require the affected portion of the associated associated system to be declared declared inoperable. However, since channels for both low pressure ECCS subsystems subsystems are inoperable inoperable (e.g., both CS subsystems), and the Completion Times started concurrently for the channels in both subsystems, this results in the affected portions in both subsystems concurrently declared subsystems being concurrently declared inoperable. For Functions 1d, 2.d, and 2.e, the affected Functions 1.d, affected portions are the associated associated low pressure ECCS pumps. As noted (Note 1), 1), Required Required Action C.1 is only applicable applicable in MODES MODES 1, 2, and 3. In In MODES 4 and 5, the specific initiation time of the ECCS ECCS is not assumed assumed and the probability of a LOCA LOCA is lower. Thus, a total loss of automatic initiation automatic initiation capability for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (as allowed by Required Required Action C.2) is allowed during MODES allowed MODES 4 and 5. .
Note 2 states that Required Action Action C.1 is only applicable applicable for Functions 1.d, 2.d, and 2.e. Required Required Action C.1 C.1 is not applicable to Functions Functions 1.e, 2.f, and 3.e 3.e (which also require entry into this Condition Condition ifif a channel in these Functions is inoperable), since they are the Manual Initiation Functions and are not assumed inoperable),
in any accident accident or transient analysis. Thus, a total loss of manual initiation initiation capability for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (as allowed allowed by Required Required Action C.2) is allowed. Required Required Action C.1 is also not applicable applicable to Function 3.c (which also requires entry into this Condition if if a channel in this Function is inoperable),
inoperable), since the loss of one one channel channel results in a loss of the Function Function (two-out-of-two logic). This loss was was considered during the development considered Reference 3 and considered development of Reference acceptable considered acceptable for the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowed by Required Action C.2.
The Completion Time is intended intended to allow the operator operator time to evaluate and and repair any discovered discovered inoperabilities. This Completion Time also allows allows for an exception to the normal "time zero" for beginning the allowed outage time "clock."
exception For Required Action C.1, C.1, the Completion Completion Time only begins upon discovery discovery that the same feature in both subsystems subsystems (e.g., both CS subsystems) cannot be be automatically initiated automatically initiated (continued)
(continued)
SUSQUEHANNA - UNIT 1 SUSQUEHANNA TS / B 3.3-126 3.3-126 Revision 1 Revision
PPL Rev. 3 ECCS Instrumentation Instrumentation B 3.3.5.1 BASES BASES ACTIONS C.1 and C.2 (continued) due to inoperable inoperable channels channels within the same Function as described described in the the paragraph above. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion paragraph Completion Time from discovery discovery of loss of initiation capability is acceptable initiation acceptable because because it minimizes minimizes risk while allowing allowing time for restoration of channels.
Because Because of the diversity diversity of sensors sensors available to provide signals provide initiation signals and the redundancy redundancy of the ECCS design, an allowable out of service service timetime of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> has been shown to be acceptable acceptable (Ref. 3) to permit restoration of any inoperable inoperable channel to OPERABLE OPERABLE status. IfIf the the inoperable channel cannot be restored inoperable restored to OPERABLE OPERABLE status within the the allowable out of service allowable service time, Condition G G must be entered and its Required Required Action taken. The Required Required Actions do not allow placing the the channel in trip since this action would either either cause the initiation or itit would would not necessarily necessarily result in a a safe state for the channel in all events.
D.1. D.2.1, and D.2.2 0.1,0.2.1, 0.2.2 Required Required Action D.1 0.1 is intended intended to ensure appropriate actions ensure that appropriate actions are
- taken if multiple, inoperable, HPCI Function Function System.
3.d inoperable, untripped Automatic channels are untripped channels within the same Function result in aa complete loss of automatic the HPCI component inoperable inoperable of automatic suction swap), the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Actions 0.2.1 D.2.1 and 0.2.2 D.2.2 is not appropriate component initiation automatic component and initiation untripped.
initiation capability for capability capability is lost ifif two untripped. In this situation allowance of Required hour allowance appropriate and the HPCI (loss situation (loss HPCI. System must be be declared inoperable declared inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after discovery discovery of loss of HPCI HPCI initiation initiation capability. A Note identifies that Required Action 0.1 Note identifies D.1 is only applicable ifif HPCI pump suction is not aligned to the suppression the HPCI suppression pool, since, if if aligned, the Function Function is already performed.
performed. This allow s the HPCI HPCI pumppump suction to be realigned realigned to the Suppression Suppression Pool within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, if if desired.
desired.
The Completion Completion Time is intended to allow the operator time to evaluate evaluate and repair any discovered discovered inoperabilities.
inoperabilities. This Completion Completion Time also allows for an exception exception to the normal "time zero" for beginning the allowed allowed outage time "clock." For Required Action 0.1, D.1, the Completion Completion Time only only discovery that the HPCI System cannot be automatically begins upon discovery automatically
- SUSQUEHANNA - UNIT SUSQUEHANNA UNIT 1 TS / B 3.3-127 3.3-127 (continued)
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Revision 1
PPL Rev. 3 ECCS Instrumentation Instrumentation B 3.3.5.1 BASES BASES ACTIONS ACTIONS DA, D.2.1, and D.2.2 (continued)
D.1. D.2.1!
aligned to the suppression pool due to two inoperable, untripped channels channels in the same Function. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time from discovery of loss loss of initiation initiation capability is acceptable acceptable because because itit minimizes risk while while allowing time for restoration or tripping of channels. Because Because of the the diversity of sensors sensors available to provide initiation signals and the the redundancy redundancy of the ECCS design, an allowable allowable out of service time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> has been shown to be acceptable acceptable (Ref. 3) to permit restoration of any inoperable inoperable channel to OPERABLE OPERABLE status. If If the inoperable inoperable channel channel cannot be restored to OPERABLE OPERABLE status within the allowableallowable out of service service time, the channel channel must be placed in the tripped condition per Required Action D.2.1 or the suction source must be aligned to the the suppression suppression pool per Required Action D.2.2. Placing the inoperable inoperable channel in trip performs performs the intended function of the channel (shifting the the suction source to the suppression pool). Performance Performance of either of these two Required Required Actions will allow operation to continue. If If it is not desired to perform perform Required Actions D.2.1 and 0.2.2, D.2.2, Condition G must be entered entered and its Required Required Action taken.
- E.1 and E.2 E.2 Required ActionAction E.1 is intended to ensure appropriate actions ensure that appropriate actions are taken ifif multiple, inoperable, untripped inoperable, untripped channels within similar ADS trip trip system A A and B Functions Functions result in redundant redundant automatic initiation automatic initiation capability being lost for the ADS. Redundant Redundant automatic automatic initiation initiation capability is lost ifif either (a) one Function 4.a channel and one Function 5.a channel are inoperable inoperable and untripped, untripped, (b) one Function 4.b channel channel and one one inoperable and untripped, or (c)
Function 5.b channel are inoperable (c) one one Function 4.d channel and one Function Function 5.d channel channel are inoperable inoperable and and untripped.
untripped.
In this situation (loss of automatic initiation capability),
In capability), the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> or applicable, of Required 8 day allowance, as applicable, Required Action E.2 is not appropriate appropriate and all ADS valves must be declared inoperable inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after after discovery discovery of loss of ADS initiation initiation capability The Completion Time is intended to allow the operator time to evaluate evaluate and repair repair any discovered discovered inoperabilities. This This
- SUSQUEHANNA SUSQUEHANNA - UNIT 1 TS / B 3.3-128 3.3-128 (continued)
Revision 0 Revision
PPL Rev.Rev. 3 ECCS Instrumentation ECCS Instrumentation B 3.3.5.1
- BASES BASES ACTIONS E.1 and E.2 (continued)
E.1 Completion Time also allows for an exception to the normal "time zero" for beginning the allowed outage time "clock." For For Required Action E.1, E.1, the the Completion Time only begins upon upon discovery discovery that the ADS cannot be be automatically initiated due to inoperable, untripped channels within similar automatically ADS trip system Functions as as described in the paragraph paragraph above. The The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time from discovery of loss of initiation capability is acceptable because itit minimizes risk while allowing time for restoration or acceptable tripping of channels.
Because of the diversity of sensors available to provide initiation signals signals and the redundancy of the ECCS design, an allowable service time allowable out of service time of 8 days has been shown to be acceptable acceptable (Ref. 3) to permit restoration of any inoperable inoperable channel to OPERABLEOPERABLE status ifif both HPCI and RCIC RCIC are OPERABLE. IfIf either HPCI or RCIC is inoperable, the time is shortened to 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />. IfIf the status of HPCI or RCIC changes such that the Completion Time changes from 8 days to 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />, the 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> discovery of HPCI or RCIC inoperability.
begins upon discovery inoperability. However, the total inoperable, untripped channel cannot exceed 8 days. If time for an inoperable, If the the status of HPCI or RCIC changes such that the Completion Completion Time changes changes from 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to 8 days, the "time zero" for beginning the 8 day "clock" begins begins upon discovery discovery of the inoperable, inoperable, untripped untripped channel. IfIf the the inoperable channel inoperable channel cannot be restored to OPERABLE OPERABLE status within the the allowable out of service allowable service time, the channel must be placed in the tripped condition per Required Required Action E.2. Placing the inoperable inoperable channel channel in trip trip would conservatively conservatively compensate compensate for the inoperability, restore capability capability to accommodate aa single accommodate single failure, and allow operation to continue.
Alternately, ifif itit is not desired desired to place the channel in trip (e.g., as in the the case where placing placing the inoperable inoperable channel in trip would would result in an initiation), Condition G initiation), Condition must be G must be entered and its entered and its Required Action taken.
Required Action taken.
F.1 F.1 and F.2F.2 Required Required Action F.1 is intended intended to ensure that appropriate appropriate actions are are taken if multiple, inoperable inoperable channels channels within similar ADS trip system Functions Functions result in automatic automatic initiation initiation capability capability being being lost for the ADS.
Automatic Automatic
- SUSQUEHANNA SUSQUEHANNA -- UNIT UNIT 1 TS / BB 3.3-129 3.3-129 (continued)
(condnued)
Revision 0
PPL Rev. 3 Instrumentation ECCS Instrumentation B 3.3.5.1 BASES BASES ACTIONS F.1 and F.2 (continued) initiation capability is lost if either (a) one Function 4.c channel and one one Function 5.c channel are inoperable, (b) a combination of Function 4.e, Function 4.f, 5.e, and 5.f channels are inoperable inoperable such that both ADS trip systems systems lose initiation initiation capability, or (c) one or more Function channels and one Function 4.g channels one or more Function 5.g channels channels are inoperable.
In this situation (loss of automatic In automatic initiation capability), the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> or 8 day allowance, as applicable, applicable, of Required Required Action F.2 is not appropriate, and all ADS valves valves must be declared declared inoperable inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after discovery of loss of ADS initiation capability. The Note discovery Note to Required Action Action F.1 states that Required Action F.1 is only applicableapplicable for Functions Functions 4.c, 4.e, 4.f, 4.g, 5.c, 5.e, 5.f, and 5.g. Required Action F.1 is applicable to Functions 4.h and 5.h (which also require entry not applicable this entry into this Condition if if a channel in these Functions is inoperable),
inoperable), since they are the the Manual Initiation Functions Manual Functions and are not assumed in any accident or transient analysis. Thus, a a total loss of manual initiation capability for 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> or 8 days (as (as allowed by Required Required Action F.2) is allowed.
allowed.
- The Completion Completion Time is intended allows for an exception intended to allow the operator time to evaluate inoperabilities. This Completion and repair any discovered inoperabilities.
outage time "clock." For Required Action F.1, begins upon upon discovery that the ADS cannot be automatically initiated due to inoperable inoperable channels channels within similar ADS trip system Functions evaluate Completion Time also exception to the normal "time zero" for beginning the allowed Functions asas allowed F.1, the Completion Time only due described in the paragraph paragraph above. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time from discovery of loss of initiation capability minimizes capability is acceptable because it minimizes risk while allowing allowing time for restoration or tripping of channels.
Because of the diversity of sensors available Because available to provide initiation signals signals and the redundancy of the ECCS design, an allowable allowable out of service time time of 8 days has been shown to be acceptableacceptable (Ref. 3) to permit restoration restoration inoperable channel to OPERABLE of any inoperable OPERABLE status ifif both HPCI and RCIC RCIC are OPERABLE OPERABLE (Required Action F.2). If If either either HPCI or RCIC is inoperable, the time shortens to 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />. If If the status of HPCI or RCIC RCIC changes such that the Completion Time changes changes from 8 days to 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />, the 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> begins upon discovery discovery of HPCI or RCIC inoperability.
However, the total time for
- SUSQUEHANNA SUSQUEHANNA -- UNIT UNIT 1 TS I/ B 3.3-130 3.3-130 (continued)
(continued)
Revision Revision 0
PPL Rev. 3 Instrumentation ECCS Instrumentation B 3.3.5.1 BASES BASES ACTIONS ACTIONS F.1 and F.2 (continued) an inoperable inoperable channel exceed 8 days. If channel cannot exceed If the status of HPCI or RCIC changes such that the Completion Time changes from 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to 8 days, the "time zero" for beginning the 8 day "clock" "clock" begins upon upon discovery discovery of the inoperable inoperable channel. If If the inoperable inoperable channel channel cannot be be restored to OPERABLE OPERABLE status within the allowable out of service service time, Condition G must be entered and its Required Action Action taken. TheThe Required Required Actions Actions do not allow placing the channel channel in trip since this action action would not necessarily necessarily result in a safe state for the channel in all events.
G.1 With any Required Required Action and associated Completion Time not met, the the associated associated supported feature(s) may be incapable incapable of performing performing the the intended intended function, and those associated with inoperable untripped channels must be declared inoperable inoperable immediately.
immediately.
SURVEILLANCE SURVEILLANCE As noted in the beginning of the SRs, the SRs for each each ECCS ECCS
- REQUIREMENTS REQUIREMENTS instrumentation instrumentation Function are found in the SRs column The Surveillances Surveillances are modified by a Note to indicate is placed in an inoperable be delayed inoperable status solely for performance Surveillances, entry into associated delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> as follows: (a) performance of required associated Conditions and Required Actions (a) for Function 3.3.5.1-1.
column of Table 3.3.5.1-1.
indicate that when a channel Actions may Function 3.c and 3.f; and (b) for Functions Functions other than 3.c and 3.f provided associated Function provided the associated Function or redundant Function maintains ECCS initiation initiation capability. Upon completion completion of the Surveillance, or expiration expiration of the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> hour allowance, the the channel must be returned returned to OPERABLE OPERABLE status or the applicable applicable Condition entered and Required Actions Actions taken. This Note is based on the the reliability analysis (Ref. 3) assumption of the average time required to '
perform channel perform channel surveillance.
surveillance. That analysis demonstrated that the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> analysis demonstrated allowance does not significantly testing allowance significantly reduce the probability that the the ECCS will initiate when necessary.
In addition, for Functions 1.a, 1.a, 1.b, 1.b, 1.c, 1 .c, 2.a and 2,b, 2.b, the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> allowance is acceptable acceptable provided both offsite sources are OPERABLE.
- SUSQUEHANNA - UNIT 1 SUSQUEHANNA TS / BB 3.3-131 (continued)
(continued)
Revision 1
PPL Rev. 3 Instrumentation ECCS Instrumentation B 3.3.5.1 BASES SURVEILLANCE SURVEILLANCE 3.3.5.1.1 SR 3.3.5.1.1 REQUIREMENTS REQUIREMENTS (continued) Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ensures that a gross failure of instrumentation instrumentation has not occurred.
occurred. A CHANNEL CHECK is normally a comparison comparison of the parameter parameter indicated indicated on one channel to a similar parameter parameter on other channels. It is based on the assumptionassumption that instrument instrument channels channels monitoring monitoring the same parameter parameter should should read approximately approximately the same value. Significant Significant deviations deviations between between the the instrument instrument channels channels could be an indication indication of excessive instrument instrument drift in one of the channels or something something even more serious. A CHANNEL CHECK guarantees that undetectedundetected channel failure is limited to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; thus, itit is key to verifying the instrumentation continues continues to operate properlyproperly between between each CHANNEL CHANNEL CALIBRATION.
CALIBRATION.
Agreement criteria which are determined determined by the plant staffstaff based based on an investigation investigation of a combination combination of the channel channel instrument instrument uncertainties, may be used to support this parameter parameter comparison comparison and include indication include indication and readability. IfIf a channel channel is outside the criteria, itit may be an indication indication that the instrument has drifted outside its limit, and does does not necessarily necessarily indicate indicate the channel channel is Inoperable.
- Frequency is based upon operating experience The Frequency channel channel failure is rare. The CHANNEL checks of channels during normal operational associated experience that demonstrates CHECK supplements demonstrates operational use of the displays associated with the channels required by the LCO.
less formal displays 3.3.5.1.2 SR 3.3.5.1.2 A CHANNEL A FUNCTIONAL TEST is performed CHANNEL FUNCTIONAL performed on each required channel to ensure that the entire channel channel will perform the intended intended function. The The Frequency Frequency of 92 days is based on the reliability analysesanalyses of Reference Reference 3.
This SR is modified modified by a Note that provides a general exception to the the definition of CHANNEL CHANNEL FUNCTIONAL FUNCTIONAL TEST. This exception exception is necessary because the design of instrumentation does not facilitate functional testing because of all required contacts of the relay which input into the combinational logic. (Reference (Reference 5) Performance of such a test could result in a plant transient or place the plant in an undo risk situation. Therefore, for this SR, the SR, the CHANNEL CHANNEL FUNCTIONAL FUNCTIONAL TEST verifies acceptable acceptable response response by verifying verifying the the
- SUSQUEHANNA SUSQUEHANNA -- UNIT 1 TS / B 3.3-132 3.3-132 (continued)
(continued)
Revision Revision 0
PPL Rev. 3 ECCS Instrumentation Instrumentation B 3.3.5.1 BASES BASES SURVEILLANCE SURVEILLANCE SR 3.3.5.1.2 3.3.5.1.2 (continued)
REQUIREMENTS REQUIREMENTS change of state of the relay which inputs into the combinational combinational logic. TheThe required contacts not tested during the CHANNEL FUNCTIONAL TEST CHANNEL FUNCTIONAL are tested under the LOGIC SYSTEM FUNCTIONAL TEST, SR 3.3.5.1.5.
SYSTEM FUNCTIONAL This is acceptable experience shows that the contacts acceptable because operating experience not tested during the CHANNEL CHANNEL FUNCTIONAL FUNCTIONAL TEST normally normally pass thethe FUNCTIONAL TEST, and the testing methodology LOGIC SYSTEM FUNCTIONAL methodology minimizes the risk of unplanned unplanned transients.
SR 3.3.5.1.3 3.3.5.1.3 and SR 3.3.5.1.4 3.3.5.1.4 A CHANNEL CHANNEL CALIBRATION CALIBRATION is a complete complete check that verifies the channel responds to the measured measured parameter parameter within the necessary necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted CHANNEL CALIBRATION adjusted to to account for instrument between successive instrument drifts between calibrations consistent successive calibrations with the plant specific specific setpoint setpoint methodology.
The Frequency Frequency of SR 3.3.5.1.3 based upon the assumption 3.3.5.1.3 is based assumption of a 92 day calibration interval in the determination of the magnitude magnitude of equipment equipment drift in the setpoint analysis.
The Frequency Frequency of SR 3.3.5.1.4 is based upon the assumption assumption of a 24 month calibration interval in the determination magnitude of determination of the magnitude equipment equipment drift in the setpoint analysis.
SR 3.3.5.1.5 3.3.5.1.5 The LOGIC LOGIC SYSTEM SYSTEM FUNCTIONAL FUNCTIONAL TEST demonstrates demonstrates thethe OPERABILITY OPERABILITY of the required initiation logic for a specific channel. The The system performed in LCO 3.5.1, system functional testing performed 3.5.1, LCO 3.5.2, LCO 3.8.1, 3.8.1, and LCO 3.8.2 overlaps this Surveillance Surveillance to complete testing of the the assumed assumed safety function. The LOGIC SYSTEM FUNCTIONAL FUNCTIONAL TEST tests the operation operation of the initiation logic up to but not including the first contact which is unique unique to an individually supported feature feature such as the starting of a DG.
DG.
- SUSQUEHANNA SUSQUEHANNA - UNIT 11 TS / B 3.3-133 3.3-133 (continued)
(continued)
Revision 0 Revision
PPL Rev. 3
.ECCS Instrumentation Instrumentation B 3.3.5.1 BASES BASES SURVEILLANCE SURVEILLANCE SR 3.3.5.1.5 (continued)
REQUIREMENTS REQUIREMENTS The 24 month Frequency Frequency is based on the need to perform perform portions of this this Surveillance under the conditions Surveillance during a plant outage and the conditions that apply during the potential for an unplanned unplanned transient ifif the Surveillance Surveillance were performed performed with the reactor at power. Operating Operating experience experience has shown that thesethese components components usually pass the Surveillance Surveillance when performed performed at the the 24 month Frequency.
Frequency.
REFERENCES REFERENCES 1. FSAR, Section Section 6.3.
- 2. FSAR, Chapter Chapter 15.
- 3. NEDC-30936-P-A, NEDC-30936-P-A, "BWR Owners' Group Technical Specification Technical Specification Improvement Analyses for ECCS Actuation Instrumentation, Improvement Instrumentation, Part 2,"
December 1988.
- 4. Final Policy Statement on Technical Technical Specifications Specifications Improvements, Improvements, July 22, 1993 (58 FR 32193).
- 5. NRC Inspection Inspection and Enforcement Guidance, Guidance, Standard Enforcement Manual, Part 9900: Technical Standard Technical Specification Section 1.0 Definitions, Issue date 12/08/86.
12/08/86.
- SUSQUEHANNA UNIT,1 SUSQUEHANNA - UNIT.1 TS / B 3.3-134 Revision 0
PPL Rev. 2 Leakage Detection RCS Leakage Detection Instrumentation Instrumentation B 3.4.6 B 3.4 B3.4 REACTOR COOLANT REACTOR COOLANT SYSTEM (RCS)
B 3.4.6 Detection Instrumentation RCS Leakage Detection Instrumentation BASES BASES BACKGROUND BACKGROUND GDC 30 of 10 CFR 50, Appendix Appendix A (Ref. 1),1), requires means detecting means for detecting and, to the extent practical, identifying the location of the source of RCS RCS LEAKAGE.
LEAKAGE. Regulatory Guide Guide 1.45 (Ref. 2) describes describes acceptable acceptable methods methods for selecting for selecting leakage detection systems.
leakage detection Limits on LEAKAGE LEAKAGE from the reactor coolant pressurepressure boundary boundary (RCPB) are required so that appropriate appropriate action can be taken before before the integrity of the RCPB-is RCPB'is impaired (Ref. 2). Leakage detection systems for the RCS RCS leakage rates above normal are provided to alert the operators when leakage background levels background levels are detected quantitative detected and also to supply quantitative measurement of leakage measurement leakage rates. The Bases for LCO 3.4.4, "RCS "RCS Operational LEAKAGE,"
Operational LEAKAGE," discuss the limits on RCS LEAKAGE LEAKAGE rates.
Systems for separating the LEAKAGE of an identified source from an unidentified source unidentified source are necessary necessary to provide prompt and quantitative quantitative information to the operators to permit them to take immediate information immediate corrective corrective
- action.
LEAKAGE LEAKAGE from the RCPB inside the drywell is detected two or three independently primary means independently monitored of monitored variables, such as sump level quantifying particulate radioactivity changes and drywell gaseous and particulate primary LEAKAGE quantifying LEAKAGE in the drywell is the detected by at least one of radioactivity levels. The The drywell floor floor monitoring system which consists of two drywell floor drain drain sump monitoring sump level Channels. Both Channels Channels are required to be Operable Operable to satisfy the LCO.
The drywell drywell floor drain sump monitoring monitoring system monitors the LEAKAGE LEAKAGE collected in the floor drain sump. This unidentified LEAKAGE consists of unidentified LEAKAGE LEAKAGE from control rod drives, valve flanges or packings, floor drains, LEAKAGE the Closed Cooling Water System, and drywell air cooling unit condensatecondensate drains, and any LEAKAGE LEAKAGE not collected collected in the drywell equipment drain drywell equipment drain tank.
The level of each drywell drywell sump is recorded recorded by continuous pen recorders located in the Main Control Room. The change in (continued)
(continued)
SUSQUEHANNA SUSQUEHANNA - UNIT 1 TS / B 3.4-30 3.4-30 Revision 0
PPL Rev. 2 RCS Leakage Detection Instrumentation Instrumentation B 3.4.6 3.4.6 BASES BASES BACKGROUND BACKGROUND sump level per unit time determines the leak rate and is calculated calculated from from (continued) the recorder.
The floor drain sump level indicators indicators have switches switches that start and stop the the sump pumps when required. If If the sump fills to the high high level setpoint, an alarm sounds in the control room.
The primary containment containment air monitoring monitoring systems continuously continuously monitor the the primary containment atmosphere for airborne particulate and gaseous primary containment gaseous radioactivity.
radioactivity. A sudden increase increase of radioactivity, which may be attributed attributed to RCPB steam or reactor water LEAKAGE,LEAKAGE, is annunciated annunciated in the control room. The primary containment containment atmosphere atmosphere particulate gaseous particulate and gaseous radioactivity monitoring systems are not capable of quantifying LEAKAGE radioactivity monitoring LEAKAGE rates. These monitors monitors provide an alternate means means of leak detection detection toto that supplied by the sump level monitors, and althoughalthough they cannot ensure detection detection of a 1 gpm leak in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in all cases, they provide provide a diverse means of leak detection detection (Ref. 3).
APPLICABLE APPLICABLE A threat of significant significant compromise to the RCPB exists ifif the barrier barrier SAFETY contains a crack crack that is large enough to propagate propagate rapidly. LEAKAGE LEAKAGE ANALYSES ANALYSES rate limits are set low enough to detect detect the LEAKAGE LEAKAGE emitted from a single crack in the RCPB (Refs. 4 and 5). Each of the leakage detection detection systems inside the drywell is designed with the capability of detecting detecting LEAKAGE LEAKAGE less than the established established LEAKAGE LEAKAGE rate limits. The allowed allowed LEAKAGE LEAKAGE rates are well below the rates predictedpredicted for critical critical crack crack sizes (Ref. 6). Therefore, these actions provide adequate adequate response response before before a significant break in the RCPB can occur.
significant RCS leakage leakage detection instrumentation instrumentation satisfies Criterion 1 of the NRC NRC Statement (Ref. 7).
Policy Statement LCO LCO The drywell drywell floor drain sump monitoring system is required to quantify the the unidentified LEAKAGE unidentified LEAKAGE from the RCS. Thus, for the system to be be considered OPERABLE, the system must be capable capable of measuring measuring reactor coolant leakage. The other monitoring monitoring systems provide early alarms to the operators operators so closer examination examination of other detection systems systems will be made will.be made (continued)
SUSQUEHANNA - UNIT 1 SUSQUEHANNA TS / B 3.4-31 Revision 0 Revision
PPL Rev. 2 Leakage Detection Instrumentation RCS Leakage Instrumentation B 3.4.6 B3.4.6 BASES BASES LCO to determine corrective action that may be required.
determine the extent of any corrective (continued) With the leakage leakage detection detection systems inoperable, monitoring monitoring for LEAKAGE LEAKAGE in the RCPB is degraded.
APPLICABILITY APPLICABILITY In MODES 1, 1, 2, and 3, leakage detection systems are required to be detection systems be OPERABLE OPERABLE to support LCO 3.4.4. This Applicability is consistent consistent with that for LCO 3.4.4.
ACTIONS ACTIONS A.1 With the drywell drywell floor drain sump monitoring monitoring system inoperable, inoperable, the the primary primary containment atmospheric activity containment atmospheric activity monitor will provide indication of changes changes in leakage.
With the drywell floor drain sump monitoring system inoperable, operation unidentified and total continue for 30 days. However, RCS unidentified may continue LEAKAGE is still required determined every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (SR 3.4.4.1).
required to be determined 3.4.4.1).
The 30 day Completion Completion Time of Required Action A.1 is acceptable, based on operating operating experience, considering the multiple multiple forms of leakage leakage detection that are still available.
detection B.2 B.1 and B.2 With both gaseous and particulate primary containment atmospheric primary containment atmospheric channels inoperable, grab samples of the primary monitoring channels primary containment containment atmosphere must be taken and analyzed atmosphere analyzed to provide periodic leakage leakage information. Provided sample is obtained Provided a sample analyzed once every obtained and analyzed operated for up to 30 days to allow restoration 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the plant may be operated of at least one of the required monitors.
The 12 provides periodic information 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval provides information that is adequate adequate to detect LEAKAGE. The 30 day Completion Time for for (continued)
- SUSQUEHANNA - UNIT 1 SUSQUEHANNA TS / B 3.4-32 3.4-32 Revision 1
PPL Rev. 2 RCS Leakage Detection Instrumentation Leakage Detection Instrumentation B 3.4.6 B 3.4.6 BASES BASES ACTIONS ACTIONS B.1 and B.2 (continued) restoration recognizes that at least one other restoration recognizes other form of leakage leakage detection detection is available.
C.2 C.1 and C.2 If any Required If Required Action of Condition A or B cannot cannot be met within the the associated associated Completion Time, the plant must be brought brought to a MODE in which the LCO does not apply. To achieve achieve this status, the plant must bebe brought to at least MODE 3 within 12 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
The allowed Completion Completion Times are reasonable, based on operating operating experience, to perform the actions in an orderly manner manner and without without challenging challenging plant systems.
D.1 With all required monitors monitors inoperable, no required automatic means of monitoring LEAKAGE are available, and immediate monitoring LEAKAGE immediate plant shutdown shutdown in accordance with LCO 3.0.3 is required.
accordance required.
SURVEILLANCE SURVEILLANCE REQUIREMENTS SR 3.4.6.1 SR 3.4.6.1 REQUIREMENTS This SR is for the performance performance of a CHANNEL CHECK CHECK of the required primary primary containment atmospheric atmospheric monitoring monitoring system. The check check gives gives reasonable reasonable confidence confidence that the channel channel is operating properly. The The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is based on instrument reliability and is reasonable reasonable for detecting off normal conditions.
(continued)
SUSQUEHANNA - UNIT 1 SUSQUEHANNA TS / B B 3.4-33 3.4-33 Revision 1
PPL Rev. 2 Detection Instrumentation RCS Leakage Detection Instrumentation B 3.4.6 3.4.6 BASES BASES SURVEILLANCE SURVEILLANCE REQUIREMENTS SR 3.4.6.2 SR 3.4.6.2 REQUIREMENTS (continued) This SR is for the performance performance of aa CHANNEL FUNCTIONAL FUNCTIONAL TEST of the the required RCS leakage detection detection instrumentation. The test ensures that that the monitors can perform their function in the desired desired manner. The The Frequency of 31 days considers Frequency considers instrument reliability, and operating operating experience has shown itit proper for detecting experience detecting degradation.
degradation.
SR 3.4.6.3 This SR is for the performance performance of a CHANNEL CHANNEL CALIBRATION CALIBRATION of required required leakage detection instrumentation instrumentation channels. The calibration the calibration verifies the instrument string, including accuracy of the instrument including the instruments located inside inside Frequency of 24 months is a typical refueling containment. The Frequency refueling cycle and and considers channel reliability.
REFERENCES REFERENCES 1. 10 CFR 50, Appendix A, GDC 30.
- 2. Regulatory Regulatory Guide 1.45, May 1973.
- 3. FSAR, Section Section 5.2.5.1.2.
- 4. GEAP-5620, April 1968.
- 5. NUREG-75/067, NUREG-75/067, October 1975.
- 7. Final Policy Statement on Technical Specifications Improvements, Technical Specifications July 22, 1993 (58 FR 39132).
- SUSQUEHANNA SUSQUEHANNA - UNIT 1I TS / BB 3.4-34 3.4-34 Revision 0