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Technical Requirements Manual Unit 1
	ML061010648
Person / Time
Site:	Susquehanna
Issue date:	04/03/2006
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To:	Gerlach R; Document Control Desk, Office of Nuclear Reactor Regulation
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Apr. 03, 2006 Page 1 of IMANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2006-16246 USER IFORAAION:

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

TO: GERLACH*ROSE M 04/03/2006 LOCATION:

USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ON THIS TRANSMITTAL.

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DOCUMENTS TYPE: TRMi A- -Oc I Apr. 03, 2006 Page 2 of 3 ID: TEXT 2.2 REMOVE: REV:4 ADD: REV: 5 CATEGORY:

DOCUMENTS TYPE: TRM1 ID: TEXT 3.1.3 REMOVE: REV:2 ADD: REV: 3 CATEGORY:

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I SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date: 03/31/2006 Procedure Name Rev TEXT LOES 27 Title: LIST OF EFFECTIVE SECTIONS Issue Date 03/31/2006 Change ID Change Number TEXT TOC Title: 7 03/31/2006 TABLE OF CONTENTS TEXT 1.1 0 11/18/2002 Title: USE AND APPLICATION DEFINITIONS TEXT 2.1 1 02/04/2005 v Title: PLANT PROGRAMS AND SETPOINTS PLANT PROGRAMS TEXT 2.2 5 03/31/2006 Title: PLANT PROGRAMS AND SETPOINTS INSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 Title: 1 r 01/06/2006 TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY a SURVEILLANCE (TRS)APPLICABILITY TEXT 3.1.1 0 11/18/2002 Title: REACTIVITY CONTROL SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI)

INSTRUMENTATION TEXT 3.1.2 0 11/18/2002 Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1.3 3 03/31/2006 Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 0 11/18/2002 Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION

&c CHECK VALVE TEXT 3.2.1 6 03/16/2006 Title: CORE OPERATING LIMITS REPORT (COLR)Page 1 of 15 Report Date: 03/31/06 SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.3.1 0 11/18/2002 Title: INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 0 11/18/2002 Title: INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 Title: INSTRUMENTATION TEXT 3.3.4 Title: INSTRUMENTATION 0 11/18/2002 METEOROLOGICAL MONITORING INSTRUMENTATION 1 07/06/2005 TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0 11/18/2002 Title: INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK"EXT 3.3.6 2 10/19/2005 Title: INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 Title: INSTRUMENTATION TEXT 3.3.8 Title: INSTRUMENTATION TEXT 3.3.9 Title: INSTRUMENTATION TEXT 3.3.10 Title: INSTRUMENTATION TEXT 3.3.11 Title: INSTRUMENTATION TEXT 3.4.1 Title: REACTOR COOLANT 0 11/18/2002 MAIN TURBINE OVERSPEED PROTECTION SYSTEM 1 10/22/2003 TRM RPS INSTRUMENTATION 2 03/31/2006 LPRM UPSCALE ALARM INSTRUMENTATION 1 12/14/2004 REACTOR RECIRCULATION PUMP MG SET STOPS 1 10/22/2003 MVP ISOLATION INSTRUMENTATION 0 11/18/2002 SYSTEM REACTOR COOLANT SYSTEM CHEMISTRYaa --. --Page 2 of 15 Report Date: 03/31/06 Page 2 of 15 Report Date: 03/31/06 i SSES MANUAL; Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.4.2 Title: REACTOR TEXT 3.4.3 Title: REACTOR TEXT 3.4.4 Title: REACTOR TEXT 3.4.5 Title: RELCTOR TEXT 3.5.1 0 11/18/2002 COOLANT SYSTEM STRUCTURALINTEGRITY 0 11/18/2002 COOLANT SYSTEM HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITORS 1 12/14/2004 COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT 0 11/18/2002 COOLANT SYSTEM REACTOR VESSEL MATERIALS 1 02/04/2005 Title: EMERGENCY CORE COOLING AND RCIC ADS MANUAL INHIBIT-EXT 3.5.2 0 11/18/2002 i.J Title: EMERGENCY CORE COOLING AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0 11/18/2002 Title: EMERGENCY CORE COOLING AND RCIC LONG TERM NITROGEN'SUPPLY TO ADS TEXT 3.6.1 0 11/18/2002 Title: CONTAINMENT VENTING OR PURGING TEXT 3.6.2 0 11/18/2002 Title: CONTAINMENT SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0 11/18/2002 Title: CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION TEXT 3.6.4 0 11/18/2002 Title: CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 0 11/18/2002 Title: PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN Page 3 of Report Date: 03/31/06 Page 3 of 1', Report Date: 03/31/06 SSES MANAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.2 Title: PLANT TEXT 3.7.3.1 Title: PLANT TEXT 3.7.3.2 Title: PLANT TEXT 3.7.3.3 Title: PLANT 0 11/18/2002 SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL 0 11/18/2002 SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM.1 08/24/2005 SYSTEMS SPRAY AND SPRINKLER SYSTEMS 2 08/18/2005 SYSTEMS C02 SYSTEMS TEXT 3.7.3.4 Title: PLANT 0 SYSTEMS HALON SYSTEMS 11/18 /2002"EXT 3.7.3.5 Title: PLANT TEXT 3.7.3.6 Title: PLANT TEXT 3.7.3.7 Title: PLANT TEXT 3.7.3.8 Title: PLANT TEXT 3.7.4 Title: PLANT TEXT 3.7.5.1 Title: PLANT TEXT 3.7.5.2 Title: PLANT 0 11/18/2002 SYSTEMS FIRE HOSE STATIONS 0 11/18/2002 SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES 0 12/18/2002 SYSTEMS FIRE RATED ASSEMBLIES 4 09/08/2005 SYSTEMS FIRE DETECTION INSTRUMENTATION.

0 11/18/2002 SYSTEMS SOLID RADWASTE SYSTEM 0 11/18/2002 SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR 0 11/18/2002 SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE Page 4 of 15 Report Date: 03/31/06 Page 4 of 15 Report Date: 03/31/06 SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.5.3 0 11/18/2002 Title: PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 1 03/01/2005 Title: PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 0 11/18/2002 Title: PLINT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING TEXT 3.7.8 1 12/14/2004 Title: PLANT SYSTEMS SNUBBERS TEXT 3.7.9 0 11/18/2002 Title: PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 1 12/14/2004 i;2 Title: PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)TEXT 3.8.1 1 02/04/2005 Title: ELECTRICAL POWER .PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT 3.8.2.1 1 12/14/2004 Title: ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION CONTINUOUS TEXT 3.8.2.2 2 12/14/2004 Title: ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION

-AU'OMATIC TEXT 3.8.3 0 11/18/2002 Title: ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT 3.8.4 0 11/18/2002 Title: ELECTRICAL POWER 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT 3.8.5 0 11/18/2002 Title: ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION Page 5 of 15 Report Date: 03/31/06 Page 5 of 15 Report Date: 03/31/06 SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.8.6 0 11/18/2002 Title: ELECTRICAL-POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.9.1 0 11/18/2002 Title: REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0 11/18/2002 Title: REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 0 11/18/2002 Title: REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 0 11/18/2002 Title: MISCELLANEOUS SEAL SOURCE CONTAMINATION"EXT 3.10.2 1 03/31/2006 Title: MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 0 11/18/2002 Title: MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)I I TEXT 3.10.4 Title: MISCELLANEOUS LEADING TEXT 3.11.1.1 Title: RADIOACTIVE EFFLUENTS 0 11/18/2002 EDGE FLOW METER (LEFM)0 11/18/2002 LIQUID EFFLUENTS CONCENTRATION TEXT 3.11.1.2 0 11/18/2002 Title: RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE TEXT 3.11.1.3 0 11/18/2002 Title: RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM TEXT 3.11.1.4 1 12/14/2004 Title: RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION

'%~Page 6 of 15 Report Date: 03/31/06 Page 6 of 15 Report Date: 03/31/06 0 SSES MANUAL 4 Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.1.5 1 12/14/2004 Title: RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT 3.11.2.1 Title: RADIOACTIVE TEXT 3.11.2.2 Title: RADIOACTIVE TEXT 3.11.2.3 Title: RAD)IOACTIVE FORM TEXT 3.11.2.4 Title: RADIOACTIVE EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS 2 08/24/2005 DOSE RATE 0 11/18/2002 DOSE -NOBLE GASES'0 11/18/2002 DOSE -IODINE,.TRITIUM, AND RADIONUCLIDES IN PARTIrCULATE 0 11/18/2002 GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3.11.2.3 Title: RAD)IOACTIVE TEXT 3.11.2.5 Title: RADIOACTIVE EFFLUENTS' EFFLUENTS 1 05/20/2005 VENTILATION EXHAUST 2 12/14/2004 RADIOACTIVE GASEOUS TREATMENT SYSTEM EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.3 Title: RADIOACTIVE TEXT 3.11.4.:L Title: RAD)IOACTIVE TEXT 3.11.4.2 Title: RAD)IOACTIVE TEXT 3.11.4.3 Title: RAD)IOACTIVE EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS 0 11/18/2002 TOTAL DOSE ..2 01/06/2006 MONITORING PROGRAM .1 12/14/2004 LAND USE CENSUS ..0 11/18/2002

..INTERLABORATORY COMPARISON PROGRAM TEXT 3.12.1 0 11/19/2002 Title: LOADS CONTROL PROGRAM CRANE. TRAVEL-SPENT FUEL POOL STORAGE POOL Pe --... .7 of 1ReorDate:03/31/06

__Page 7 of 1!5 Report Date: 03/31/06 SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.12.2 0 11/19/2002 Title: LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0 11/19/2002 Title: LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENT TEXT B3.0 1 01/06/2006 Title: APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.1.1 0 11/19/2002 Title: REACTIVITY CONTROL SYSTEMS BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI)

INSTRUMENTATION TEXT B3.1.2 0 11/19/2002 Title: REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT-EXT B3.1.3 3 03/31/2006 Title: REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT B3.1.4 0 11/19/2002 Title: REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.1 0 11/19/2002 Title: CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR)TEXT B3.3.1 0 11/19/2002.

Title: INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 0 11/19/2002 Title: INSTRUMENTATION BASES-SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 1 02/04/2005 Title: INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 1 07/06/2005 Title: INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Page 8 of 15 Report Date: 03/31/06 SSES MANUAL' Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.3.5 Title: INSTRUMENTATION TEXT B3.3.6 Title: INSTRUMENTATION TEXT B3.3.7 Title: INSTRUMENTATION TEXT B3.3.8 Title: INSTRUMENTATION TEXT B3.3.9 Title: INSTRUMENTATION

'EXT B3.3.10 Title: INSTRUMENTATION 0 11/19/2'002 BASES THIS PAGE INTENTIONALLY LEFT BLANK 3 10/19/2005 BASES TRM ISOLATION ACTUATION INSTRUMENTATION 0 11/19/2002 BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM 1 10/22/2003 BASES TRM REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION 2 03/31/2006 BASES LPRM UPSCALE ALARM INSTRUMENTATION 0 11/19/2002 BASES REACTOR RECIRCULATION PUMP MG SET STOPS TEXT B3.3.11 1 10/22/2003 Title: INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3.4.1 Title: REACTOR TEXT B3.4.2 Title: REACTOR TEXT B3.4.3 Title: REACTOR TEXT B3.4.4 Title: REACTOR TEXT B3.4.5 Title: REACTOR 0 11/19/2002 COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY 0 11/19/2002 COOLANT SYSTEM BASES STRUCTURAL INTEGRITY 0 11/19/2002 COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR 0 11/19/2002 COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT'-'0 11/19/2002 COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS Pag 9_ of 13Rpr at:0/10 Page 9 of 15 Report Date: 03/31/06 SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.5.1 Title: ECCS AND RCIC TEXT B3.5.2 Title: ECCS AND RCIC TEXT B3.5.3 Title: ECCS AND RCIC TEXT B3.6.1 0 11/19/2002 BASES ADS MANUAL INHIBIT 0 11/19/2002 BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION 0 11/19/2002 BASES LONG TERM NITROGEN SUPPLY TO ADS 0 11/19/2002 Title: CONTAINMENT BASES VENTING OR PURGING TEXT B3.6.2 0 11/19/2002 Title: CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 0 11/19/2002 Title: CONTAINMENT BASES SUPPRESSION POCL ALARM INSTRUMENTATION TEXT B3.6.4 1 12/14/2004 Title: CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES K-)TEXT B3.7.1 Title: PLANT TEXT B3.7.2 Title: PLANT TEXT B3.7.3.1 Title: PLANT TEXT B3.7.3.2 Title: PLANT TEXT B3.7.3.3 Title: PLANT SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES 0 11/19/2002 EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN) 0 11/19/2002 ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL 0 11/19/2002 FIRE SUPPRESSION WATER SUPPLY SYSTEM 1 08/24/2005 SPRAY AND SPRINKLER SYSTEMS o 11/19/2002 C02 SYSTEMS Page 10 of 15 Report Date: 03/31/06 SSES. MNUANL) Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.3.4 Title: PLANT TEXT B3.7.3.!;Title: PL.NT TEXT B3.7.3.6;Title: PLANT TEXT B3.7.3.'t Title: PL.NT TEXT B3.7.3.J Title: PLINT 0 11/19/2002 SYSTEMS BASES HALON SYSTEMS 0 11/19/2002 SYSTEMS BASES FIRE HOSE STATIONS SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES 0 YARD 0 FIRE I FIRE 11/19/2002 FIRE HYDRANTS AND HYDRANT HOSE HOUSES 11/19/2002 RATED ASSEMBLIES 01/12/2004 DETECTION INSTRUMENTATION T EXT B3.7.4 I Title: PLANT 0 11/19/2002 SYSTEMS BASES SOLID RADWASTE SYSTEM TEXT B3.7.5.:.Title: PLANT TEXT B3.7.5.2 Title: PLANT TEXT B3.7.5.3;Title: PLANT TEXT B3.7.6 Title: PLANT SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES 0 11/19/2002 MAIN CONDENSER OFFGAS HYDROGEN MONITOR 0 11/19/2002 MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE 0 11/19/2002 LIQUID HOLDUP TANKS 1 03/01/2005 ESSW PUMPHOUSE VENTILATION TEXT B3.7.7 0 11/19/2002 Title: PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT B3.7.8 1 12/14/2004 Title: PLANT SYSTEMS BASES SNUBBERS Page 11 of 15R Report Date: 03/31/06 SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 K)TEXT B3.7.9 1 12/14/2004 Title: PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1 12/14/2004 Title: PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.8.1 Title: ELECTRICAL PROTECTIVE TEXT B3.8.2.1 Title: ELECTRICAL CONTINUOUS TEXT B3.8.2.2 Title: ELECTRICAL AUTOMATIC T'EXT B3.8.3 Title: ELECTRICAL TEXT B3.8.4 Title: ELECTRICAL TEXT B3.8.5 Title: ELECTRICAL TEXT B3.8.6 Title: ELECTRICAL 1 02/04/2005 POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT DEVICES 0 11/19/2002 POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL C 1 09/17/2004 POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL C 0 11/19/2002 POWER BASES DIESEL GENERATOR (DG) MAINTENANCE AC'0 11/19/2002 POWER BASES'24 VDC ELECTRICAL POWER SUBSYSTEM 0 11/19/2002 POWER BASES DEGRADED VOLTAGE PROTECTION 1 02/04/2005 POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING)VERLOAD PROTECTION

-)VERLOAD PROTECTION

-TIVITIES KU TEXT B3.9.1 0 11/19/2002 Title: REFUELING OPERATIONS BASES DECAY TIME TEXT B3.9.2 0 11/19/2002 Title: REFUELING OPERATIONS BASES COMMUNICATIONS TEXT B3.9.3 0 11/19/2002 Title: REFUELING OPERATIONS BASES REFUELING PLATFORM Page 2 of 15 Report Date: 03/31/06

& SSES MANUAL) Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.10.1 Title: MISCELLANEOUS TEXT B3.10.2 Title: MISCELLANEOUS TEXT B3.10.3 Title: MISCELLANEOUS TEXT B3.10.4 Title: MISCELLANEOUS TEXT B3.11.1.1 Title: RADIOACTIVE EF"EXT B3.11.1.2 tJ* Title: RADIOACTIVE EF TEXT B3.11.1.3 Title: RADIOACTIVE EF TEXT B3.11.1.4 Title: RADIOACTIVE EF TEXT B3.11.1.5 Title: RADIOACTIVE EF INSTRUMENTATIC TEXT B3.11.2.1 Title: RADIOACTIVE EF TEXT B3.11.2.2 Title: RADIOACTIVE EF TEXT B3.11.2.3 Title: RADIOACTIVE EF PARTICULATES F 0 11/19/2002 BASES SEALED SOURCE CONTAMINATION 1 03/31/2006 BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION 0 11/19/2002 BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)0 11/19/2002 BASES LEADING EDGE FLOW METER (LEFM)0 11/19/2002

'FLUENTS BASES LIQUID EFFLUENTS CONCENTRATION 0 11/19/2002

'FLUENTS BASES LIQUID EFFLUENTS DOSE 0 11/19/2002

'FLUENTS BASES LIQUID WASTE TREATMENT SYSTEM 0 11/19/2002 FLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION 0 11/19/2002

'FLUENTS BASES RADIOACTIVE LIQUID.-PROCESS MONITORING IN 1 12/14/2004

'FLUENTS BASES DOSE RATE 0 11/19/2002 FLUENTS BASES DOSE -NOBLE GASES 0 11/19/2002

'FLUENTS BASES DOSE -IODINE, TRITIUM, AND RADIONUCLIDES IN'ORM Pag... of ... Reor Dae 03/31/06 Page 13 .8f 15 Report Date: 03/31/06 SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.11.2.4 0 Title: RADIOACTIVE EFFLUENTS BASES 11/19/2002 GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.11.2.5 3 05/20/2005 Title: RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3.11.2.6 Title: RADIOACTIVE EFFLUENTS INSTRUMENTATION 1 01/27/2004 BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING TEXT B3.11.3 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES TOTAL DOSE TEXT B3.11.4.1 2 01/06/2006 Title: RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3.11.4.2 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS-BASES LAND USE CENSUS I TEXT B3.11.4.3 0 Title: RADIOACTIVE EFFLUENTS BASES TEXT B3.12.1 0 Title: LOADS CONTROL PROGRAM BASES TEXT B3.12.2 0 Title: LOADS CONTROL PROGRAM BASES 11/19/2002 INTERLABORATORY COMPARISON PROGRAM 11/19/2002 CRANE TRAVEL-SPENT FUEL STORAGE POOL 11/19/2002 HEAVY LOADS REQUIREMENTS TEXT B3.12.3 0 11/19/2002 Title: LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS TEXT 4.1 0 08/31/1998 Title: ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 0 08/31/1998 Title: ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION I.*Page 14 of 15 Report Date: 03/31/06 Page 14 of 15 Report Date: 03/31/06 SSES MANUAL* Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 4.3 Title: TEXT 4.4 Title: TEXT 4.5 Title: TEXT 4.6 Title: TEXT 4. 7 Title: 0 08/31/1998-CONTROLS SAFETY LIMIT VIOLATION ADMINISTRATIVE ADMINISTRATIVE CONTROL ADMINISTRATIVE CONTROL ADMINISTRATIVE CONTROL 0 08/31/1998 S PROCEDURES

& PROGRAMS 0 08/31/1998 S REPORTING REQUIREMENTS 0 08/31/1998 S RADIATION PROTECTION PROGRAM 0 08/31/1998 S TRAINING CONTROL'ADMINISTRATIVE Page 15 of 15 Report Date: 03/31/06 Page 1 5 of 1'5 Report Date: 03/31/06 SUSQUEHANNA STEAM ELECTRIC STATION TA BLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)PPL Rev. 7 SECTION TITLE PAGE 1.0 1.1 USE AND APPLICATION

.................

I TRM/1.0-1 Definitions

.................

TRM/1.0-2 2.0 2.1 2.2 3.0 3.0 3.0 3.1 3.1.'1 3.1.2 3.1 .3 3.1.4 3.2 3.2.1 3.3: 3.3.1 3.3.2 3.3.3 3.3.4 3.3.5 3.3.6 3.3.7 3.38 3.39 3.3110 3.3 11 3.4 3'4 341 2 3.45 PLANT PROGRAMS ...................................

2.0-1 Plant Programs .. .................................

2.0-1 Instrument Trip Setpoint Table .................

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TRM/2.0-5 APPLICABILITY

..........

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TRM/3.0-1 TRO) -TR for Operation (TRO) Applicability

.................................

-.:.;.TRM/3.0-1 (TRS) -TR Surveillance (TRS) Applicability

.......................

TRM/3.0-3 REACTIVITY CONTROL SYSTEM S, .............................

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3.1-1 Alternate Rod Injection

........ f CRD Housing Support ...............

' ' ...... 3.1-4 Control Rod Block Instrumentation

...........................

3.1-5 Control Rod Scram Accumulators Instrumentation lnd Check Valve ..........................

.... ..... TRM/3.1-9 CORE OPERATING LIMITS REPORT .TRMI3.2-1 Core Operating Limits Report `...2...........................

.TRMI3.2-1 0 , I .>'^ It i j , INSTRUMENTATION..."................

TRM13.3-1 Radiation Monitoring Ins trumen tation .TRM'3.3-1 Seismic Monitoring Instrumntation. .TRMI3.3-4 Meteorological Monitoring Instrumentation

.3.3-7 TRM Post-Accident Monitoring Instrumentation .TRMI3.3-9 Section Not Used .TRM/3.3-12 TRM(Containment Isolation'Instrumentation

.................................

'.TRM/3.3-13 Turbine Overspeed Protection

'System .TRM/3.3-17-Section Not Used ...................

..TRM/3.3-19 ,OIRM Instrumentation .TRM/3.3-22 Reactor Recirculation Pump MG Set Electrical and' Mechanical Stops ........ .... TRM/3.3-23 MVP Isolation Instrumentation

.' .TRM/3.3-25 REACTOR COOLANT SYSTEM .' .3.4-1 Reactor Coolant System Chemistry

...................................

3.4-1 Striuctutral Integrity

... 3.4-6 High/Low Pressure Interface Leakage Monitors ..............................

3.4-9 Reactor Recirculation Fldw and Rod Line Limit..TRM/3.4-12 Reactor Vessel Material Surveillances Program ...................................

3.4-13 SU3QUEHANNA-UNIT 1 ,: P 4 TRM / TOC-1 EFFECTIVE DATE 03/22/2006 SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev'. 7 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)SECTION TITLE PAGE 3.5 EMERGENCY CORE COOLING AND RCIC .........................................

TRM13.5-1 3.5.1 ADS Manual Inhibit .........................................

TRM'3.5-1 3.5.2 ECCS and RCIC System Monitoring Instrumentation

.................................

3.5-3 3.5.3 Long Term Nitrogen Supply to ADS ................

.........................

3.5-6 3.6 CONTAINMENT

.........................................

3.6-1 3.6.1 VENTING or PURGING .........................................

3.6-1 3.6.2 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication................................................................I.....................................

3.6-2 3.6.3 Suppression Pool Alarm Instrumentation

......................................

3.6-3 3.6.4 Primary Containment Closed System Boundaries

..............................

TRM.3.6-6 3.7 PLANT SYSTEMS .......................................

3.7-1 3.7.1 Emergency Service Water System (Shutdown)

......................................

3.7-1 3.7.2 Ultimate Heat Sink and Ground Water Level ................................

3.7-3 3.7.3.1 Fire Suppression Water Supply System ..................

..............

TRM'3.7-4 3.7.3.2 Spray and Sprinkler Systems ................................

TRM.'3.7-8 3.7 3.3 C02 systems ................................

TRM'3.7-12 3.7 3.4 Halon Systems ................................

TRM,'3.7-16 3.7 3.5 Fire Hose Stations ................................

TRM,!3.7-18 3.7 3.6 Yard Fire Hydrants and Hydrant Hose Houses .................................

TRM,!3.7-22 3.7. 3.7 Fire Rated Assemblies

.................................

TRM,3.7-24 3.7 3.8 Fire Detection Instrumentation

........................

TRM/3.7-26 3.7 .Solid Radwaste System ..................................

TRMI3.7-35 3.7 5.1 Main Condenser Offgas Hydrogen Monitor ...................................

3.7-38 3.7.5.2 Main Condenser Explosive Gas Mixture ..................................

3.7-39 3.7.5.3 Liquid Holdup Tanks .............

3.7-40 3.7.6 ESSW Pumphouse Ventilation

.....................

TRM,!3.7-41 3.7.7 Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation

... ....... 3.7-42 3.7.8 Snubbers ..................

TRM,3.7-44 3.7.9 Control Structure HVAC...............

TRMI3.7-50 3.7.10 Spent Fuel Storage Pools ...................

.TRM/'3.7-52 i ID SU',QUEHANNA UNIT I TRM /TQC-2 EFFECTIVE DATE O3/22I2036 I

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 7 TA BLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)SEDTION TITLE PAGE 3.8 ELECTRICAL POWER .TRM3.8-1 3.8.1 Primary Containment Penetration Conductor Overcurrent Protective Devices..........TRM'3.8-1 ProtectiveDevices

..... j.... ..........................................................

R /.-3.8.2.1 Motor Operated Valves Thermal Overload Protection

-Continuous .TRM3.8-5 3.8.2.2 Motor Operated Valves Thermal Overload Protection

-Automatic

...........................................

TRMM3.8-1 1 3.8.3 Diesel Generator (DG) Maintenance Activities

...........................................

3.8-13 3.8.4 24VDC Electrical Power Subsystem

...........................................

TRM/3.8-15 3.8.5 Degraded Voltage Protection

.................

..........................

TRM/3.8-21 3.8.6 Emergency Switchgear Room Cooling ...........................................

3.8-24 3.9 REFUELING OPERATIONS

...........................................

3.9-1 3.9.1 Decay Time ...........................................

3.9-1 3.9.2 Communications

...........................................

3.9-2 3.9 3 Refueling Platform ...........................................

3.9-3 3.1') MISCELLANEOUS

...........................................

3.10-1 3.10.1 Sealed Source Contamination

...........................................

3.10-1 3.1 0.2 MODE 5 Shutdown Margin Test RPS Instrumentation

...............................

3.10-4 3.10.3 Independent Spent Fuel Storage Installation (ISFSI) .........................

TRM,'3.10-7 3.10.4 Leading Edge Flow Meter (LEFM) ...........................................

TRM,'3.10-8 3.11 RADIOACTIVE EFFLUENTS

...........................................

3.11-1 3.1 1.1.1 Liquid Effluents Concentration

...........................................

3.11-1 3.11.1.2 Liquid Effluents Dose ...........................................

3.11-4 3.11.1.3 Liquid Waste Treatment System ....................

.......................

3.11-6 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation

.................................

3.11-8 3.11 .1.5 Radioactive Liquid Process Monitoring Instrumentation

.............................

3.11-13 3.11.2.1 Dose Rate ...........................................

3.11-17 3.11.2.2 Dose -Noble Gases.. 3.11-20 3.11.2.3 Dose Iodine, Tritium, and Radionuclides in ,lrticulate Form ............

I..3.11-21 311.2.4 Gaseous'Radwaste Treatment System ...........

.................

TRM.'3.11-22 3: 1.2.5 Ventilation Exhaust Treatment System ............................

TRM.'3.11-23 311 i 4.2.6 Radioactive Gaseous Effluent Monitoring J* 1 Instrumentation

.............

.3.11-25 3!1.33 Total Dose .............

.3.11-33 3111.4.1 Monitoring Program .............

TRI/3.11-35 3 1 .4.2 Land Use Census.........

.... TRM/3.11-45 3.1 1.4.3 Interlaboratory Comparison Program ..........................

3.11-47-EI SU',QUEHANNA -UNIT 1 TRM / TOC-3 EFFECTIVE DATE 03/22/2006 SU'SQUEHANNA STEAM ELECTRIC STATION TA13LE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)PPL Rev. 7 SEC TION TITLE PAGE 3.12 3.12.1 3.12.2 3. 1,2.3 LOADS CONTROL PROGRAM ............................

TRM/3.12-1 Crane Travel -Spent Fuel Storage Pool .........

...................

TRM/3.12-1 Heavy Loads Requirements

.............................

TRM/3.12-3 Light Loads Requirements

............................

TRM/3.12-5 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 ADMINISTRATIVE CONTROLS ......................

4.0-1 Organization

......................

4.0-1 Reportable Event Action ......................

4.0-2 Safety Limit Violation

......................

4.0-3 Procedures and Programs ......................

4.0-4 Reporting Requirements

......................

4.0-5 Radiation Protection Program ...............

4.0-7 Training............................................................................................................

4.0-8' ! .1 ,.I : .: i I ...i I ,. I.i ..I l i ! , I I i I I i I .! i I i 1.I I !1 .: I I : i w: I I , I.1 :i ;1!I SUSQUEHANNA

-UNIT I TRM/TOC-4 EFFECTIVE DATE 03/22/2006 SUSQUEHANNA -UNIT 1 r TRM / TOC-4 Ij t!EFFECTIVE DATE 03122/20()6 SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 7 TA13LE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)SEC'TION TITLE PAGE B 3.0 Applicability

...................................

B 3.0-1 B 3.0 (TRO) -TR for Operation (TRO) Applicability .B 3.0-1 B 3.0 (TRS) -TR Surveillance (TRS) Applicability .B 3.0-9 B 3.1.1 Alternate Rod Injection .TRM'B 3.1-1 B 3.1.2 CRD Housing Support .TRM.'B 3.1-4 B 3.1.3 Control Rod Block Instrumentation .TRM./B 3.1-5 B 3.1.4 Control Rod Scram Accumulators Instrumentation and Check Valve ........ TRM./B 3.1-8 B 3.2.1 Core Operating Limits Report (COLR) ........ B 3.2-1 B 3.3.1 Radiation Monitoring Instrumentation

........ TRM.'B 3.3-1 B 3.3.2 Seismic Monitoring Instrumentation

........ B 3.3-2 B 3.3.3 Meteorological Monitoring Instrumentation

........ TRM,'B 3.3-3 B 3.3.4 TRM Post-Accident Monitoring Instrumentation

........ TRM.'B 3.3-4 B 3.3.5 Section Not Used ........ TRM,'B 3.3-7 B 3.3.6 TRM Containment Isolation Instrumentation

........ B 3.3-10 B 3.3.7 Turbine Overspeed Protection System ........ TRM/'B 3.3-14 B 3.3.8 Section Not Used ........ TRM/B 3.3-15 B 3.3.9 OPRM Instrumentation

........ TRM/B 3.3-17 B 3.3.10 Reactor Recirculation Pump MG Set Electrical and Mechanical Stops ........ TRM,'B 3.3-18 B 3.3.11 MVP Isolation Instrumentation

........ TRM/'B 3.3-20 B 3.4.1 Reactor Coolant System Chemistry

........ B 3.4-1 B 3.4.2 Structurai Integrity

........ B 3.4-2 B 3.4.3 High/Low Pressure Interface Leakage Monitors ........ B 3.4-4 B 3.4.4 Reactor Recirculation Flow and Rod Line Limit ........ TRM,'B 3.4-5 B 3.4.5 Reactor Vessel Material Surveillances Program ........ B 3.4-6 B 3.5.1 ADS Manual Inhibit..........

... B 3.5-1 B 3.5.2 ECCS and RCIC System Monitoring Instrumentation

... B 3.5-3 B 3.5.3 Long Term Nitrogen Supply to ADS .. .B 3.5-4: I SUSQUEHANNA

-UNIT 1 TRM / TOC-5 EFFECTIVE DATE 03/22/2006 SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 7 TA BLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)SE ,TION TITLE PAGE;B 3.6.1 VENTING or PURGING .....................................

TRM'B 3.6-1 B 3.6.2 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication

.....................................

B 3.6-3 B 3.6.3 Suppression Pool Alarm Instrumentation

.....................................

TRM'B 3.6-4 B 3.6.4 Primary Containment Closed System Boundaries

.............................

TRM'B 3.6-6 B 3.7.1 Emergency Service Water System (Shutdown)

.....................................

B 3.7-1 B 3.7.2 Ultimate Heat Sink and Ground Water Level .....................................

B 3.7-2 B 3.7.3.1 Fire Suppression Water Supply System .....................................

TRM./B 3.7-3 B 3.7.3.2 Spray 'and Sprinkler Systems ...........

..........................

TRM'B 3.7-5 B 3.7.3.3 C02 systems .....................................

TRM'B 3.7-7 B 37.3.4 Halon Systems .....................................

TRM.B 3.7-8 B 3 7.3.5 Fire Hose Stations .....................................

TRM,'B 3.7-10 B 3;7.3.6 Yard Fire Hydrants and Hydrant Hose Houses ..................................

TRM.'B 3.7-11 B 37.3.7 Fire Rated Assemblies

.....................................

TRM,'B 3.7-12 B 37.3.8 Fire Detection Instrumentation

............

.........................

TRMIB 3.7-14 B 3.7.4 Solid Radwaste System .....................................

TRMIB 3.7-15 B 3.7.5.1 Main Condenser Offgas Hydrogen Monitor .......................

..............

B 3.7-17 B 3.7.5.2 Main Condenser Explosive Gas Mixture .....................................

B 3.7-19 B 3.7.5.3 Liquid Holdup Tanks ... B 3.7-20 B 3.7.6 ESSW Pumphouse Ventilation

......................

TRMI'B 3.7-21 B 3.7.7. Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation

...................

TRMIB 3.7-22 B 3.f7.8 Snubbers ...................

B 3.7-24 B 3.1.9 Control Structure HVAC ...................

TRMj'B 3.7-31 B 3 7.10 Spent Fuel Storage Pools ...................

TRMjB 3.7-33 B 3 8.1' Primary Containment Penetration Conductor Overcurrent B 1 Protective Devices .............

TRMi'B 3.8-1 B 3.8.2.1 Motor Operated Valves Thermal Overload Protection

-Continuous

....... TRMj'B 3.8-3 B 3.8.2.2 Motor Operated Valves Thermal Overload Protection

-l Automatic

...... .TRMI1B 3.8-4 B 3.8.3 Diesel ,Generator (DG) Maintenance Activities

..................................

B 3.8-5 B 3.8.41 24VDC Electrical Power Subsystem

..................................

B 3.8-6 B 3.8.5 Degraded Voltage Protection

..................................

TRMIB 3.8-16 B 3.8.61 Emergency Switchgear Room Cooling ..................................

TRMj'B 3.8-17 B.3.9.1 Decay .Tie....................................

B 3.9-1 B 3.9.2 Communications

...........

B 3.9-2 SU'SQUEHANNA

-UNIT 1 TRM / TOC-6 EFFECTIVE DATE 03/22/2006 SUSQUEHANNA STEAM ELECTRIC STATION TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)PPL Rev. 7 SECTION TITLE PAGE B 2.9.3 B 2.10.1 B 3.10.2 B 3.10.3 B 3.10.4 B 3.11.1.1 B 3.11.1.2 B 3.11.1.3 B 3.11.1.4 B 3.11.1.5 B 3.11.2.1 B 3.11.2.2 B 3.11.2.3 B 3:11.2.4 B 3.11.2.5 B 3;11.2.6 B 3.11.3 B 3.11.4.1 B 3.11.4.2 B 3.11.4.3 B.3.12.1 B.3.12.2 B.3.12.3 TRM1 text TOC 212/C5 Refueling Platform ........................................

B 3.9-3 Sealed Source Contamination

........................................

B 3.10-1 MODE 5 Shutdown Margin Test RPS Instrumentation

......................

TRM/B 3.10-2 Independent Spent Fuel Storage Installation (ISFSI) .........................

TRM/B 3.10-4 Leading Edge Flow Meter (LEFM) .......................................

TRM/B 3.10-6 Liquid Effluents Concentration

.........................................

B 3.11-1 Liquid Effluents Dose ........................................

B 3.11-4 Liquid Waste Treatment System .......................................

B 3.11-6 Liquid Radwaste Effluent Monitoring Instrumentation

.................................

B 3.11-7 Radioactive Liquid Process Monitoring Instrumentation

....................

TRM/B 3.11-10 Dose Rate .............

TRM/B 3.11-12 Dose -Noble Gases .............

B 3.11-16 Dose -Iodine, Tritium, and Radionuclides in Particulate Form .............

B 3.11-18 Gaseous Radwaste Treatment System .............................

TRM/B 3.11-20 Ventilation Exhaust Treatment System ..............................

TRMIB 3.11-21 Radioactive Gaseous Effluent Monitoring Instrumentation

.............................

TRM'B 3.11-24 Total Dose .............................

B 3.11-26 Monitoring Program ............................

TRM.'B 3.11-28 Lanid Use Census..................

..........

B 3.11-34 Interlaboratory Comparison Program .........

...................

TRM./B 3.11-36 Crane Travel -Spent Fuel Storage Pool ............

................

TRMrB 3.12-1 Heavy Loads Requirements

............................

TRM1B 3.12-2 Light Loads Requirements

.............

TRM/B 3.12-3.z; ...i .I;I , .;4 !i .; i I r1 i.j ;,: I U .E N .I I SUSDQUEHANNA.

UNIT 1 TRM / TOC-7 EFFECTIVE DATE 03/2212006 SUSQIJEHANNA STEAM ELECTRIC STATION PPL Rev. 27 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date Pages TRM / 3.3-17 and TRM / 3.3-18 Pages TRM / 3.3-19 through TRM / 3.3-21 Page TRM / 3.3-22 Page TRM / 3.3-22a Pages TRM / 3.3-22b through TRM / 3.3-22d Page TRM / 3.3-23 Pages TRM / 3.3-24 and TRM / 3.3-25* Page TRM / 3.3-26 06/14/2002 10/22/20)3 03/22/2006 11/15/2004 03/22/2006 12/03/2004 05/16/2003 10/22/2003 3.4 REACTOR COOLANT SYSTEM Pages 3.4-1 through 3.4-5 Pages 3.4-6 through 3.4-11 Page TRM / 3.4-12 Page 3.4-13 3.5 EMERGENCY CORE COOLING AND RCIC Page TRM / 3.5-1 Pages 3.5-2 and 3.5-3 Page TRM / 3.5-4 Pages 3.5-5 through 3.5-7 3.6 CONTAINMENT Pages 3.6-1 through 3.6-3 Page TRM / 3.6-4 Page 3.6-5 Pages TRM / 3.6-6 through TRM / 3.6-8 10/23/1998 08/31/1998 12/03/20()4 08/31/1998 01/28/20()5 08/31/1998 04/17/2000 08/31/1998 08/31/1998 01/07/2002 08/31/1998 12/31/2002 3.7 PLANT SYSTEMS Pages 3.7-1 through 3.7-3 Pages TRM I 3.7-4 through TRM / 3.7-8 Pages TRM / 3.7-9 and TRM / 3.7-10 Page TRM / 3.7-11 Pages TRM / 3.7-12 and TRM / 3.7.13 Page TRM / 3.7-14 Pages TRM / 3.7-15 through TRM / 3.7-27 Pages TRM / 3.7-28 and TRM / 3.7-29 Page TRM / 3.7-30 Pages TRM / 3.7-31 and TRM 3.7-32 Page TRM / 3.7-33 Page TRM / 3.7-34 Page TRM / 3.7-34a Pages TRM / 3.7-35 through TRM / 3.7-37 Pages 3.7-38 through 3.7-40 Pages TRM / 3.7-41 and TRM I 3.7-41a 08/31/1998 08/02/1999 08/16/2005 12/29/1999 08/02/1999 08/09/2005 08/02/1999 08/09/2005 08/25/2005 11/16/2001 01/09/2004 11/16/20011 10/05/2002 02/01/1999 08/31/1998 02/14/2005 SUSQUEHANNA I! UNIT 1 i, TRM / LOES-2 EFFECTIVE DATE 03/22/2006 SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 27 LIST CF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title 1 Effective Date Pages 3.7-42 and 3.7-43 Page TRM / 3.7-44 Pages 3.7-45 through 3.7-48 Page TRM / 3.7-49 Pages TRM / 3.7-50 and TRM / 3.7-51 Pages TRM / 3.7-52 Page TRM / 3.7-53 Page TRM / 3.7-54 08/31/1998 12/03/2004 10/13/1998 03/08/20()3 03/09/2001 12/03/20()4 04/15/20()3 07/29/1999 3.8 ELECTRICAL POWER Page TRM / 3.8-1 Pages TRM / 3.8-2 through TRM / 3.8-4 Pages TRM / 3.8-5 and TRM / 3.8-6 Pages TRM / 3.8-7 through TRM / 3.8-10 Page TRM I 3.8-11 Page TRM I 3.8-12 Pages 3.8-13 and 3.8-14 Pages TRM / 3.8-15 through TRM / 3.8-17 Page 3.8-18'Page TRM/ 3.8-19 Page 3.8-20 Pages TRM / 3.8-21 through TRM / 3.8-23 Pages 3.8-24 and 3.8-25 04/02/2002 01/28/2005 04/02/200)2 12/03/200)4 08/10/200)4 12/03/200)4 08/31/1998 04/02/20()2 08/31/1998 04/02/2002 08/31/1998 06/06/1999 08/31/1998 3.9 3.10 3.11 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 MISCELLANEOUS Pages 3.10-1 through 3.10-4 Pages TRM / 3.10-5 and TRM / 3.10-6 Page TRM /3.10-7 Page6TRM!/

3.10-8 RADIOACTIVE EFFLUENTS Pages 3.l1-1 through 3.11-9 Page 'TRM'/ 3 11-10 Pages 3.11-1 i and 3.11-12 Page 3.11-13 i Page TRM:/ 3.11-14 Pages 3.'1 1115'and 3.11.16 Pages 3.l11i7iand 3.11-18 Page jTRM 1I 3.11-19 1 Pages 3'. '1k2 jand 3.11-211 PageT l/i12 l I Pages TRM i 3.11-23 and TRM / 3.11-24 Page 3.11-25 08/31/1998 08/31/1998 03/22/20t)6 04/07/2000 04/17/2002 08/31/1998 12/03/2004 08/31/1998 09/011998 12/03/2004 09/01/1998 08/31/19'98 08/15/2005 08/31/1998 04/02/2002 05/13/2005 09/01/1998 I SUSQUEHANNA

-UNIT I TRM / LOES-3 EFFECTIVE DATE 03/22/2006 SUSQUEHANNA

-UNIT 11 ;!, TRM / LOES-3 i EFFECTIVE DATE 03/22/2006 SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 27 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date Pages TRM / 3.11-26 through TRM / 3.11-28 Page TRM / 3.11-29 Pages TRM / 3.11.30 through TRM / 3.11.32 Pages 3.11-33 and 3.11-34 Pages TRM / 3.11-35 through TRM /3.11-39 Pages 3.11-40 through 3.11-44 Page TRM / 3.11-45 Pages 3.11-46 and 3.11-47 01/21/2004 12/03/2004 01/21/2004 08/31/1998 11/30/2005 08/31/1998 12/b3/2004 08/31/1998 3.12 4.0 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-5 02/05/1999 ADMINISTRATIVE CONTROLS Pages 4.0-1 through 4.0-8 08/31/199 l lI I* :I j, t,,I: : I .I t I 1*p-SUSQUIEHANNA -UNIT 1 TRM / LOE S-A EFFECTIVE DATE 03/22/2006 SUSQIJEHANNA STEAM ELECTRIC STATION PPL Rev. 27 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date B 3.0 APPLICABILITY BASES Pages B 3.0-1 through B 3.0-10 Pages TRM / B 3.0-11 and TRM / B 3.0-12 Pages TRM / B 3.0-13 and TRM / B 3.0-14 Page TRM / B 3.0-15 08/31/1998 03/15/2002 11/30/2005 03/15/2002 B 3.1 REACTIVITY CONTROL SYSTEMS BASES Pages TRM / B 3.1-1 through TRM / B 3.1-3 Page B 3.1-4 Page TRM / B 3.1-5 Pages TRM / B 3.1-6 and TRM / B 3.1-7 Page TRM / B 3.1-8 07/13/19'99 08/31/1998 11/15/2005 03/22/20136 02/18/1999 B 3.2 CORE OPERATING LIMITS BASES Page B 3.2-1 08/31/1998 B 3.3 INSTRUMENTATION BASES Page TRM / B 3.3-1 Page B 3.3-2 Pages TRM / B 3.3-3 and TRM / B 3.3-3A Pages TRM / B 3.3-4 through TRM / B 3.3-6 Pages TRM / B 3.3-7 through TRM I B 3.3-9 Page B 3.3-10.Pages TRM / B 3.3-11 and TRM / B 3.3-12 Page TRM / B 3.3-13 Page TRM / B 3.3-14 Page TRM / B 3.3-14a Page TRM / B 3.3-14b Pages TRM / B 3.3-15 and TRM / B 3.3-16 Page TRM / B 3.3-17 Pages TRM / B 3.3-17a through TRM I B 3.3-17f Pages TRM / B3.3-18 and TRM / B 3.3-19 Page TRM / B 3.3-20 Page TRM / B 3.3-21 04/07/201)0 08/31/1938 01/31/2005 0S/02/2005 03/30/2001 08/31/1998 09/13/201)5 12/03/2004 06/25/20102 06/14/2002 06/14/2002 10/22/2003 03/22/20106 03/22/20136 05/16/2033 10/22/2033 05/16/20)3 I B 3.4 B 3.5 B 3.6 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 through B 3.4-4 Page TRM / B 3.4-5 Page B 3.4-6 ECCS AND RCIC BASES Pages B 3.5-1 through B 3.5-5 CONTAINMENT BASES Page TRM / B 3.6-1 Page TRM / B 3.6-2 Page B 3.6-3 08/31/1998 10/15/1999 08/31/1998 08/31/1998 07/26/2001 02/01/1999 08/31/1998 SUSQIJEHANNA

-UNIT I TRM / LOES-5 EFFECTIVE DATE 03/22/2006 SUSQUEHANNA

-UNIT 1 TRM / LOES-5 EFFECTIVE DATE 03/22/2006 SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 27 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Sectio, Title Effective Date Page TRM / B 3.6-4 Page TRM / B 3.6-5 Pages TRM / B 3.6-6 Pages B.3.6-7 through TRM / B 3.6-11 09/23/1999 01107/2002 12/03/2004 12/31/2002 B 3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 Pages TRM / B 3.7-3 through TRM / B 3.7-5 Page TRM I B 3.7-6 Pages TRM / B 3.7-7 and TRM / B 3.7-7a Pages TRM / B 3.7-8 through TRM / B 3.7-10 Page TRM / B 3.7-10a Pages TRM / B 3.7-11 and TRM / B 3.7-11 a Pages TRM / B 3.7-12 through TRM / B 3.7-14 Page TRM / B 3.7-14a Page TRM / B 3.7-14b Pages TRM / B 3.7-15 and TRM / B 3.7-16 Pages B 3.7-17 through B 3.7-20 Pages TRM/B 3.7-21 and TRM/B 3.7-21 a Pages TRM/B 3.7-22 and TRM/B 3.7-23 Page B 3.7-24 Page TRM / B 3.7-25 Pages B 3.7-26 through B 3.7-30 Page TRM / B 3.7-31 Page TRM / B 3.7-32 Page TRM / B 3.7-33 Page TRM / B 3.7-34 Page TRM / B 3.7-35 08/31/1998 08/02/1999 08/16/2005 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08/02/1999 01/09/2004 02/01/1999 08/31/1998 02/14/2005 04/07/2000 08/31/1998 12/03/2004 08/31/1998 12/03/2004 03/09/2001 04/15/2003 12/03/2004 07/05/2000 B 3.8 B.3.9 ELECTRICAL POWER BASES Page TRM / B 3.8-1 Fages TRM / B 3.8-2 and TRM / B 3.8-2a Page TRM / B 3.8-3 Piage TRM / B 3.8-3a Fage TRM / B 3.8-4 eage TRM / B 3.8-4a Page TRM / B 3.8-5 Iages TRM / B 3.8-6 through TRM / B 3.8-16 Page TRM / B 3.8-17 REFUELING OPERATIONS BASES Pages B 3.9-1 through B 3.9-7* I 1 ': 04/02/2002 01/28/2005 04/02/2002 04/02/2002 08/10/2004 04/02/2002 08/31/1998 04/02/2002 01/28/2005 08/31/1998 SUSQUEHANNA

-UNIT I TRM / LOES-6 EFFECTIVE DATE 03/22/2006 SUSQUEHANNA

-UNIT 1 TRM / LOES-6 EFFECTIVE DATE 03/22/2006 SUSQIJEHANNA STEAM ELECTRIC STATION PPL Rev. 27 LIST CPF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title B 3.10 MISCELLANEOUS BASES Page B 3.10-1 Page TRM / B 3.10-2 and TRM / B 3.10-3 Pages TRM / B 3.10-4 and TRM / B 3.10-5 Pages TRM / B 3.10-6 and TRM / B 3.10-7 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 Page TRM / B 3.11-10 Pages TRM/B 3.11 -11 and TRM/B 3.11 -1 Ia Pages TRM/B 3.11-12 and TRM/B 3.11-13 Page TRM / B 3.11-14 Page TRM / B 3.11-15 Pages! B 3.11-16 through B 3.11-19 Page TRM / B 3.11-20 Page TRM / B 3.11-20a Pages TRM / B 3.11-21 through TRM / B 3.11.23a Pages TRM / B 3.11-24 and TRM /B 3.11-25 Pages B 3.11-26 and B 3.11-27 Pages TRM / B 3.11-28 and TRM / B 3.11-29 Page TRM / B 3.11-30 Pages B 3.7-31 through B 3.7-35 Page TRM / B 3.11-36 B.3.12 LOADS CONTROL PROGRAM BASES Pages TRM / B 3.12-1 through TRM / B 3.12-3 Effective Date 08/31/1998 03/22/20106 08/23/1999 04/17/2002 08/30/1998 02/01/1999 04/07/2000 02/01/1999 12/03/2004 02/01/1999 08/30/1998 04/02/201)2 04/02/201)2 05/13/2005 01/21/2004 08/30/1998 11/30/2005 12/03/2004 08/30/1998 02/12/1999 02/05/1999 TRM1 text LOES 3/22/06 SUSQLUEHANNA

-UNIT 1 I -TRM / LOES-7 EFFECTIVE DATE 03/22/2006 Instrument Trip Setpoint Program 2.2 PPL Rev. 5%4I,",-2.0 2.2 PLANT PROGRAMS AND SETPOINTS Instrument Trip Setpoint Table The Instrument Trip Setpoint Limits in Table 2.2-1 are the Trip Setpoint value limits that were contained in~the Instrumentation Setpoint tables for protection systems aid other functions important to safety that were included in the scope of the original Standard Technical Specifications.

Actual instrument setpoints are established utilizing the Allowable yalues specified in the Technical Specifications and Technical Requirements.

Allowable Values are established in the Reference LCOs and TROs identified in this Tabled TRO references are enclosed in square brackets.Instrumentation process setpoints for the listed subsystems and trip functions are set consistent with the Trip Setpoint Limit Column of Table 2.2-1. Actual setpoints are established in accordance with engineering procedures.

Alarm setpoints and other non-protection system trip settings as may be found in the Technical Specifications or in the Technical Requirements are not included in this table.Reference NDAP-QA-1104 Setpoint Change Control.11.I 4 I j i, d; I! 1 1 1 : SUSQUJEHANNA

-UNIT 1 TRM /2.0-5 EFFECTIVE DATE 04/02/1999 Instrument Trip Setpcint Program 2.2 PPL Rev. 5 TABLE 2.2-1 (Page 1 of 8)INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO [TRO] TRIP FUNCTION TRIP SETPOINT 2.2.1 Reactor Protection 2.2.1.1 3.3.1.1 Intermediate Range Monitor, Neutron Flux - 120/125 divisions of full scale High 2.2.1.2 3.3.1.1 Average Power Range Monitor, Neutron Flux 15% of RATED THEiRMAL POWER-High (Setdown)2.2.1.3 3.3.1.1 Average Power Range Monitor, Simulated See COLR -TRO 3.2 Thermal Power- High, Two Loop Operation 2.2.1.4 3.3.1.1 Average Power Range Monitor, Simulated See COLR -TRO 3.2 Thermal Power- High, Single Loop Operation 2.2.1.5 3.3.1.1 Average Power Range Monitor, Simulated 113.5% of RATED THERMAL Thermal Power- High, Clamp POWER 2.2.1.6 3.3.1.1 Average Power Range Monitor, Neutron Flux - 118% of RATED TH ERNMAL High POWER 2.2.1.7 3.3.1.1 Reactor Vessel Steam Dome Pressure -High 1087 psig 2.2.1.8 3.3.1.1 Reactor Vessel Water Level -Low, Level 3 13.0 inches(a)2.2.1.9 3.3.1.1 Main Steam Isolation Valve -Closure 10% closed 2.2.1.10 This Section Not Used 2.2.1.11 3.3.1.1 Drywell Pressure-High 1.72 psig 2.2.1.12 3.3.1.1 Scram Discharge Volume Water Level -High - 65 gallons Level Transmitter 2.2.1.13 3.3.1.1 Scram Discharge Volume Water Level -High -61 gallons Float Switch 2.2.1.14 3.3.1.1 Turbine Stop Valve -Closure 5.5% closed 2.2.1.15 3.3.1.1 : Turbine Control Valve Fast Closure, Trip 2 500 psig Oil Pressure -Low (continued)(a) See Figlure 2.2-1 I i I I I : SUSQUEHANNA

-UNIT 1 TRM / 2.0-6 EFFECTIVE DATE 3122/2006 Instrument Trip Setpoint Program 2.2 PPL Rev. 5 TABLE 2.2-1 (Page 2 of 8)INSTRUMENTATION SETPOINTS i SYSTEM/REFERENCE LCO [TRO] TRIP FUNCTION TRIP SETDOINJT 2.2.1.16 OPRM Instrumentation 2.2.1.16.1 3.3.1.1 Sp PBA Amplitude Trip See COLR-TRO 3.2 2.2.1.16.2 3.3.1.1 Np PBA Successive Confirmation Count Trip See COLR -TRO 3.2 2.2.1.16.3

[3.3.9] TOL (E) Period Tolerance 0.10 sec 2.2.1.16.4

[3.3.9] fc Conditioning Filter Cutoff Frequency 1.50 Hz 2.2.1.16.5

[3.3.9] Tmin Oscillation Period Lower Time Limit 1.00 sec 2.2.1.16.5

[3.3.9] Tmax Oscillation Period Upper Time Limit 3.50 sec 2.2.1.16.7

[3.3.9] LPRMmin Minimum LRPMs/Cell Required for 2 Cell Operability 2.2.1.16.B

[3.3.9] S1 Peak Threshold SetpointlABA

& GRBA 1.2C 2.2.1.16.9

[3.3.9] S2 yalley Threshold Setpoint/ABA

& GRBA 0.85 2.2.1.16.10

[3.3.9] i Smax Amplitude Trip Setpoint/ABA 1.50 2.2.1.16.11

[3.3.9] i DR3 Growth Rate Factor Setpoint/GRBA 1.60 2.2.2 Isolation Actuation Instrumentation 2.2.2.1 Primary Containment Isolation' 2.2.2.1.1 3.3.6.1 Reactor Vessel Water Level Low, Level 3 2 13.0 inchesca)2.2.2.1.2 3.3.6.1 Reactor Vessel Water Level Low Low, Level 2 2 -38.0 inches(a)2.2.2.1.3, 3.3.6.1 Reactor Vessel Water Level Low Low Low, 2-129 inches(a)Level 1 2.2.2.1.4 3.3.6.1 i Drywell Pressure -High 1.72 psig 2.2.2.1.5 3.3.6.1/[3.3.6]

SGTS Exhaust Radiation

-High 23.0 mR/hr 2.2.2.1.6

[3.3.6] Main Steam Line Radiation

-High High < 15 x full power background without hydrogen in'ection (continued)(a) See Fig;ure 2.2-1.i;1 Ii I i1.11 ii.II iI:i1 I1!i I SUSQUEHANNA

-UNIT 1 TRM / 2.0-7 EFFECTIVE DATE: 3/22/2006 Instrument Trip Setpoint Program 2.2 PPL Rev. 5 TABLE 2.2-1 (Page 3 of 8)INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO[TRO] TRIP FUNCTION TRIP SET:OlJNT 2.2.2.2 2.2.2.2.1 2.2.2.2.2 2.2.2.2.3 2.2.2.2.4 2.2.2.2.5 Secondary Containment Isolation 3.3.6.2 3.3.6.2 3.3.6.2 3.3.6.2 3.3.6.2 2.2.2.3 Main Steam Line Isolation 2.2.2.3.1 2.2.2.3.2 2.2.2.3.3 2.2.2.3.4 2.2.2.3.5 3.3.6.1 3.3.6.1 3.3.6.1 3.3.6.1 3.3.6.1 Reactor Vessel Water Level -Low Low, Level 2 Drywell Pressure -High Refuel Floor High Exhaust Duct Radiation

--High Railroad Access Shaft Exhaust Duct Radiation

-High Refuel FloorWall Exhaust Duct Radiation

-High Reactor Vessel Water Level -Low Low Low, Level 1 Main Steam Line Pressure -Low Main Steam Line Flow- High Condenser Vacuum -Low Reactor Building Main Steam Line Tunnel Temperature

-High This Section Not Used Reactor Building Main Steam Line Tunnel A Temperature

-High Turbine Building Main Steam Tunnel Temperature

-High 2-38.0 inches(a) 1.72 psig 18 mR/hr 5 mR/hr 21 mR/hr 2 -129 inches(.)2 861 psig 113 psid 2 9.0 inches Hg vacuum 177TF 990: 197'F 2.2.2.3.6 2.2.2.3.7[3.3.6]2.2.2.3.8[3.3.61 I 2.2.2.4 Reactor Water Cleanup System Isolation 2.2.2.4.1 2.2.2.4.2 2.2.2.4.3 2.2.2.4.4 2.2.2.4.5 2.2.2.4.6 2.2.2.4.7 3.3.6.1 3.3.6.1 3.3.6.1 3.3.6.1[3.3.6]I -i i -2.2.2.4.8 2.2.2.4.9 I .3.3.6.1 :- i[3.3.6]3.3.6.1[3.3.6] i El.I i Reactor Vessel Water Level -Low Low, Level 2 RWCU A Flow- High RWCU Flow -High RWCU Penetration Area Temperature

-High RWCU Penetration Room Area A Temperature-High RWCU Pump Area Temperature

-High RWCU Pump Room Area A Temperature

-High RWCU Heat Exchanger Area Temperature

-L High RWCU Heat Exchanger Room Area A Temperature

-High-38 inches(a)s59gpm462gpm 131'F 6901: s 147'F 6901: S 147'F 690I: (continued)(a) See Figure 2.2-1 SUSQUEHANNA

-UNIT 1 TRM / 2.0-8 EFFECTIVE DATE 12/0312004 Instrument Trip Setpoint Program 2.2 PPL Rev. 5 iXwo 4 TABLE 2.2-1 (Page 4 of 8)INSTRUMENTATION SETPOINTS I; SYSTEM/REFERENCE LCO[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.2.5 Reactor Core Isolation Cooling System Isolation_ _ _ _ ,, 2.2.2.5.1 3.3.6.1 RCIC Steam Line A Pressure-High 2.2.2.5.2 3.3.6.1 RCIC Steam Supply Line Pressure -Low 2.2.2.5.3 3.3.6.1 RCIC Turbine Exhaust Diaphragm Pressure-High 2.2.2.5.4 3.3.6.1 RCIC Equipment Room Temperature

-High 2.2.2.5.5 3.3.6.1, RCIC Pipe Routing Area Temperature

-High 2.2.2.5.6 3.3.6.1 RCIC Emergency Area Cooler Temperature

-High 2.2.2.5.7 3.3.6.1 Drywell Pressure -High 2.2.2.5.8

[3.3.6] RCIC Equipment Room A Temperature

-High 2.2.2.5.9, [3.3.6] RCIC Pipe Routing Area A Temperature

-High 2.2.2.6 High Pressure Coolant Injection System Isolation s 188 inches H 2 0 2 60 psig< 10.0 'DSig s 167 0 F 167 0 F 167 0 F s 1.72 psig 89 0 F s891F 2.2.2.6.1 2.2.2.6.2 2.2.2.6.3, 2.2.2.6.4 2.2.2.6.5 2.2.2.6.6,i 2.2.2.6.7 2.2.2.6.8 2.2.2.6.9!

2.2.2.7 2.2.2.7.1 2.2.2.7.2 2.2.2.7.3 2.2.3 2.2.3.1 2.2.3.1.1 2.2.3.1.2 2.2.3.1.3 3.3.6.1 3.3.6.1 3.3.6.1.3 .1 3.3.6.1 3.3.6.1 HP(HP(HP(Higi HP(HP(Higl CI Steam Line A Pressure -High CI Steam Supply Line Pressure -Low Cl Turbine Exhaust Diaphragm Pressure -Cl Equipment Room Temperature

-High'I Emergency Area Cooler Temperature

-CI Pipe Routing Area Temperature

-High well Pressure -High ,I Equipment Room A Temperature

-High CI Pipe Routing Area A Temperature

-3.3.6.1 HP(3.3.6.1 Dry\.[3.3.6] HP([3.3.6] HP(Higl Shutdown Cooling/System Isolation , Rea 3.3.6.!1 I l Ree[3.3.6] I, RHf ECCS Actuation' Core Spray System 3.3.5.1 Rea I Lev, 3.3 .5.1] Dry 3.3.'5.1Res ire 2.2-1 370 inches H 2 0 2 104 psig S 10 psig 167 0 F 1670F 167*F 1.72 psig 89'F 891F 2 13.0 inches(a)5 98 psig s 25,00C gpm 2 -129 inches(a) 1.72 Dsig 2 413, S 4:27 psig actor Vessel Water Level -Low, Level 3 ictor Vessel Steam Dome Pressure -High R Flow- High ictor Vessel Water Level -Low Low Low, el 1 Nell Pressure -High ictor Vessel Steam Dome Pressure -Low ction permissive (continued)(a)See FigI i I SUSQUEHANNA-i.UNIT 1 1, TRM / 2.0-9 EFFECTIVE DATE 11/15/2004 Instrument Trip Setpoint Program PPL Rev. 5 2.2 TABLE 2.2-1 (Page 5 of 8)! ?IN.ZTRI IhArFKTATlr)K QrFT0('l MTCZh I II N!J S JIVI IN I 1N U %- IN lu 01 IS I N S I SYSTEM/REFERENCE LCO[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.3.2 LPCI Mode of RHR System 2.2.3.2.1 3.3.5.1 Reactor Vessel Water Level -Low Low Low, 2 -129 inches~a)Level 1 2.2.3.2.2 3.3.5.1 Drywell Pressure -High 1.72 psig 2.2.3.2.3 3.3.5.1 Reactor Vessel Steam Dome Pressure -Low, 2 413, < 427 psig injection permissive 2.2.3.2.4 3.3.5.1 Reactor Vessel Steam Dome Pressure -Low, > 236 psig, cecreasing Recirculation Discharge Valve permissive 2.2.3.3 HPCI System 2.2.3.3.1 3.3.5.1 Reactor Vessel Water Level -Low Low, 2 -38 inches(a)Level 2 2.2.3.3.2 3.3.5.1 Drywell Pressure -High 1.72 psig 2.2.3.3.3 3.3.5.1 Condensate Storage Tank Level -Low 2 36.0 inches above tank bottom 2.2.3.3.4 3.3.5.1 Reactor Vessel Water Level -High, Level 8 54 inches 2.2.3.4 Automatic Depressurization System (ADS)2.2.3.4.1 3.3.5.1 Reactor Vessel Water Level -Low Low Low, -129 in hes i Level 1 2.2.3.4.2 3.3.5.1 Drywell Pressure -High 1.72 psig 2.2.3.4.3 3.3.5.1 ADS Timer 102 seconds 2.2.3.4.4 3.3.5.1 Core Spray Pump Discharge Pressure -High 2 135, 15i5 psig 2.2.3.4.5 3.3.5.1 Low Pressure Coolant Injection Pump 2 121, < 129 psig Discharge Pressure -High 2.2.3.4.6 3.3.5.1 Reactor Vessel Water Level -Low, Level 3 2 13 inches Confirmatory 2.2.3.4.7 3.3.5.1 ADS Drywell Pressure Bypass Timer 420 seconds 2.2.3.5 Loss of Power -ECCS Actuation 2.2.3.5.1 4.16kv ESS Bus Undervoltage (Loss of Voltage < 20%)2.2.3.5.1 1 3.3.8.1 I Bus Undervoltage

> 823.2, 856.8 Volts 2.2.3.5.1 2 3.3.8.1 , Time delay 2 0.4, 0.6 seconds (continued)(a) See Fi ]ure 2.2-1 I ; 1.11 : ; I !I , i I , I i 1.; I I i I I j I 11 1 i I t44o*i SUSQUEHANNA

-UNIT 1TRM / 2.0-10 EFFECTIVE DATE'l 1/15/2004 Instrument Trip Setpoint Program PPL Rev. 5 2.2 TABLE 2.2-1 (Page 6 of 8)INSTRUMENTATION SETPOINTS I; ; SYSTEM/REFERENCE LCO[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.3.5.2 2.2.3.5.2.1 2.2.3.5.2.2 2.2.3.5.3 2.2.3.5.3.1 2.2.3.5.3.2 2.2.3.5.3.4 2.2.3.5.4 2.2.3.5.4.1 2.2.3.5.4.2 2.2.3.5.5 2.2.3.5.5.1 2.2.3.5.5.2 2.2.4 2.2.4.1 2.2.4.1 2.2.5 2.2.5.1 2.2.5.2 2.2.6 2.2.6.1 2.2.6.2 2.2.6.3 4.16kV ESS Bus Undervoltage (Degraded Voltage < 65%)3.3.8.1 Bus Undervoltacge 3.3.8.1 Time delay 4.16kV ESS Bus Undervoltage (Degraded Voltage, < 93%)3.3.8.1 Bus Undervoltage 3.3.8.1 Time Delay (Non-LOCA) 3.3.8.1 Time Delay (LOCA)480V ESS Bus OB565 Undervoltage (Degraded Voltage, < 65%)[3.8.5] 480V Basis[3.8.5] Time Delay 480V ESS Bus 0B565 Undervoltage (Degraded Voltage, < 92%)[3.8.5] 480V Basis[3.8.5], Time Delay ATWS Alternate Rod Injection and Recirculation Pump Trip 3.3.4.2/[3.1.1]

Reactor Vessel, Water Level -Low Low, Level 2 3.3.4.2/[3.1.1]

Reactor Vessel Steam Dome Pressure -High End of Cycle Recirculation Pump Trip 3.3.4.1 Turbine Stop Valve-Closure 3.3.4.1 Turbine Control Valve -Fast Closure Reactor Core Isolation Cooling System Actuation 3.3.5.2 Reactor Vessel Water Level -Low Low, Level 2 3.3.5.2 Reactor Vessel Water Level -High, Level 8 3.3.5.2 Condensate Storage Tank Level -Low 2 2:.2.2-1 I2641.1, 2748.9 Volts 2 2.7, 3.3 seconds 2 3829.3, < 3906.7 Volts 2 4 minute, 30 seconds< 5 minute, 30 seconds 2 9, 11 seconds 2 308.9, 315.1 Volts> 4.5, < 5.5 seconds437.6, S 416.4 Volts 2 9, 11 seconds 2 -38 inches(a) 1135 psig 5.5% closed 2 500 psig 2 -38 inches(a) 54 inches(a)2 36.0 inches abcve tank bottom (continued)(a)See Figure SUSQUEHANNA

-UNIT 1'TRM / 2.0-11 i EFFECTIVE DATE 11/15/2004 PPL Rev. 5 Instrument Trip Setpoint Program 2.2 TABLE 2.2-1 (Page 7 of 8)I INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.7 Control Rod Block 2.2.7.1 Rod Block Monitor 2.2.7.1.1 3.3.2 2.2.7.1.2 3.3.2 Low Power Range Upscale -Two Loop Operation Low Power Range Upscale -Single Loop I Operation Downscale s 0.58W + 52%< 0.58 (W-AW), + 52%('5%2.2.7.1.3 2.2.7.2 APRM 2.2.7.2.1[3.1.3]2.2.7.2.2 2.2.7.2.3 2.2.7.2.4 2.2.7.2.5[3.1.3][3.1.3][3.1.31[3.1.3]Simulated Thermal Power-High

,-Two Loop Operation Simulated Thermal Power-High

-Single Loop Operation Simulated Thermal Power-High

-Clamp Downscale Neutron Flux -High (Setdown)See COLR -lRO 3.2 lSee COLR -TRO 3.2 ls 108% of RATED THERMAL I POWER 2 5% of RATED THERMAL POWER 12% of RATED THERMAL POWER I 2.2.7.3 Source Range Monitors 2.2.7.3.1 2.2.7.3.2 2.2.7.4[3.1.3] I1!Upscale

[3.1.3] l Ir Downscale Intermediate Range Monitors l i 2E5 cps 2 3.0 cps(b)2.2.7.4.1 2.2.7.4.2[3.1.3][3.1.3]i Upscale , Downscale 2.2.7.5 Scram Discharge Volume 2.2.7.5.1

[3.1.3] Water Level -High 2.2.7.6 Reactor Coolant System Recirculation Flow 2.2.7.6.1

[3.1.3] Upscale 2.2.7.6.2

[3.1.3] Comparator 108/125 divisions of full scale 2 5/125 divisions of full scale 35.9 gallons 114%< 10% flow deviation Ii (bWith a signal-to-noise ratio 2, or within the limits of Figure 2.2-2.(c) See COLR TRO 3.2 for value of AW (continued)

SUSQUEHANNA

-UNIT 1 TRM / 2.0-12 EFFECTIVE DATE 3/22/2006 Instrument Trip Setpoint Program 2.2 PPL Rav. 5 l>, _Awe TABLE 2.2-1 (Page 8 of 8)INSTRUMENTATION SETPOINTS I SYSTEMIREFERENCE LCO[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.8 CREOASS 2.2.8.1 3.3.7.1 Main Control Room Outside Air Intake 5 mF/hr Radiation Monitor 2.2.8.1.1 3.3.7.1 Reactor Vessel Water Level -Low Low, > -38.0 in.hes(a)Level 2 2.2.8.1.2 3.3.7.1 Drywell Pressure -High 1.72 ,sig 2.2.8.1.s; 3.3.7.1 Refuel Floor High Exhaust Duct Radiation 18 mR/hr-High 2.2.8.1.4 3.3.7.1 Railroad Access Shaft Exhaust Duct 5 mRFhr Radiation

-High 2.2.8.1.5 3.3.7.1 Refuel Floor Wall Exhaust Duct Radiation 21 mR/hr-High 2.2.9 Feedwater/Main Turbine Trip System Actuation 2.2.9.1 3.3.2.2 Reactor Vessel Level -High 54.0 inches(3)2.2.10 MVP Isolation 2.2.10.1 [3.3.11] Main Steam Line Radiation

-High High 15 x full power background without hydrogen injection (a) See Fi'ure 2.2-1!1 i, jl.i! II , I! l1 I'r:.i iI SUSQLIEHANNA

-UNIT.1 TRM / 2.0-13 EFFECTIVE DATE 11/15/2004 Instrument Trip Setpoint Table 2.2 PPL Rev. 5 1 i i 1 I I i TRM / 2.0-14 I Ii SUSQUEHANNA

-UNIT 1 EFFECTIVE DATE 11/15/2004 PPL Rev. 5 Instrument Trip Setpoint Table 2.2 Instrument Trip Setpoint Table 2.2 3 ,2.8 2.6 2.4 2.2 2 U, a-%(n CL 0 1--z D 0 U, 1.8 1.6 1.4 1.2 1 0.8-I 1 1 1 1 1 1 1 1 1 1 1 1 1 1 I I I 1 lXrl l 111 1 1 1 1-LTrl [ F l T I T I I I n 1\ 1 1 I T I I T I T I I I T 1 101 I T:T I I T 1 TTI 1 T1 1\1 1 ItT I I I I T l l l l 1 1N I I;T I I I I Tll I IXl 0 l l l l Accep.oble:-

l l l l l1S 1 1 I Ll I Ll___ _ ___- _ __Not Acceptable

_. _ .-_ _ _l ' _ .__ _X X X X X_ ! : _0.6 0.4 0.2 0 2 6 ; 10 '14 18 22 26 30 i, d i i i 1 :I i ;.- I ' E l Signal-to-Noise Ratio Figure 2.2-2 Setpoint Ver;us Sign;:3I-to-Noise Ratio Minimum SRM !Trip I .;: ~SUSQUEHANNA

-UNIT I TRM / 2.0-15 EFFECTIVE DATE 11115/2005 PPL Rev. 3 Control Rod Block Instrumentation 3 .1.3 3.1 Reactivity Control Systems 3.1.3 Control Rod Block Instrumentation The control rod block instrumentation for each function in Table 3.1.3-1 shall be OPERABLE.APPLIC ABILITY: According to Table 3.1.3-1 ACTIO NS NOTE-Separate condition entry is allowed for each channel CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required KA.1 Enter the Condition referenced Immediately channels inoperable.

in Table 3.1.3-1for the channel.B. As equired by Required .B.1 Place at least one inoperable 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery Act on A.1 and referenced channel in the tripped of loss of trip in Table 3.1.3-1. condition.

capability AND B.2 Place the inoperable channel 7 days in the tripped condition.

C. As required by Required:'

C.1 Place the inoperable channel 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action A.1 and referenaced l in the tripped condition.

in Table 3.1.3-1. I-D. Required Actions and li D 1 Suspend Control Rod Immediately Completion Time of withdrawal.

Conditions B or C not met.D__ ___ ___ _ _ ll __ l __[I' 1 : SUSQUEHANNA

-UNIT 1 3.1-5 EFFECTIVE DATE 8/31/1998 Control Rod Block Instrumentation 3.1.3 PPL Rev. 3 TECHNICAL REQUIREMENT SURVEILLANCE

-- NOTES 1. Ref er to Table 3.1.3-1 to determine which TRSs apply for each Control Rod Block I Function.2. Neutron detectors may be excluded from CHANNEL CALIBRATION.

3. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided at least one other OPERABLE channel in the same trip system is moiitoring that parameter.

'%,, WI'I SURVEILLANCE FREQUENCY TRS 3.1.3.1 Perform CHANNEL CHECK 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months TRS 3.1.3.2 -- ----- NOTE For Function 1.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.Perform CHANNEL FUNCTIONALTEST 184 days TRS 3.1.3.3 Perform CHANNEL FUNCTIONAL TEST 7 days TRS 3.1.3.4 Perform CHANNEL FUNCTIONAL TEST 92 days TRS 3.1.3.5 Perform CHANNELFU CALIBRATION 1T 84 days-- NOTE Neutron detectors are excluded.TRS 3.1.3.6 Perform CHANNELCALIBRATION 24 months TRS 3.1.3.7 Perform LOGIC SYSTEM FUNCTIONAL TEST *24 months 1aiv SUSQUEHANNA

-UNIT 1 TRM / 3.1-6 EFFECTIVE DATE 3/22/2006 Control Rod Block Instrumentation C..1.3 PPL Rev. 3 TABLE 3.1.3-1 (Page 1 of 2)CONTROL ROD BLOCK INSTRUMENTATION APPLICABLE REQUIRED CONDITIONS MODES OR OTHER CHANNELS REFERENCED FROM SPECIFIED REQUIRED ACTION SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS A.1 REQUIREMENTS VALUE 1. APRM a. Neutrcn Flux- 2,5'a) 3 B TRS3.1.3.2 s1 4%RTP High (;etdown)

TRS 3.1.3.6 b. Simulated Thermal 1 3 B TRS 3.1.3.2 See COLR Power -High TRS 3.1.3.6 TRD 3.2 (b)c. Down.,cale 1 3 B TRS3.1.3.2 23Y6RTP TRS 3.1.3.6 d. Inop 1,2 3 B TRS3.1.3.2 NA 5(3) 3 B TRS 3.1.3.2 NA 2. Source R inge Monitors a. Detectzr not full in 2(c) 3 B TRS 3.1.3.3 NA TRS 3.1.3.7 51i 2 B TRS3.1.3.3 NA TRS 3.1.3.7 b. Upscae 2(d) 3 B TRS3.1.3.3 S3.SE5cps TRS 3.1.3.6 TRS 3.1.3.7 56) 2 B TRS 3.1.3.3 S 3.1E5 cps TRS 3.1.3.6 TRS 3.1.3.7 c. Inop 2(d) 3 B TRS 3.1.3.3 NA TRS 3.1.3.7 5G) 2 B TRS 3.1.3.3 NA TRS 3.1.3.7 (continued)(a)(b)(c)(d)U)When performing Shutdown Margin Demonstration per Technical Specification 3.10.8.See COLR for single loop operation per Technical Specification 3.4.1, Recirculation Loops Operating When not automatically bypassed with SRM counts 2 100 cps or the IRM channels on range 3 or higher.When not automatically bypassed with IRM channels on range 8 or higher.With any control rod withdrawn from a core cell containing one or more fuel assemblies.

SUSQUEHANNA

-UNIT 1 TRM /3.1-7 EFFECTIVE DATE 3/22/2006 Control Rod Block Instrumentaition PPL Rev. 3 3.1.3 TABLE 3.1.3-1 (Page 2 of 2)CONTROL ROD BLOCK INSTRUMENTATION APPLICABLE REQUIRED CONDITIONS MODES OR OTHER CHANNELS REFERENCED FROM SPECIFIED REQUIRED ACTION SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS A.1 REQUIREMENTS VALUE d. Downscale 2(e) 3 B TRS3.1.3.3 21.8cps(f TRS 3.1.3.6 TRS 3.1.3.7 506) 2 B TRS 3.1.3.3 2 1.8 cps('TRS 3.1.3.6 TRS 3.1.3.7 3. Intermediate Range Monitors a. Detectr not full in 2, 50) 6 B TRS 3.1.3.3 NA TRS 3.1.3.7 b. NeutrcnFlux-2,50) 6 B TRS3.1.3.1 S110/125 High TRS 3.1.3.3 divisions of full TRS 3.1.3.5 scale TRS 3.1.3.7 c. Inop 2. 5@) 6 B TRS 3.1.3.3 NA TRS 3.1.3.7 d. Downscale 2(0 50) 6 B TRS 3.1.3.1 3/125 divisions TRS 3.1.3.3 of full scale TRS 3.1.3.5 TRS 3.1.3.7 4. Scram Discharge 1.2,5(h) 2 C TRS 3.1.3.4 S 36.5 gallons Volume Water Level -TRS 3.1.3.6 High 5. Reactor Coolant System R Rcirculation Flow a. Upscale H 3 C TRS3.1.3.2 S117/125 I TRS 3.1.3.6 divisions of fu I scale b. Comparator 1 " 1 C TRS3.1.3.2 11% flowv I [ TRS 3.1.3.6 devuiation (e) When not automatically bypassed with IRMs on range 3 or higher.With a signal-to-noise ratio 2 '2,' or w~ithin the limits of TS Figure 3.3.1.2-1.

9 When not automatically bypassed uwith IRM channels on range 1.(h) When more than one control rod is withdrawn.

Not applicable to control rods removed per Technical Specification 3.10.5or 3.1o.6.Not required when eight or fewer fuel assemblies (adjacent to the SRMs) are in the core.With any control rod withdrawn from a core cell containing one or more fuel assemblies.

SUSQLEHANNA-UNIT1 TRM / 3.1-8 EFFECTIVE DATE 3/22/200E6 OPRM Instrumentation 3.3.9 PPL. Rev. 2 3.3 Instrumentation 3.3.9 OPRM Instrumentation Configuration TRC) 3.3.9 Oscillation Pow)er Range Monitor (OPRM) supporting setpoints and settings shall be within the specified limits.APPLICABILITY:

ACTIONS Thermal POWER >25% RTP KItT 1\I'J) I t-------------

1. , Separate Condition entry is allowed for each channel., i Jo CONDITION REQUIRED ACTION COMPLETION TIME-A. OPRM Setpoints and l A.1 Enter the condition referenced in Immediately Settings not in accordance Table 3.3.9-1 for the parameter with Table 3.3.9-1 Al B. As required by Required B.1 Declare affected OPRM channel Immediately Action A.1 and referenced inoperable.

in Table 3.3.9.1 C. As required by Required C.1 Restore the OPRM Setpoints and 120 days Action A.1 and referenced Settings to within the specified in Table 3.3.9-1 limits.OR C.2 Declare affected OPRM channel F .Immediately I__________

_i Inoperable D. Alternate method to detect D.1 Initiate monitoring to detect entry Immediately and suppress thermal' into Conditions E,F, and/or G.hydraulic instability loscillations required by LCO 3.3.1.1 Required Action 1.1.(continued)

I1s/2 i SUSQUEHANNA

-UNIT 1 TRM / 3.3-22 EFFECTIVE DATE 3/22/2006 OPRM Instrurr entation PPI Rev. 2 3.3.9 11 %1W.ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. a- NOTE-----'Only applicable as required by Required Action D.1 E.1 Place reactor mode switch in the Immediatelv Total core flow as a sudw oiin'function of THERMAL POWER within Region I of,'the Power Flow map as specified in the COLR.OR Total core flow as a function of THERMAL POWER within Region II 'of the Power Flow map as specified in the COLR and less than 50% of required, ,LPRM upscale alarms'OPERABLE F. -NOTE---Only applicable as required by Required Action D.1 and when in Region 11 of the Power JFl6w map as specified,'in th4 COLR.Two or more APRM lM readings oscillating with lone or more oscillatingI 20% of RTP pak-to-peak OR F.1 Place the reactor mode switch in the shutdown position.Immediately (continued)

I .I kI ,;! fill i 1 !I I : II ! ; I SUSQUEHANNA

-UNIT 1 I TRM / 3.3-22a EFFECTIVE DATE 1111512004 PPIi Rev. 2 OPRM Instrumentation 3.3.9"tqgv CONDITION REQUIRED ACTION COMPLETION TIME F. (continued)

Two or more LPRM upscale alarms activating and deactivating with a period 1 second and S5 seconds.OR Sustained LPRM oscillations

>10 W/cm 2 peak-to-peak with a period1 second and <5 seconds.G. ---NOTE---Only applicable as required by Required Action D.1.Total core flow as a G.1 Initiate action to restore total core Immediately function of THERMAL flow as a function of THERMAL POWER is within Region II POWER outside of Region II.of the Power Flow map as specified in the COLR.H. Less than 50% of the [ H.1 Post sign on the reactor control 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months required LPRM Upscale panel that less than 50% of the Alarms are OPERABLE I LPRM Upscale Alarms are'___ ___I,=OPERABLE.

I'N 1 1:I I I1[,;I;i:1 I-i I l!Il: II1 SU%13'QUEHANNA

-UNIT 1.TRM / 3.3-22b, EFFECTIVE DATE 3/22/2006 OPRM Instrumentation 3.3.9 PPL Rev. 2 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TR' 3.3.9.1 ----NOTE----Only required to be met when an alternate method to detect and suppress thermal hydraulic instability oscillations is required by LCO 3.3.1.1 Required Action 1.1 .;Verify total core flow as a function of THERMAL POWER is outside of Region I and 11 of the Power 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Flow map as specified in the COLR.TR'; 3.3.9.2 Perform CHANNEL CALIBRATION on the LPRM 24 months Upscale alarm 24 months TRES 3.3.9.3 Verify OPRM parameter setpoints and settings are within limits.1:11 I i i Ii i 1 !, I1, I i i iI 11 i a I 1, iI i I I,Ii I i q I i: I;SUSQUEHANNA

-UNIT 1 TRM / 3.3-22c EFFECTIVE DATE 3/22/2006 PPL Rev. 2 OPRM Instrumentation 3.3.9 Table 3.3.9-1 OPRM SETPOINTS AND SETTINGS CONDITIONS REFERENCE D FROM OPRM REQUIRED PARAMETER DESCRIPTION ACTION A.1 VALUE 1. TOL (£) Period Tolerance B 20.10 and<0.30 sec 2. fc Conditioning Filter Cutoff Frequency B 1.5 Hz 3. Tmin Oscillation Period Lower Time Limit B >1.0 and 51.2 sec 4. Tmax Oscillation Period Upper Time Limit B 3.5 sec 5. LPRMmin Minimum LRPMs/Cell Required for Cell B 2 Operability

6. S1 Peak Threshold SetpoinVABA

& GRBA C 21.10 and<1.20 7. S2 Valley Threshold SetpointVABA

& GRBA C >0.85 cand s0.95 8. Smax Amplitude Trip SetpointVABA C >1.30 and<1.50 9. DR3 Growth Rate Factor SetpointVGRBA C >1.30 and<1.60; ' ! I ! 1 ,!I , t i F I i i i it I i i i I .t 1 .1 1 1 I I i I 1I i 1 1; ; I i 1 i I t d Iup SLISDUEHANNA

-UNIT 1 TRM / 3.3-22d EFFECTIVE DATE 3/22/2006 Shutdown Margin Test RPS Instrumentation 3.10.2 PPI. Rev. 1 3.10 Miscellaneous 3.10.2 Shutdown Margin Test RPS Instrumentation TRC) 3.10.2 The Shutdown Margin Test RPS instrumentation for each Function in Table 3.10.2-1 shall be OPERABLE with "shorting links" removed.APPLICABILITY:

MODE 5, During shutdown margin demonstrations per LCO 3.1.1 AC--IONS-- ------------

NOTES Separate Condition entry is allowed for each channel.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Enter the Condition Immediately channels inoperable referenced in Table 3.10.2-1 for the channel B. As required by B.1 Suspend all operations Immediately Required Action A.1 involving CORE and referenced in ALTERATIONS and initiate Table 3.10.2-1 actions to insert all insertable control rods C. As required by C.1 Restore RPS trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Required Action A.1 capability and referenced in lTable 3.10.2-1 AND C.2 Place channel in trip 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D. Required Action and ; l D.1 Suspend all operations associated Completion involving CORE Times of Condition C ALTERATIONS and initiate not met E actions to insert all OR insertable control rods Requirements of the TRO otherwise not met _ __SUr-;QUEHANNA

-UNIT 1 1 TRM / 3.10-4 1 i I EFFECTIVE DATE 8/31/1998 Shutdown Margin Test RPS Instrumentation 3.10.2 PPL. Rev. 1 TECHNICAL REQUIREMENT SURVEILLANCE

NOTES ---- ----------------

1. Refer to Table 3.10.2-1 to determine which TRSs apply for each TRM RPS nstrumentation function.2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the trip function is maintained.

SURVEILLANCE FREQUENCY TR'; 3.10.2.1 Verify SRM is OPERABLE per TRO 3.1.3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months "Control Rod Block Instrumentation" TRS 3.10.2.2 Verify that the RPS circuitry "shorting 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months links" have been removed TRE 3.10.2.3 Perform CHANNEL FUNCTIONAL TEST 7 days TRS 3.10.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST 184 days with "shorting links" removed TRS 3.10.2.5 Perform CHANNEL CALIBRATION 24 months TRS 3.10.2.6 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months z T I;i I!I I SUSQUEHANNA

-UNIT 1 TRM / 3.10-5 EFFECTIVE DATE 3/2:2/2006 PPI Rev. 1 Shutdown Margin Test RPS Instrumentation 3.10.2 TABLE 3.10.2-1 TRM RPS INSTRUMENTATION CONDITIONS REQUIRED REFERENCED CHANNELS FROM PER TRIP REQUIRED SURVEILLANCE FUNCTION SYSTEM ACTION A1 REQUIREMENTS ALLOWABLE VALUE 1. Source Range Monitor (a) B TRS 3.10.2.1 < 3.31-5 CPS TRS 3.10.2.2 TRS 3.10.2.3 TRS 3.10.2.4 TRS 3.10.2.5 2. Intermediate Range Monitor a. Neutron Flux-High 6 C TRS 3.10.2.2 (b)TRS 3.10.2.4 b. Inop 6 C TRS 3.10.2.2 N/A TRS 3.10.2.4 3. Average Power Range Monitor'a. Neutron Flux-High (b) C TRS 3.10.2.2 (b)(Setdown)

TRS 3.10.2.6 b. Inop (b) C TRS 3.10.2.2 N/A TRS 3.10.2.6 c. 2-Out-of-4 Voter l (b) C TRS 3.10.2.2 N/A TRS 3.10.2.6 1 APRM not required for mode 5 as per LCO 3.3.1.1, but is required for other conditions during shutdown margin demonstrations required per LCO'3.1.1.(a) As specified in LCO 3.3.1.2 (b) As specified in LC) 3.3.1.1 I Ii I SU';QUEHANNA

-UNIT 1 I I,.i EFFECTIVE DATE 3/22'2006 TRMJ3.1046 Control Rod Block Instrumentation PPL! Rev. 3 B 3.1.3 B 3.1.3 Control Rod Block Instrumentation BASES_TRC) The Control Rod Block Instrumentation is a portion of the Reactor Manual Control System (RMCS), which upon receipt of input signals from other systems and subsystems, inhibits movement or selection of control rods (Reference i). The purpose of the Control Rod Block function is to avoid conditions that would require Reactor Protection System (RPS) action if allowed to proceed.The specific Functions associated with the TRM Control Rod Block Instrumentation are identified in Table 3.1.3-1 and are discussed below.1. Average Power Rance Monitors (APRM)2. Source Range Monitors (SRM)3. Intermediate Range Monitors (IRM)The same grouping of neutron monitoring equipment (APRM, SRM, and IRM)that ii used in the RPS is also used in the rod block circuitry.

Half of the total monitors (APRM, SRM, and IRM) provide inputs to one of the two RMCS rod block logic circuits and the remaining half provide inputs to the other RMCS rod block circuit.The APRM rod block settings are varied as a function of Reactor Coolant System (RCS) recirculation flow. The settings are selected so that all the neutron monitoring rod blocks are sufficient to avoid an RPS action.Mechanical switches in the SRM and IRM detector drive systems provide the position signals used to indicate that a detector is not fully inserted.The SRM minimum count rate Allowable Value is discussed in the TS Bases for SR 3.3.1.2.4.

4. Scram Discharge Volume Water Level -High Scrami Discharge Volume Water Level -High signals are provided as inputs into both rod block logic circuits.

Both rod block logic circuits sense when the high water level scram trip for the Scram Discharge Volume is bypassed.The rod block from Scram Discharge Volume Water Level -High corries from 6ne of two float type level switches installed in each of two scram discharge instrument volumes. The second float switch in each instrument volurme provides a control room annunciation of increasing level below the level at which'a rod block occurs.l I l (continued) 11&mb-SUSQUEHANNA

-UNIT 1 TRM / B 3.1-5 EFFECTIVE DATE 11/15/2005 Control Rod Block Instrumentation B 3.1.3 PPL. Rev. 3 iI B 3.1.3 'Control Rod Block Instrumentation BAES I IBA';ES, _TRC)(continued)

5. RCS Recirculation Flow The recirculation flow system consists of four separate transmitters on each of two recirculation loops (eight total). The transmitter output signals from one flow channel is routed to one of four APRM channels.

Each APRM processes and sums the transmitter's signals. Each APRM then sends its total flow signal to both RBMs. Each RBM then compares the four flows and issues Alarms based on user entered values. Both RBM channels are identical, but are configured to support either RBM channel A or channel B.With the NUMAC PRNMS system, the Upscale flow function is performed within the APRM and sent on to the reactor manual control system. The flow comparator is performed with the RBM. There is no separate 'inop'functiorn from the APRM 'Upscale/lnop' and RBM 'Upscale/lnop' functions for the recirculation flow.ACTIONS The ACTIONS are defined to ensure proper corrective measures are taken in response to the inoperable components.

i i ,, TRS The TRSs are performed at the specified Frequency to ensure that the Control Rod Block Function is maintained OPERABLE.TRS 3.1.3.1, TRS 3.1.3.2, TRS 3.1.3.3, TRS 3.1.3.4, TRS 3.1.3.5, TRS 3.1.3.6. and TRS 3.1.3.7 Control Rod Block Instrumentation surveillances are performed consistent with the6 Bases forthe comparable channels in LCO 3.3.1.1 and LCO 3.3.1.2.cn

! , (continue I I I~d)j .I I', .; I 1 r" I , I I I i I I I-i L : I i I I ;4 i ..I ; .I ).i ; i I I : , I i i .SUSQUEHANNA-UNIT TEEE2 T RM / B 3.1-6 EFFECTIVE DATE 3/2212006 Control Rod Block Instrumentation B 3.1.3 PP1. Rev. 3 B 3.1.3 Control Rod Block Instrumentation BASES (continued)

REFERENCE

1. FSAR Section 7.7.1 2. NEDC-32410P-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option III Stability Trip Function" SUSQUEHANNA

-UNIT 1 TRM / B 3.1-7 EFFECTIVE DATE 3/22/2006 PPL Rev. 2 i I B 3.3.9 OPRM BASE<;TRO l OPRM Instrumentation B 3.3.9 Instrumentation

=The OPRM system configuration governs its operation in accordance with the licensing analysis.

Several configuration parameters are intrinsic to the trip function safety setpoint bases or provide settings for defense-in-depth algorithm features that are not assumed in the basis for the protection system safety analysis (Reference 2, Reference 3).Each of the setting values may be used as the process setpoint or device setting without further adjustment for uncertainties.

Setpoints and Settings Bases TOL(E) Period Tolerance The specified range of values for the period tolerance has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability.

A range of values is provided to allow system tuning to avoid spurious alarms on period confirmations.

Limiting the setpoint adjustment range provides assurance that the Peri6d Based Detection Algorithm will provide sufficient.

confirmations for a growing instability.

Conditioning Filter Cutoff Frequency I I I The specified value for the Conditioning Filter Cutoff Frequency has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability.

Setting minimizes impact on signal amplitude and provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability.

I I Tmin Oshcillation Period LowverTime Limit Tmax Oscillation Period Urger Time Limit The Oscillation Period Time Limit parameters establish the range of detectable oscillation periods of OPRM cell signals for signal oscillations associated with reactor core thermal-hydraulic instability.(continued)

SUSQUEHANNA

-UNIT 1 TRM / B 3.3-17 EFFECTIVE DATE 3/22/2006 OPRM Instrumentation B 2.3.9 PPL Rev. 2 B 3.3.9 OPRM Instrumentation BASEE I__TRO (continued)

LPRMmin This value determines the availability and resulting sensitivity of cells in the reactor core in the event of LPRM channel failures.

The minimum LPRM per cell parameter is an assumption of the OPRM trip setpoint (Sp) basis calculation.

Amplitude and Gr owth Rate Based Algorithm Parameters Si Peak Threshold Setpoint / ABA + GRBA S2 Smax DR3 Valley Threshold Setpoint / ABA + GRBA I T , Amplitude Trip Setpoint / ABA Growth Rate Factor Setpoint ! GRBA These parameters calibrate the Amplitude and Growth Rate Based Algorithm, described in References 2 and 3, which provides an OPRM trip output to the Reactor Protection System. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algorithm.

The algorithm is provided as a defense-in-depth feature in the event of unanticipated power oscillations.

These Amplitude and Growth Rate Based Algorithm Paramelers are considered sufficient to provide backup protection and to avoid spurious trips by maximizirng margin to expected operating conditions and transients.

ACTIONS The required actions assure that the system settings that support the Period Based Algorithm setpoint analysis, and those parameters that define the Amplitude anid Growth Rate Based Algorithm are returned in a timely manner to the values assulmed in the analysis (Reference 2, Reference

3) or that the affected channel is declared inoperable and the applicable Required Action of LCO 3.3.1.1 is then entered, or an alternate method to detect and suppress thermail hydraulic instability oscillations is employed...1L: l l (continued)

SUSQUEHANNA

-UNIT 1 TRM / B 3.3-17a EFFECTIVE DATE 3/22/2006 OPRM Instrumentation B 3.3.9 PPL Rev. 2 B 3.3.9 OPRM Instrumentation', BASE'; i ACTIO.NIS Note 1 has been provided to modify the ACTIONS related to affected OPRM (continued) channels.

Technical Specification Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits will not result in separate entry into the Condition.

Technical Specification Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition.

However, the Required Actions for affected OPRM channels provide appropriate compensatory measures.

As such, a Note has been provided that allows separate Condition entry for each affected OPRM channel.B. 1 Several paraImeter settings are essential for the proper operation of the OPRM period-based trip algorithm.

The permissible values of Period Confirmation' Tolerance, Averaging Filter time constant, Conditioning Filter Cutoff Frequency, and minimum operable LPRM per cell parameters are limited by the setpoint basis calculations and system transient response analysis.

The Minimum and Maximum Oscillation Period settings limit the algorithm wirndow to the cell signal resonances that can be associated with unstable thefmal-hydraulic conditions.

Because the 'ability of the OPRM channel to perform its safety function is affected by tlhese parameter settings, the affected OPRM channel must be considered inoperable when these conditions are not met.Operability is evaluated for each inoperable channel and Required Actions taken in accordance with LCO 3.3.1.1.0. 1 The design objective for the Amplitude and G owth Rate Based Algorithms is to provide automatic action to limit the size of these unanticipated oscillations, thereby preventing fuel cladding damage. Several parameter settings define the function of the Amplitude and Growth Rate Based Algorithm.

The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algorithm,!

which is provided as a defense-in-depth feature in the event of unanticipated oscillations.

I I I: (continued)

SUSQUEHANNA

-UNIT 1 TRM / B 3.3-17b UREFFECTIVE DATE 3/22/2006 OPRM Instrumentation PPL Rea. 2 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS C.1 (continued)

Because the ability of the OPRM Channel to perform its safety function is not affected by these parameter settings, the affected OPRM Channel need not be immediately considered inoperable when these conditions are not met.These parameters are to be maintained for conformance with the licensing requirement of a defense-in-depth feature in addition to the licensed OPRM trip function.

This is corrected by returning the parameters to conformance within 120 days of identification.

Since the Amplitude and Growth Rate Based parameters affect only the defense-in-depth response within each channel, failure to maintain the proper parameters in the channel affects only the operability of that channel.D.l1 This Action is to be taken if the Period Based Detection Algorithm trip function is not available in accordance with LCO 3.3.1.1, and initiation of a, alternate method to Detect and Suppress thermal hydraulic instability oscillations is required by the referenced LCO Required Actions. The applicable Conditions are entered as required.E.1 As directed from Required Action D.1, this Action provides preemptive protection through Power/Flow Map operating restrictions When operating in Region I of the Power / Flow map specified in the COLR, or when operating in IRegion 11 of the Power / Flow map specified in the COLR with less than 50% of the required LPRM upscale alarms OPERAB'..E, the potential for thernal-hydraulic oscillations is greatly increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations.

Therefore, the reactor mode switch must be immediately placed in the shutdown position.

Action is taken immediately todplace the plant in a condition where any potential for thermal-hydraulic instabilities will be terminated.

l!Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciationialarm.

Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors.(continued)

SUSQUEHANNA

-UNIT 1.TRM / B 3.3-17c EFFECTIVE DATE 3/22/2006 OPRM Instrumentation B 3.3.9 PPL Rev. 2 B 3.3.9 OPRM Instrumentation

BASES I I ___I ACTIONS (continued)

F. 1 As directed fro mn Required Action D.1, this Action provides guidance for Operator action in response to thermal-hydraulic instability oscillations.

When operating in Region II of the Power/Flow map specified in the COLR immediate response is necessary when there are indications that thermal hydraulic oscillations are occurring as defined in the CONDITION.

LPRM upscale' alarms are required to detect reactor core thermal-hydraulic instability events. The criteria for determining which LPRM upscale alarms are required is based on assignment of these alarms to designated core zones. These core zones consist of the level A, B, and C alarms in 4 or 5 adjacent LPRM strings. The number and location of LPRM strings in each zone assure that with 50% or mare of the associated LPRM upscale alarms OPERABLE sufficient monitoring capability is available to detect core wide and regional oscillations.

Operating plant instability data is used to determine the specific LPRM strings assigned to each zone.Al, `Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible'observance of'the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/alarm.

Identification of individual LPRM Upscale is possible by observance of the'various Operator display assemblies and control panel monitors.G.1 As directed from Required Action D.1, this Action provides guidance for Operator action' in response to operation in conditions that may lead to thermal-hydraulic instability oscillations.

When operating in Region II of the Power/Flow map specified in the COLF, the potential for 1 thermal-hydraulic oscillations is increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations.

Therefore, action must be initiated immediately to restore operation outside of Regions II of the Power/Flow map specified in the bOLR. i Thii can be accomplished by either decreasing THERMAL POWER with control rod insertion or increasing core flow by increasing recirculationipump speed. The starting of a recirculation pump will not be used as a means to 6xit the excluded Regions because the starting of a recirculation pum'p with tihe plant operating above the 80% rod line is prohibited due to potential instability problems.(continued)

SUSQU EHAN NA -UNIT 1 I I: ITRM / B 3.3-17d; l i I 1. 11 EFFECTIVE DATE 3/22/2006 OPRM Instrumentation PPL Rev. 2 B 3.3.9 B 3.3.9 OPRM Instrumentation BASESl ACTIONS H. 1 (continued)

I The LPRMs provide a capability to monitor power in selected locations of the reactor core. The LPRM Upscale Alarm Instrumentation provides information concerning local power oscillations.

Condition F requires a reactor scram when operating in Region II of the Power/Flow map specified in the COLR with indications that thermal hydraulic oscillations are occurring.

The number and location of LPRM strings in each zone assures that with 50% or more of the associated LPRM upscale alarms OPERABLE any power oscillations which could occur would be detected and proper actions can be taken.Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/alarm.

Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors.A sign is posted in the Control Room to ensure that plant operators are aware of the system condition if a plant transient results in the plant entering into the instability region.TRS TRS 3.3.9.1 Required only when the OPRM trip function is not available, this TRS ensures the combination of core flow and THERMAL POWER are within required limits to prevent uncontrolled thermal hydraulic oscillations by ensuring the recirculation loops are within the limits established by the Power/ Flow map specified in the COLR. At low recirculation flows and high reactor power, the reactor exhibits increased susceptibilityto thermal-hydraulic instability.

The Power / Flow map specified in the COLR is based on guidance provided in References 7, 8, and 9 which' also provided the guidance on how to respond to operation in these conditions.

The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency is based on operating experience'and the operator's inherent knowledge of the current reactor status, including significant changes in THERMAL' POWER and core flow to ensure the requirements are constantly met.TRS 3.3.9.2 This TRS is to be performed at the specified Frequency to ensure that the LPRM Upscale Alarm Instrumentation are maintained OPERABLE.(continued)

SUSQUEHANNA

-UNIT 1 TRM / B 3.3-17e SEFFECTIVE DATE 3/22/2006 R PPL RE- v. 2 OPRM Instrumentation B 3.3.9 B 3.3.9 OPRM Instrumentation BASES=TRS TRS 3.3.9.3 (contirnued)

The parameter setpoint verification surveillance compares the desired settings and setpoints to the values contained in the processor memory.This surveillance is required to assure that the settings are maintained in accordance with the setpoint analysis.

The frequency is based on the OPRM CALIBRATION frequency per SR 3.3.1.1.18.

REFERENCES

1. NEDO-31960-A, BWROG Long Term Solution Licensing Methodology

2. NEDO-31960-A, Supp. 1, BWROG Long Term Solution Licensing Methodology

3. NEDO-32465-A, BWROG Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications

4. Deleted.5. Generic Letter 94-02, Long-Term Solutions and Upgrade Of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in Boiling Water Reactors 6. LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation

7. GE Service Information Letter No. 380, "BWR Core Thermal Hydraulic Stability," Revision 1, February 10, 1984.8. Letter, L. A. England to M. J. Virgilio, 'BWR Owner's Group Guidelines for Stability Interim Corrective Action," June 6, 1994.9. EMF-CC-074(P)(A), Volume 4, Revision 0, 'BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2," November 1999.10. NEDC-3241 OP-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option III Stability Trip Function" I I I SUSQUEHANNA

-UNIT 1 TRM / B3.3-17f EFFECTIVE DATE 3/22/2006 Shutdown Margin Test RPS Instrumentation B 3.10.2 PPL. Rev. 1 B 3.10.2 Shutdown Margin Test RPS Instrumentation BASES TRC)Prior to demonstration of adequate shutdown margin, neutron monitoring system trips provide a level of defense-in-depth to assure that the reactor remains will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition:

The intent of the requirement is to ensure that the protection system coincident trip logics are removed if a rod has been withdrawn and shutdown margin has not been demonstrated.

With the shorting links removed, the trip function is in the non-coincident mode, such that all trip channels go to both trip systems, effectively producing one trip system. For the NUMAC PRNMS, only the 2-Out-of-4 Voter logic provides trip inputs to RPS.Therefore, when the shorting links are removed, the Minimum OPERABLE Channels Per Trip system is four 2-Out-of-4 Voters and 6 IRM Neutron Flux High or Inop. Two SRM channels are required, one in, and one near, the affected core quadrant undergoing shutdown margin testing.I ACTIONS The Actions are defined to ensure that defense-in-depth protection against inadvertent core criticality is provided during initial startup with a new full core; CORE ALTERATIONS (i.e. -control rod withdrawals) are prohibited, and withdrawn rods are inserted, to assure a subcritical core. The Conditions cover inoperable instrument channels and failure to remove the shorting links. These Actions are consistent with the non-coincident logic.(continued).I,: I I I SUSQUEHANNA

-UNIT 1 TRIVI / B 3.10-2 EFFECTIVE DATE 3/22/2006 Shutdown Margin Test RPS Instrumentation BE 3.10.2 PPL. Rev. 1 B 3.10.2 Shutdown Margin Test RPS Instrumentation BASES (continued)

TRS)The TRSs listed provide for the proper channel surveillances for the SRM trip that assure the trip function operates per design when needed. TRS 3.10.2.1 provides assurance that the SRM monitoring function that drives the RPS function remains OPERABLE.

The IRM and APRM surveillances are properly defined for MODE 5 OPERABILITY in LCO 3.3.1.1.TRS 3.10.2.2 assures that the shorting links are removed prior to and during MODE 5 Shutdown Margin demonstrations per LCO 3.1.1.TRS 3.10.2.4 assures that the resulting RPS trip logic performs as designed with the shorting links removed.REFERENCES

1. LCO 3.1.1 2. LCO 3.3.1.1 I 1 i II i I I. i Ii I I;:i;I I i 1 !I 1i I I1:i i ii I i1 SWESQUEHANNA

-UNIT 1 TRM / B 3.10-3 EFFECTIVE DATE 3/222006

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ML061010648: Difference between revisions

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