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Technical Requirements Manual
	ML15329A165
Person / Time
Site:	Susquehanna
Issue date:	11/11/2015
From:	Gerlach R; Susquehanna
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML15329A165 (96)
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Nov. 11, 2015 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2015-45662 U_$SER INFORMATION:

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

TO: GERLACH*ROSEY N 11/11/2015 LOCATION: USNTRC 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 INFORM~ATION ON THIS TRANSMITTAL. WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE O UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS.

ATTENTION: "REPLACE' directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.

TRŽ42 - TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 11/03/2015 ADD MANUAL TABLE OF CONTENTS DATE: 11/10/2015 CATEGORY: DOCUMENTS TYPE: TRI42 At(

Nov. 11, 2015 Page 2 of 2 ID: TEXT 3.2.1 ADD: REV: 12 REMOVE: REV:11 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.3.7 REMOVE: REV:l1 ADD: REV: 2 CATEGORY: DOCUMENTS TYPE: TR142 ID: TEXT B3.3.7 ADD: REV: 2 REMOVE: REV:l1 CATEGORY: DOCUMENTS TYPE: TRX2 ID: TEXT LOES ADD: REV: 87 REMOVE: REV: 86 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 FOR ASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.

SSES MANUAL Manual Name: TRM2 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents Issue Date: 1.1/10/2 015 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 87 11/10/2 015 Title: LIST OF EF:FECTIVE SECTIONS TEXT TOC 24 04/28/2015 Title: TABLE OF CONTENTS TEXT 1.1 0 11/19/2002 Title: USE AND APPLICATION DEFINITIONS TEXT 2.1 1 02/04/2005 Title: PLANT PROGRAMS AND SETPOINTS PLANT PROGRAMS TEXT 2.2 11 01/31/2014 Title: PLANT PROGRAMS AND) SETPOINTS INSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 6 03/05/2015 Title: APPLICABILITY TECHNICAL REQUIREMENT FOR OPERATION (TR0) APPLICABILITY TEXT 3i.1. 1 11/09/2007 Title: REACTIVITY CONTROL SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT 3.1.2 0 11/19/2002 Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1.3 4 05/14/2009

.....Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION ........... ....

TEXT 3.1.4 0 11/19/2002 Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT 3.2.1 12 11/10/2015 Title: CORE OPERATING LIMITS REPORT (COLR)

Report Date: 11/11/15 Page !1 of of 15 15 Report Date: 11/11/15

SSES MANUAL Manual Name: TRM2 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.3.1 0 11/19/2002 Title: INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 3 03/31/2011 Title: INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 2 11/09/2007 Title: INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 8 10/14/2015 Title: INSTRUMENTATION TRN POST-ACCIDENT MONITORING INSTRUMENTATION LDCN 4553 TEXT 3.3.5 0 11/19/2002 Title: INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK TEXT 3.3.6 4 04/29/2014 Title: INSTRUMENTATION TEN ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 2 11/10/2015 Title: INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 1 10/22/2003 Title: INSTRUMENTATION TRNMRPS INSTRUMENTATION TEXT 3.3.9 3 05/14/2009 Title: INSTRUMENTATION LPRM UPSCALE ALARM INSTRUMENTATION TEXT 3.3.10 1 12/14/2004 Title: INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1 10/22/2003 Title: INSTRUMENTATION MVP ISOLATION INSTRUMENTATION TEXT 3.3.12 1 Title: WATER MONITORING INSTRUMENTATION 03/05/2015 0

Report Date: 11/11/15 Page2 Page 2 of of 15.

15 Report Date: 11/11/15

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. Manual Title:

i Manual Name:*

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TRM2 TEXT 3.4.1 1 04/26/2006 Title: REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY TEXT 3.4.2 1 04/16/2009 Title: REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY TEXT 3.4.3 1 11/09/2007 Title: REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM (RCS)

TEXT 3.4.4 2 05/14/2009 Title: REACTOR COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT 3.4.5 1 04/26/2006 Title: REACTOR COOLANT SYSTEM REACTOR VESSEL MATERIALS TEXT 3.4.6 1 04/25/2013 Title: REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT 3.5.1 1 02/04/2005 Title: ECCS AND RCIC ADS MANUAL INHIBIT TEXT 3.5.2 1 11/09/2007 Title: ECCS AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0 11/19/2002 Title: ECCE AND RCIC LONG TERM NITROGEN SUPPLY TO ADS TEXT 3.6.1 0 11 /19/2 002 Ti*t1]-CONTA-I-NHNrT*ENTTNG-OR-PURG-ING TEXT 3.6.2 2 04/29/2014 Title: SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0 11/19/2002 Title: CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION Report Date: 11/11/15 Page -3 Page 3 of of 15 15 Report Date: 11/11/15

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}Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.6.4 0 11/19/2002 Title: CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 0 11/19/2002 Title:* PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN TEXT 3.7.2 0 11/19/2002 Title : PLANT SYSTEMS ULTIMATE HEAT SINK (URS) AND GROUND WATER LEVEL TEXT 3.7.3.1 2 04/16/2009 Title : PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 3 04/16/2009 Title:* PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS TEXT 3.7.3.3 3 04/16/2009 Title : PLANT SYSTEMS C02 SYSTEMS TEXT 3.7.3.4 2 04/16/2009 Title: PLANT SYSTEMS HALON SYSTEMS TEXT 3.7.3.5 2 04/16/2009 Title : PLANT SYSTEMS FIRE HOSE STATIONS TEXT 3.7.3.6 2 04/16/2009 Title : PLANT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT 3.7.3.7 1 04/26/2006 Title:. PLANT SYSTEMS FIRE RATED ASSEMBLIES TEXT 3.7.3.8 11 09/27/2012 Title : PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION TEXT 3.7.4 1 04/26/2006 Title : PLANT SYSTEMS SOLID RADWASTE SYSTEM Report Date: 11/11/15 Page 4 Page ~f of 15 15 Report Date: 11/11/15

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Ma3nual Name : TRM2 I anual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7.5.1 1 03/05/2015 Title: PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT 3.7.5.2 0 11/19/2002 Title: PLANT SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXWURE TEXT 3.7.5.3 1 04/26/2006 Title: PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 3 06/04/2012 Title: PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 2 09/05/2008 Title: PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION

~MONITORING INSTRUMENTATION TEXT 3.7.8 9 03/05/2015 Title: PLANT SYSTEMS SNUBBERS TEXT 3.7.9 1 08/28/2006 Title: PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 2 04/29/2014 Title: PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)

TEXT 3.7.11 1 10/02/2009 Title: PLANT SYSTEMS

-TEXT--3-.8 1 3 05120L20 12.

Title: ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT 3.8.2.1 2 11/09/2007 Title: ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTIC DN -

CONTINUOUS TEXT 3.8.2.2 2 12/14/2004

-- ~ Title: ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTICDN -

AUTOMATIC Report Date: 11/11/15 Page 55 of of 15 15 Report Date: 11/11/15

SSES MANUAL Manual Name: TRM2 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.8.3 2 06/20/2012 Title: ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT 3.8.4 1 02/04/2005 Title: ELECTRICAL POWER 24 VDC ELECTRICAL SUBSYSTEM TEXT 3.8.5 1 11/14/2013 Title: ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION TEXT 3.8.6 2 12/14/2006 Title: ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8.7 2 10/22/2009 Title: BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT 3.9.1 0 11/19/2002 Title: REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0 11/19/2002 Title: REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 0 11/19/2002 Title: REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 1 04/26/2006 Title: MISCELLANEOUS SEALED SOURCE CONTAMINATION TEXT 3.10.2 1 04/09/2007 Title: MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 2 06/15/2010 Title: MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) 0 TEXT 3.11.1.1 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION Report Date: 11/11/15 Page 6 Page of of 15 i__55 Report Date: 11/11/15

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-*i Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.11.1.2 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE TEXT 3.11.1.3 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM TEXT 3.11.1.4 2 10/09/2012 Title: RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.1.5 3 03/05/2015 Title: RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT 3.11.2.1 3 04/26/2006 Title: RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3.11.2.2 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES TEXT 3.11.2.3 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM TEXT 3.11.2.4 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3.11.2.5 4 07/03/2013 Title: RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3.11.2.6 5 03/05/2015 Title: RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.3 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS TOTAL DOSE TEXT 3.11.4.1 4 03/05/2015 Title: RADIOACTIVE EFFLUENTS MONITORING PROGRAM Report Date: 11/11/15 Page 72 of of 15 15 Report Date: 11/11/15

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' Manual Title: TECHNICAL REQUIREMENTS MANU]TAL UNIT 2 0 TEXT 3.11.4.2 2 04/26/2006 Title: RADIOACTIVE EFFLUENTS LAND USE CENSUS TEXT 3.11.4.3 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS INTERLABORATORY COMPARISON PROGRAM TEXT 3.12.1 0 11/19/2002 Title: LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT 3.12.2 4 04/17/2008 Title: LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0 11/19/2002 Title: LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENTS TEXT 4.1 0 09/27/2003 Title: ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 0 09/27/2003 Title: ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION TEXT 4.3 0 09/27/2003 Title: ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION TEXT 4.4 1 12/18/2008 Title: ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT 4.5 0 09/27/2003 Title: ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS TEXT 4.6 0 09/27/2003 Title: ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM

TEXT 4.7 0 09/27/2003 Title: ADMINISTRATIVE CONTROLS TRAINING Report Date: 11/11/15 Page 8 Page of 15 Report Date: 11/11/15

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. Manual Title: TECHNICAL REQUIREMENTS Manual Name: TRN2 MANUAL UNIT 2 TEXT B3.0 6 03/05/2015 Title: APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.1.1 2 04/29/2014 Title: REACTIVITY CONTROL SYSTEM BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.1.2 0 11/19/2002 Title: REACTIVITY CONTROL SYSTEM BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT B3.1.3 3 04/10/2007 Title: REACTIVITY CONTROL SYSTEM BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT B3.1.4 0 11/19/2002 Title: REACTIVITY CONTROL SYSTEM BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION

& AND CHECK VALVE TEXT B3.2.1 0 11/19/2002 Title: CORE OPERATING L,IMITS BASES CORE OPERATING LIMITS REPORT (COLR)

TEXT B3.3.1 1 01/31/2014 Title: INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 2 03/31/2011 Title: INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 2 11/09/2007 Title: INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION

EXTB3*-~- 5 1 01_4/_2015 Title: INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT B3.3.5 2 11/09/2007 Title: INSTRUMENTATION BASES THIS PAGE INTENTIONALLY LEFT BLANK TEXT B3.3.6 5 01/31/2014 Title: INSTRUMENTATION BASES TRN ISOLATION ACTUATION INSTRUMENTATION Report Date: 11/11/15 Page 9 Page ~ of of 15 15 Report Date: 11/11/15

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}**-* Manual Title: TECHINICAL REQUIREMENTS MANUAL UNIT 2 TEXT B33.3.7 2 11/10/2015 Title: INSTRUMENTATION BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 133.3.8 1 10/22/2003 Title: INSTRUMENTATION BASES TRM RPS INSTRUMENTATION TEXT B3.3.9 3 05/14/2009 Title: INSTRUMENTATION BASES LPRM UPSCALE ALARM INSTRUMENTATION TEXT B33.3.10 3 02/22/2012 Title: INSTRUMENTATION BASES REACTOR RECIRCULATION PUMP MG SET STOPS TEXT B3.3.11 110/22/2003 Title: INSTRUMENTATION BASES MV.P ISOLATION INSTRUMENTATION TEXT B33.3.12 0 04/16/2009 0 Title: WATER MONITORING INSTRUMENTATION TEXT 133o4.1 0 11/19/2002 Title: REACTOR COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY TEXT B3.4.2 1 04/16/2009 Title: REACTOR COOLANT SYSTEM BASES STRUCTURAL INTEGRITY TEXT B33.4.3 1 11/09/2007 Title: REACTOR COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR TEXT 133.4.4 0 11/19/2002 Title: REACTOR COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT 83.4.5 0 11/19/2002 Title: REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS TEXT 133°4.6 1 04/25/2013 Title: REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION Report Date: 11/11/15 10 Page iO0 Page of of 15 155 Report Date: 11/11/15

SManual Name: TRMq2 Manual Title: TECENICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.5.1 o 11/19/2002 Title: ECCS AND RC3IC BASES ADS MANUAL INHIBIT TEXT B3.5.2 1 11/09/2007 Titles ECCS AND RC]IC BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT B3.5.3 1 11/09/2007 Title: ECCS AND RC]IC BASES LONG TERM NITROGEN SUPPLY TO ADS TEXT B3.6.1 o 11/19/2002 Title: CONTAINMENT BASES VENTING OR PURGING TEXT B3.6.2 0 11/19/2002 Title: CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWNELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 1 04/19/2007 Title: CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION TEXT B3.6.4 1 12/14/2004 Title: CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT B3.7.1 0 11/19/2002 Title: PLANT SYSTEM'ES BASES EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN)

TEXT B3.7.2 0 11/19/2002 Title: PLANT SYSTEM. [S BASES ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL TEXTB3,L73-*I Title: PLANT SYSTEMiS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT B3.7.3.2 2 04/26/2006 Title: PLANT SYSTEM IS BASES SPRAY AND SPRINKLER SYSTEMS TEXT B3.7.3.3 0 11/19/2002 Title: PLANT SYSTEM, S BASES C02 SYSTEMS Report Date: 11/11/15 Page iiil Page of of 15 15 Report Date: 11/11/15

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.i:*Manual Title: TECHNICAL REQUIREMENTS MANUOAL UNIT 2 TEXT B337.3.4 2 04/29/2014 Title:* PLANT SYSTEMS BASES HALON SYSTEMS TEXT B337.3.5 1 04/26/2006 Title: PLANT SYSTEMS BASES FIRE HOSE STATIONS TEXT B337.3.6 1 04/26/2006 Title: PLANT SYSTEMS BASES YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT B337.3.7 0 11/19/2002 Title: PLANT SYSTEMS BASES FIRE FATED ASSEMBLIES TEXT B337.3.8 3 09/27/2012 Title : PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION TEXT B337.4 0 11/19/2002 Title: PLANT SYSTEMS BASES SOLID RADWASTE SYSTEM TEXT B337.5.1 0 11/19/2002 Title:- PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT 33.7.5.2 0 11/19/2002 Title: PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT B3.7.5.3 0 11/19/2002 Title : PLANT SYSTEMS BASES LIQUID HOLDUP TANKS TEXT 33.7.6 4 06/04/2013 Title: PLANT SYSTEMS BASES ESSW PUMPHOUSE VENTILATION 2 01/31/2008 TEXT B3.7.7 Title: PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT 33.7.8 4 01/31/2 014 Title: PLANT SYSTEMS BASES SNUBBERS Report Date: 11/11/15 12 Page i__22 Page of of 15 15 Report Date: 11/11/15

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Manual Name TRM2 TECHNICAL REQUIREM4ENTS MANUAL UNIT 2 TEXT B3.7.9 2 12/08/2011 Title: PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1 12/14/2004 Titles PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.7.11 2 04/14/2010 Title: STRUCTURAL INTEGRITY TEXT B3.8.1 2 03/10/2010 Title: ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT B3.8.2.1 0 11/19/2002 Title: ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

CONTINUOUS TEXT B3.8.2.2 1 09/17/2004 Title: ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

AUTOMATIC TEXT B3.8.3 0 11/19/2002 Title: ELECTRICAL POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT B3.8.4 0 11/19/2002 Title: ELECTRICAL POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT B3.8.5 1 11/14/2013 Title: ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B37__6 Title: ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 2 06/04/2013 Title: BATTERY MAINTENANCE AND MONITORING PROGRAM STEXT B3.9.1 0 11/19/2002 Title: REFUELING OPERATIONS BASES DECAY TIME Report Date: 11/11/15 Page ~

Page 13 of of 15..

i_55 Report Date: 11/11/15

SSES MANUAL Manual Name: TRIM2 anzual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2 M::

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 TEXT B3.10.1 0 11/19 /2 002 Title: MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 1 04/10/2007 Title: MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT B3 10.3 0 11/19/2002 Title: MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

TEXT B3 .11.1. 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3.11.1.2 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3.11.1.3 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3.11.1.4 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.1.5 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.11.2.1 1 12/14/2004 Title: RADIOACTIVE EFFLUENTS BASES DOSE RATE TEXT B3.11.2.2 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES Report Date: 11/11/15 Page 14 Page i_44 of of 15 15 Report Date: 11/11/15

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_!Manual Title: TECHNICAL REQUIREMENTS Name : TRM2 MANUAL UNIT 2 TEXT B3.l1.2.3 0 11/19/2 002 Title: RADIOACTIVE EFFLUENTS BASES DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE S FORM TEXT B3.11.2.4 0 11/19 /2 002 Title: RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.11.2.5 5 07/03/2013 Title: RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3.11.2.6 1 01/27 /2 004 Title: RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.3 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES TOTAL DOSE TEXT B3.11.4.1 5 03/05/2015 Title: RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3.11.4.2 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES LAND USE CENSUS TEXT B3.l1.4.3 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAM TEXT B3.12.1 1 10/ 04/20 07 Title: LOADS CONTROL PROGRAM BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT B3.12.2 1 12/03/2010 Title: LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS TEXT B3.12.3 0 11/19/2002 Title: LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Report Date: 11/11/15 Page 15 Page 15 of of 15 1-5 Report Date: 11/11/15

SUSQUEHANNA STEAM ELECTRIC STATION Rev. 87 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date TOC TABLE OF CONTENTS 04/23/2015 1.0 USE AND APPLICATION Page TRM / 1.0-1 08/31/1998 Page TRM / 1.0-2 10/04/2002 Page TRM / 1.0-3 08/31/1998 2.0 PLANT PROGRAMS Page 2.0-1 08/31/11998 Pages TRM / 2.0-2 and TRM 2.0-3 01/28/2005 Page TRM / 2.0-4 }06/25/2002 Page TRM / 2.0-5 01/21/2014 Page TRM / 2.0-6 04/15/2009 Page TRM / 2.0-7 05/15/2008 Pages TRM / 2.0-8 and TRM / 2.0-9 01/07/2011 Page TRM / 2.0-10 02/02/2010 Page TRM / 2.0-11 11/15/2004 Page TRM / 2.0-12 04/15/2009 Pages TRM / 2.0-13 and TRM /2..1 11/15/2004 Page TRM I 2.0-15 @ 11/15/2005 APPLICABILITY

3.0 Pages TRM/I3.0-1 and TR .0-2 02/19/2015 Page TRM / 3.0-3 ; 03/15/2002 Page TRM I 3.0-4 02/19/2015 REACTIVITY CONROL SSTEMS 3.1 10/31/2007 Page TM/.- 08/31/1998 PagesTRTRM//3..-7 03/27/2007 04/15/2009 PageTRM I 3.1-8 03/27/2007 iPage TR /3.1-9 and TRM / 3.1-9a 02/18/1999 Page TRM / 3.1-10 02/18/1999 COEOPERATING LIMITS REPORT 3.2 Page TRM / 3.2-1 08/31/1998 Pages TRM / 3.2-2 through TRM / 3.2-63 11/04/2015 iNSTRUMENTATiON ..........

3.3 Pages TRM / 3.3-1 through TRM / 3.3-3 07/16/1999 Pages TRM / 3.3-4 and TRM / 3.3-5 10/31/2007 Page TRM I 3.3-6 03/10/2011 Page TRM 3.3-7 10/31/2007 Page 3.3-8 08/31/1998 SUSQUEHANNA - UNIT 2 TRM / LOES-1 2 RM UNT LOS-1EFFECTIVE SUSQEHANADATE 11/04/2015

SUSQUEHANNA STEAM ELECTRIC STATION Rev. 87

LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

L:Section Title Effective Date Page TRM 10/07/2015 Page TRM /I 3.3-9 3.3-9a 06/30/2010 Page TRM / 3.3-10 10/31/2007 Page TRM / 3.3-11 10/07/2015 Page TRM I 3.3-11a 10/07/2015 Page TRM / 3.3-12 03/30/2001 Page TRM / 3.3-13 01/07/2011 Page TRM / 3.3-14 12/14/1998 Page TRM / 3.3-15 04/11/2014 Page TRM 1 3.3-16 01/07/2011 Page TRM / 3.3-17 11104/2015 Page TRM / 3.3-17a Page TRM / 3.3-18 Pages TRM / 3.3-19 and TRM / 3.3-20 11/04/2015 10/31/2007 10/22/2003 I

Page TRM / 3.3-21 04/15/2009 Page TRM I 3.3-21a 11/15/2004 Pages TRM /3.3-21 b through TRM I 3.3-21d 03/27/2007 Page TRM / 3.3-22 12/03/2004 Pages TRM I 3.3-23 and TRM / 3.3-24 05/16/2003 Page TRM I 3.3-25 10/22/2003 Page TRM / 3.3-26 02/19/2015 Page TRM / 3.3-27 04/07/2009 REACTOR COOLANT SYSTEM 3.4 03/31/2006 Page TRM / 3.4-1 Pages 3.4-2 through 3.4-5 10/23/1998 pages TRM / 3.4-6 through TRM / 3.4-8 04/01/2009 Page 3.4-9 08/31/1998 Page 3.4-10 10/31/2007 Page 3.4-11 08/31/1998 Page TRM / 3.4-12 04/17/2009 Page TRM / 3.4-13 03/31/2006 Page TRM / 3.4-14 04/25/2013 3.5 EMERGENCY CORE COOLING AND RCIC Page TRM / 3.5-1 01/28/2005 Pages 3.5-2 and 3.5-3 08/31/1998 Page TRM I 3.5-4 10/31/2007 Pages 3.5-5 through 3.5-7 08/31/1998 3.6 CONTAINMENT_______

Pages 3.6d-1n3_6-2 -08/3t1't998-Pages TRM / 3.6-3 and TRM I 3.6-3a 04/16/2014 Page 3.6-4 08/31/1998 Page TRM I 3.6-5 01/07/2002 Page 3.6-6 08/31/1998 Pages TRM / 3.6-7 through TRM / 3.6-9 12/31/2002 SUSQUEHANNA - UNIT 2 TRM / LOES-2 TM/LE- EFFECTIVE DATE 11/04/2015

SUSQUEHANNA STEAM ELECTRIC STATION Rev, 87

~LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Titl__ee Effective Date 3.7 PLANT SYSTEMS Pages TRM / 3.7-1 and TRM / 3.7-2 07/29/1999 Page 3.7-3 08/31/1998 Page TRM / 3.7-4 03/3 1/2 006 Page TRM / 3.7-5 04/07/2009 Pages TRM / 3.7-6 through TRM / 3.7-8 08/02/1999 Pages TRM /3.7-9 and TRM / 3.7-10 04/07/2009 Page TRM / 3.7-11 01/21/2000 Page TRM / 3.7-12 08/02/1999 Page TRM / 3.7-13 04/07/2009 Page TRM / 3.7-14 08/09/2005 Pages TRM / 3.7-15 and TRM / 3.7-16 08/02/1999 Page TRM / 3.7-17 04/07/2009 Page TRM / 3.7-18 08/02/1999 Page TRM / 3.7-19 04/07/2009 Pages TRM / 3.7-20 through TRM / 3.7-22 08/02/1 999 Page TRM / 3.7-23 04/07/2009 Page TRM / 3.7-24 03/31/2006 Page TRM / 3.7-25 08/02/1999 Page TRM / 3.7-26 09/25/2012 Page TRM / 3.7-27 11/24/2011 Pages TRM / 3.7-28 through TRM / 3.7-32a 09/25/2012 Page TRM I 3.7-33 09/25/2012 Page TRM / 3,7-34 03/31/2006 Pages TRM / 3.7-35 and TRM / 3.7-36 02/01/1999 Page TRM / 3.7-37 02/19/2015 Page TRM / 3,7-38 08/31/1998 Page TRM I 3.7-39 03/31/2006 Page TRM / 3.7-40 05/24/2012 Pages TRM / 3.7-40a through TRM I 3.7-40c 05/24/2012 Page TRM I 3.7-41 09/04/2008 Page TRM / 3.7-42 08/31/1998 Pages TRM / 3.7-43 02/19/2015 Pages TRM / 3.7-44 and TRM / 3.7-45 10/05/2006 Page TRM / 3.7-46 06/07/2007 Page TRM / 3.7-47 09/05/2012 Page TRM / 3.7-48 06/07/2007 Page TRM I 3.7-49 03/09/2001 Page TRM I 3.7-50 08/16/2006 Page TRM / 3.7-51 12/03/2004 Page TRM / 3.7-52 04/15/2003 Page TRM I 3.7-53 07/29/1999 Page TRM / 3.7-54 04/01/2009 Page TRM / 3.7-55 09/25/2009 Page TRM / 3.7-56 04/01/2009 TRM / LOES-3 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA SUSQUEHANNA-UNIT2 - UNIT 2 TRM / LOES-3 EFFECTIVE DATE 11/04/2015

=*rt t**:*'-*:*'* *.*..&*_*-*... _* -*

SUSQUEHANNA STEAM ELECTRIC STATION Rev. 87 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQU IREMENTS MANUAL)

Section Title Effective Date 3.8 ELECTRICAL POWER Page TRM 1 3.8-1 04/02/2002 Page TRM / 3.8-2 01/28/2005 Pages TRM / 3.8-3 and TRM / 3,8-4 06/12/2012 Pages TRM / 3.8-5 and TRM / 3.8-6 04/02/2002 Pages TRM / 3.8-7 through TRM / 3.8-10 10/31/2007 Page TRM 1 3.8-11 09/03/2004 Page TRM / 3.8-12 12/03/2004 Page TRM / 3.8-13 06/12/2012 Page TRM / 3.8-14 08/31/1998 Page TRM / 3,8-15 01/28/2005 Pages TRM / 3.8-16 and TRM / 3.8-17 04/02/2002 Page 3.8-18 02/01/1999 Page TRM / 3.8-19 04/02/2002 Page TRM / 3.8-20 02/01/1999 Pages TRM / 3.8-21 and TRM / 3.8-22 06/06/1 999 Page TRM / 3.8-23 11/07/2013 Page TRM / 3.8-24 11/30/2011 Page TRM / 3.8-25 06/11/2012

Pages TRM /3.8-25a and TRM /3.8-25b 11/30/2011 Page TRM / 3.8-26 05/28/2009 Page TRM / 3.8-27 11/29/2006 Page TRM / 3.8-28 05/28/2009 Page TRM / 3.8-29 10/20/2009 3.9 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 08/31/1998 3.10 MISCELLANEOUS Page TRM / 3.10-1 03/31/2006 Pages 3.10-2 through 3.10-4 08/30/1,998 Pages TRM / 3.10-5 and TRM / 3.10-6 03/27/2 007 Page TRM I 3.10-7 06/10/2010 3.11i RADIOACTIVE EFFLUENTS Page TRM / 3.11-1 03/31/2006 Pages 3.11-2 through 3.11-3 08/31/1998 Page TRM / 3.11-4 03/31/2006 Page 3.11-5 08/31/1998 Page TRM / 3.11-6 03/31/2006 Pages 3.11-7 and R .1--8~ -08!3-14998-Pages TRM / 3.11-9 and TRM / 3.11-10 10/09/2012 Pages TRM /3.11-11 and TRM /3.11-12 08/31/1998 SUSQUEHANNA-UNIT2 TRM / LOES-4 SUSQEHANA UNT 2 RM LOS-4EFFECTIVE DATE 11/04/2015

I IAŽ~~-- I SUSQUEHANNA STEAM ELECTRIC STATION Rev. 87 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Titl._e Effective Date Page TRM / 3.11-13 02/19/2015 Page TRM / 3.11-14 12/03/20O04 Pages 3.11-15 and 3.11-16 09/01/1998 Page TRM /3.11-17 03/31/2006 Page 3.11-18 08/31/1998 Page TRM / 3.1 1-19 08/15/2005 Pages TRM / 3.11-20 and TRM / 3.11-21 03/31/2006 Page TRM / 3.11-22 04/02/2002 Page TRM / 3.11-23 11/14/2006 Page TRM / 3.11-24 06/18/2013 Page TRM / 3.11-25 04/12/2007 Pages TRM / 3.11-26 and TRM / 3.11-27 01/21/2004 Page TRM / 3.11-28 09/08/2009 Page TRM / 3.11-29 12/03/2004 Pages TRM 3.11-30 and TRM / 3.11-31 01/21/2004 Page TRM / 3.11-32 02/19/2015 Page TRM / 3.11-33 03/31/2006 Page 3.11-34 08/31/1998 Page TRM / 3.11-35 03/31/2006 Pages TRM / 3.11-36 through TRM / 3.11-39 11/30/2005 Page TRM / 3.11-40' 02/19/2015 Pages TRM / 3.11-41 through TRM / 3.11-44 08/31/1998 Page TRM / 3.11-45 03/31/2006 Page 3.11-46 08/31/1998 Page TRM / 3.11-47 03/31/2006 3.12 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-3 02/05/1 999 Page TRM / 3.12-4 03/14/2008 Page TRM / 3.12-5 02/05/1999 4.0 ADMINISTRATIVE CONTROLS Pages TRM / 4.0-1 through TRM / 4.0-3 08/31/1998 Page TRM / 4.0-4 12/11/2008 Pages TRM / 4.0-5 th~rough TRM / 4.0-8 08/31/1998 TRM / LOES-5 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA - UNIT-UNIT 2 2 TRM / LOES-5 EFFECTIVE DATE 11/04/2015

____ I I I SUSQUEHANNA STEAM ELECTRIC STATION Rev. 87 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date B 3.0 APPLICABILITY BASES Pages TRM I B 3.0-1 through TRM / B 3.0-3 08/31/1998 Page TRM / B 3.0-4 02/19/2015 Pages TRM / B 3.0-4a and TRM / B 3.0-4b 02/19/2015 Page TRM / B 3.0-5 02/19/2015 Pages TRM / B 3.0-6 and TRM / B 3.0-7 06/12/2012 Pages TRM / B 3.0-8 through TRM / B 3.0-10 08/31/1 998 Pages TRM / B 3.0-11 and TRM / B 3.0-12 03/15/2002 Pages TRM / B 3.0-13 through TRM / B 3.0-15 02/19/2015 B 3.1 REACTIVITY CONTROL SYSTEMS BASES Page TRM / B 3.1-1 07/13/1999 Page TRM / B 3.1-2 04/16/2014 Page TRM / B 3.1-3 10/31/2007 Page B 3.1-4 08/31/1998 Pages TRM / B 3.1-5 through TRM t B 3.1-7 03/27/2007 Page TRM / B 3.1-8 02/18/1999 B 3.2 CORE OPERATING LIMITS BASES Page B 3.2-1 08/31/1998 Q** SPage TRM / B 3.3-1

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B 3.3 INSTRUMENTATION BASES Page TRM / B 3.3-2 01/21/2014 03/10/2011 Page TRM / B-3.3-2a 10/31/2007 Pages TRM / B 3.3-3 and TRM / B 3.3-3a 10/31/2007 Page TRM / B 3.3-4 06/30/2010 Pages TRM / B 3.3-5 through TRM / B 3.3-7 10/07/2015 Page TRM / B 3.3-8 06/30/2010 Page TRM / B 3.3-9 10/31/2007 Page TRM / B 3.3-10 01/07/2011 Page TRM / B 3.3-11 02/21/2014 Pages TRM / B 3.3-12 and TRM / B 3.3-13 01/07/2011 Page TRM / B 3.3-14 06/25/2002 Page TRM / B 3.3-14a 11/04/2015 Page TRM / B 3.3-14b 11/04/2015 Page TRM / B 3.3-14c 11/04/2015 Pages TRM / B 3.3-15 through TRM / B 3.3-17 10/22/2003 Pages TRM / B 3.3-18 and TRM / B 3.3-19 03/27/2007 Pages TRM / B 3.3-1 9a and TRM / B 3.3-1 9b 03/27/2007 Page TRM / B 3.3-19c 04/17/2009 TRM I LOES-6 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA SUSQUEHANNA-UNIT2

- UNIT 2 TRM / LOES-6 EFFECTIVE DATE 11/04/2015

-~ ~:2-*xs~4~ I I ~ ~ -

SUSQUEHANNA STEAM ELECTRIC STATION Rev. 87 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date Pages TRM / B 3.3-19d and TRM I B 3.3-19e 03/27/2 007 Page TRM I B 3.3-20 02/16/2012 Page TRM / B 3.3-21 08/03/2010 Page TRM I B 3.3-22 10/22/2003 Page TRM I B 3.3-23 05/16/2003 Pages TRM / B 3.3-24 and TRM / B 3.3-25 04/07/2009 B 3.4 REACTOR COOLANT SYSTEM BASES Page TRM / B 3.4-1 08/31/1 998 Pages TRM / B 3.4-2 and TRM / B3.4-3 04/01/2009 Pages TRM / B 3.4-4 and TRM / B 3.4-4a 10/31/2007 Page TRM I B 3.4-5 10/1 5/1 999 Page B 3.4-6 08/31/1998 Page TRM I B 3.4-7 04/25/2013 B 3.5 ECCS AND ROIC BASES Pages B 3.5-1 and B 3.5-2 08/31/1998 Pages TRM / B 3.5-3 and TRM / B 3.5-3a 10/31/2007 Page B 3.5-4 08/31/1998 Page TRM / B 3.5-5 10/31/2007 B 3.6 CONTAINMENT BASES Page TRM / B 3.6-1 07/26/2001 Page TRM / B 3.6-2 02/01/1999 Page B 3.6-3 08/31/1998 Page TRM / B 3.6-4 03/29/2007 Page TRM / B 3.6-5 04/04/2007 Page TRM / B 3.6-6 12/03/2004 Pages TRM / B 3.6-7 through TRM / B 3.6-11 12/31/2002 B 3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 08/31/1998 Page TRM / B 3.7-3 06/10/2010 Page TRM / B 3.7-3a 12/27/2007 Page TRM I B 3.7-4 03/31/2006 Page TRM / B 3.7-5 08/02/1999 Pages TRM / B 3.7-6 and TRM / B 3.7-6a 03/31/2006 Pages TRM / B 3.7-7 and TRM I B 3.7-7a 08/02/1999 Page TRM I B 3.7-8 08/02/1999 Page TRM I B 3.7-9 04/11/2014

-Page-T-RM-I*-B&71 10 -0810-2/-999-TRM / LOES-7 EFFECTIVE DATE 11/04/2015 UNIT 2 SUSQUEHANNA - UNIT

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2 TRM / LOES-7 EFFECTIVE DATE 11/04/2015

SUSQUEHANNA STEAM ELECTRIC STATION Rev. 87 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date Pages TRM / B 3.7-10Oa through TRM / B 3.7-11 a 03/31/2006 Pages TRM / B 3.7-12 and TRM / B 3.7-13 08/02/1999 Pages TRM / B 3,7-14 through TRM / B 3.7-14b 09/25/2012 Pages TRM / B 3.7-15 and TRM / B 3.7-16 02/01/1999 Pages B 3.7-17 through B 3.7-20 08/31/1998 Page TRM / B 3.7-21 05/29/2013 Pages TRM / B 3.7-21a through TRM I B 3.7-21d 05/24/2012 Pages TRM / B 3.7-21e through TRM / B 3.7-21g O5/2 9/2013 Pages TRM / B 3.7-22 and TRM / B 3.7-23 01/30/2008 Page TRM / B 3.7-24 10/05/2006 Page TRM / B 3.7-25 01/2.1/2014 Pages TRM / B 3.7-26 through TRM / B 3.7-29 10/05/2006 Page TRM / B 3.7-30 06/07/2007 Page TRM / B 3.7-30a 1 0/05/2006 Page TRM / B 3.7-30b 01/21/2014 Page TRM / B 3.7-31 11/30/2011 Page TRM / B 3.7-32 03/09/2001 Page TRM / B 3.7-33 04/15/2003 Page TRM / B 3.7-34 12/03/2004 Page TRM / B 3.7-35 07/05/2000 Pages TRM / B 3.7-36 and TRM / B 3.7-37 04/0 1/2 009 Page TRM / B 3.7-38 09/25/2009 Page TRM / B 3.7-39 04/01/2009 Page TRM / B 3.7-40 04/08/2010 B 3.8 ELECTRICAL POWER BASES Page TRM / B 3.8-1 04/02/2002 Pages TRM / B 3.8-2 01/28/2005 Page TRM / B 3.8-2a 03/0 1/20 10 Pages TRM / B 3.8-3 and TRM / B 3.8-3a 04/02/2002 Page TRM / B 3.8-4 09/03/2004 Page TRM / B 3.8-4a 04/02/2002 Page TRM / B 3.8-5 08/31/1998 Pages TRM / B 3.8-6 through TRM / B 3.8-15 04/02/2002 Page TRM / B 3.8-16 11/07/2013 Page TRM / B 3.8-17 11/30/2011 Page TRM / B 3.8-17a 06/11/2012.

Page TRM / B 3.8-17b 11/30/2011 Pages TRM / B 3.8-18 through TRM / B 3.8-20 05/29/2013 Pages TRM / B 3.8-21 and TRM / B 3.8-22. 05/28/2009 Pa~geJTRMJB3*8_-23 05/29/2013 Page TRM / B 3.8-24 05/28/2009 TRM / LOES-8 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA SUSQUEHANNA-UNIT2

- UNIT 2 TRM / LOES-8 EFFECTIVE DATE 11/04/2015

-Ž-~--~ I - ~ LŽ~.z~&&~i SUSQUEHANNA STEAM ELECTRIC STATION Rev. 87 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date B.3.9 REFUELING OPERATIONS BASES Pages B 3.9-1 and B 3.9-2 08/31/1 998 Pages B 3.9-3 through B 3.9-7 10/23/1998 B 3.10 MISCELLANEOUS BASES 08/3111998 Page B 3.10-1 Pages TRM / B3.10-2 and TRM /B 3.10-3 03/27/2007 Pages TRM / B 3.10-4 and TRM / B 3.10-5 08/23/1999 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 08/31/1998 Page TRM / B 3.11-10 02/01/1999 Pages TRM / B 3.11-11 and TRM / B 3.11-11a 04/07/2000 Pages TRM / B 3.11-12 and TRM / B 3.11-13 02/01/1999 Page TRM / B 3.11-14 12/03/2004 Page TRM / B 3.11-15 02/01/1999 Pages B 3.11-16 through B 3.11-19 08/31/1 998 Pages TRM / B 3.11-20 and TRM / B 3.1 1-20a 04/02/2002 Page TRM /B 3.11-21 05/13/2005 Pages TRM / B 3.11-22 and TRM / B 3.11-23 11/14/2006 Pages TRM / B 3.1 1-23a and TRM / B 3.1 1-23b 06/18/2013 Pages TRM / B 3.11-24 and TRM / B 3.11-25 0 1/21/2004 Pages B 3.11-26 through B 3.11-27 08/31/1998 Page TRM / B 3.11-28 11/30/2005 Page TRM / B 3.11-29 02/19/2015 Pages TRM / B 3.11-30 and TRM I B 3.11-31 05/29/2013 Page TRM / B 3.11-32 08/31/1 998 Page TRM / B 3.11-33 06/30/2010 Pages TRM / B 3.11-34 and TRM / B 3.11-35 08/31/1998 Page TRM / B 3.11-36 02/12/1999 B.3.12 LOADS CONTROL PROGRAM BASES Page TRM / B 3.12-1 09/19/2007 Page TRM / B 3.12-2 11/29/2010 Page TRM / B 3.12-3 02/05/1999 TRM2 text LOES.doc 11/412 015 SUSQUEHANNA-UNIT2 TRM / LOES-9 UNT SUSQEHANA 2 RM LOS-9EFFECTIVE DATE 11/04/2015

Core Operating Limits Report (COLR) aRev. 12 3.2.1t 3.2 Core Operating Limits Report (CQLR) 3.2.1 Core Operating Limits Report (COLR)

TRO 3.2.1 The'Core Operating Limits specified in the attached COLR shall be met-APPLICABILITY: Specified in the referenced Technical Specifications.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core Operating Limits not A.1 Perform action(s) Specified in referenced met. described in referehced Technical Technical Specification. Specifications.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY S.-----------NOTE--..-..-.. -... -..-.......... N/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications.

SUSQUEHANNA-UNIT2 TRM ! 3.2-1 TM I .2-1EFFECTIVE SUSQEHANA-UNT2DATE 08/3 111998

Rev. 12 PL-N F-I15-002 Rev. 1 Page 1 of 62 Susquehanna SES Unit 2 Cycle 18 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering September 2015 SUSQUEHANNA UNIT 2 TRM/3.2-2 2 RM/32-2EFFECTIVE UNT SUSQEHANA DATE 11/04/2015

Rev. 12 PL-NF-15-002 Rev. 1 Page 2 of 62 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev. fAffected No. Sections Description/Purpose of Revision 0 ALL issuance of this COLR is in support of Unit 2 Cycle i 8 operation.

I ALL New COLR for the inclusion of operating limits regarding a Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closure event. This revision also changes the Turbine Bypass Inoperable MCPRf limits that were updated in the licensing analysis to remove conservatisms from the initial analysis that are not required per the NRC approved methodology.

FORM NFP-QA-008-2, Rev. I SUSQUEHANNA UNIT 2 TRM/3.2-3 TRMI.2-3EFFECTIVE DATE 11/04/2015

Rev. 12 PL-NF-15-002 Rev. 1 Page 3 of 62 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 18 CORE OPERATING LIMITS REPORT Table of Contents

1.0 INTRODUCTION

............................................................................. 4 2.0 DEFINITIONS................................................................................ 5 3.0 SHUTDOWN MARGIN ...................................................................... 6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ................. 7 5.0 MINIMUM CRITICAL POW ER RATIO (MCPR)............................................ 9 6.0 LINEAR HEAT GENERATION RATE (LHGR)............................................. 27 7.0 ROD BLOCK MONITOR ('RBM) SETPOINTS AND OPERABILITY REQUIREMENTS............................................................................ 38 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION .............................. 40 9.0 POWER / FLOW MAP ...................................................................... 58 10.0 OPRM SETPOINTS ......................................................................... 60 1-t0--REEERENCE &.................. . . . ... ............................. _1 SUSQUEHANNA UNIT2 TRM/3.2-4 SUSQEHANA U~T 2 RM/32-4EFFECTIVE DATE 11104/2015

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Rev. 12 PL-NF-1 5-002 Rev. 1 Page 4 of 62

1.0 INTRODUCTION

2 Cycle I8 is This CORE OPERATING LIMITS REPORT for ,Susquehanna Unit 2, Technical of Susquehanna Unit prepared in accordance with the requirements core shutdown Specification 5.6.5. As required by Technical Specifications 5.6.5, setpoints, and OPRM setpoints presented herein margin, the core operating limits, RBM such that all were developed using NRC-approved methods and are established applicable limits of the plant safety analysis are met.

El TRM/3.2-5 DATE 11/04/2015 SUSQEHANA UNT 2 RM/32-5EFFECTIVE SUSQUEHANNA UNIT 2

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SRev. 12 PL-NF-1 5-002

Rev.Page 5 of 62 2.0 DEFINITIONS Terms used in this COLR but not defined in Section 1.0 of the Technical Specifications or Section 1.1 of the Technical Requirements Manual are provided below.

2.1 The AVERAGE PLANAR EXPOSURE at a specified height shall be equal to the total energy produced per unit length at the specified height divided by the total initial weight of uranium per unit length at that height.

2.2 The PELLET EXPOSURE shall be equal to the total energy produced per unit length of fuel rod at the specified height divided by the total initial weight of uranium per unit length of that rod at that height.

2.3 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGIR limit for the applicable fuel bundle type.

2.4 LHGRFACf is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFA~r multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbm/hr.

S2.5 LHGRFACp is a multiplier applied to the LHGR limit when operating at less than i' RATED THERMAL POWER. The LHGRFACp multiplier protects against both

,* fuel centerline melting and cladding strain during anticipated system transients initiated from partial power conditions.

2.6 MFLCPR is the ratio of the applicable MCPR operating limit for the applicable fuel bundle type divded by the MCPR calculated by the core monitoring system for each fuel bundle.

2.7 MAPRAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLGHR limit for the applicable fuel bundle type.

2.8 OPRM is the Oscillation Power Range Monitor. The Oscillation Power Range Monitor (OPRM) will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR safety limit is not violated.

2.9 Np is the OPRM setpoint for the number of consecutive confirmations of oscillation half-cycles that will be considered evidence of a stability related power oscillation.

2.10 Sp is the OPRM trip setpoint for the peak to average OPRM signal.

2.11I Fp is the core flow, in Mlbm / hr, below which the OPRM RPS trip is activated.

SUSQUEHANNA UNIT 2 TRM/3.2-6 SUSQEHANA NIT2 TM/32-6EFFECTIVE DATE 11/04/201 5

..... %*1j ta'S*t a am *ai... i...........t . 4t* I Ifl&.L SRev. 12 PL-NF-15-002

_ Rev. 1 Page 6 of 62 3,0 SHUTDOWN MARGIN 3.1 Technical Specification Reference Technical Specification 3.1.1 3.2 Description The SHUTDOWN MARGIN shall be equal to or greater than:

a) 0.38% Ak/k with the highest worth rod analytically determined O__R b) 0.28% Ak/k with the highest worth rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and poison bumup, Beginning of Cycle (BOQ) SHUTDOWN MARGIN (8DM) tests must also account for changes in core reactivity during the cycle. Therefore, the 5SDM measured at BOO must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, "R"'. The adder, "R", is the difference between the calculated value of maximum core reactivity (that is, O minimum SUM) during the operating cycle and the calculated BOO core

-

-. reactivity. Ifthe value of "R"~ is zero (that is, BOO is the most reactive point in the

-=-v cycle) no correction to the BOO measured value is required.

The SHUTDOWN MARGIN limits provided in 3.2a and 3.2b are applicable in MODES 1, 2, 3, 4, and 5. This includes core shuffling.

SUSQUEHANNA UNIT 2 TRM/3.2-7 NIT TRI3 2-7EFFECTIVE SUSQEHANA DATE i1110412015

SRev. 12 PL-NF.-15-002 Rev. I

-

Page 7 of 62 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 TechicalSpecification Reference Technical Specification 3.2.1 4.2 Description The APLHGRs for ATRlUM-TM-I0 fuel shall not exceed the limit shown in Figure 4.2-1.

The APLHGR limits in Figure 4.2-1 are valid for Main Turbine Bypass Operable and inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable in Two Loop operation. The APLi-GR limits for Single Loop operation are provided in Section 8.0.

SUSQUEHANNA UNIT 2 TRMI3.2-8 SUSQEHANA UNT2 RMI32-8EFFECTIVE DATE 11104/2015

CO SSES UNIT 2 CYCLE 18 GC 16.0 Co c ll l 1 1 1 1 1 1 1! __ l__ ___ l_ ___ lll C I l l I . . . IIl .l l l l iID~rl llkllCT '4*I,

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:Dr-

-o 0

AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS a' AVERAGE PLANAR EXPOSURE -TWO LOOP OPERATION '*

ATRIUMTM-t0 FUEL FIGURE 4.2-1

tLd~, L fl-~ - - ~amI bhhama~a..'....e .&t%.1 flflSS -. .. %..adI I

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Q *Rev. 12 Rev.

PL-NF-1I 5-002

!/*:*Page 9 of 62 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) 5.1 Technical Specif~ication Reference Technical Specification 3.2.2, 3.3.4.1[, 3.7.6, and 3.7.8 5.2 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 5.3 Description The MCPR limit is specified as a function of core power, core flow, average scram insertion time per Section 5.3 and plant equipment operability status. The MCPR limits for all fuel types (ARUTM-j0) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.

a) Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOG to EOCC Figure 5.2-2: Power-Dependent MGPR value determined from BOG to EQG I x:b) Main Turbine Bypass Inoperable Figure 5.2-3: Flow-Dependent MCPR value determined from BOG to EOC Figure 5.2-4: Power-Dependent MGPR value determined from DCC to OCC c) EOC-RPT Inoperable Figure 5.2-5: Flow-Dependent MCPR value determined from BOG to EGG Figure 5.2-6: Power-Dependent MGPR value determined from BOG to OCC di) Backup Pressure Regulator Inoperable Figure 5.2-7: Flow-Dependent MCPR value determined from BOG to EGG Figure 5.2-8: Power Dependent MGPR value determined from BOG to EGG e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TGV) Closed Figure 5.2-9Y*low-eped*iMGPR v--iue-d~tarmirred-fnroBOG(*toEOC Figure 5.2-1O:Power-Dependent MCPR value determined from DOC to EGG SUSQUEHANNA UNIT 2 TRM/3.2-10 SUSQEHANA UIT TRM3.21DATE 0EFFECTIVE 11/04/2015

hAv.ikaa..t.a..wrAfla I OhM. - sa.aa.. ¶* I

. flhS-fliS.4taal lss,&amn.L..XitiJ 1SudaSSksfr.w~I flamE#tl Rev. 12 PL-NF-15-002 Rev. I Page 10 of 62 The MCPR limits in Figures 5.2-1 through 5.2-10 are valid for Two Loop operation.

The MCPR limits for Single Loop operation are provided in Section 8.0.

5.4 Averaoqe Scram Time Fraction If the average measured scram times are greater than the Realistic Scram times listedl in Table 5.3-1 then the MCPR operating limits corresponding to the Maximum Allowable Average Scram Insertion Time must be implemented.

Determining MCPR operating limits based on interpolation betweentime scram insertion times is not permitted. The evaluation of scram insertion data, as it relates to the attached table should be performed per Reactor Engineering procedures.

A TRM/3.2-11 UiT SUSQEHANA IEFFECTIVE 2TRM3.2.1DATE 11/04(20"15 SUSQUEHANNA UNIT 2

SRev. 12 PL-N F-i15-002 RvPage 11 of 62 Main Turbine Bypass I EOC-RPT I

97. Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 TRM/3.2-12 2EFFECTIVE UIT TRM3.21 SUSQEHANA DATE 11/04/2015

CI) SSES UNIT 2 CYCLE 18 C 2.2 0) m 2.1 I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM z I INSERTION TIME z

C 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z

1.9 1.8 a.

-I 1.7 0 CD0 63 1.6 1.5 Il 1.4 m

1.3 m

0

-4 1.2 40 50 60 Total Core70 Flow (MLB!HR)80 90 100 110

[I MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW "ow "

MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (SOC TO EOC)

FIGURE 5.2-1 0"0 oh. -- 0

9 9!

C, SSES UNIT 2 CYCLE 18 C,, 3.6 C

m 3,4, 3.2 A: MAXIMUM ALLOWABLE AVERAGE SCRAM ]NSERTION TIME z B: REALISTIC AVERAGE SCRAM INSERTION TIME

'.

3.0 C: CORE POWER*<26% AND CORE FLOW <_50 MLBMIHR 2.8 E

2.6 SAFETY ANALYSES PER SR 3.7.6.1 ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE AND 3.7.6.2 0..

--4 0-CjO 2.4 3

O~ CD C., 2.2 2.0 1.8

-n1 1.6

-H m 1.4 1.2 m

30 40 50 60 70 50 910 100 Core Power (% RATED)

"o "o S. MCPR OPERATING LIMIT VERSUS CORE POWER 0l MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC)

FIGURE 5.2-2 ."J 0 hO 0-*I.

[-:2~~- *.~-~-'-~-=~-J ---- ~--~-'s.s'-'.-

____

I -

Rev. 12 PL-NF-1 5-002 Rev. 1 Page 14 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-15 SUSQEHANA UIT TRM3 .-15EFFECTIVE DATE 11/04/2016

SSES UNIT 2 CYCLE 18 (O3 C 2.2 CD 0

2.1 C.URVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME SLEGEN'D' z CURVE B: REALISTIC AVERAGE SCRAMl INSERTION TIME z

C 2.0 z SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE 1.9 1.8 I.-

1.7

-I 0

CD REFERENCEPERE: 3T.S.1OR337..6 1.6

__US____ _I_ __ERINN __L__

1.5 m"-1 1.4

-n m

1.3 m

1.2 H 30 401 50 60 70 (MLBIHR) 80 90 100 110 Total Care Flow rn "-U "0 CDz MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE oa TWO LOOP OPERATION (BOO TO EOC) 0CD <

FIGURE 5.2-3

SSES UNIT 2 CYCLE 18 03 C

C z

=1 N

E 0.J

-4 0-C)) C) m

-n

-I m

50 60 (% RATED) 70 Core Power

"-

C0 MCPR OPERATING LIMIT VERSUS CORE POWER r-I MAiN TURBINE BYPASS INOPERABLE 0Q

-ii TWO LOOP OPERATION (BOC to EOC)

FIGURE 5.2-4 S0

M~U9kdCOM~wWuI I~'q~C~tithAa.tt~aaZZ2ua*-% I hSfleA alma ..... .1 I.q.t .4.t...aaJ ..qA...SLI h.a.a.Jbflaa

.,fj.&I IqcLh.wa .A.CaiU~I Rev. 12 PL-N F-I15-002 Rev. I Page 17" of 62 EOC-RPT Inoperable SUSQUEHANNA UNIT 2TR/2I8 TRM/3.2-18 EFFECTIVE DATE 1110412015

S SSES UNIT 2 CYCLE t8 C')

C C,, 2.2 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM I INSERTION TIME z 2.0 iCURVE B: REALISTIC AVERAGE SCRAM~I INSERTION TIME

'Z 1.9 CO E*

1.8 1.7 0

13.

1')

1.6 1.5 1.4 m

1.3 1.2

,-.

70 ¶10 m Total Core Flow (MLB/HR) 0:

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW N) EOC-RPT INOPERABLE 0l TWO LOOP OPERATION (BOO TO EOC). -* -- nIX FIGURE 5.2-5

0 SSES UNIT 2 CYCLE 18 C 3.6 3.4

z:

z 3.2 C

z :3.0

.)

2.8 2.6

.- I H~ 2.4 a-o CD 2.2 N)

N) 2,0 1.8

"-n

-n' 1.6

--t 1.4 m

1.2 -

m 2C 30 40 50 60 Core Power (% RATED) 70} 80 90 100 0

MCPR OPERATING LIMIT VERSUS CORE POWER 0 EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC to EOC) *~ -n*C FIGURIE 5.2-6 0")" 0

Rev. 12 PL-NF-1 5-002 Rev. 1 Page 20 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT2 TRM/3.2*I SUSQEHANA NIT TR/3.-21EFFECTIVE DATE 11/04/2015

'9:ll SSES UNIT 2 CYCLE 18 ct:~

C 2.2 cn 0

C ni 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME z

z 2.0 C

z N, 1.9 E= 1,8

-I

=o 1.7

()3 <D N,

M 1.6 N,

1.5 1"11 "11 1.4

-- I 1.3 U

-'H 1.2

,,,,i 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) 0 -u3 "

4I=.

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 0 BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC) o 0*

FIGURE 5.2-7 < 0-

J ....

@

03, SSES UNIT 2 CYCLE 18 C

3.6 03 C

3,4

-m I

z 3.2 z

3.0 2.8 E

2.6

'J 0=

2.4 C.3 0

..D 2.2 2.0 1.8 m

1.6

.- I m

1.4

-I m 1.2 20 30 40 50 60 70 80 90 100

-1 Core Power (% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER ,-n BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC to EOC)

FIGURE 5,2-8 -h3 .O PO --

Rev. 12 PL-NF-1 5-002 Rev. I Page 23 of 62 One TSV or TCV Closed SUSQUEHANNA UNIT2 TRM/3.2-24 SUSQEHANA DATE 11104/2015 NIT TR/3.-24EFFECTIVE

SO SSES UNIT 2 CYCLE 18 CO C

2.2 Cr)

C LEGEND 2.1 ______ -CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM z INSERTION TIME z

C 2.0 -CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z

1.*g

-I E 1.8 Cl 0

C, 1.7 0.

0 CD a- ie C-, "3 1.5 1.4 "1"1

--I REFERENC: T.S. 3.2.2 and TRM 3.3.7] ____ ____ ________

1.3 I _____ _______ I ______ ______ _______ ______ ______ _____

'i-i 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)

-I '13 "c 0 I-MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED*

CO3

TWO LOOP OPERATION (BOC TO EOC)

FIGURE 5.2-9 Operation with one TSV or TCV closed is only supported at power levels < 75% rated power.

SSES UNIT 2 CYCLE 18 C,

C 3.6 Co 0

3.4 C

rn z 3.2 z

C 3.0 2.8

~2.6 w 2.4 C?

(D

2.2 N)

O) 2,0 1.8

-rri m 1.8 0

1.4 m

-*1 t.2 m 80 20 30 40 50 60 70 Core Power (% RATED) 0 MCPR OPERATING LIMIT VERSUS CORE POWER CD '

ONE TSV OR TCV CLOSED TWO LOOP OPERATION (BOC TO EOC)

FIGURE 5.2-10 o.

Rev. 12 PL-N F-I 5-002 Rev. I Page 26 of 62 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent PJCPR Operating Limits Control Rod Average Scram Time to Position (seconds)

Position 45 0.470 0.520 39 0.630 0.860 26 1.500 t1.910 5 2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 2 TRM/3.2-27 NIT TR/3.-27EFFECTIVE SUSQEHANA DATE 11t/04/2015

Rev. 12 PL-NF-1 5-002 Rev. 1 Page 27 of 62 6.0 LINEAR HEAT GENERATIQN RATE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 6.2 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 6.3 Description The maximum LHGR for ATRlUMTM-I0 fuel shall not exceed the LHGR limit determined from Figure 6.2-1. The LHGR limit in Figure 6.2-1 is valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable.

To protect against both fuel centerline melting and cladding strain during anticipated system transients initiated from reduced power and flow conditions, power and flow dependent LHGR limit multipliers are provided in the following figures:

a) Main Turbine Bypass Operable Figure 6.2-2: Flow-Dependent LHGR Limit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multiplier b) Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Uimit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier c) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCy) Closed Figure 6.2-6: Flow-Dependent LHGR Limit Multiplier Figure 8.2-7: Power-Dependent LHGR Limit Multiplier The LHGR limits and LHGR limit multipliers in Figures 6.2-2 and 6.2-3 are applicable to EOC-RPT Operable and Inoperable and Backup Pressure Regulator Operable and Inoperable.

The LGHR limits and L.HGR limit multipliers in Figures 6.2-1 through 6.2-7 are valid for both Two Loop and Single Loop operation.

SUSQUEHANNA UNIT 2 TRMI3.2-28 SUSQEHANA NIT TRI3.-28EFFECTIVE DATE 11/04/2015

SSES UNIT 2 CYCLE 18 C

16.0

'BiI , !i iB B I I I B B ! B 1i1I1 !1!1 I1 C

.

B IB.. B..

i B B B I BI I BI B B l 14.0

-B+BB B -- I *B"B - - *B-BB1 - -

P B -i, - B5 B- ii u 1ll--+ - - - * - i - B - I- - - B- - - - - Mf*i

,I

-UEINDETERM]INGFDLR E B ' B ,i B , . . . I I I I /IB, B B

. B.' B B I I B ,

Cu 12.0 I IBB B B E BB 11 1 BIBB. "t-- B ....

u.2_ ,I i I 1 ! B i I Ii i i i B IB I I , if C.-! 10.0

,1 i1 i 11

'i:l B l l

B B

I un Ii il,I I CD 5

a,-

8.0

...

I

.1-I, . . Y.. 1 I i w- r

,B u t i

- III B'

II B B r I'- *I B

10

,.. &' , I I Ii II i&i-i i I I ' B1 40 71 BIB B BI IB B B B B

Jl I t. I

.... . . . . . . 4..,~..

B B B B B B F m

m 6.0 I BKI III

. . . .. B.. B B B I II m 'I a is l I I1 I u I liI u B..BB. . t t *..

4.0 m

I, 10000 20000 30000 40000 50000 60000 70000 80000 Pellet Epoure(MWDJMTU)

"o -T a, r LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE "1D ATRIUMTM-10 FUEL

-CD FIGURE 6.2-1

. * . .... *4,1J. .. .. . ,....... rel,,* ,%_, . I , ' .....*T.*........ .... . * . . ... *;* .. . ..... *%*.1....,I.

r L. . . .. . . ..... *,*lI.,.k* " .* .

1 Kanna 4'.-..- ca-i ia... ~ .~ . '.*. ... -

StflSL IIU~.*MSIBrL~.I baigdab444.taSLI L&~EtanI.t~w..-th4 Rev. 12 PL-NF-It5-Q02 Rev. I Page 29 of 62 Main Turbine Bypass Operable TRM/3,2-30 SUSQEH.ANA DATE 11/04/2015 NIT TR/3 .-30EFFECTIVE SUSQUEHANNA UNIT 2

C' SSES UNIT 2 CYCLE 18

.10 C I , _ _ _ _

I_ _ _ _IiI I

1.00

a108, 1.001 z I I t t a _ _

z

, B U , , I B i z 0.90 I ,I , I a

= 0.80 I I I iii

-r*-P

- - I-- -- - I- - --. . -B--- - - - I - - -- --- I -- -I. . i . .. - -- ... ---. . - - -. .

B B B B I B l I B

-J 1 i BI I Ii IlB B

'~0.70 I"~ i~I , B I , , , I ,

I B ,I BI I I

, ,-,

CD "oa I-, BI i i a i i I

B i I a Bi I +/-

I I B

4i B

'B i. SAET I ANLYE ASUM TA OU BYASVLE BI B B B B B m "--B', B B B B S DI E E MNN D R

-n i i I I I I USE m

0.40 B. . . . I , LI I I I ,IIB, ,B m

BI B B B Bi I Bl B B B B i B B B B B 0.30 m 40 70 30 100 50 60 90 110 Total Core Flow (MLBIhr) 0 FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS OPERABLE ATRIUMrM-10 FUEL FIGURE 6.2-2 o"*. 0

0 C--

SSES UNIT 2 CYCLE 18 1.10 CO LEGEND 0r 1.0

-- 4 CURVE A: BASE CURVE 1 .00 i CURVE B: CORE POWER < 26% AND CORE FLOW < 50 MLBM/HR 1rlr1*, t .00 0.90 I I I ' a tiA! *

. .. . . C -*

.- t 0.80 I I. ... "-1 -.

i. ..

I.

.. . . .. ..- . . . . ... . . .

CA

~1 0.70 I , I -i~-'---i-I Ii I CI C; C. m , , L I---* ... PERABEN PER TSR 3.2.63, AN.4,ad 3.7.6.

0 I I I l I __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

0.60

_--I-

--i - - -- i-..... --......--

. ...

i ,

.. . -- ,-

- F-iR- NC----T.S..3.3....1 nd37 I I I I I I I 1*-

_ _ _ _ _ _ _ _ _ _

I I I m I I I iI I I I I I I I 2 j I USDIDEEM IN FLR 0.50 m E II 126. 0.45 I II I I "11

°. *---_..m.*..*_.*j .... *_*...* .... *..--__* .... ; .... *-.*--. ....

"rn 0.40 7.41

'V 7I

~T~42 1 2 I 2I I I 0 I I I2 l I I I I I I 2 I 2 I I I l II I I I I I I I 2 I I I l I I a I I I I i m

0.30 I I 2 I 2 2 I I I I I l II t 30 40 60 (% RATED) 70 80 90 100 Core Power POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS OPERABLE 0" AT*iUM*U-10 FUEL FIGURE 6.2-3 O)" 0

SRev. 12 PL-NF-t 5-002 Rev. 1

. Page 32 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-33 SUSQEHANA NIT TR/3.-33EFFECTIVE DATE 1110412015

SSES UNIT 2 CYCLE 18 1.10 m

I 1.00 z

C z 0.90 0

0.80 N,

CD

=

..1 Ha 0.70 0

0 C<

I, C

0 a.

0 N) 0 0.60 0

U-0.50

-I']

"-n

m. 0.40 m

0.30 40 80 60 Total Core 70 110 icj Flow (MLB/HR) 80 90 100

"-3 -O Q) I-FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE Co" ATRIUMTM-10 FUEL Cl , - p FIGURE 6.2-4

SSES UNIT 2 CYCLE 18

(/o 0 1.10 a).

k 01 a). .<

a,.

'-TI

'-'n I',]

i-1 30 40 50 60 (% RATED) 70 80 90 100 m Core Power "13 -U 0 POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE -n1 I'.

ATRIUMTM-I0 FUEL oCD FIGURE 6.2-5 '-

o')

0 0

Rev. 12 P L-NF-1 5-0 02 O: Rev. 1

" Page 35 of 62 One TSV or TCV Closed SUSQUEHANNA UNIT 2 TM323 TRMt3.2-36 EFFECTIVE DATE 11/04/2015

0ii t

SSES UNIT 2 CYCLE 18 Cd, C 1.10 -iB Cd) a U

II a a

I a

a a

a a

i*tta a a C I -----. I---I-4---I-------- I - e I I I I C

m I i I a a l

aI i

I i

I I

I C a I I

= 1.00 a a a a a a a a a z a a i a a a a ia aa = -, .

z ,I I

,I a , aa,

,

a a

.

a aa a.

a a

.08,..

a a

a I

aa a aIa a

a

... I 4 C

0.90 I aIaIaI a a a i U z

Ia

a I

---I----*-*"-- - - .U"-'.+0- '-l-- -- 1.4..." . .t* ...... 4,. ,,-.4.,-----b..

i a a a a a a a a a a P..

I'0 I* I I I I . . .. aa a a a a I I a a II 0.80 a a

____I a a a a a a aL a

a a

a I I a a a a I 0a I a 2 a aI I a a i i I a 0 I I I I I .aa""" I

-1 S a a a a I a a a a a

-J

-a-' 0.70 a a a a Ia a II I C CD C)

C '-*a--I II 'C C) 0.

C) "3

-'1 C 0.60 a- a VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 a a! a. I . ...

a _ _ _ _ _ _ __i_ _ _ _ _ _

S a _ _ _ _ _ _

ii-a . . ,a

REFERENCE:

T.S. 3.2.3 and TRIW! 3.3.7 0.50 a a I I a L a a p a I a a a a 3 - I a a rn m

1 a a a1 a a a a a a a

, a J a i , , ,,,

ii a a a ' I* SE aIN DETERMINING FDLRX m

0 0.40

-H I I II I aI a a a a I

a I

a a a i I i aIa I I a a a a Ill I a I i a a a a a a a a a a a a I a C a a I I a a I I I a a I a a a a a aII

-H 0.30 m 50 90 100 110 40 60 Total Core 70 Flaw (MLBIHR) 80

~2.

g,T 0

FLOW DEPENDENT LHGR LIMIT MULTIPUIER ONE TSV OR TCV CLOSED*

0 ATRIUMTM-10 FUEL 00,*

(11 FIGURE 6.2-6

Operation with one TSV or TCV closed is only supported at power levels S 75% rated power.

SSES UNIT 2 CYCLE 18 Co 1.10 CO m

-=

1.00 z

C z 0.90 I.i Q.

0.80

=1 I)

"a-0.70 Ho (P

'C

-It Cl.

0.80 0.50

-n 0.40 m

0.30 20 30 40 50 60 70 80 Core Power (% RATED)

-D CD -c,r

,--t POWER DEPENDENT LHGR LIMIT MULTIPLIER OC ONE TSV OR TCV CLOSED ATRIUMTM-I10 FUEL " 00i FIGURE 6.2-7 oI,<

")" C

Rev. 12 PL-NF-15-002 Rev. I Page 38 of 62 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS 7.1 Technical Specification Reference Technical Specification 3.3.2.1 7.2 Description The RBM Allowable Value and Trip Setpoints for; a) Low Power Range Setpoint, b) Intermediate Power Range Setpoint, c) High Power Range Setpoint, d) Low Power Range - Upscale, e) Intermediate Power Range - Upscale, and f) High Power Range - Upscale shall be established as specified in Table 7.2-1. The RBM setpoints are valid toy Two Loop and Single Loop Operation, Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable.

The RBM system design objective is to block erroneous control rod withdrawal initiated by the operator before fuel design limits are violated. If the full withdrawal of any control rod would not violate a fuel design limit, then the RBM system is not required to be operable. Table 7.2-2 provides RBM system operability requirements to ensure that fuel design limits are not violated.

4-SUSQUEHANNA UNIT 2 TRM/3.2-39 SUSQEHANA NIT TRI3.-39EFFECTIVE DATE 11/0412015

SRev. 12 PL-NF-1 5-002

~Rev. "1 f~i ::::Page 39 of 62 Table 7.2-1 REM Setpoints Function

________________

FuctonAllowable Value(1 ) Nominal SetpointTrip Low Power Range Setpoint 28.0 24.9 Intermediate Power Range Setpoint 63.0 61.0 High Power Range Setpoint 83.0 81.0 Low Power Range -Upscale 123.4 "123.0 Intermediate Power Range - Upscale 1 17.4 1 17.0 High Power Range - Upscale 107.6 "107.2 (I) Power setpoint function (Low, Intermediate, and High Power Range Setpoints) determined in percent of RATED THERMAL POWER. Upscale trip setpoint function (Low, Intermediate, and High Power Range - Upscale) determined in percent of reference level.

Table 7.2-2 RBM System Operability Requirements Thermal Power MCPR (2,3)

(% of Rated)

->28and <90 < 1.76

Ž-90 andc<95 <1.47

> 95 < 1.68 t* Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable.

) Applicable to both Two Loop and Single Loop Operation.

SUSQUEHANNA UNIT2 TRMt3.2-40 TM/3.-40EFFECTIVE SUSQEHANAUNT2 DATE 11/04/2015

SRev. 12 PL-NF-1 5-002

-,. Rev. 1

-* Page 40 of 62 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 TeChnical Specification Reference Technical Specification 3.2.1, 3.2,2, 3.2.3, 3.3.4.1, 3.4.1, 3.7.6, and 3.7.8 8.2 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 8.3 Description

APLHGR The APLHGR limit for ATRIUM TM-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1.

The APLHGR limits in Figure 8.2-1 are valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and inoperable in Single Loop operation.

O *:. Minimum Critical Power Ratio Limit

- :=*The MCPR limit is specified as a function of core power, core flow, and plant

': : equipment operability status. The MCPR limits for all fuel types (ATRIUM TM-10) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.

a) Main Turbine Bypass I EOC-RPT / Backup Pressure Regulator Operable Figure 8.2-2: Flow-Dependent MCPR value determined from BOO to EOC Figure 8.2-3: Power-Dependent MOPR value determined from BOC to EOC b) Main Turbine Bypass Inoperable Figure 8.2-4: Flow-Dependent MCPR value determined from BOO to EOC Figure 8.2-5: Power-Dependent MCPR value determined from BOO to EOC c) EOG-RPT Inoperable Figure-8.-2*-6-Ftew-Dependent-MGPR-4value-determined from300iCoJEOC Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC SUSQUEHANNA UNIT 2 TRM/3.2-41 SUSQEHANA NIT TR/3.-41EFFECTIVE DATE 11104/2015

_t * *÷ :*o k*,*.*- h,.i. I -_*,thodv, Ifl *-*uS M -h,*._ad IaI*_':sr s_. a I Lfi ... g b-a- . ..a J... . ..... -..

a.

SRev. 12 PL-NF-1 5-002

-: Rev. I

i~i::Page 41 of 62 d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow-Dependent MCPR value determined from BOG to EQOC Figure 8.2-9; Power-Dependent MCPR value determined from BOC to FOC e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 8.2-10:Flow-Dependent MCPR value determined from BOG to EOC Figure 8.2-11 :Power-Dependent MCPR value determined from BOG to EOC The MCPR limits in Figures 8.2-2 through 8.2-11 are valid only for Single Loop operation.

Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0.

RBM Setpoints and Operability Requirements

..... The RBM setpoints and operability requirements for Single Loop

.:-*;Operation are defined in Section 7.0.

SUSQUEHANNA UNIT 2 TRM/3.2-42 SUSQEHANA UNT 2 RMJS2-42EFFECTIVE DATE 11104/2015

9 CD SSES UNIT 2 CYCLE 18 C

Co 16.0 ,. ,. I,, I

. I . . 1.

I.

.. .. , .. ... I. . ,I I ,I I ,I I I ,I ,I ,t K I . . .' ,

Il lK I lI l lIlt I I I I 1 1 C i l l l l l

lIl I I I I II Kl I 1 1 1 1 1J 1[ 1 I I rn a i

a I I i*

K UI ia ai I

l l l Kl l l ll1I11 1

z 14.0 ....... . .... . I REFERENCE T.S. 3.4.1land 3.2,1 3 C}

i! II I USED[N DETERMINING MAPT ,

l I I 1 U 1 1 I 1 1*

I I SI, , ,, ,, , I , i , I I I I I I I I I , K , , , , , 1 1 , I

]

1

, 11 1 I I 1 1

l. 1

. I 1 I 1

l. 1 l

1

.

l l 1I1

.

l lI 3 . 1 I3 t. 1l K 1 .

l 1 l .

1. l Il a. li . l l l

.. . . . . . . .aI a . . . . . . . . .I Il . . lK

--12.0 E

, , 1 , I , , I I, Kt K! I . . . I I . . . .I I 1 1IL 1 1I1 I1 1 1 1 1 1 K I 1

&iN 10.0 0I0n0n ,Inn1

. 1.1 1 ,l ___nn 0 0% 1

_ _nnl 0.

I I 1

.

I'l I

I,

'

1 1

l 1I

.. ;. . -;. .

, 1 U

l K

N l

1 1 l

. .-

I1I 1

l

1 1

J 1

l H Itt 1 1 I

1 l . . ..*

I I

l I

IF

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1 1K111 1

1 1

1 1I 1 1 1 1 1 11K KI1 I Il IK Ill I

.0

, 1- -a , 7 1 'r ,1I111m1 I l? _l ,I ,] 1 I

1 I I1 t I 1

I iI I1 1

.0 . 1a1

. .

1 1 i 1 i1 11 1 1 I 1 1 1 1 1 1 g 0 I t l 1 1 1

. . . , 1.,L. K . . . . . . . . . , , 1

8.0 1 1 1 1 1 I lil 1 1K1I11 1 1 1 1' 1 1I 1K, 1 1 1 1 1 11 11 1 ll l

-.

J 11 I1 ,I, *I . . .

1 K Il

l i l *ll K l l l , ii l a la *l ai l l Il Il

l1 ' , ' 1 1 i 111 I , , I1 , ,1 ,

rri i i K II I al aI I I I II 1 1 1 1 1t i1 llil 1 1 1 1 I I I I Il l l l

-n[

6.0 . . . . . .

I I I I I I I.*.. . . .

l l l l l

l lKill l ll l l lll II I I1

-H I I II I I I I I I l l II I l*

C 4.0 C .0 1I0000.0 20000.0 80000.0 40000.0 80000.0 60000.0 70000.0 Average Planar Exposure (MWDIMTLJ)

-*

LU-'+ -u" E

0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE - SINGLE LOOP OPERATION (0' ATRIUMTM-t~0 FUEL PC -D I FIGURE 8.2-1

flfl*.:,ai o,Ak. j-: ......... . I, I.. fle .[ *.** ..... -_ a a.......

.-,. . . . . .- ..

1 tu 4 idIU*_*_.

ad-.l-a,_ - ima=*'_<. -.

-..

.1 IfltM*.

.**- A.I.

r*'t-4,_b--

, t.- att',*. _A'*.._-**:

SRev. 12 PL-NF.-1 5-002

.... Rev. I Page 43 of 62 Main Turbine Bypass!/ EOC-RPT /

Q* Backup Pressure Regulator Operable TRM/3.2-44 SUSQEHANAUIT TRM3 DATE 1110412015

.-44EFFECTIVE SUSQUEHANNA UNIT 2

C',

SSES UNIT 2 CYCLE 18 C 3.6 CD C LEGEND m 3.4 -- I .4

= CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM z INSERTION TIME z 3.2 I ~ 1.

CURVE B: REALISTIC AVERAGE SCRAMI INSERTION TIME z

3.0 -" 4. 4 I I I I 2.8 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES

_E ARE OPERABLE PER SR 3.7.6,1 AND 3.7.6.2

,_1 2.6 H0 Oa I-a, 2.4 L USED IN DETERMINING MFLCPR o.

2.2 2.0 rni

-nl 1.8

-n m

REFERENCE:

T.S. 3.4.1 and 3.2.2 "-- t8 1.6 m

1.4 30 401 50 60 70 80 90 100 110 0 Total Core Flow (MALB/HR) 01 MAIN TURBINEMCPR OPERATING BYPASS / EOC-RPTLIMIT VERSUS TOTAL CORE FLOW I BACKUP PRESSURE REGULATOR OPERABLE Co

C c SINGLE LOOP OPERATION (BOC to EOC)

FIGURE 8.2-2 0-" 0

I.

SSES UNIT 2 CYCLE 18 4.6 4.4 I

> 4.2 z

C 4,0 z 3.8 3.6

.4-3.4

..1 3.2 I

.4-.

a, 3.0 C 03 fk~ 2.8 0~

0 2.6 2A4 2.2 "11 2.0 m

1.8 1.6 1.4 m

20 30 4.0 60 60 (% RATED)070 Core Power 80 90 100

-* "-3 MCPR OPERATING LIMIT VERSUS CORE POWER t.,c I 0

MAIN TURBINE BYPASS I EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE OTo 01 SINGLE LOOP OPERATION (BOG to EOC)

FIGURE 8.2-3 -- oCt,

<0*

C)*.- I0

SRev. 12 PL-NF-1 5-002

. Rev. I

" Page 46 of 62 Main Turbine Bypass 0.*.*-.-Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-47 SUSQEHANA DATE 1110412015 NIT TRIS.-47EFFECTIVE

-SSES UNIT 2 CYCLE 18 Co, 4.2 C

4.0 m

-I z 3.8 z

t- 3.6 z

--I 3.4 3.2 4--

S 3.0

--i I.

2.8 0

I.3 2.6 0O 2.4 2.2 2.0 m

1.8 rll 1.6 1.4 3C 40 50 60 Total Core 70 Flow (MLB/HR) 80 90 100 110

-o =0,

-1 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW (0 MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)

FIGURE 8,2-4 <3 C:

03 SSES UNIT 2 CYCLE 18 CITt 4.2 23 _______CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM Z" 4. INSERTION TIME z 4.

-> - CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME JC 26.3.8 CURVE C: CORE POWER_~ 26% AND CORE FLOW s; 50 MLBM/'HR 3.6-

.E 3.4 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS

~VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2

.I

3.2 2.4 f26,0,

-r

-4 1.8 Im 202 30 405-07 090 o - )

~~MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE .j7=

~~SINGLE LOOP OPERATION (BOC to EOC)o ;

01FIGURE 8.2-5 o<

"--:--*'.-*-*.'-2:.*.* '-*-*--*."---*-"-**, .. -*.*-.*-*-.:.* *'*',* :*.*'*', - .*'=*,.--*÷*-*--'-:-'--=*-*<-*:.:*$*'..* '-*-1 .* ......... * ..... .*- ... . *~*-:.*=..* *-*-* *...... I Rev. 12 PL-N F-I15-002 Rev. 1 Page 49 of 62 EOC-RPT Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-50 SUSQEHANA DATE 1 1/04/2015 NIT TR/3.-50EFFECT]VE

0 SSES UNIT 2 CYCLE 18 ci 4.0 3.8 3.6 z

3.4 3.2 H

.6- 3.0 2.8 m

o-2.6 CD 2.4 rP3 2.2 2.0 "11

-nl 1.8 m 1.6 1.4 m

30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)

-o "1 C1 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE O(D SINGLE LOOP OPERATION (BOC to EOC)

-4.

FIGURE 8.2-6

C', SSES UNIT 2 CYCLE 18 C

4'6

-', 4.4 0

-CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAMl 4.2 C INSERTION TIME m -

4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 _____ CURVE C: CORE POWER *;26% AND CORE FLOW <60 MLBM/HR 3.6

°E 3.4

________SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 3.2 ________________ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.

3.0 C,

I'3 2.8 2.6 2.4 2.2 REFEENCE T..2.4.1,3341an 3.. _____

-in 2.0 I"11 1.8 1.6 1.4

-I1 20 30 40 50 60 70 80 S0 100 Core Power (% RATED) m MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) os,*

FIGURE 8.2-7 "", .< Q o3"."

,- *.**

_...:.*

...* *..* ' t:.:-* -. " ..z-= _--*:.: :*:.I- ÷ ,*'-:**'-**:*r--, I- . *

5_2;:::. . -,-.,-:*_-,,*. .*J%:! = -

12 PL-N F-I15-002 SRev.

Rev. 1

" -:-Page 52 of 62 Backup Pressure Regulator Inoperable TRM/3.2-53 EFFECTIVE DATE 11/0412015 SUSQUEHANNA UNIT 2 TM32

0 CG, SSES UNIT 2 CYCLE 18 C-C,, 4.0 C I 3.8

,:MAXIMUM ALLOWABLE AVERAGE SCRAM 3.6 .1. I INSERTION TIME z I: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 4 0 I H 1 I 3.2 4 1 ____________ 1 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2 3,0 I 4-I USED IN DETERMINING MFLCPR 2.8 0.

0 2.6 C.,

2.4 2.2 2.0 m

"11

-1n m 1.8 C)

]

REFERENCE:

TS. 3,4.1, 3.7.8, and 3.2,2 "* " 108, 1.48 m 1.8 H 1.4 3C 40 50 60 70 80 90 100 110 ni Total Core Flow (MLBIHR) "T -0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD Z 0l BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (SOC to EOC)

FIGURE 8.2-8 0* 0

SSES UNIT 2 CYCLE 18 On C 4.6 C 4.4 m

4.2 A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 4.0

]CURVE B: REALISTIC AVERAGE SCRAIMJ INSERTION TIME N> 3.8

[CURVE C: CORE POWER < 26% AND CORE FLOW _<50 MLBM/HR 3.6 3.4 3.2 3.0 CD 2.8 0) 2.6

0. 2.4 2.2 m

"1i "n 2.0" m

() 1.8 !4 m 1.6

-I 1.4 m 20 304 0Core Pow~er (% RATED) 7080 90 100 C3 N> MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE

-o ,=

C O1" I-SINGLE LOOP OPERATION (BOG to EOC) 0, FIGURE 8.2-9

SRev. 12 PL-NF-156-002 RvPage 55 of 62 a One TSV or TCV Closed SUSQUEHANNA UNIT 2 TRM/3.2-56 SUSQEHANA DATE 111D4120 15 2 RM/32-56EFFECTIVE UNT

SSES UNIT 2 CYCLE 18 4.0 C

m :3.8 3.6 C 3.4 Z

3.2

"-I Em :3,0 a- 2.8

01 0 2.6 CD a-.

2.4 2.2 2.0 m

1-I 1.8

<1 m

1.6 m

1.4

,-. 30 40 60 60 70 80 90 100 110 m: Total Core Flow (MLBIIHR)

-U -o 0o CD MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Co CD Z 0 ONE TSV OR TCV CLOSED* ~11

01. SINGLE LOOP OPERATION (BOC to ECC)

FIGURE 8.2-10 ow

-I, .~ ~

'Operation with one TSV or TCV closed is only supported at power levels < 75% rated power, 0)' 0

0!I SSES UNIT 2 CYCLE 18 4.6 4.4 I~r 4.2 z

4,0 z

3.8 3,6 3.4 3.2 Ou Cu 3.0 I CD a- 2.8

,'1 2.6 2.4 2.2 IT[

"1" 2.0 mT C)

H-- 1.8 i

1.6 H

1.4 2C 30 40 Core Power 50 (% RATED) 60 70 80

-0 "

MCPR OPERATING LIM1T VERSUS CORE POWER CD ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (BOG to EOC)

,'1 F[GURE 8.2-11I o*0

. .... .. ........... . . ..... * " * .. ... * * " ==* *,

n** * .nl'*.=

... .. ........... .. ....... *,* '* . . . ....... .*;* * ,* ........ ;* ;........ ............... * ........ .. .......... ....... . ......... r . * ..... . ... . ... .... (, *. I* .

Rev. 12 PL-N F-I15-002 Rev. 1 Page 58 of 62 9~o POWER I FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Fow map, Figure 9A.1 Stability Regions ! and II of the Power/R If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power I Flow map is considered an immediate exit region.

Ifthe OPRM Instrumentation is inoperable per TS 3.3.1 .1, Region [ of the Power I Flow map is considered an immediate scram region.

Region II of the Power/ Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation.

TRM/3.2-59 UIT 2TR SUSQEHANA EFFECTIVE /3.-59 DATE 11/04/2015

Rev. 12 PL-NF-l 5-002 Ray. 1 Page 59 of 62

.I4.c 120 Purpose:

110 J nd. . . 110 Initial / Date: I 100 100 90 90

_I 80-II 70 70 I

80 60 E

1- 50 50 I-40 40 30 30 20 20 10 10 Total Core Flow (Mlbnilhr)

(for SLO <75% Pump Speed Use Form G0-200-009-2)

Figure 9.1 SSES Unit 2 Cycle 18 Power / Flow Map SUSQUEHANNA UNIT 2 TRM/3.2-60 SUSQEHANA NITTR/3.-60EFFECTIVE DATE 11/04/2015

I L.-.-2 Rev. 12 PL-NF-l15-002 Rev. I Page 60 of 62 10.0 OPRM SETPOINTS 10.1 Technical Specification Reference Technical Specification 3.3.1.1 10.2 Description Setpoints for the OPRM Instrumentation are established that will reliably detect and suppress anticipated stablility related power oscillations while providing a high degree of confidence that the MCPR Safety limit is not violated. The setpoints are described in Section 2.0 and are listed below:

Sp - 1.12 Np = 16 Fp = 60OMlbm /hr SUSQUEHANNA UNIT 2 TRM/3.2-61 DATE 11/04/2015 SUSQEHANA UNT 2 RMI3-61EFFECTIVE

I I. '7. S . .s.s&SJ I -2 L.AI-.~-t:.. -. -. 1 Rev. 12 FL-N F-I15-002 O ~i Rev. I

-i* Page 6i of 62

11.0 REFERENCES

11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. XN-NF-81-58(P)(A), Revision 2 and Supplements 1Iand 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984.

2. EMF-2361 (P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model,"

Framatome ANP, May 2001.

3. EMF-2292(P)(A), Revision 0, "ATRIUMP&.i10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.

4. XN-NF-84-105(P)(A), Volume I and Volume 1 Supplements I and 2, "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic C3ore Analysis," Exxon Nuclear Company, February 1987.

5. XN-NF-80-19(P)(A), Volume I and Supplements I and 2, "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983.

O *- 6. XN-NF-80-I19(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," Exxon Nuclear Company, September 1982.

7. XN-NF-80-1 9(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987.

8. XN-NF-80-1 9(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, June 1986.

9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc.,

September 1986.

10. ANF-524(P)(A), Revision 2 and Supplements I and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors,"

November 1990.

II. NE-092-OOIA, Revision 1, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993).

SUSQUEHANNA UNIT 2 TRMI3.2-62 SUSQEHANA NIT TRI3.-62EFFECTIVE DATE 11/04/2015

Rev. 12 PL-NF-15-002 Rev. I l Page 62 of 62

12. ANF-89-98(P)(A} Revision I and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.

13. EMF-2209(P)(A), Revision 3, "SPCB Critical Power Correlation," ARE VA NP, September 2009.

14. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A),

"ROIJEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model,"

Siemens Power Corporation, February 1998.

15. EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4lMicroburn-B2," Siemens Power Corporation, October 1999.

16. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis -

Assessment of STAIF with Input from MICROBURN-B2," Siemens Power Corporation, August 2000.

17. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.

18. AN-1()AVolume 1 Revision I and Volume I Supplements 2, 3, and 4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation, August 1990.

19. ANF-1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005.

SUSQUEHANNA UNIT 2 TRMi3.2-63 NIT TRIS.-63EFFECTIVE SUSQEHANA DATE 1110412015

Main Turbine Overspeed Protection System Rev. 2 3.3.7 3.3 Instrumentation 3.3.7 Main Turbine Overspeed Protection System TRO 3.3.7 One Main Turbine Overspeed Protection system shall be OPERABLE.

APPLICABILITY: MODES 1 and 2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Two of eight stop valves and A. 1.1 Close one of the inoperable 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months control valves inoperable, valves.

AND A.1.2 Limit THERMAL POWER 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months following

< 75% RTP. closure of the inoperable valve AND A. 1.3 Apply the following limits for a 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months following closed Turbine Stop Valve or closure of the Turbine Control Valve as inoperable valve specified in the COLR:

a. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR),"

b. LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)."

OR A-.2--16l~te- min-tu]rb ine-fro m-the---- 2-h ou rs steam supply.

(continued)

SUSQUEHANNA - UNIT 2 TRM / 3.3-17 SUSQEHANA UNT2 RM 3.-17EFFECTIVE DATE 11/04/2015

Main Turbine Overspeed Protection System

.Rev. 2 3.3.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Two of twelve intercept B.1 Close either the intercept valve 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months valves and intermediate stop or the intermediate stop valve valves inoperable, within one of the affected combined intermediate valves.

OR B.2 Isolate main turbine from the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months steam supply.

C. Turbine Overspeed C.1 Isolate main turbine from the 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Protection System steam supply.

inoperable for reasons other than Condition A or B.

SUSQUEHANNA - UNIT 2 TRM / 3.3-17a SUSQEHANA

-UNI 2 RM/3.317aEFFECTIVE DATE 11/04/2015

Main Turbine Overspeed Protection System Rev. 2 3.3.7 TECHNICAL REQUIREMENT SURVEILLANCE

NOTE----- ---------

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 up to 6-hours provided the redundant overspeed trip device is OPERABLE.

SURVEILLANCE FREQUENCY

- - - NOTE---...............................

The provisions of TRS 3..0.4 are not applicable TRS 3.3.7.1 Cycle each high pressure turbine control valve from the running position and observe valve closure. 92 days

NOTE-------------------

The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.2 Cycle each low pressure turbine combined intermediate 92 days valve from the running position and observe valve closure.

.. . . .. . .. . . .. . -.... . . .. . .N O T E-....................-

The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.3 Cycle each high pressure turbine stop valve from the 92 days running position and observe valve closure.

TRS 3.3.7.4 Perform a CHANNEL CALIBRATION of main turbine 24 months overspeed protection instrumentation TRS 3.3.7.5 Disassemble one of each type valve identified in 40 months on a TRS 3.3.7.1, TRS 3.3.7.2, and TRS 3.3.7.3, perform a STAGGERED vi*uah-and-surfaee-inspectioroLovalve seats, disks and TEST BASIS stems and verify no unacceptable flaws or corrosion.

SUSQUEHANNA - UNIT 2 TRM / 3.3-18 SUSQEHANA UNT2 RM 3.-18EFFECTIVE DATE 10/31/2007

I .. :::---:*

-- . -IZ:-'--*, ___- **.-_- = -** * .*. _L "* , , .* **.::: -- I-* -> '**--* * ' ,** *

Main Turbine Overspeed Protection System SRev. 2 B 3.3.7

- --- B 3.3.7 Main Turbine Overspeed Protection System BASES TRO The Main Turbine Overspeed Protection System is designed to protect the main turbine from excessive overspeed by initiating a turbine trip by fast closure of the turbine control valves and closure of the intercept valves to essentially secure all steam flow to the turbine (Ref. 1).

To protect the turbine generator from overspeed conditions, two trip devices are provided. Either device, when initiated, will close the main stop valves, control valves, and combined intermediate valves thus isolating the turbine (Ref. 2).

These two trip devices are as follows:

A mechanical overspeed trip which is initiated if the turbine speed reaches approximately 10% above rated speed, and

An electrical overspeed trip which serves as a backup to the mechanical trip and is initiated at approximately 12% above rated speed.

OPERABILITY of at least 1 of the 2 overspeed protection systems is required for the Turbine Overspeed Protection System to be considered OPERABLE.

O. Main Turbine Overspeed Protection System (MTOPS) OPERABILITY is also based upon the ability of the valves that control steam flow to the turbine to close following the receipt of a closure signal. The 4 stop valves, 4 control valves, 6 intermediate stop valves, and 6 intercept valves make up a system of 20 valves. A single failure to any one of the above system of 20 valves will not prevent a turbine trip (Ref. 2). Hence, if 19 of the 20 noted valves are OPERABLE, the MTOPS is OPERABLE. Note that for this statement to be true, the intermediate stop valves and intercept valves are considered separate valves. Overspeed protection is only disabled on a CIV failure if both valves within a CIV are inoperable. Failure of only one valve in a CIV does not prevent an overspeed trip, and does not affect operability. Actions to close one inoperable valve iftwo valves are inoperable maintain the unit within the analysis in Ref. 2. However, redundancy is reduced and repairs should be completed in accordance with the corrective action program.

Excessive turbine overspeed could generate potentially damaging missiles that could present a personnel and equipment hazard. MTOPS is not necessary to provide adequate protection of the public health and safety and 1s-not-required-to-obviate~thepossibility of an abnormal situation or event giving rise to an immediate threat to the publi*-health-and-safety.

ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components.

(continued)

SUSQUEHANNA-UNIT2 TRM / B 3.3-14 SUSQEHANA

-UNI 2 TM IB3.-14EFFECTIVE DATE 06/25/2002

Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7Main Turbine Overspeed Protection System BASES ACTIONS A.1.1, A.1.2, A.1.3, and A.2 (continued)

If two of eight stop valves and control valves are inoperable, action must be taken to restore at least one of the valves to OPERABLE status in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

This action ensures steam isolation to the turbine in the event of an overspeed condition, and maintains the unit within the bounds of the FSAR analysis. The 72-hour Completion Time provides a reasonable time to troubleshoot the problem, make repairs, and reduce power in an orderly manner if required without challenging plant systems. The required action ifthe problem is not resolved is to close one of the inoperable valves, or to isolate the main turbine from the steam supply. If one of the inoperable valves is closed, then limit thermal power to less than or equal to 75% of rated power, and apply Minimum Critical Power Ratio (MCPR) and Linear Heat Generation Rate (LHGR) limits as specified in the COLR within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Restricting thermal power to less than or equal to 75% of rated power eliminates possible shock loads to the turbine blades that could occur from a non-uniform circumferential steam flow distribution entering the turbine for this configuration. If the MCPR and LHGR limits are not in compliance with the applicable requirements at the end of this period, the ACTIONS required by the applicable specifications must be implemented. This time is provided to stabilize operation with a closed Turbine Stop Valve or Turbine Control Valve.

B. 1 and B.2 If two of twelve intercept valves and intermediate stop valves are inoperable, action must be taken to restore at least one of these valves to OPERABLE status in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . This action ensures steam isolation to the turbine in the event of an overspeed condition. The 72-hour Completion Time provides a reasonable time to troubleshoot the problem, make repairs, and reduce power in an orderly manner if required without challenging plant systems. The required action if the problem is not resolved is to close either the intercept valve or the intermediate stop valve within one of the affected combined intermediate valves, or to isolate the main turbine from the steam supply.

C.1I If the MTOPS is inoperable for reasons other than conditions A or B, then

_____________action must be taken to isolate the main turbine from the steam supply.

6-hours-allews-a-reasonable amount of time to complete the plant shutdown associated with isolating the main turbine-fr-5Y-the-steam-supply.--------_

(continued)

SUSQUEHANNA-UNIT2 TRM / B 3.3-14a SUSQEHANA EFFECTIVE

-UNIT2 TR

/ 3.314a DATE 11/04/2015

Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES (continued)

TRS The TRSs are performed at the specified Frequency to ensure that the turbine overspeed protection function is maintained OPERABLE.

The TRSs are modified by a Note to indicate that 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 redundant overspeed trip device is OPERABLE. Upon completion of the Surveillance, or expiration of the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months allowance, the channel must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken. This Note is based on the average time required to perform channel Surveillance. The 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months testing allowance does not significantly reduce the probability that the Main Turbine Overspeed Protection System will function when necessary.

TRS 3.3.7.1. TRS 3.3.7.2. and TRS 3.3.7.3 Verification of the movement of each of the four high pressure turbine control valves, six low pressure turbine combined intermediate valves (composed of 6 intermediate stop valves and 6 intercept valves), and four high pressure turbine stop valves ensures the OPERABILITY of each valve and that it will be able to close in the event of a turbine trip condition. The 92 day Frequency is based upon current surveillance practice as recommended by the turbine vendor and described in the FSAR (Ref. 3).

TRS 3.3.7.4 This TRS is for the performance of a CHANNEL CALIBRATION of the required main turbine overspeed protection instrumentation. The calibration is a complete check of the instrument channel from the sensing device to'main turbine trip initiation. The Frequency of 24 months is a typical refueling cycle and considers channel reliability.

(continued)

SUSQUEHANNA - UNIT 2 TRM / B 3.3-14b SUSQEHANA EFFECTIVE

-UNIT2 TR

/ 3.314b DATE 11/04/2015

S Rev. 2 Main Turbine Overspeed Protection System B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES TRS TRS 3.3.7.5 (continued)

The disassembly and inspection of the valves referenced ensures that abnormal wear is not occurring which could result in the valves inability to close upon receipt of a close signal. The Frequency is such that only one of each type valve (i.e., high pressure turbine stop; high pressure turbine control; and low pressure turbine combined intermediate), is required to be inspected within a 40 month period. If unacceptable flaws or excessive corrosion are found in a valve, all valves of its type are inspected (Ref. 3). Valve bushings are inspected and cleaned, and bore diameters are checked for proper clearance.

REFERENCES 1. FSAR Section 7.7.1.5.

2. FSAR Section 10.2.2.6.

3. FSAR Section 10.2.3.6.

SUSQUEHANNA - UNIT 2 TRM / B 3.3-14c SUSQEHANA EFFECTIVE

-UNIT2 TR

/ 3.314c DATE 11/04/2015