Text

Technical Requirements Manual
	ML15329A166
Person / Time
Site:	Susquehanna
Issue date:	11/11/2015
From:	Gerlach R; Susquehanna
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
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Nov. 11, 2015 Page 1 of 2 MANIJAL HARD COPY DISTRIBUTION DOCUMENT TRANMSMITTAL 2015-45734 USER INFORMATION:

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

TO: GERLACH*ROSEY N 11/11/2015 LOCATION:

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

WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE.UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MNAL. 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.TRMI -TECHNICAL REQUIREMENTS MANUAL UNIT 1 REMOVE MANUAL TABLE OF CONTENTS DATE: 11/03/2015 ADD MANUAL TABLE OF CONTENTS DATE: 11/10/2015 CATEGORY:

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SSES MNUALm Manual Name:z TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date: 1 Procedure Name TEXT LOES Title: LIST OF EF: LI/I10/2 015 Rev 84 FECTIVE SECTIONS Issue Date 11/10 /2 015 Change ID Change Numiber TEXT TOC Title: TEXT 1.1 Title: 25 04/28/2015 TABLE OF CONTENTS 1 01/31/2014 USE AND APPLICATION DEFINITIONS TEXT 2.1 2 04/28/2015 Title: PLANT PROGRAMS AND SETPOINTS PLANT PROGRAMS TEXT 2.2 10 01/31/2014 Title: PLANT PROGRAMS AND SETPOINTS INSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 Title: 5 03/05/2015 TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY

& SURVEILLANCE (TRS)APPLICABILITY TEXT 3.1.1 1 11/09/2007 Title: REACTIVITY CONTROL SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI)

INSTRUMENTATION TEXT 3.1.2 0 11/18/2002 Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1.3 5 04/16/2009 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

&CHECK VALVE TEXT 3.2.1 16 11/10/2015 Title: CORE OPERATING LIMITS REPORT (COLR)Pagel of i~ Report Date: 11/11/15 Page ! of 16 Report Date: 11/11/15 SSES MANUAL Manual Name: TRMI Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.3.1 0 11/18/2002 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 Title: INSTRUMENTATION 8 10/14/2015 TRN POST-ACCIDENT MONITORING INSTRUMENTATION LDCN 4552 TEXT 3.3.5 0 11/18/2002 Title: INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK TEXT 3.3.6 4 04/29/2014 Title: INSTRUMENTATION TRN ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 2 11/10/2015 Title: INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 Title: INSTRUMENTATION TEXT 3.3.9 1 10/22/2003 TEN RPS INSTRUMENTATION 3 04/17/2008 Title: OPEN INSTRUMENTATION CONFIGURATION 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 03/05/2015 Title: WATER MONITORING INSTRUMENTATION Page 2 of 16 Report Date: 11/11/15 Page of I__66 Report Date: 11/11/15

~SES MANTJAIJ Manual Namue: TRMI Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.4.1 Title: REACTOR TEXT 3.4.2 Title: REACTOR TEXT 3.4.3 Title: REACTOR TEXT 3.4.4 Title: REACTOR TEXT 3.4.5 Title: REACTOR TEXT 3.4.6 Title: REACTOR TEXT 3.5.1 1 04/26/2006 COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY 1 04/16/2009 COOLANT SYSTEM STRUCTURAL INTEGRITY 1 11/09/2007 COOLANT SYSTEM HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITORS 2 04/17/2008 COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT 1 04/26/2006 COOLANT SYSTEM REACTOR VESSEL MATERIALS 2 04/25/2013 RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION 1 02/04/2005 Title: EMERGENCY CORE COOLING AND RCIC ADS MANUAL INHIBIT TEXT 3.5.2 1 11/09/2007 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 2 04/29/2014 Title: SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0 11/18/2002 Title: CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION Page~ of 16 Report Date: 11/11/15 Page of Report Date: 11/11/15 SSES MANUJAL Manual Name : 21:Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.6.4 0 11/18/2002 Titles CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 Title : PLANT 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 TEXT 3.7.3.4 Title : PLANT TEXT 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 0 11/18/2002 SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN 0 11/18/2002 SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL 2 04/16/2009 SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM 3 04/16/2009 SYSTEMS SPRAY AND SPRINKLER SYSTEMS 3 04/16/2009 SYSTEMS C02 SYSTEMS 2 04/16/2009 SYSTEMS HALON SYSTEMS 2 04/16/2009 SYSTEMS FIRE HOSE STATIONS 2 04/16/2009 SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES 1 04/26/2006 SYSTEMS FIRE RATED ASSEMBLIES 10 09/27/2012 SYSTEMS FIRE DETECTION INSTRUMENTATION 1 04/26/2006 SYSTEMS SOLID RADWASTE SYSTEM Page 4 of 16 Report Date: 11/11/15 Page A of 16 SSES MUANTAI.Manual Name: TRJi1I IManual Title: TECHNICAL REQUIREMVENTS MANUAL UNIT 1 TEXT 3.7.5.1 1 03/05/2015 Title: PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT 3.7.5.2 0 11/18/2002 Titleg PLANT SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE 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 Titles PLANT SYSTEMS MAIM CONDENSER 0FFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING TEXT 3.7.8 5 03/05/2015 Title: PLANT SYSTEMS SNUBBERS TEXT 3.7.9 2 01/31/2014 Title: PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 1 12/14/2004 Title: PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)TEXT 3.7o11 Title: STRUCTURAL INTEGRITY 0 04/16/2009 TEXT 3.8.1 2 04/05/2010 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 PROTECTI(CONTINUOUS TEXT 3.8.2.2 2 12/14/2004 Title: ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTIC AUTOMATIC ON -.ON -Page 5 of 16 Report Date: 11/11/15 Page of 16 Report Date: 11/11/15 SSES MANUAL Manual TRNI SManual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.8.3 Title : ELECTRICAL TEXT 3.8.4ELECTRICAL TEXT 3.8.5 Title : ELECTRICAL TEXT 3.8.6 Title : ELECTRICAL TEXT 3.8.7 2 03/05/2015 POWER DIESEL GENERATOR CDG) MAINTENANCE ACTIVITIES 0 11/18/2002 POWER 24 VDC ELECTRICAL POWER SUBSYSTEM 1 11/14/2013 POWER DEGRADED VOLTAGE PROTECTION 1 12/08/2011 POWER EMERGENCY SWITCHGEAR ROOM COOLING 1 06/15/2009 Title: BATTERY MAINTENANCE AND MONITORING PROGRALM TEXT 3.9.1 0 11/18/2002 Title: REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0 11/18/2002 Title: REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 0 11/18/2002 Title: REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 1 04/26/2006 Title: MISCELLANEOUS SEAL SOURCE CONTAMINATION TEXT 3.10.2 2 08/08/2006 Title: MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 2 06/15/2010 Title: MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)TEXT 3.10.4 2 04/17/2008 Title: MISCELLANEOUS LEADING EDGE FLOW METER (LEFM)Page 6 of 16 Report Date: 11/11/15 Page of 16 Report Date: 11/11/15 SSES MANUJALManual Name: TRN1-Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.1.1 Title: RADIOACTIVE TEXT 3.11.1.2 Title: RADIOACTIVE TEXT 3.11.1.3 Title: RADIOACTIVE TEXT 3.11.1.4 Title: RADIOACTIVE TEXT 3.11.1.5 Title: RADIOACTIVE 1 04/26/2006 EFFLUENTS LIQUID EFFLUENTS CONCENTRATION 1 04/26/2006 EFFLUENTS LIQUID EFFLUENTS DOSE 1 04/26/2006 EFFLUENTS LIQUID WASTE TREATMENT SYSTEM 2 10109/2012 EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION 3 03/05/2015 EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUTMENTATION

...TEXT 3.11.2.1 Title: RADIOACTIVE TEXT 3.11.2.2 Title: RADIOACTIVE TEXT 3.11.2.3 Title: RADIOACTIVE FORM TEXT 3.11.2.4 Title: RADIOACTIVE TEXT 3.11.2.5 Title: RADIOACTIVE TEXT 3.11.2.6 Title: RADIOACTIVETEXT 3.11.3 Title: RADIOACTIVE EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS 3 04/26/2006 DOSE RATE 1 04/26/2006 DOSE -NOBLE GASES 1 04/26/2006 DOSE -IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE 0 11/18/2002 GASEOUS RAD WASTE TREATMENT SYSTEM 4 07/03/2013 VENTILATION EXHAUST TREATMENT SYSTEM 5 04/28/2015 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 1 04/26/2006 TOTAL DOSE Page :i~ of 16 Report Date: 11/11/15 Page of I_66 Report Date: 11/11/15 SSES MANUAL Manual Name : TRMI Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.4.1 5 03/05 /2015 Title: RADIOACTIVE EFFLUENTS MONITORING PROGRAM TEXT 3.11.4.2 2 04/26 /2006 Title: RADIOACTIVE EFFLUENTS LAND USE CENSUS TEXT 3.11.4.3 Title: RADIOACTIVE EFFLUENTS 1 04/26/2006 INTERLABORATORY COMPARISON PROGRAM TEXT 3.12.1 0 11/19/2002 Title: LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL POOL 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 REQUIREMENT 0 TEXT 4.1 Title: TEXT 4.2 Title: TEXT 4.3 Title: TEXT 4.4 Title: TEXT 4.5 Title: TEXT 4.6 Title: ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE 0 08/31/1998 CONTROLS ORGANIZATION 0 08/31/1998 CONTROLS REPORTABLE EVENT ACTION 0 08/31/1998 CONTROLS SAFETY LIMIT VIOLATION 1 12/18/2008 CONTROLS PROCEDURES

& PROGRAMS 0 08/31/1998 CONTROLS REPORTING REQUIREMENTS 0 08/31/1998 CONTROLS RADIATION PROTECTION PROGRAM Page8.a 16Reprt Dte:11/1/1 Page of 16 Report Date: 11/11/15 SSES MANUJAL.1 Manual Name: TRMI-- Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 4.7 0 08/31/1998 Title: ADMINISTRATIVE CONTROLS TRAINING TEXT B3.0 5 03/05/2015 Title: APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.1.1 2 04/29/2014 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 TEXT B3.1.3 3 03/31/2006 Title: REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT B3.1.4 0 11/19/2002 Title: REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD SCRAM ACCUMU/LATORS AND CHECK VALVE TEXT B3.2.1 0 11/19/2002 Title: CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR)INSTRUMENTATION TEXT B3.3.1 Title: INSTRUMENTATION BASES TEXT B3.3.2 Title: INSTRUMENTATION BASES 1 01/31/2014 RADIATION MONITORING INSTRUMENTATION 2 03/31/2011 SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 3 12/18/2008 Title: INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 5 10/14/2015 Title: INSTRUMENTATION BASES TEN POST ACCIDENT MONITORING (PAM) INSTRUMENTATION

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Manual Name: TRMI=iManual Title: TECHNICAL REQUIREM'cENTS MANUAL UNIT 1 TEXT B3.4.6 2 04/25/2013 Title: REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT B3.5.1 0 11/19/2002 Title: ECCS AND RCIC BASES ADS MANUAL INHIBIT TEXT B3.5.2 1 11/09/2007 Title: ECCS AND RCIC BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT B3.5.3 1 11/09/2007 Title: ECCS AND RCIC BASES LONG TERM NITROGEN SUPPLY TO ADS TEXT B3.6.1 0 11/19/2002 Title: CONTAINMENT BASES VENTING OR PURGING TEXT B3.6.2 0 11/19/2002 Title: CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 2 04/17/2008 Title: CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION TEXT B3o6.4 1 12/14/2004 Title: CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT B3.7.1 0 11/19/2002 Title: PLANT SYSTEMS BASES EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN)

TEXT B3.7.2 0 11/19/2002 Title: PLANT SYSTEMS BASES ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL TEXT B3.7.3.1 3 06/15/2010 Title: PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM* TEXT B3.7.3.2 2 04/26/2006 W. Title: PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS Page 1_1 of i__66 Report Date: 11/11/15 SSES MANUAL Manual Name: TRMI SManual TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.3.3PLANT TEXT B3.7.3.4PLANT TEXT B3.7.3.5 Title : PLANT TEXT B3.7.3.6 Title : PLANT TEXT B3.7.3.7 Title : PLANT STEXT B3.7.3.8 Title: PLANT TEXT B3 7.4 Title : PLANT TEXT B3.7.5.1 Title : PLANT TEXT B3.7.5.2 Title : PLANT TEXT B3.7.5.3 Title : PLANT TEXT B3.7.6 Title : PLANT.TEXT B3.7.7...- Title : PLANT SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES 0 11/19/2002 C02 SYSTEMS 3 04/29/2014 HALON SYSTEMS 1 04/26/2006 FIRE HOSE STATIONS 1 04/26/2006 YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES 0 11/19/2002 FIRE RATED ASSEMBLIES 3 09/27/2012 FIRE DETECTION INSTRUMENTATION 0 11/19/2002 SOLID RADWASTE SYSTEM 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 4 06/04/2013 ESSW PUMPHOUSE VENTILATION 2 01/31/2008 MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION Page 12 of 16 Report Date: 11/11/15 Page 1/2 of 16 Report Date: 11/11/15 SSES MANTJAI~Manual Name : TPR41 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.8 Title: PLANT TEXT B3.7.9 Title : PLANT TEXT B3.7.10 Title : PLANT 4 SNUBBERS 01/31/2 014 SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES 2 12/08/2011 CONTROL STRUCTURE HVAC 1 12/14/2004 SPENT FUEL STORAGE POOLS TEXT B3.7.11 Title: STRUCTURAL INTEGRITY 1 04/14/2010 TEXT B3.8.1 Title: ELECTRICAL PROTECTIVE TEXT B3.8.2.1 Title: ELECTRICAL CONTINUOUS TEXT B3.8.2.2 Title: ELECTRICAL AUTOMATIC 2 03/10/2010 POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT DEVICES 0 11/19/2002 POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD 1 09/17/2004 POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION

-PROTECTION

-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 B3.8.6 2 12/08/2011 Title: ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 2 06/04/2013 Title: BATTERY MAINTENANCE AND MONITORING PROGRAM Page i~ of ii Report Date: 11/11/15 Page 13 of 16 Report Date: 11/11/15 S.~ES MM~AL<?=Manual Name: TRMI" Titles° TECHNICAL REQUIREMENTS MANUAL UNIT 1 0 TEXT B3.9.l 0 11/19/2002 Title: REFUELING OPERATIONS BASES DECAY TINE TEXT B3.9.2 0 11/19/2002 Title: REFUELING OPERATIONS BASES COMM4UNICATIONS TEXT B3.9.3 0 11/19/2002 Title: REFUELING OPERATIONS BASES REFUELING PLATFORM TEXT B3.10.1 0 11/19/2002 Title: MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 1 03/31/2006 Title: MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT B3.10.3 0 11/19/2002 Title: MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)TEXT B3.10.4 1 Title: MISCELLANEOUS BASES LEADING 04/17/2 008 EDGE FLOW METER (LEFM)TEXT B3.ii.ioi 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3ol.11Io2 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3.ii.i.3 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3.11.I.4 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.I.5 Title: RADIOACTIVE EFFLUENTS INSTRUMENTATION 0 11/19/2002 BASES RADIOACTIVE LIQUID PROCESS MONITORING Page 14 of ~ Report Date: 11/11/15 Page 14 of Report Date: 11/11/15 SSES MANUJAI O Manual Name: TRMI...Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.11.2.1 Title: RADIOACTIVE EFFLUENTS TEXT B3.11.2.2 Title: RADIOACTIVE EFFLUENTS TEXT B3.11.2.3 Title: RADIOACTIVE EFFLUENTS SPARTICULATES FORM TEXT B3.11.2.4 Title: RADIOACTIVE EFFLUENTS TEXT B3.11.2.5 Title: RADIOACTIVE EFFLUENTS TEXT B3.11.2.6 Title: RADIOACTIVE EFFLUENTS INSTRUMENTATION TEXT B3.11.3 Title: RADIOACTIVE EFFLUENTS TEXT B3.11.4.1 Title: RADIOACTIVE EFFLUENTS TEXT B3.11.4.2 Title: RADIOACTIVE EFFLUENTS TEXT B3.11.4.3 Title: RADIOACTIVE EFFLUENTS TEXT B3.12.1 Title: LOADS CONTROL PROGRAM TEXT B3.12.2 1 12/14/2004 BASES DOSE RATE 0 11/19/2002 BASES DOSE -NOBLE GASES 0 11/19/2002 BASES DOSE -IODINE, TRITIUM, AND RADIONUCLIDES IN 0 11/19/2002 BASES GASEOUS RADWASTE TREATMENT SYSTEM 5 07/03/2013 BASES VENTILATION EXHqAUST 1 01/27/2004 BASES RADIOACTIVE GASEOUS TREATMENT SYSTEM EFFLUENT MONITORING 0 11/19/2002 BASES TOTAL DOSE 5 03/05/2015 BASES MONITORING PROGRAM 0 11/19/2002 BASES LAND USE CENSUS 0 11/19/2002 BASES INTERLABORATORY COMPARISON PROGRAM 1 10/04/2007 BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL 1 12/03/2010 Title: LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS Page i~. of 16 Report Date: 11/11/15 Page 15 of I__66 Report Date: 11/11/15 SSES MANUJALManual Name: TRN1 Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.12.3 0. 11/19/2002 Title: LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Page 16 of 16 Report Date: 11/11/15 Page 16 of 16 Report Date: 11/11/15 SUSQUEHANNA STEAM ELECTRIC STATION Rev. 64 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Titl__ee Effective Date TOC 1.0 TABLE OF CONTENTS USE AND APPLICATION Page TRM / 1.0-1 Page TRM / 1.0-2 Page TRM / 1.0-3 2.0 3.0 3.1 3.2 PLANT PROGRAMS Page TRM / 2.0-1 Pages TRM / 2.0-2 and TRM / 2.0-3 Page TRM / 2.0-4 Page TRM / 2.0-5 Page TRM / 2.0-6 Page TRM / 2.0-7 Pages TRM / 2.0-8 and TRM / 2.0-9 Page TRM / 2.0-10 Page TRM / 2.0-11 Page TRM / 2.0- 12 Pages TRM / 2.0-13 and TRM / Page TRM / 2.0-15 I I Pages TRM / 3.0-1 and Page TRM / 3.0-3 Page TRM / 3.0-4 REACTIVITY CON Page TRM / Pages TRM an Pages 3. 5 Page TR 04/23/2015 10/04/2002 01/21/2014 10/04/2002 04/23/2015 01/28/2005 06/25/2002 01/21/2014 03/27/2008 05/15/2008 01/07/2011 02/02/2010 11/15/2004 03/27/2008 11/15/2004 11/15/2005 02/19/2015 03/15/2002 02/19/2015 10/3112007 08/31/1998 08/31/1998 03/22/2006 04/07/2009 03/27/2008 02/18/1999 02/18/1999 07/07/1999 11/04/2015 07/16/1999 10/31/2007 03/10/2011 3.1-9 and.1-10 TRM / 3.1,9a iERATING LIMITS REPORT Pages TRM / 3.2-2 through TRM / 3.2-63 3.3 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 Page TRM / 3.3-4 and TRM / 3.3-5 Page TRM / 3.3-6 SUSQUEHANNA-UNIT1 TRM / LOES-1 SUSQEHANA UNT I RM LOS-1EFFECTIVE DATE 11/04/2015 SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date Page TRM / 3.3-7 Page TRM / 3.3-8 Page TRM / 3.3-9 Page T'RM / 3.3-9a Page TRM / 3.3-10 Page TRM /3.3-11 Page TRM / 3.3-11a Page TRM I 3.3-12 Page TRM / 3.3-13 Page TRM / 3.3-14 Page TRM / 3.3-15, Page TRM I 3.3-16 Page TRM / 3.3-17 Page TRM / 3.3-17a Page 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 I 3.3-25 Page, TRM / 3.3-26 Page TRM / 3.3-27 Page TRM / 3.3-28 REACTOR COOLANT SYSTEM Page TRM / 3.4-1 Pages TRM / 3.4-2 through TRM / 3.4-5 Pages TRM / 3.4-6 through TRM / 3.4-8 Page TRM / 3.4-9 Page TRM / 3.4-10 Page TRM / 3.4-11 Page TRM / 3.4-12 Page TRM / 3.4-13 Pages TRM / 3.4-14 and TRM / 3.4-15 EMERGENCY CORE COOLING AND RCIC Page TRM / 3.5-1 Pages TRM / 3.5-2 and TRM / 3.5-3 Pages TRM / 3.5-4 and TRM / 3.5-5 Pages 3.5-6 and 3.5-7 10/31/2007 08/31/1998 10/07/2015 06/30/2010 10/31/2007 10/07/2015 10/07/2015 03/30/2001 01/07/2011 12/1 4/1 998 04/11/2014 01/07/2011 11/04/2015 11/04/2015 10/31/2007 10/22/2003 03/27/2008 11/15/2004 03/22/2006 12/03/2004 05/16/2003 10/22/2003 02/19/2015 04/07/2009 03/31/2006 10/23/11998 04/01/2009 08/31/1998 10/31/2007 08/31/1998 03/27/2008 03/31/2006 04/25/2013 01/28/2005 08/31/1998 10/31/2007 08/31/1998 3.4 3.5 SUSQUEHANNA-UNIT 1 TRM / LOES-2 SUSQEHANA UNT I RM LOS-2EFFECTIVE DATE 11/04/2015 SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date 3.6 3.7 CONTAI NMENT Page 3.6-1 Pages TRM / 3.6-2 and TRM I 3.6-2a Page 3.6-3 Page TRM / 3.6-4 Page 3.6-5 Pages TRM / 3.6-6 through TRM / 3.6-8 PLANT SYSTEMS Pages 3.7-1 through 3.7-3 Page TRM / 3.7-4 Pages TRM / 3.7-5 Pages TRM / 3.7-6 through TRM / 3.7-8 Pages TRM / 3.7-9 and TRM / 3.7-10 Page TRM / 3.7-11 Page TRM / 3.7-12 Page TRM / 3.7.13 Page TRM / 3.7-14 Pages TRM / 3.7-15 and TRM / 3.7-16 Page TRM / 3.7-17 Page TRM / 3.7-18 Page TRM / 3.7-19 Pages TRM / 3.7-20 through TRM / 3.7-22 Page TRM / 3.7-23 Page TRM / 3.7-24 Page TRM / 3.7-25 Page TRM / 3.7-26 Page TRM / 3.7-27 Pages TRM / 3.7-28 through TRM / 3.7-34a Page TRM / 3,7-35 Pages TRM / 3.7-36 and TRM / 3.7-37 Page TRM / 3.7-38 Page TRM / 3.7-39 Page TRM / 3.7-40 Page TRM / 3.7-41 Pages TRM / 3.7-41a through TRM / 3.7-41c Page TRM / 3.7-42 Page TRM / 3.7-43 Page TRM / 3.7-44 Pages TRM / 3.7-45 and TRM / 3.7-46 Page TRM / 3.7-47 08/31/1998 04/16/2014 08/31/1998 01/07/2002 08/31/1998 12/31/2002 08/31/1998 03/31/2006 04/07/2009 08/02/1999 04/07/2009 12/29/1999 08/02/1999 04/07/2009 08/09/2005 08/02/1999 04/07/2009 08/02/1999 04/07/2009 08/02/1999 04/07/2 009 03/31/2006 08/02/1999 09/25/2012 11/24/2011 09/25/2012 03/31/2006 02/01/1999 02/19/2015 08/31/1998 03/31/2006 05/24/2012 05/24/2012 09/04/2008 08/31/1998 02/19/2015 10/05/2006 06/07/2007 SUSQUEHANNA-UNITI TRM / LOES-3 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA-UNIT1 TRM / LOES-3 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date 3.8 3.9 Page TRM I 3.7-48 Page TRM I 3.7-49 Pages TRM / 3.7-49a and TRM / 3.7-49b Page TRM / 3.7-50 Page TRM / 3.7-51 Page TRM / 3.7-52 Page TRM / 3.7-53 Page TRM / 3.7-54 Pages TRM / 3.7-55 through TRM / 3.7-57 ELECTRICAL POWER Page TRM / 3.8-1 Page TRM / 3.8-2 Pages TRM / 3.8-3 and TRM /3.8-4 Pages TRM / 3.8-5 and TRM / 3.8-6 Page TRM / 3.8-7 Pages TRM / 3.8-8 through TRM / 3.8-10 Page TRM /3.8-11 Page TRM / 3.8-12 Page TRM / 3.8-13 Page TRM / 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 and TRM / 3.8-22 Page TRM / 3.8-23 Pages TRM / 3.8-24 and TRM / 3.8-25 Page TRM / 3.8-26 Page TRM / 3.8-27 Pages TRM / 3.8-28 and TRM / 3.8-29 10/05/2006 06/07/2007 10/05/2006 01/21/2014 08/16/2006 12/03/2004 04/15/2003 07/29/1999 04/01/2009 04/02/2002 01/28/2005 03/25/2010 04/02/2002 10/31/2007 12/03/2004 09/03/2004 12/03/2004 02/19/2015 08/31/1998 04/02/2002 08/31/1998 04/02/2002 08/31/1998 06/06/1999 11/07/2013 11/30/2011 05/28/2009 11/29/2006 05/28/2009 08/31/1998 03/31/2006 08/31/1998 08/01/2006 03/22/2006 06/10/2010 03/27/2008 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 3.10 MISCELLANEOUS Page TRM / 3.10-1 Pages TRM / 3.10-2 and TRM / 3.10-3 Page TRM / 3.10-4 Pages TRM / 3.10-5 and TRM / 3.10-6 Page TRM / 3.10-7 Page TRM / 3.10-8 SUSQUEHANNA

-UNIT 1 TRM / LOES-4 SUSQEHANA UNT I RM LOS-4EFFECTIVE DATE 11/04/2015 SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date 3.11 3.12 RADIOACTIVE EFFLUENTS Page TRM / 3.11-1 Pages TRM / 3.11-2 and TRM / 3.11-3 Page TRM / 3.11-4 Page TRM / 3.11-5 Page TRM / 3.11-6 Pages TRM / 3.11-7 and TRM / 3.11-8 Pages TRM / 3.11-9 and TRM / 3.11-10 Pages TRM / 3.11-11 and TRM / 3.11-12 Page TRM /3.11-13 Page TRM / 3.11-14 Pages 3.11-15 and 3.11-16 Page TRM / 3.11-17 Page 3.11-18 Page TRM / 3.11-19 Pages TRM / 3.11-20 and TRM / 3.11-21 Page TRM / 3.11-22 Page TRM / 3.11-23 Page TRM / 3.11-24 Page TRM / 3.11-25 Pages TRM / 3.11-26 and TRM / 3.11-27 Page TRM /3.11-28 Page TRM / 3.11-29 Pages TRM / 3.11.30 and TRM / 3.11.31 Page TRM / 3.11.32 Page TRM / 3.11-33 Page TRM / 3.11-34 Page TRM / 3.11-35 Pages TRM / 3.11-36 through TRM / 3.11-39 Page TRM / 3.11-40 Pages TRM / 3.11-41 through TRM / 3.11-43 Page TRM / 3.11-44 Page TRM / 3.11-45 Page 3.11-46 Page TRM / 3.11-47 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM /3.12-3 Page TRM / 3.12-4 Page TRM / 3.12-5 03/31/2006 08/31/1998 03/31/2006 08/31/1998 03/31/2006 08/31/1998 10/09/2012 08/31/1998 02/19/2015 12/03/2004 09/01/1998 03/31/2006 08/31/1998 08/15/2005 03/31/2006 04/02/2002 11/14/2006 06/18/2013 04/12/2007 01/21/2004 09/08/2009 12/03/2004 01/21/2004 04/23/2015 03/31/2006 08/31/1998 03/31/2006 11/30/2005 02/19/2015 08/31/1998 08/01/2006 03/31/2006 08/31/1998 03/31/2006 02/05/1999 03/14/2008 02/05/1999 08/31/1998 12/11/2008 08/31/1998 4.0 ADMINISTRATIVE CONTROLS Pages 4.0-1 through 4.0-3 Page TRM / 4.0-4 Pages 4.0-5 through 4.0-8 SUSQUEHANNA-UNIT1 TRM/LOES-5 SUSQEHANA UNT I RM LOS-5EFFECTIVE DATE 11/04/2015 SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date B 3.0 B 3.1 APPLICABILITY BASES Pages TRM / B 3.0-1 through TRM / B 3.0-3 Page TRM / B 3.0-4 Page TRM / B 3.0-4a and TRM / B 3.0-4b Page TRM / B 3.0-5 Page TRM I B 3.0-6 Page TRM I B 3.0-7 Pages TRM / B 3.0-8 through TRM I B 3.0-10 Pages TRM / B 3.0-11 and TRM / B 3.0-12 Pages TRM / B 3.0-13 through TRM / B 3.0-15 REACTIVITY CONTROL SYSTEMS BASES Page TRM / B 3.1-1 Page TRM / B 3.1-2 Page TRM /B 3.1-3 Page B 3.1-4 Page TRM / B 3.1-5 Pages TRM I B 3.1-6 and TRM / B 3.1-7 Page TRM / B 3.1-8 B 3.2 B 3.3 CORE OPERATING LIMITS BASES Page B 3.2-1 INSTRUMENTATION BASES Page TRM / B 3.3-1 Page TRM / B 3.3-2 Page TRM / B 3.3-2a Page TRM / B 3.3-3 Page TRM / B 3.3-3a Page TRM / B 3.3-4 Page TRM / B 3.3-5 Page TRM I B 3:3-6 Page TRM I B 3.3-7 Page TRM / B. 3.3-8 Page TRM I B 3.3-9 Pages TRM / B 3.3-10 through TRM I B 3.3-12 Page TRM / B 3.3-13 Page TRM / B 3.3-14 Page TRM / B 3.3-14a Page TRM I B 3.3-14b Page TRM / B 3.3-14c Pages TRM / B 3.3-15 and TRM I B 3.3-16 Page TRM / B 3.3-17 Pages TRM / B 3.3-17a through TRM / B 3.3-17c Page TRM / B 3.3-17d 08/31/1998 02/19/2015 02/19/2015 02/19/2015 08/31/1998 04/12/2007 08/31/1998 03/15/2002 02/19/2015 07/13/1999 04/16/2014 10/31/2007 08/31/1998 11/15/2005 03/22/2006 02/18/1999 08/31/1998 01/21/2014 03/10/2011 10/31/2007 12/11/2008 10/31/2007 06/30/2010 10/07/2015 06/30/2010 10/07/2015 06/30/2010 10/31./2007 01/07/2011 01/21/2014 06/25/2002 11/04/2015 11/04/2015 11/04/2015 10/22/2003 03/22/2006 03/22/2006 03/27/2008 SUSQUEHANNA-UNITI TRM / LOES-6 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA

-UNIT 1 TRM / LOES-6 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date B 3.4 B 3.5 B 3.6 Pages TRM / B 3.3-17e and TRM I B 3.3-17f Pages TRM / B 3.3-18 and TRM I B 3.3-19 Page TRM / B 3.3-20 Page TRM / B 3.3-21 Pages TRM / B 3.3-22 and TRM / B 3.3-23 REACTOR COOLANT SYSTEM BASES Page B 3.4-1 Pages TRM / B 3.4-2 and TRM / B 3.4-3 Pages TRM 1 B 3.4-4 and TRM / B 3.4-4a Page TRM / B 3.4-5 Page B 3.4-6 Pages TRM / B 3.4-7 and TRM / B 3.4-8 ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 Pages TRM / B 3.5-3 through TRM / B 3.5-5 CONTAINMENT BASES Page TRM / B 3.6-1 Page TRM / B 3.6-2 Page B 3.6-3 Page TRM / B 3.6-4 Page TRM / B 3.6-5 Page TRM / B 3.6-6 Pages TRM / B.3.6-7 through TRM / B 3.6-11 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 Page TRM/IB 3.7-3 Page TRM / B 3.7-3a Page TRM / B 3.7-4 Page TRM / B 3.7-5 Page TRM / B 3.7-6 Pages TRM / B 3.7-7 and TRM / B 3.7-7a Page TRM / B 3.7-8 Page TRM / B 3.7-9 Page TRM / B 3.7-10 Page TRM / B 3.7-I0a Page TRM / B 3.7-11 Page TRM / B 3.7-11a Pages TRM / B 3.7-12 and TRM / B 3.7-13 Pages TRM / B 3.7-14 and TRM / B 3.7-14a 03/22/2006 08/03/2010 10/22/2003 05/16/2003 04/07/2009 08/31/1998 04/01/2009 10/31/2007 10/1 5/1 999 08/31/1998 04/25/2013 08/31/1998 10/31/2007 07/26/2001 02/01/1999 08/31/1998 03/27/2008 04/04/2007 12/03/2004 12/31/2002 08/31/1998 06/10/2010 12/27/2007 03/31/2006 08/02/1999 03/3"1/2006 08/02/1999 O5/2 9/2013 04/11/2014 08/02/1999 03/31/2006 08/02/1999 03/31/2006 08/02/1999 09/25/20 12 B 3.7 SUSQUEHANNA

-UNIT I TRM / LOES-7 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA-UNIT1 TRM / LOES-7 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date Page TRM / B 3.7-14b Pages TRM / B 3.7-15 and TRM I B 3.7-16 Pages B 3.7-17 through B 3.7-20 Page TRM I B 3.7-21 Pages TRM / B 3.7-21a through TRM / B 3.7-21d Pages TRM / B 3.7-21e through TRM / B 3.7-21g Page TRM / B 3.7-22 and TRM / B 3.7-23 Page TRM / B 3.7-24 Page TRM / B 3.7-25 Pages TRM / B 3.7-26 through TRM / B 3.7-28 Pages TRM / B 3.7-29 and TRM I B 3.7-30 Page TRM / B 3.7-30a Page TRM / B 3.7-30b 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 Pages TRM / B 3.7-36 through TRM / B 3.7-39 Page TRM / B 3.7-40 ELECTRICAL POWER BASES Page TRM / B 3.8-1 Page TRM / B 3.8-2 Page TRM / B 3.8-2a Page TRM / B 3.8-3 Page TRM / B 3.8-3a Page TRM / B 3.8-4 Page TRM / B 3.8-4a Page B 3.8-5 Pages TRM / B 3.8-6 through TRM / B 3.8-15 Page TRM / B 3.8-16 Page TRM / B 3.8-17 Pages TRM / B 3.8-17a and TRM / B 3.8-17b Pages TRM / B 3.8-18 through TRM / B 3.8-20 Pages TRM / B 3.8-21 and TRM I B 3.8-22 Page TRM I B 3.8-23 Page TRM / B 3.8-24 REFUELING OPERATIONS BASES Pages B 3.9-1 through B 3.9-7 11/24/2011 0210111999 08/31/1998 05/29/2013 05/24/2012 05/29/2013 01/30/2008 10/05/2006 01/21/2014 10/05/2006 06/07/2007 10/05/2006 01/21/2014 11/30/2011 03/09/2001 04/15/2003 12/03/2004 07/05/2000 04/01/2009 04/08/2010 04/02/2002 01/28/2005 03/01/2010 04/02/2002 04/02/2002 09/03/2004 04/02/2002 08/31/1998 04/02/2002 11/07/2013 11/30/2011 11/30/2011 05/29/2013 05/28/2009 05/29/2013 05/28/2009 08/31/1998 B 3.8 B.3.9 SUSQUEHANNA

-UNIT I TRM / LOES-8 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA

-UNIT 1 TRM / LOES-8 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MAN UAL)Section Title Effective Date B 3.10 MISCELLANEOUS BASES Page B 3.10-1 Pages TRM / B 3.10-2 and TRM / B 3.10-3 Pages TRM / B 3.10-4 and TRM / B 3.10-5 Page TRM / B 3.10-6 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 3.1 1-11a Pages TRM/B 3.11-12 and TRM/B 3.11-13 Page TRM /B 3.11-14 Page TRM / B3.11-15 Pages B 3.11-16 through B 3.1 1-19 Page TRM / B 3.11-20 Page TRM / B 3.1 1-20a Page TRM /B 3.11-21 Pages TRM / B 3.11-22 and TRM / B 3.11-23 Pages TRM / B 3.1 1-23a and TRM / B 3.1 1-23b Pages TRM / B 3.11-24 and TRM / B 3.11-25 Pages B 3.11-26 and B 3.11-27 Page TRM / B3.11-28 Page TRM / B 3.11-29 Pages TRM / B3.1 1-30 and TRM / B 3.11-31 Page TRM /B 3.11-32 Page TRM / B 3.11-33 Pages B 3.11-34 and B 3.11-35 Page TRM / B 3.11-36 B.3.12 LOADS CONTROL PROGRAM BASES Page TRM / B3.12-1 Page TRM / B 3.12-2 Page TRM / B 3.12-3 08/31/1998 03/22/2006 08/23/1999 03/27/2008 08/30/1998 02/01/1999 04/07/2000 02/01/1999 12/03/2004 02/01/1999 08/30/1998 04/02/2002 04/02/2002 05/13/2005 11/14/2006 06/18/2013 01/21/2004 08/30/1998 11/30/2005 02/19/2015 05/29/2013 08/30/1 998 06/30/2010 08/30/1998 02/12/1999 09/19/2007 11/29/2010 02/05/1999 TRM1 text LOES 11/4/2015 SUSQUEHANNA

-UNIT 1 TRM / LOES-9 SUSQEHANA UNT I RM LOS-9EFFECTIVE DATE 11/04/2015 Core Operating Limits Report (COLR)Rev. 16 3.2.1 3.2 Core Operating Limits Report (COLR)3.2.1 Core Operating Limits Report (COLR)TRO 3.2.1 The Core Operating Limits specified in the attached COLR shall be met.APPLI(CABILITY:

SPecified in the referenced Technical Specifications.

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

Technical Specifications.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY------ NOTE-..........

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

..N/A No associated Surveillances.

Surveillances are implemented in the applicable Technical Specificatiorns.

SUSQUEHANNA-UNIT1 TRM / 3.2-1 SUSQEHANA -UNI 1 TM/32-1EFFECTIVE DATE 0710711999 Rev. 16 PL-NF-14-001 Rev. 2 Page "i of 62 Susquehanna SES Unit I Cycle 19 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering September 2015 SUSQUEHANNA UNIT1 TRM!3.2-2 SUSQEHANA UNT I RM/32-2EFFECTIVE DATE 11/0412015 Rev. 16 PL-NF-14-001 Rev. 2 Page 2 of 62 CORE OPERATING LIMITS REPORT REVISION DESCRiPTiON INDEX Rev. Affected , No. Sections Description/Purpose of Revision 0 1 2 ALL ALL ALL Issuance of this COLR is in support of Unit I Cycle 19 operation.

New COLR required due to Power/Flow Map revision.New COLR required for the inclusion of operating limits regarding a Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closure event.~J. J FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 1 TRM/3.2-3 TRM/.2-3EFFECTIVE DATE 11/04/2015 Rev. 16 PL-NF-14-00i Rev. 2 Page 3 of 62 SUSQUEHANNA STEAM ELECTRIC STATION Unit I Cycle 19 CORE OPERATING LIMITS REPORT Table of Contents 1 .0 INTRODUCTION............................................................................

4 2.0 DEFINITIONS................................................................................6 3.0 SHUTDOWN MARGIN .......................................................................

6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)..................

7 6.0 MINIMUM CRITICAL POWER 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 I FLOW MAP ..............................................

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

58 10.0 OPRM SETPOINTS..........................................................................

60

11.0 REFERENCES

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

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61 SUSQUEHANNA UNIT 1 TRM/3.2-4 SUSQEHANA NIT TR/3..-4 EFFECTIVE DATE 11/04/2015 Rev. 16 PL-NF-14-0O1 Rev. 2 Page 4 of 62 1.0 iNTRODUCTION This CORE OPERATING LIMITS REPORT for Susquehanna Unit t Cycle 19 is prepared in accordance with the requirements of Susquehanna Unit 1, Technical Specification 5.6.5. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits, RBM setpoints, and OPRM setpoints presented herein were developed using NRC-approved methods and are established such that all applicable limits of the plant safety analysis are met.SUSQUEHANNA UNIT 1 TRM/3.2-5 SUSQEHANA UNT I RM/32-5 EFFECTIVE DATE 11/04/2015 Rev. 16 PL-NF- 14-001 Rev. 2 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 LHGR limit for the applicable fuel bundle type.2.4 LHGRFACT is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFAC 1 multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbmlhr.2.5 LHGRFACp is a multiplier applied to the LHGR limit when operating at less than 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 divided by the MCPR calculated by the core monitoring system for each fuel bundle.2.7 MAPRAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLGHR limit for the applicable fuel bundle type.2.8 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.2.11 Fp is the core flow, in Mlbm I hr, below which the OPRM RPS trip is activated.

SUSQUEHANNA UNIT 1 TRM/3.2-6 SLJSUEHNNAUNITI TMI32-6 EFFECTIVE DATE 111/0412015 Rev. 16 PL-NF-1 4-001 Rev. 2 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 OR b) 0.28% Ak/k with the highest worth rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and poison burnup, Beginning of Cycle (BOG) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivty during the cycle. Therefore, the SUM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, "R". The adder, "R", is the difference between the calculated value of maximum core reactivity (that is, minimum 8DM) during the operating cycle and the calculated BOG core reactivity.

If the value of "R" is zero (that is, BOG is the most reactivepoint in the cycle) no correction to the BOG 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 t TRM/3.2-7 SUSQEHANA UNT I RM/32-7 EFFECTIVE DATE 11104/2015 Rev. 16 PL-NF-14-O01 Rev. 2 Page?7 of 62 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)4.1 Technical Specification Reference Technical Specification 3.2.1 4.2 Description The APLHGRs for ATRIUMT'-10 fuel shall not exceed the limit shown in Figure 4.2-1.The APLHGR limits in Figure 4.2-1 are valid for Main Turbine Bypass Operable*and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable in Two Loop operation.

The APLHGR limits for Single Loop operation are provided in Section 8.0.SUSQUEHANNA UNIT 1 TRM/3.2-8 SUSQEHANA UNT I RM/32-8 EFFECTIVE DATE 11/04/20 15 9!SSES UNIT I CYCLE 19 02 C C rn.--z z C*16.0 1[4.0 12.0'-I 1111 IIl 1 1 111III I III la ma , a a I , I , , I Ia' II 1 1,1 a , , .......1 1 1a I I a aIn II I 1 4 i i i i i l l i 1 1 1 1 11__ ___ a I 1 I I I I I I I I I I I K I I 2 iI -1 1 l O = .I I 2 I 1 I I I I I I I 4 j t l l I 2lI IlIIl l I a al U I I I i I K 1 I --t-1 I-- a I I--1I- ..... .. ...................

........4 ' .....,IIII2, ,K,2,*,*,t*IaI*I l I I I;! IIlIt I i i i i i i a a a a a t m I 2 II! i i 1 i i I I00 12 5 a .5 0 ,1 ..a: : .....I I .. ..1... I .. .2 .. ...~ i i i I ll aii i i iai i I I I II 1 I Il l i l l l l l/ / 1 1 1 11 1Il l l l1/ I II...1 1I ._ , , ....! I I I I /I i i i i i i i i i i 1 1 0 i i i 1 i i i i I I I I I Ia nIi a1 1 I I I I I I 11 liii !1

.1 1111I 1 i 1 i i i i i i iai i1I a a ......I I a a a a ,,. a a .a.a.a.a.a.a.a

I IIaIaI IaI IaIaI aI IaI Ia al l l a..., , ! I ,," , I I a a a a l I a I I1la.lal laimla.! I I ~ ~ a a a i l l l' al l Il lllam a m a I3l l i 1 i l l ,I K I a a I. .a. a--a-- : I I i i I a a a a I " I ' i l li 'a1 1a1 1 a1 a g all 1 1 1 11I a aI aI I II a a n a ai i a a a Ia a I I I I I I! ia aII li1 alal a l l l l Ii a i I ~ a a_ _ a a iI__ .aL2 .. ._L .J aI /a aal la aal la aal la aal a1a1a1a1a1a a tI -, , , , , , I I 3 , I , I I I.1._,<,-.0)-I',"-1 Cn-,.-t--I mr 0 6.0 4.0 0 10000 20000 30000 40000 Average Planar Exposure (MWDIMTU)50000 60000 70000 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE -TWO LOOP OPERATION ATRIUMTM-10 FUEL FIGURE 4.2-1,r-SI)Coz C:'(D7 Rev. 18 PL-NF-14-001 Rev. 2 Page 9 of 62 5.0 .MINIMUM CRITICAL POWER RATIO (MCPR)5.1 Technical Specification 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 MOPR 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 (ATRIUM T M-1O) shall be the greater of the Flow-Dependent or the Power-Dependent MOPR, depending on the applicable equipment operability status.a) Main Turbine Bypass I EOO-RPT I Backup Pressure Regulator Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOO to EDOC Figure 5.2-2: Power-Dependent MOPR value determined from BOO to EGOC b) Main Turbine Bypass lnoperable Figure 6.2-3: Flow-Dependent MCPR value determined from BOO to EDOC Figure 5.2-4: Power-Dependent MOPR value determined from BOO to EGOC c) EOC-RPT Inoperable Figure 5.2-5: Flow-Dependent MCPR value determined from BOO to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOG to EOO d) Backup Pressure Regulator Inoperable Figure 5.2-7: Flow-Dependent MCPR value determined from BOO to EDOC Figure 5.2-8: Power Dependent MCPR value determined from BOG to EDOC e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 5.2-0: Flow-Dependent MCPR value determined from BOO to EGG Figure 5.2-1 O:Power-Dependent MCPR value determined from BOO to EDO SUSQUEHANNA UNIT 1 TRM/3.2-10 SUSQEHANA UIT TRM3.2I 0 EFFECTIVE DATE 11/04/2015 Rev. 16 PL-NF-1 4-001 Rev. 2 Page 1 0 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 Averauqe Scram Time Fraction If the average measured scram times are greater than the Realistic Scram times listed in Table 5.3-1 then the MCPR operating limits corresponding to the Maximum Allowable Average Scram Insertion Time must be implemented.

Determining MCPR operating limits based on interpolation between scram insertion times is not permitted.

The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.

SUSQUEHANNA UNIT1 TRM/3.2-11 SUSQEHANA UIT TRM3.21 I EFFECTIVE DATE 11104/2015 Rev. i6 PL-NF-14-O01 Rev. 2 Page Ii of 62 Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-12 SUSQEHANA NIT TR/32I 2 EFFECTIVE DATE 1110412015 SSES UNIT 1 CYCLE 19 C'C c, z z zCA._E 0.0o 2.2 2,1 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 1.2 CD<)m Ill C)H rn ci H Ill 30 40 50 60 70 80 90 Total Core Flow (MLBIHR)100 110 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS 1 EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC)FIGURE 5.2-1-o "o n, I (.Q0* -< 0.... ..... .... ... ..... ...... .... .... .. .... ... ...... ...... ...... ... ........ , ... .. .. .. .. ... .. ,,,,, .. .. .. ........ ... .. 1 ... .. ..... ... ..... ... ............ .I J ... .... .,J , , = ... ... .

SSES UNIT 1 CYCLE 19 cj 0 z z C z H 1J 0.0 m 0 0" 20 30 40 50 60 70 80 90 100 Core Power (% RATED)MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOO TO EOC)FIGURE 5.2-2"13 -OI-(3 " I i --.n Rev. 16 PL-NF- 14-001 Rev. 2 Page 14 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT1 TRM/3.2-15 SUSQEHANA UIT TRM3.2l 5 EFFECTIVE DATE 1 1/04/2015 0 SSES UNIT 1 CYCLE 19 03 C z C z-1 H.0J o-01 2.2 2.1 2.0 1.9 1.8'1.7 1,6 1.5 1.4'1.3 1.2 LEGEND-CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 I EEENCE:_T.S.

3.7.6 and 3.2.2 ___________

__________-I"I---m Hr iii--t 30 40 50 60 70 80C Total Gore Flow (MLB/H-R)MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC)FIGURE 5.2-3 I0 100 110"D " ,.-4 < 0 Q)"*

SSES UNIT 1 CYCLE 19 CI, C Ci, C mR c Z-t 3.6-H-.4.E_0 O.-11"51 m-H<m Fi (73$o z3 51 CD-Z 77 20 30 40 50 60 70 80 90 Core Power (% RATED)100 MCPR OPERATING LIMIT VERSUS CORE POWER*MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC to EOC)FIGURE 5.2-4-U CD--h 0)

Rev. 16 PL-NF-14-001 Rev. 2 Page 17 of 62 EOC-RPT Inoperable SUSQUEHANNA UNIT 1 TRM/3,2-18 SUSQEHANA UIT TRM3.2I 8 EFFECTIVE DATE 11/04/2015 SSES UNIT 1 CYCLE 19 CD 03 C m=C z-H-4.C0 E L.0.o 2.2 2.1 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 1.2 4.ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I I IJ USED IN DETER[MIN1NG MFLCPR I

REFERENCE:

T.S. 3.3.4.1 and 3.2.2 CD-3.C)-rr--Il<r m m U 30 40 50 60 70 80 Total Core Flow (MLBIHR)90 100 110 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC)FIGURE 5.2-5 0""

SSES UNIT 1 CYCLE 19 ci C I z z z 0 E 0 (D C)m n-I 0 H m 0n-20 30 40 50 60 70 Core Power (% RATED)MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC to EQO)FIGURE 5.2-8 80 90 100Z O-" -1 Rev. 16 PL-NF-14-0O1 Rev. 2 Page 20 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-21 SUSQEHANA NIT TR/3.-21 EFFECTIVE DATE 11/04/2015 SSES UNIT 1 CYCLE 19 Cn m z C z I-0 10.2.2 2.1 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 LEGEND_______ ______ -CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME________ -CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME_______ _______ -SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 A BI 0, m"1 rri 0 m 0 0 o',

IREFERENCE:

TS. 3.7.8 and 3.2.2~I-~ { 4 1 ~~-f 108, 1.221 1.2 30 40 50 60 70 80 Total Core Flow (MVLB/HR)90 100 110 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EQO)FIGURE 5.2-7"-D "-"'.)<c 0 0)"

SSES UNIT I CYCLE 19 60 C z-Il'i,, m o1-L 0,.2 CD C-3.0)100,1.35 20 30 40 50 60 70 80 90 Core Power (% RATED)100 MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOO to EOC)FIGURE 5.2-8 T1 T1Z~-,h .0 0)' ,C Rev. 16 PL-NE-14-001 Rev. 2 Page 23 of 62 One TSV. or TCV Closed SUSQUEHANNA UNIT 1 TRM/3.2-24 SUSQEHANA UIT ITR IS. -24 EFFECTIVE DATE 11104/2015

-r" NJ U'.4-E2 C., 2.2 2,1 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 1.2 SSES UNIT 1 CYCLE 19 I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME_______ _______ -CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 130, 1.831 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES I ARE OPERABLE PER SR 3.7.5.1 AND 3.7.6.2_ USED IN DETERMINING MFLCPR

REFERENCE:

T.S. 3.2.2 and TRM 3.3.71_ _ I _ I_ _ _ _ _ _ _ _ _ _CD m-I-1 m 0 I-4 m 0 N)30 40 50 60 70 Total Core Flow (MLBIHR)80 90 100 110 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED*TWO LOOP OPERATION (BOC TO EOC)FIGURE 5.2-9*Operatofl with one TSV or TCV closed is only supported at power levels -<75% rated power.CD Z-,-<0 SSES UNIT 1 CYCLE 19 cj C m--z C z-I S 0.-0m CD m-n m m C)-9 20 30 40 50 60*Core Power (% RATED)MCPR OPERATING LIMIT VERSUS CORE POWER*ONE TSV OR TCV CLOSED TWO LOOP OPERATION (BOC TO EOC)FIGURE 5.2-10 70 80 Co I Rev. 16 PL-NF-14-O01 Rev. 2 Page 26 of 62 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)Position 45 0.470 0.520 39 0.630 0.860 25 1.500 1.910 5 -oo70 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 1 SUQEAN NTITRM/3.2-27 EFFECTIVE DATE 11/0412015

1. ...1 I * ...A... ..--- a L.~cgaa. ... .. * .1 L. * -- ..*... ..&. aaau I 1S a. .....aJ L&...aa......a..n.

Rev. 16 PL-NF- 14-001 Rev. 2 Page 27 of 62 6.0 LINEAR HEAT GENERATION (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 ATRIUMTZ-I 0 fuel shall not exceed the LHGR limit determiined 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 Uimit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multipiier b) Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier c) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 6.2-6: Flow-Dependent LHGR Limit Multiplier Figure 6.2-7: 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 LHGR limit multipliers in Figures 6.2-1 through 6.2-7 are valid for both Two Loop and Single Loop operation.

SUSQUEHANNA UNIT 1 TRM/3.2-28 SUSQEHANA NIT TRI3.-28 EFFECTIVE DATE 11/04/2015 SSES UNIT 1 CYCLE 19 C,)C Co 0 C m=z z C z H N)N)Co 4" La-2 0 Cu C a'a" Cu a-0 V CD 4-a 0 0 I-0 ali C 16.0'14.0 12.0 10.0 8.0 6.0 4.0 a a a a a a I i I i I i I I i!I I I i I i ii ili iI a a a a la l a a l la l a l I El ' I* I 11111 i!i I i I ii al lala ala a alalala alIlal al a la aa a a a a L +/- Z .... L 1 --.....t....J......-

-0.,3. ----f=--I--+ I 900 4 ,-I--S-I--..

..J- REFERENCE; T.S 3.2.3 L --i --I I I a a a. a ..a ..a ..a ..a .I & a I 1 a a a a aI IaI-aI IaIaI IaI a I al l al lalal lala I I I I ~ l i alala alalalala a n a a a a a[ a aI a al a a. .a a a a la i a I Ia a a a I I a la alaa a la l a .a .a a l la aal ....1I t. t. .1 I .. ... ... ..... .. .aI Ial lal la"1a1 1ajj ~ I i jII !i i l al a lala alalal aI a i l /aa a a a a a1 1 a a1 a ..a. a. a a a a, a a Iaf a a a I at aIa aI a a.a.a. a. a aIa a ala aIala ii l l l al al l al a l I I I I I I I I I 1 1 11 1 11 1 ~ a a a a. I I I I I I I I I I I a I I a~II Ia aaI Ia a aaI l a a al II I l lall l la lalala al iala aialaIa a a- a- aI -- --a aI 4 a-- a a- a a-- a- a a a a I I a a a4 --ta al l a al la al aI a a aIaa a aI IIaa aI IaI Ia a I Il aa a a a a a a a a Ia Ia atai i iiaa a a ,a a a a a ,a a a , , a Ia a l a a alalI a aia a a a a a a a a a a a a a a a l a a a a a a .a ..a.a a .a .a a a a a a a a a a a a Ia aIa a a aI a a.. ..a a aI a Ialal al i lalalala a a alal aI I a a a1 I l l l l l l l1-Ta-TaII I I-I I-yi rw- l l l- ...al lalala a a ai la. alal a a a a l ia l la la a la l la l a a i a a a la a a a a a a a"a a a a a a a a a a a a a a l a a a i aI a I Ia I Ia I a a Ia a Ia a a a la a a l la l la a a l a Ia a la a la a a a l I I I Ill I I I a iII I Ia Il I lll Ial a lI ll l a 1 l i l lI l .a. .a. al l 1 l 7 l iI al~ l l l l1l l l lal lal l lanl l l i I I I I I I I I I I I I I I I I I I I a.. .a.. .a a j , , I a , , t , ,I a a ,i I, a a I !1 1 1 1 1 1 11 1111 ai a a a a I a I a a a all lal al aI 1 CD C 0)m m-I-rn<-H C H rr-I-0 10000 20000 30000 40000 50000 Pellet Exposure (MWDIMTU)60000 70000 80000 UNEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE ATRIUM T M-10 FUEL FIGURE 6.2-1 T-0 " Oco a -0")' 0 Rev. 16 PL-NF-'I4-001 Rev. 2 Page 29 of 62 Main Turbine Bypass Operable SUSQUEHANNA UNIT 1 TRM/3.2-30 SUSQEHANA NIT TR/3.-30 EFFECTIVE DATE 11/04/2015 SSES UNIT 1 CYCLE 19 C,, Co z z-I ('3 ('3 1.10 1.00 0.90-I--._1 a, 0.80 0.70 0.60 0,50 0.40 0.30<D._)-n r-n m m-I m: 0)NJ 30 40 50 60 70 80 90 100 Total Core Flow (MLB/hr)110 FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS OPERABLE FUEL FIGURE 8.2-2 (03 SSES UNIT 1 CYCLE 19 C m3 T"-I k C)H.-.03 N,3 0 1.10"" 'U"' ...........

" ' *L I & m L 4 4 A A i i.. .. ... " ' ' t I " I I I LEGEND i i----,-------~.------.I-------, 9 Fji o I--,.I 0.0 1.00 0.90 0.80 0.70 0.60 CURVE A: BASE CURVE CURVE B: CORE POWER __26% AND CORE FLOW <_.0 MLBM1HR T r I --- -... .-I --- -* I I S 1 31 1 I j. a I I I I a I i I I II

l l I I i [ a I li l i I I I IIS I .1 z*. _ _ _ _ _ ._ ..IJ .1_J _ _ J. _ '- 1 ; _1 J LI .I I I I I 1 1 5 I I I I 1 I I I I I I I l ARE OPRAL PE SR I... ANI37l....._ 1. ._ ._ ........./II I I 1 I ___ _ _ ___ ___ __ ___ ___ ___..,. .IL.__J._.I

..-1 REOERABENCE:

TSR 3.2.3,1 3.A4N an 3.7.6 8 I H ; / I i i i_ _ 1 ,,_,, 1_-0.50 -iL I yr i!I" '-- ' "" "- -! ... .... .. .... .-. -- -'- --l .----; ' .. ..l 26 04 0.40 0.30-- I -" -I -'-I.... .. F --' l ---- -----l- -- -t ----f -----d --II I I I I I I / 3I I I 23 0.0. I... I , ~ , I , , I , I , i I I I I I I I I I I I! J ,, IJ, I I I I I r I I I I I I I -3 I I I I I II r I I 1 2,0 30 40 50 60 Core Power (% RATED)70 80 90 100 POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS OPERABLE FUEL FIGURE 6.2-3 o ,z Rev. 16 PL-NF-14-O01 Rev. 2 Page 32 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT I TRM/3.2-33 SUSQEHANA NIT TR/3.-33 EFFECTIVE DATE 11t10412015 SSES UNIT 1 CYCLE 19 Co I z C: Z.-I C;, C),.1.10 1.00 0.90 0."-J._0, 0)03 0o Ct 0.80 0.70 0.60 C;o 0.50 m C)-H m1 0 H-1 m]01 0.40 0.30 30 40 50 60 70 80 90 100 Total Core Flow (MLB/HR)110 FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE ATRIUMTMea-t FUEL FIGURE 6.2-4"0 nD C.D 0O"-z-Il 0 SSES UNIT 1 CYCLE 19 CO, C 03 m=z z C z--I!: 1'3 1.10 a...5..5 0-I a, a, 0 I..a)0 0.oD m m 0.-I m 0 4>--I, 01" C?20 30 40 50 60 70 80 90 100 Core Power (% RATED)POWER DEPENDENT LH-GR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE ATRIUMTM.-10 FUEL FIGURE 6.2-,5 Co Rev. 16 PL-NF-14-00l Rev. 2 Page 35 of 62 One TSV or TCV Closed SUSQUEHANNA UNIT 1 TRM/3.2-36 SUSQEHANA NIT TR/3.-36 EFFECTIVE DATE 11/04/2015 0 O SSES UNIT 1 CYCLE 19 C i"1 C z-H1",4 a,-_J CD U..1.10 1.00 0.90 0.80 0.70 0.60 CD 0.50-T1-IT m m 0 rl3 0 0.40 0.30 30 40 50 60 70 80 90 100 Total Core Flow (MLB/hr)110 FLOW DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED*ATRIUMTM-t10 FUEL FIGURE 6.2-6*Operation with one TSV or TCV closed is only supported at power [evels 75% rated power.0-" 0 D' I, -=n ,, n SSES UNIT 1 CYCLE 19 C', C 03 m C z--I C,)cc 13{.i ,-J.1_0 0L 0)mT"rn ml 0<m1 H3 rn-I 20 30 40 50 60 70 Core Power (% RATED)80 POWER DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED ATRIUMTM-10 FUEL FIGURE 6,2-7 CD Z*i --nc Rev. 16 PL-NF-14-OO1 Rev. 2 Page 38 of 82 7.0 ROD BLOCK MONITOR (RBM SETFOINTS 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 I) High Power Range -Upscale shall be established as specified in Table 7.2-1. The RBM setpoints are valid for 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.SUSQUEHANNA UNIT 1 TRM/3.2-39 SUSQEHANA NIT TRIS.-39 EFFECTIVE DATE 11/04/2015 Rev. 16 PL-NF-14-001 Rev. 2 Page 39 of 62 Table 7.2-I RBM Setpoints Allowable Nominal Trip Function Value(1) Setpoint 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 117.4 117.0 High Power Range -Upscale 107.6 107.2 (1) 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)> 28 andc<90 < 1.76~90 and <95 <1.47>_95 < 1.70 (2) Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable.

(3 Applicable to both Two Loop and Single Loop Operation.

SUSQUEHANNA UN]T 1 TRMI3.2-40 SUSQEHANA NIT TRI3.-40 EFFECTIVE DATE 11/04/201 5

Rev. 18 PL-NF-1 4-001 Rev. 2 Page 40 of 62 8.0 REGIRCULATION 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 Req~uirements Manual Reference Technical Requirements Manual 3.3.7 8.3 Description APLHGR The APLHGR limit for ATRlUMTM-I 0 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.

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 T M-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 BOC to EOC Figure 8.2-3: Power-Dependent MCPR value determined from BOC to EOC b) Main Turbine Bypass [noperable Figure 8.2-4: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-5: Power-Dependent MCPR value determined from BOC to IEOC c) EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOG to EOC Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC SUSQUEHANNA UNIT 1 TRMI3.2-41 SUSQEHANA NIT TRI3.-41EFFECTIVE DATE 11/04/2015 Rev. 18 PL-NF-14-OO1 Rev. 2 Page 4l of 62 d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow-Dependent MCPR value determined from BOO to EGOC Figure 8.2-9: Power-Dependent MCPR value determined from BOO to EDO e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 8.2-1O:Flow-Dependent MOPR value determined from BOO to EDO Figure 8.2-11 :Power-Dependent MOPR value determined from BOO to EOC The MOPR limits in Figures 8.2-2 through 8.2-1 1 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 andOperabilityRequirem~ents The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0.SUSQUEHANNA UNIT 1 TRM/3.2-42 SUSQEHANA NIT TRI3.-42 EFFECTIVE DATE 1110412015 C 16.0 T T T r T ~ T ~ u 1 1 ~ I r QI I I ' I I l Il l t I I la 1 l l i0 9 1 'I E lI I I l l Ii l llI lI lz. .1. .11 1. ..II II1lIti1 1 I, I I I I,. i s i r i m i .m m m ii.m n l4...4 mm~~u mm.4.*" I1 I 1I 1 I i l I IlC Il l i l IlIII1I I1I1 1 Il l l ~l t l I! ~ l l l O l 1 1 I I I l I I I I Ii ~l l I I l1 1 1I tltitjilt SED IND*ERINIG0--J- I---. ii! .--I --I-I I-- j--i-..J..-,Lf lf...f I I1 1'I Ii I I I II£ I 1 I I I 1 I1 1 1 I1 1 1 1 1 I I I 1 II I I IIlli l l I I I I I 0l3l l l l l l l I 1 1= Ioo , I IO ll .I I, , 1I II I II I I I I I I I I I I 3 l l l I [ II IIII II Il l l lI I 1 1 1 I mI.._1111l1 I I lllll1 :11! l111 l1!. 1 l11l Iiii II ! II 11 11 lll ll l Il I ll HI l l l l I I l l l l~ll l li l l l:l l1 :l l l l I I I I , I , I I I I" I I I , I , , I I 1 67000,5.6 1o 1 1111 11 1 Il liIljlIlIIIIIl l l ll II Ill l l l l I l l I I Il l 4.0 L U' i41-- LI4l2 M --L --~L- AJ-J ...........

L..L ... -- , I , ,. , I 0.0 l1000. l 2000.0 ll 000. 4000.08000.06000.07000.-L~l l l l l l l lI l l i l l Averag PlanalEpour MWIMTU)l o = a l l l l l l l l2l l l i t l l A Ca ' I I I I l ..AVRAEPLNR INA HA GENERATION RAELMITlERSUtll o AERAE PANA EPOSRE..SIGL.LOP.OERAIO ATRIUMTMAOll FUELll l owlll l FIGURE 8.2-1ll l l l l l l lI I...... , , ..... ........ .... ..... .. .......................

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

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

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

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

.........

....... ...... ... .. i, .... .. ... ... ... .... .. .

Rev. 16 PL-NF.-14-001 Rev. 2 Page 43 of 62 Main Turbine Bypass I EOC-RPT/I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-44 SUSQEHANA UIT TRM3.2-44 EFFECTIVE DATE 11/0412.015 9 SSES UNIT 1 CYCLE 19 m z z C z H0 4-.D.1 o~0, 0 3.6 3.4 3.2 3.0 2.8 2.6 2.4 2.2 2.0'.8 1.6'1.4 I I 4. a-LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME+ I 4-t 1--i.m I I I I I ..I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.t AND 3.7.6.2 K I I I Ii L USED IN DETERMINING MFLCPR

REFERENCE:

" T.S. 3.4.1 and 3.2.21 1 08, 1.49'i'1-m rI, H-m 0 1N1 0 30 40 50 60 70 80 Total Core Flow (MLB/HR)90 100 110 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS 1 EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8.2-2 Co 9 0 SSES UNIT I CYCLE 19 o0 z Ho N)0)S 03 0 4.6 4.4 4.2 4.0 3.6 3.4 3.2 3.0 2.8 2.6 2.4 2.2 2.0 1.8 1.6 1.4___ LEGEND________CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM____INSERTION TIME____________CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME~-CURVE C: CORE POWER _< 26% AND coRE FLOW 50 MLBM/HR__ ------!SAFETY ANALYSES ASSUME THAT F~OUR BYPASS VALVES--fl ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2_____USED IN DETERMINING MFLCPR_ _ 1.CD 0);-Iil m 0 Hr o mn f ,4 140. 2.08!4 -.--------

~ I"t 100, 'F .. ... ... .t REEEC: T.S. 3.4.1 and 3.2.2 "Z 20 2040 50co RAE70 80 90 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8.2-3 100"0 " CD°< IO 0)' C Rev. 16 PL-NF-14-OO1 Rev. 2 Page 46 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT1 TRM/3.2-47 SUSQEHANA NIT TR/3.-47 EFFECTIVE DATE 1110412015 C'C-z z z H0 co3 4.2 4.0 3.8 3.6 3.4 ,4D 3.23.0 0 2.4.SSES UNIT 1 CYCLE 19 I I II________ _______ ________ LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM-INSERTION TIME________________CURVE B: REALISTIC AVERAGE SCRAM iNSERTiON TIME-SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS -VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2-1

REFERENCE:

T.S. 3.4.1, 3.7.6,, and22 -- _,118 ._ _ _ _ _ I _ _ _-_-_-_CD 0)m"I1 m 0 m m 0-J.2.2 2.0 1.8 1.6 1.4 30 40 50 60 70 80 Total Core Flow (MLB/HR)90 t00 110 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8,2-4 CD Z o)" 0 C, C-Cin z z Z-I 123,4A41 SSES UNIT I CYCLE 19-I C~)N)CO.1.a E Cu I-w 0.0 a.0 4.2 4.0 3.8 3.6 3.4 3.2 3.0 2.8 2.6 2.4 2,2 2.0 1.8 IllF~, 3,61 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER_ 26% AND CORE F~LOW _<50 MLBMIHR____________

4-.t-l 1I~Z~38 I m I--.*- 4. I-I ISAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6,2"1 " I m * =* *_____ USED IN DETERMINING MFLCPR 1~oi .41 ______ _ ________

REFERENCE:

T.S. ,3.4.1, 3.7.6, and 3.2.2 ..CD 0)m 0r-I N)20 30 40 6060 o70 50Core Power (%o RATED)MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8,2-5 80 90 100"0 "T CD Com I.CD ow.h. h< .-

Rev. 16 PL-NF-14-O0l Rev. 2 Page 49 of 62 EOC-RPT Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-50 SUSQEHANA NIT TR/3.-5OEFFECTIVE DATE 11/0412015 p m z z C z-1 N, 0I E ,U I-4, 0.0 4.0 3.8 3.6 3.4 3,2 3.0 2,8 2.6 2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 1 CYCLE 19 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM~________________INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVESl-ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR

REFERENCE:

T.S 3..,.341 and 3.2.2 _ "_-_-_-[_08t" 0)m 0<m 030 40 50 60 70 80 9 Total Core Flow (MLB/HR)MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8.2-6 t0 100 110,I--Q* .:

SSES UNIT 1 CYCLE 19Cbz.-I C.'N)C,'C., CD 0)'-I"1['11-IT m 1-1 m 0,-20 30 40 5060 70 80Core Power' (% RATED)MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8.2-7 80 90 100-U Co ow'-D z ,C 0 Rev. 15 PL-NF-14-OO1 Rev. 2 Page 52 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-53 SUSQEHANA NIT TRIS.-53 EFFECTIVE DATE 11/04/2016 SSES UNIT I CYCLE 19 C', CO m z C zS C C)a.0 0~C, 4.0 3.8 3.6 3.4 3.2 3.0 2,8 2,6 2.4 2,2 2.0 1.8 1.6 1,4 ALLOWABLE AVERAGE SCRAM INSERTION TIME I: REALISTIC AVERAGE SCRAM INSERTION TIME I .4 4.-V 2 f , , ..,I.,,.I,, I , " " SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR I I I I A-__---_ _ _ ___ __ B._

REFERENCE:

T.S. 3.4.1, 3.7.8, and 3.2.2[ ____.__ .. _. _ _ .J._108, 1.48 CD r-n-n'rni m 0*30 40 50 60 70 80 90 Total Core Flow (MLBJHR)MOPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC to EGOC)FIGURE 8.2-8 100 110 w r 01 0O" 0' I ....... .... ....... " ..............

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

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

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

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

.. .. .. ..= ..... " L ............

.....

SSES UNIT 1 CYCLE 19 CD CC m-i-z z C m m.-I m J\)0J E 0.=0)O-4.4 ---- LEGEND 4.2 CURVE A: MAXIM____ ___ _ __ ___ ___INSERi 4.0 CURVE B: 3._____,_.__1CURVE C: CORE 3.0 26.01, 2.90 2.6 A 2.2 2.0 1.8

REFERENCE:

T.S. 3.4.1, 3.7.8, and 3.2.2J11ii 1.4 20 30 40 60 ...I I I rY ANALYSES ASSUME THAT FOUR BYPASS VALVES l---ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2" 'I-UM ALLOWABLE AVERAGE SCRAM nION TIME STIC AVERAGE SCRAM INSERTION TiME POWER < 26% AND CORE FLOW < 60 MLBMIHR USED IN DETERMINING MFLCPR CD*1*60, 2.18 1100 " 4 4 -1...60 ... .. ..70 80 90 100 uore r'ower rio KAI i )uJ MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOO to EOC)FIGURE 8.2-9 CD"11 (:I' .Q DO O--

Rev. 16 PL-NF-14-001 Rev. 2 Page 55 of 62 One TSV or TCV CloSed SUSQUEHANNA UNIT 1 TRM/3.2-56 SUSQEHANA NIT TR/3.-56 EFFECTIVE DATE 11/04/2015 S SSES UNIT 1 CYCLE 19 0o C-i-z z zE 0.0-C, 3,6 3.4 3.2 3.0 2.8 2.6 2.4 2.2 2.0 1.8 1.6 1.4 rri"11 m m r'ri Ccj 30 40 50 60 70 80 90 100 Total Core Flow (MLB/HR)110 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED*SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8.2-10* Operation with one TSV or TCV closed is only supported at power levels -< 75% rated power.o ,-n o~

0 SSES UNIT 1 CYCLE 19 oi)m z z C z 4.6I 4.4 LEGEND 4.2 ______ CURVE 4.0 CURVE E 23 .61 23,3.7 CURVE c I I IMAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3: REALISTIC AVERAGE SCRAM INSERTION TIME.: CORE POWER < 26% AND CORE FLOW < 50 MLBM/HR--CJ1 CD C,i 3.6 3.4 3.2 3.0 2.8 2.6 2.4 2.226, 3.56-" tt C......SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES t 26,C 3.33 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2___________USED IN DETERMINING MFLCPR__ _ _ _ _ _ _ _ _ __ _ _ _ _6,19_________

6.01, 2.40_____

_________

-519 0).-.n m 01 2.0 1.8 1.6 1.4 20 30 40 50 60 Core Power (% RATED)MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8.2-11 70 80-0 7ci w"I-0)' i jq L ..... ....... ....... .... ............

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

........ T .. .. .............

.... ...... ... ... .... -:-.! .. ... .=

Rev. 16 PL-NF-14-OO1 Rev. 2 Page 58 of 62 9.0 POWERI/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 Stability Regions I and II of the Power/IFlow map, Figure 9.1.If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power! Flow map is considered an immediate exit region.If the OPRM Instrumentation is inoperable perT"S 3.3.1.1, Region I of the Power!Flow map is considered an immediate sca region.Region Il of the Power!/Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation.

SUSQUEHANNA UNIT1 TRM/3.2-59 SUSQEHANA NIT TR/3.-59 EFFECTIVE DATE 11104/2015 Rev. 16 PL-NF-14-O01 Rev. 2 Page 59 of 62 120 110*100 9o.Purpose: InitialI/Date: " I120 1100 90 80 L.0 fi-70 60 50 40 30 If 201 10 0 10 20 30 40 50 50 70 80 90 Total Core Flow (Mlbmlhr)(for SLO <75% Pump Speed Use Form GO-100-009-2)-H-I-I-4--]l- 100 110 Figure 9.1 SSES Unit 1 Cycle 19 Power/IFlow Map SUSQUEHANNA UNIT 1 TRM/3.2-60 SUSQEHANA NIT TR/3.-60 EFFECTIVE DATE 11104/2015 Rev. 16 PL-NF-14-001 Rev. 2 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 stability related power oscillations while providing a high degree of confidence that the MCPR Safety limit is not violated.

The setpoints are described in Section 2.0 and are fisted below: SF = 1.11 Np = 15 Fp = 60OMlbm /hr SUSQUEHANNA UNIT !TRM/3.2-61 SUSQEHANA UNT I RM/32-61EFFECTIVE DATE 11/04/20 15 Rev. 16 PL-NF-14-001 Rev. 2 Page 61 of 82

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 I and 2, "RQDEX2 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, "ATRlUMW-10:

Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.4. XN-NF-84-105(P)(A), Volume 1 and Volume I Supplements 1 and 2, lJXCOBRA-T:

A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," Exxon Nuclear Company, February 1987.5. XN-NF-80-19(P)(A), Volume 1 and Supplements I and 2, "Exxon Nuclear Methodology for Boiling Water Reactors:

Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983.6. XN-NF-80-19(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors:

EXEM BWR ECCS Evaluation Model, t' Exxon Nuclear Company, September 1982.7. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987.8. XN-NF-80-1 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 1 and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors 1" November 1990.11. NE-092-001A, Revision 1, "Licensing Topical Report for Power Uprate With increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993).12. ANF-89-98(P)(A)

Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.SUSQUEHANNA UNiT1 TRM/3.2-62 EFFECTIVE DATE 11/04/2015 Rev. 16 PL-NF-14-001 Rev. 2 Page 62 of 62 13. EMF-22O9(P)(A), Revision 3, "SPCB Critical Power Correlation," AREVA NP, September 2009.14. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A),"RQDEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Siemens Power Corporation, February 1998.15. EMF-2168(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors:

Evaluation and Validation of CASMO-4/Microburn-B2," Siemens Power Corporation, October 1999.16. 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. ANF-913(P)(A), Volume t 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-1 358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005.SUSQUEHANNA UNIT1 TRM/3.2-63 SUSQEHANA NIT TR/3.-63 EFFECTIVE DATE 11/04/2015 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 I and 2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Two of eight stop valves A. 1.1 Close one of the inoperable 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and control valves valves.inoperable.

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 Isolate main turbine from the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months steam supply.(continued)

SUSQUEHANNA-UNIT1 TRM / 3.3-17 SUSQEHANA-UITITRM 3.-17EFFECTIVE DATE 11/04/2015 Main Turbine Overspeed Protection System 3.3.7 Rev. 2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Two of twelve intercept B.1 Close either the intercept 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months valves and intermediate valve or the intermediate stop stop valves inoperable, valve within one of the affected combined intermediate valves.OR 8.2 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-UNIT1 TRM / 3.3-17a SUSQEHANA -UNI I RM I3.317aEFFECTIVE 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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 92 days running position and observe valve closure.-- -- 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.------...................

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

The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.3 Cycle each high pressure turbine stop valves 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 TEST visual and surface inspection of valve seats, disks and BASIS stems and verify no unacceptable flaws or corrosion.

SUSQUEHANNA-UNIT1 TRM / 3.3-18 SUSQEHANA UNT I RM 3.-18EFFECTIVE DATE 10/31/2007 Main Turbine Overspeed Protection System Rev. 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 o 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 I of the 2 overspeed protection systems is required for the Turbine Overspeed Protection System to be considered OPERABLE.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 if two 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 is not required to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety.(continued)

SUSQUEHANNA

-UNIT 1 TRM / B 3.3-14 SUSQEHANA -UNI I TM /B 3.-14EFFECTIVE DATE 06/25/2002 Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES (continued)

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

A.1.l, A.1.2, A.1.3 and A.2 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 if the 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 HP 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.(continued)

SUSQUEHANNA-UNIT1 TRM / B 3.3-14a SUSQEHANA-NITI TR / 3.314aEFFECTIVE 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 ACTIONS C.1 (continued)

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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months allows a reasonable amount of time to complete the plant shutdown associated with isolating the main turbine from the steam supply.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).(continued)

SUSQUEHANNA

-UNIT 1 TRM / B 3.3-14b SUSQEHANA-NIT TRM/ B3.314bEFFECTIVE 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 TRS TRS 3.3.7.4 (continued)

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.

TRS 3.3.7.5 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-UNIT1 TRM / B 3.3-14c SUSQEHANA -UNITI TR / 3.314cEFFECTIVE DATE 11/04/2015 Nov. 11, 2015 Page 1 of 2 MANIJAL HARD COPY DISTRIBUTION DOCUMENT TRANMSMITTAL 2015-45734 USER INFORMATION: