ML20097E377
| ML20097E377 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/18/2020 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PL-NF-18-003 | |
| Download: ML20097E377 (83) | |
Text
{{#Wiki_filter:IVlct.L * .1.0 1 L'.;U~U MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2020-4699 USER INFORMATION: GERLACH*ROSEY M Address: NUCSA2 Phone#: 542-3194 EMPL#: 028401 CA#: 0363 TRANSMITTAL INFORMATION: TO: GERLACH*ROSEY M 03/18/2020 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2) Page 1 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 MANUAL. TOOLS ~OM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ,..,.RRORS. ATTENTION: "REPLACE" directions do not affect* the Table _of Contents, Therefore no TOC will be issued with the updated material. TRMl - TECHNICAL REQUIREMENTS MANUAL UNIT 1 REMOVE MANUAL TABLE OF CONTENTS DATE: 03/11/2020 ADD MANUAL TABLE OF CONTENTS DATE: 03/17/2020 CATEGORY: DOCUMENTS TYPE: TRMl of 2
lld.L * ..LO I L; UL; V ID: TEXT 3.2,1 REMOVE : REV: 18 ADD: REV: 19 CATEGORY: DOCUMENTS TYPE: TRMl ID: TEXT B3.5.l REMOVE: REV: 1 ADD: REV: 2 Page 2 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS@ X3171 OR X3194 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. of 2
SSES MANUAL Manual Name: TRMl ~anual
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TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date: 03/17/2020 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 96 01/03/2019
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REACTIVITiY 'E_0NTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT \\ "')} "-.:::,/ TEXT 3.1.3 6 12/18/2017
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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 19 03/+ 7 /2020
Title:
CORE OPERATING.LIMITS REPORT (COLR) l?age 1 of 16 Report Date: 03/18/20
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TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.3.1 0 11/18/2002
Title:
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Title:
INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 2 11/09/2007
Title:
INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 11 06/29/2017
Title:
INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION _TEXT 3. 3.*5 0 11/18/2002
Title:
INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK "EXT 3.3.6 5 03/05/2019
Title:
INSTRUMENTATION TRM 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 INTENTIONALLY LEFT BLANK TEXT 3.3.9 3 04/17/2008
Title:
OPRM 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 2
- 04/02/2019
Title:
WATER MONITORING INSTRUMENTATION Page 2 of 16 Report Date: 03/18/20
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Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 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 INTENTIONALLY LEFT BLANK TEXT 3.4.3 1 11/09/2007
Title:
REACTOR COOLANT SYSTEM HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITORS TEXT 3.4.4 2 04/17/2008
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
- EXT 3.4.6 2
04/25/2013
Title:
REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT 3.5.1 2 03/05/2019
Title:
ECCS RPV.WATER INVENTORY CONTROL AND RCIC SYSTEM ADS MANUAL INHIBIT TEXT 3.5.2 2 03/05/2019
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ECCS RPV WATER INVENTORY CONTROL AND RCIC MONITORING INSTRUMENTATION TEXT 3.5.3 1 03/05/2019
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCI~ SYSTEM LONG TERM NITROGEN SUPPLY TO ADS TEXT 3.6.1 0 11/18/2002
Title:
CONTAINMENT VENTING OR PURGING .TEXT 3. 6.2 3 01/03/2019
Title:
SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKER POSITION INDICATION
- TEXT 3. 6. 3 0
11/18/2002
Title:
CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION Page 3 of 16 Report Date: 03/18/20
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Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.6.4 0 11/18/2002
Title:
CONTAINMENT PRIMARY CONTAINMENT CLO.SED SYSTEM BOUNDARIES TEXT 3.7.1 0 11/18/2002
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN TEXT 3.7.2 0 11/18/2002
Title:
PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL TEXT 3.7.3.1 5 02/13/2020
Title:
PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 3 04/16/2009
Title:
PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS ~EXT 3. 7. 3. 3 4 05/16/2016
Title:
PLANT SYSTEMS CO2 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 13 12/18/2017
Title:
PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION TEXT 3.7.4 1 04/26/2006
Title:
PLANT SYSTEMS SOLID RADWASTE SYSTEM Page 4 of 16 Report Date: 03/18/20
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Title:
TECHNICAL REQUIREMENTS 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
Title:
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:
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Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING ~EXT 3.7.8
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Title:
PLANT SYSTEMS SNUBBERS 03/05/2015 TEXT 3.7.9 3 03/05/2019
Title:
PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 1 12/14/2004
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS) TEXT 3.7.11 1 11/01/2018
Title:
STRUCTURAL INTEGRITY 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 PROTECTION - CONTINUOUS TEXT 3.8.2.2 2 12/14/2004 Page 5
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION~ AUTOMATIC of 16 Report Date: 03/18/20
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Title:
TECHNICAL REQUIREMENTS MANUAL 1JNIT 1 TEXT 3. 8. 3 4- .01/28/2020 .Title: ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT 3.8.4 0 11/18/2002
Title:
ELECTRICAL POWER 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT 3.8.5 1 11/14/2013
Title:
ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION TEXT 3.8.6 2 03/05/2019
Title:
ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8;7 1 06/15/2009
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM '?EXT 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 1 03/12/2019
Title:
REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 1 04/26/2006
Title:
MISCELLANEOUS SEAL SOURCE CONTAMINATION TEXT 3.10.2 3 06/19/2019
Title:
MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 3 10/17/2019
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) TEXT 3.10.4 2 04/17/2008
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Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.1.1 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CON.CENTRATION TEXT 3. 11. 1. 2 1 04/26/2006
Title:
RADIOACTIVE E.FFLUENTS LIQUID EFFLUENTS DOSE TEXT 3.11.1.3 1 . 04/26/2006
Title:
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Title:
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RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3. 11. 2. 2 04/26/2006
Title:
RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES TEXT 3.11.2.3 1
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Title:
RADIOACTIVE EFFLUENTS DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM TEXT 3. 11. 2. 4 0 11/18/2002
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 8
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Title:
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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 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS INTERLABQRATORY 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 LOAD$.REQUIREMENTS -:'EXT 3.12. 3 0 11/19/2002
Title:
LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENT TEXT 4.1 0 08/31/1998
- Title: ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 1
01/03/2019
Title:
ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION TEXT 4.3 1 01/.03/2019
Title:
ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION TEXT 4.4 ) 1 12/18/2008
Title:
ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT 4.5 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS REPORTING. REQUIREMENTS TEXT 4.6 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM Page 8 of 16 Report Date: 03/18/20.
SSES MANUAL Manual Name: TRMl ~1anual
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:l.1 2 04/29/2014
Title:
REACTIVITY CONTROL SYSTEMS BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE-ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.l.2 0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD DRlVE (CRD) HOUSING SUPPORT TEXT _B3.1. 3 4 12/18/2017
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD BLOCK INSTRUMENTATION
- EXT B3.l.4 0
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Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.l 0 11/19/2002
Title:
CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR)" TEXT B3.3.1 1 01/31/2014
Title:
INSTRUME~TATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 2 03/31/2011
Title:
.INSTRUME~TATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 3 12/18/2008
Title:
INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 7 06/29/2017
Title:
I~STRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT B3.3.5 2 11/09/2007
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TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.3.6 6 03/05/2019
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INSTRUMENTATION BASES TRM ISOL~TION ACTUATION INSTRUMENTATION TEXT B3.3.7 2 11/10/2015
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INSTRUMENTATION BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT B3.3.8 1 10/22/2003
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INTENTIONALLY LEFT BLANK TEXT B3.3.9 4 01/03/2019
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OPRM INSTRUMENTATION TEXT B3.3.10 3 08/09/2010
Title:
INSTRUMENTATION BASES REACTOR RECIRCULATION PUMP MG SET STOPS "'.'EXT B3. 3. 11 1 10/22/2003
Title:
INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3. 3. 12. 1 04/02/2019
Title:
WATER MONITORING INSTRUMENTATION TEXT B3.4.l 0 11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY TEXT B3.4.2 1 04/16/2009
Title:
INTENTIONALLY LEFT BLANK TEXT B3.4.3 1 11/09/2007
Title:
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REACTOR COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT*B3.4.5 0 11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS Page 10 of 16 Report Date: 03/18/20
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Title:
. TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.4.6 3 01/03/2019
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REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT B3.5.l 2 03/17/2020
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ADS MANUAL INHIBIT TEXT B3.5.2 2 03/05/2019
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ECCS RPV WATER INVENTORY CONTROL AND RCIC MONITORING INSTRUMENTATION TEXT B3.5.3 2 03/05/2019
Title:
ECCS RPV WATER INVENTORY.CONTROL AND RCIC SYSTEM LONG TERM NITROGEN SUPPLY TO ADS TEXT B3. 6.*l .o 11/19/2002
Title:
CONTAINMENT BASES VENTING OR PURGING ~EXT 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 B3.6.4* 1 12/14/2004
Title:
CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT B3.7.l 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 4 02/16/2017
Title:
PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT B3.7.3.2 2 04/26/2006
Title:
PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS Page 11 of 16 Report Date: 03/18/20
SSES MANUAL Manual Name: TRMl ~anual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT* 1 TEXT B3.7.3.3 1 01/03/2019
Title:
PLANT SYSTEMS BASES CO2 SYSTEMS TEXT B3.7.~.4 4 06/19/2019
Title:
PLANT SYSTEMS BASES HAL.ON* SYSTEMS TEXT B3.7.3.5 1 04/26./2006
Title:
PLANT SYSTEMS BASES FIRE HOSE STATIONS TEXT B3.7.3.6 1 04/26/2006
Title:
PLANT SYSTEMS BASES YARD.FIRE HYDRANTS AND HYDRANT HOSE.HOUSES TEXT B3.7.3.7 0 11/19/2002
Title:
PLANT SYSTEMS BASES.FIRE RATED ASSEMBLIES ~EXT B3.7.3.8 3 09/27/2012
Title:
PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION TEXT B3.7.4 0 11/19/2002
Title:
PLANT SYSTEMS BASES SOLID RADWASTE SYSTEM TEXT B3.7.5.1 0 11/19/2002
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT B3.7.5.2 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 B3.7.6 4 06/04/2013
Title:
PLANT SYSTEMS BASES ESSW PUMPHOUSE VENTILATION TEXT B3.7.7 2 01/31/2008
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION Page 12 of 16 Report Date: 03/18/20
SSES MANUAL Manual Name: TRMl. ~1anual_Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.8 4 01/31/2014
Title:
PLANT SYSTEMS BASES SNUBBERS TEXT B3.7.9 3 03/05/2019
Title:
PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1 12/14/2004
Title:
PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.7.ll 2 11/01/2018
Title:
STRUCTURAL INTEGRITY TEXT B3.8.l 2 03/10/2010
Title:
ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES ,EXT B3. 8. 2.1 0 11/19/2002
Title:
ELE_CTRICAL 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 AcrIVITIES 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 3 03/05/2019
Title:
ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 2 06/04/2013
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM Page 13 of 16 Report Date: 03/18/20
-SSES MANUAL Manual. Name: TRMl 'fanual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.9.l 0 11/19/2002
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REFUELING OPERATIO~S BASES DECAY TIME TEXT B3.9.2 0 11/19/2002.
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REFUELING OPERATIONS BASES COMMUNICATIONS TEXT B3.9.3 1 03/12/2019
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REFUELING OPERATIONS BASES REFUELING PLATFORM TEXT B3.10.l 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 ,EXT B3.10. 3 2 10/17/2019
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MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) TEXT B3.10.4 1 04/17/2008
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RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3.ll.l.4 0 11/19/2002
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RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.1. 5 0 11/19/2002
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- ssES MANUAL Manual NaI!le:
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RADIOACTIVE EFFLUENTS BASES DOSE RATE TEXT B3.ll.2.2 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES TEXT B3.ll.2.3 0 11/19/2002
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RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.ll.2.5
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BASES 2 07/03/2013 VENTILATION EXHAUST TREATMENT SYSTEM 09/08/2016 ':'EXT B3. 11. 2. 6
Title:
RADIOACTIVE EFFLUENTS INSTRUMENTATION BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING TEXT B3. 11. 3 0 11/19/2002
Title:
RADIOACTIVE. EFFLUENTS BASES TOTAL DOSE TEXT B3.ll.4.l 5 03/05/2015
Title:
RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3.ll.4.2 0 11/19/2002
Title:
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Title:
RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAM TEXT B3.12.1 1 10/04/2007.
Title:
LOADS CONTROL PRQGRAM BASES CRANE TRAVE.L-SPENT FUEL STORAGE POOL TEXT B3.12.2 1 12/03/2010
Title:
LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS IN Page 15 of 16 Report Date: 03/18/20
SSES MANUAL ~-. Manual Name: TRMl ~anual
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: 03/18/20
Rev. 19 Core Operating Limits Report (COLR) 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. APPLICABILITY: Specified in the referenced Technical Specifications. ACTIONS CONDITION A. Core Operating Limits not met. REQUIRED ACTION A1 Perform action(s) described in referenced Technical Specification. TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE
~---------------NOTE----------------------------------------
No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications. SUSQUEHANNA - UNIT 1 TRM / 3.2-1 COMPLETION TIME Specified in referenced Technical Specifications. FREQUENCY NIA
Rev. 19
- Susquehanna SES -
Unit 1 Cycle 21 PL-NF-18-003
- Rev. 1 Page 1 of 62 CORE OPERA TING LIMITS
- REPORT SUSQUEHANNA UNIT-1. TRM/3.2-2 Nuclear Fuels Engineering March 2020
Rev. Affected No. Sections 0 ALL 1 9.0 ALL Rev. 19 PL-NF-18-003 Rev. 1 Page 2 of 62 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Description/Purpose of Revision Issuance of this COLR is in support of Unit 1 Cycle 21 operation. Figure 9.1 is revised to account for the cycle achieving a greater core average exposure than what was assumed to initially analyze Unit 1 Cycle 21 (U1C21), addressing CR-2020-02163. Updated U1C21 licensing analysis results (Framatome, formerly AREVA, report ANP-3625, Rev. 1) at a bounding core average exposure only affects the Power/ Flow Map Region II Stability Boundary. Removed Effective Date from footer to align formatting to current process. _FORM NFP-QA-008-2, Rev. 2 SUSQUEHANNA UNIT 1 TRM/3.2-3 l
1.0 2.0 3.0 4.0 5.0 6.0 7.0 Rev. 19 SUSQUEHANNA STEAM ELECTRIC STATION Unit 1 Cycle 21 CORE OPERA TING LIMITS REPORT Table of Contents PL-NF-18-003 Rev. 1 Page 3 of 62 INTRODUCTION........................................................................-................................. 4 DEFINITIONS.......... :........ -.......................................................................................... 5 SHUTDOWN MARGIN.............. :.............. :*.................................................................. 6 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)........ _............... 7 MINIMUM CRITICAL POWER RATIO (MCPR)......... :................................................. 9 LINEAR HEAT GENERATION RATE (LHGR)............................................................. 27 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
11.0 REFERENCES
........................................................................................................,... 61 SUSQUEHANNA UNIT 1 TRM/3.2-4
Rev. 19 1,0 INTRODUCTION PL-NF-18-003 Rev. 1 . Page 4 of 62 This CORE OPERATING LIMITS REPORT for Susquehanna Unit 1 Cycle 21 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 NRG-approved methods and are established such that all applicable limits of the plant safety analysis are met.
SUSQUEHANNA UNIT 1 TRM/3.2-5
2.0 DEFINITIONS Rev. 19 PL-NF-18-003 Rev. 1 Page 5 of 62 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 LHGRFACf is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFACf multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from* core flows less than -108 Mlbm/hr. 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 MAP RAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided-by the APLHGR 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 / hr, below which the OPRM RPS trip is activated. SUSQUEHANNA UNIT 1 TRM/3.2-6
Rev. 19 PL-NF-18-003 Rev. 1 Page 6 of 62 3.0 SHUTDOWN MARGIN ~.1 3.2 References Technical Specification 3.1.1 Description The SHUTDOWN MARGIN shall be equal to or greater than: a) 0.38% ~k/k with the highest worth rod analytically determined b) 0.28% ~k/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 (BOC) SHUTDOWN MARGIN (SOM) tests must also account for changes in core reactivity during the cycle. Therefore, the SOM 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 bE3tween the calculated value of maximum core reactivity (that is, minimum SOM)' during the operating cycle and the calculated BOC core reactivity. If the value of "R" is zero (that is, BOC is the most reactive point in the cycle) no correction to. the BOC 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 1 TRM/3.2-7
Rev. 19 PL-NF~18-003 Rev. 1 Page 7 of 62 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)
- 4. 1 References 4.2 Technical Specification 3.2.1 Description The APLHGRs for ATRIUM'-10 fuel shall not exceed the limit shown in Figure 4.2-1.
The APLHGR limits in Figure 4.2-1 are valid in Two Loop Operation for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve {TCV) closed. The APLHGR limits for Single Loop operation are provided in Section 8.0. SUSQUEHANNA UNIT 1 TRM/3.2-8
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5.0 Rev. 19 PL-NF-18-003 . Rev. 1 Page 9 of 62 MINIMUM CRITICAL POWER RATIO (MCPRl 5.1 References 5.2 Technical Specification 3.2.2, 3.3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 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 (ATRIUM'-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/ EOC-RPT /Backup Pressure Regulator Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOC b) Main Turbine Bypass Inoperable Figure 5.2-3: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-4: Power-Dependent MCPR value determined from BOC to EOC c) EOC-RPT Inoperable Figure 5.2-5: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOC to EOC d). Backup Pressure. Regulator Inoperable Figure 5:2-7: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-8: Power Dependent MCPR value determined from BOC to EOC e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 5.2-9: Flow-Dependent MCPR value determined from BOC to EOG Figure 5.2-10:Power-Dependent MCPR value determined from BOC to EOC The MCPR limits in Figures 5.2-1 through 5.2-1 O are valid for Two Loop operation. The MCPR limits for Single Loop operation are provided in Section 8.0. SUSQUEHANNA UNIT 1 TRM/3.2-10
5.3 Rev. 19 Average Scram Time Fraction PL-NF-18-003 Rev. 1 Page 10 of 62 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 n*ot permitted. The evaluation of scram insertion time data, as rt relates to the attached table should be performed per Reactor Engineering procedures. SUSQUEHANNA UNIT 1 TRM/3.2-11
Rev. 19 PL-NF-18-003 Rev. 1 Page 11 of 62 Main Turbine Bypass./ EOC-RPT / Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-12
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REFERENCE:
T.S. 3.2.2" ~ 30 40 --...__ -~ 110s, 1.22 r 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2.:1
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REFERENCE:
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20 30 40 ~ 60 ro 80 90 100 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-2 ....i.. c.o
Rev. 19 Main Turbine Bypass Inoperable.
- SUSQUEHANNA UNIT 1 TRM/3.2-15 PL-NF-18-003 Rev.1 Page 14 of 62
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REFERENCE:
T.S. 3.7.6 and 3.2.2 I 1.3 1.2 30 40 50 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-3 100 110 co
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SSES UNIT 1 CYCLE 21 38 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.4 1--__.\\1,-1: 23, 3.42 1-----4-----1 INSERTION TIME \\'.. 1--~\\...--__.__.._ __ _--lCURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME j 26, 3.15 I I 23, 3.0311---1--==:::::::i===----1----1 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 3.0 '\\ 3.2 '§
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REFERENCE:
T.S. 3. 7.6 and 3.2.2:1--1------1------1-------1------1-----1 1.4 1-------1-------1------1------+------1------1-----~i--------, 1.2 L--------L------L-----.J---------L-------L...----..L..---------------' . 20 30 40 50 60 70 80 90 100 Core Power(% RATED) MCPR OPERA TING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS.INOPERABLE TWO LOOP OPERATION (BOC to EOC) FIGURE 5.2-4
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SUSQUEHANNA UNIT 1 Rev. 19
- EOC-RPT Inoperable TRM/3.2-18 PL-NF-18-003 Rev. 1 Page 17 of 62
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~ ~ ll. w N (.) I 2l: cp SSES UNIT 1 CYCLE 21 2.2 LEGEND 2.1 CURVE A: MAXIMUM ALLOWAB.lE AVERAGE SCRAM INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME - 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES - ARE OPERABLE PERSR3.7.6.1 AND 3.7.6.2 1.8 I USED IN DETERMINING MFLCPR 1.7 1.6 130, 1.531 1;5 1.4 ~----------- A B I
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 I 1.3 1.2 30 40 50 r----._ - I 108, 1.221 60 70 80 90 100 110 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE TWO l,OOP OPERATION (BOC TO EOC) FIGURE 5.2-5
- co
(I) C (I) 0 C m I
- i> z z
- i>
C z ....l. E
- i C)
C
- l cu...
Ill C.
- 0 0
s:: ~ c.. w N (.) I 2: N 0 SSES UNIT 1 CYCLE 21 36. I 3.4 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 JNSERTION TIME I 23, 3.03 i I 23, 3.06 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME ~ 3.0 ~ CURVE C: CORE POWER:;; 26% AND CORE FLOW:;; 50 MLBM/HR _ C J26, 2.931 \\ 2.8 126, 2.83 1 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7:s.1 AND 3.7.6.2 2.4 I I I I I USED IN DETERMINING MFLCPR [ 2.2 2.0 \\ 26.01, 11.97 \\ '- ~ 140, 1.731 11.8 A-B 1.6 ~
REFERENCE:
T.S. *3.3.4.1 and 3.2.2 ! r---__ 180, 1.431 I 100, 1.43 I 1.4 1.2 20 30 40. 50 60 70 80 Core Power (% RA TED) MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC to EOC) FIGURE 5.2-6 90
- 0.
(I) <.
Rev. 19 PL-NF-18-003 Rev. 1 Page 20 of 62
- Backup. Pressure Regulator*
Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-21
(/) 2.2 C en 0 C m 2.1
- c
- t> z z 2.0
- t>
C z =i 1.9 ~ .... *e 1.8
- J C')
C I'll... 1.7 -I (I) C.
- 0 0
~ ~ 03 ll. N (.) 1.6 I ~ N N 1.5 , 1.4 1.3 1.2 SSES UNIT 1 CYCLE 21 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 I I I I USED IN DETERMINING MFLCPR r 130, 1.531
~
r-----._ A B I
REFERENCE:
T.S. 3.7:s and 3.2.21 ~ r----_ 30 40 50 ~ r-----._ I 108, 1.221 r---.::- 60 70 80 90 Total Core Flow (MlB/HR) i\\llCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-7 100 .110
en C en 0 C m I )> z z )> C z -I .....l,. '§
- .::i C)
C i... -I (I) Q.
- o 0
§;: a: w Q. N 0 I
- i'1l:
N (.,.) SSES UNIT 1 CYCLE 21 36 3.4 LEGEND CURVE A: MAXI.MUM ALLOWABLE AVERAGE SCRAM 3;2 INSERTION TIME I 23, 3.03 I-~ 23, 3.os I. / CURVE B: REAL.ISTIC AVERAGE SCRAM INSERTION TIME 3.0 ~'- \\ "\\ 12s, 2.93 I CURVE C: CORE POWER:::;; 26% AND CORE FLOW :s; 50 MLBM/HR
- -- C
\\ 2.8
- 26, 2.83:
I I 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 'ARE OPERABLE PER SR 3.7.6;1 AND 3.7.6.2
- 26.01, 2.30 1 I
I I I 2,4 USED IN DETERMINING MFLCPR 140, 2.os 1 2.2 2.0 r-............. A -.............. i,,.,.._ 1.8 ~ ~ 1.S I 80, 1.48 I ~
REFERENCE:
T.S. 3.7.8 and 3.2.2! ~- 1.4 1.2 20 30 40 50 60 70 80 ~ore Power(% RATED)
- MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABllE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-8 90 [ 1100, 1.36 I 100 .....l,. c.o
Rev. 19 One TSV or TCV Closed SUSQUEHANNA UNIT 1 TRM/3.2-24 PL-NF-18-003. Rev. 1 Page 23 of 62
(/) C (/) 0 C m
- c
,)> z z )> C z -I '§
- J C'l C:
cu... -I (!) C.
- a 0
s:: et: 03
- a.
~ (.) I ~ N CJ'I SSES UNIT 1 CYCLE21 2.2 I LEGEND 2.1 CURVIE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 1.8 I I I I 130, 1.12j USED IN DETERMINING MFLCPR 1.7 1.6 1.5 1.4 1.3 1.2 30
..... ~
A B
r-----..__ ~
~ J
REFERENCE:
T.S. 3.2.2 and TRM 3.3.7 j 40 50 60 70 80 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW. ONE TSV OR TCV CLOSED* TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-9 90 100 I 108, 1.371
- Operation with one TSV or TCV closed is only supported at power levels S 75% rated power.
I co -a -a n> r (Q I CD z N 7! ~ ;::a...... 0 CD Cf ....,< 0 0). 0 N ......_ uJ
(J) C (J) 0 C m I )>
- z z
)> C z -I '§
- J C)
C: I:!! -I Cl) Q.
- a 0
s: ~ (.,.) ll. N (.) I 2: N. Q') SSES UNIT 1 CYCLE 21 3.4 I I I T .2 LEGEND 123., 3.061 123,3.031 ~ CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3*0 ~\\, I 26, 2.93 I CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
C
'\\ 3 2.8 I I , 26, 2.83, CURVE C: CORE POWER :S:: 26% AND CORE FLOW :s:: 50 MLBM/HR 2.6 I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE - 2.4 PER SR 3.7.6.1 AND 3.7.6.2 ~ 2.2 USED IN DETERMINING MFLCPR ~ 2.0 126.01, 1.97 I ~..,...... _ H ~ 1.8 I 40, 1.73 I 26.01, 1.89 I ~-............ A 'i.S 140, 1.641 175, 1.471 1.4 1.2 20 8 I
REFERENCE:
T.S. 3.2.2 and TRM 3.3.7 j 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 5.2-10 175, 1.431 70 80 -a -a ID r (0 I CD z N 7l 01 ;;o....>. 0 CD 'f -<o 0). 0 N....>.W
I. Rev. 19 Table 5.3-1 PL-NF-18-003 Rev. 1 Page 26 of 62 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod . Position 45 0.470 39 0.630 25 1.500 5 2.700 Average Scram Realistic Insertion Time SUSQUEHANNA UNIT 1 Average Scram Time to Position (seconds) TRM/3.2-27 0.520 . 0.860 1.910 3.440 Maximum Allowable I
6.0 Rev. 19 PL-NF-18-003. Rev. 1 Page 27 of 62 LINEAR HEAT GENERATION RA TE (LHGR)
- 6. 1 References 6.2 Technical Specification 3.2.3, 3.3.4.1, 3. 7.6, and 3. 7.8 Technical Requirements Manual 3.3.7 Description The maximum LHGR for ATRIUM'-10 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, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve {TCV) closed.
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 / EOC-RPT / Backup Pressure Regulator Operable Figure 6.2-2: Flow-Dependent LHGR Limit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multiplier b) Main Turbine Bypass or EOC-RPT or Backup Pressure Regulator 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 6.2-1 through 6.2-7 are valid for both Two Loop and Single Loop operation. SUSQUEHANNA UNIT 1 TRM/3.2-28
(./) C (./) 0 C m
- r::
)> z z )> C z -I 16.1[) 14.[) 12.IO 10.0 8.0 6,1[) 4.1[) 0 SSES UNIT 1 CYCLE 21 I I I I I I , I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I --T--~---r--,---r--T---.---r--,---r--T*--;---r--,---r--T**....--*T*-,---r-*T---r~-T--,---r-*T*-..,-*-r*-~---r--,---r--*T*-,---r--,---i---T**,--- 1 I I I I I I I I I I . J I I I I I I I I I I I I I I I I I i I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I o;o, '.13~ f1---f--J--+-f--J11~9~0. \\34 ~1---f-~--+--P-+-~--i : : : :R~F~R~N~E:: T~s.: 3.~.3: : : : ~- I I I I I I I I I I
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- 70000, 80000 Pellet Exposure (MWD/MTU)
LINEAR HIEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE . ATRIUM'-10 FUEL FIGURE 6.2-1 CD
Rev. 19 PL-NF-18-003 Rev. 1 Page.29 of 62 Main Turbine Bypass I EOC-RPT /. Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-30
Cl) C Cl) 0 C m I )> z z )> C z -I SSES UN!T 1 CYCLE 21 1.10.--r----.----,-----,---.---r---r---.------,----,----.---r---~---r----,-----r---. I I I I I I I 11.00 0.90 0.80 0.70 0.60 0.50 0.40 I I I I I J I I I I I I I I I I I I I I I I I I I I I I I I I I I g I I I I I I I I I I 1 I I I I I I I
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- 0) 0 N -'- w
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Rev. 19 One TSV or TCV Closed SUSQUEHANNA UNIT 1 TRM/3.2-36 PL-NF-18-003 Rev. 1 Page 35 of 62
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Rev. 19 PL-NF-18-003 Rev. 1 Page 38 of 62 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS. 7.1 References 7.2 Technical Specification 3.3.2.1 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 for Two Loop and Single Loop Operation, Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and,Inoperable, and with one Turbine Stop Valv~ (TSV) or Turbine Control Valve (TCV) closed.. 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
Rev. 19 Function Low Power Range Setpoint Table 7.2-1 RBM Setpoints Intermediate Power Range Setpoint High Power Range Setpoint Low Power Range - Upscale Intermediate Power Range - Upscale High Power Range - Upscale Allowable Value(1l 28.0 63.0 83.0 123.4 117.4 105.6 PL-NF-18-003 Rev. 1 Page 39 of 62 Nominal Trip Setpoint 24.9 61.0
- 81.0 123.0 117.0 105.2 (1l 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 and< 90 < 1.76 .:: 90 and< 95 < 1.47 ~95 < 1.68 (2> Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed. (3) Applicable to both Two Loop and Single Loop Operation. SUSQUEHANNA UNIT 1. TRM/3.2-40
8.0 Rev. 19 PL-NF-18-003 Rev. 1* Page 40 of 62 RECIRCULATION LOOPS ~- SINGLE LOOP OPERATION 8.1 References 8.2 Technical Specification 3.2.1, 3.2.2," 3.3.4.1, 3.4.1, 3.7.6, and 3.7."8 Technical Requirements Manual 3.3.7 Description APLHGR The APLHGR limit for ATRIUM'-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1. The APLHGR limits in Figure 8.2-1 are valid in Single Loop Operation for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine* Stop Valve (TSV) or Turbine Control Valve (TCV) closed. 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'-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 l 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 Inoperable 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 EOC c) EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow~Dependent MCPR value determined from BOC to EOC Figure 8.2-9: Power-Dependent MCPR value determined from BOC to EOC SUSQUEHANNA UNIT 1
- TRM/3.2-41
Rev. 19 PL-NF-18-003 Rev. 1 Page 41 of 62 e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 8.2-10:Flow-Dependent MCPR value determined from BOC _to EOC Figure 8.2-11 :Power-Dependent MCPR value determined from BOC 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 Setpoin_ts and Operability Requirements The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0. SUSQUEHANNA UNIT 1 TRM/3.2-42
CJ) C CJ) 0 C m I ):> z z ):> C z =i 14.l!ll 6.ID SSES UNIT 1 CYCLE 21 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I . I I I I I I I J I I I I I --+---~---~---~---~---~---:---...:.---~---~---~---~---~---~--...:---~---~---~---i---~---~--4---~---~---4---~---~---~---1---~---~---~---~---~--- I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I J I I l l l l l l l l l l l
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I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I. I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I ---l---i---~---f---t---t---~---1---i---i---f---t---t---~---l---i---~---1--- 1---~---l---i---i---f---t---t---~---~--i---i---{---t---t--- l I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
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Rev. 19 PL-NF-18-003 Rev. 1 Page 43 of 62 Main Turbine Bypass/ EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-44
(/') C (/') 0 C m I )> z z )> C z -I E
- i C)
C cu... -I Cl) C.
- a 0
~ ~ 03 ll. N (.) I 2: ~ CJ1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ SSES UNIT 1 CYCLE 21 3.0 LEGEND 2.8 CURVE A; MAXIMUM ALLOWABLE AVERAGE SCRAM
- INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.4 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.0 I
USED IN DETERMINING MFLCPR I I I 1.8 1.6 H3o, 1.ssl A B 1.4 1108, 1.251 1.2
REFERENCE:
T.S. 3.4.fand 3.2.2j '11.0 30 40 50 60 70 80 90 100 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OP_ERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-2. 110 c.o
(./) C (./) 0 C m
- r:
)> z z )> C z -I .....l,. 'i§
- i C)
C l'CS... -I Q) Q.
- 0 0
s:: 0:: c.. w .N (.) I 2 ~
- 0)
SSES UNIT 1 CYCLE 21 40. LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.S INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 3*2 c=;-J 23, 3.09 I I I 123,3.06:~ SAFETY ANAL VSEs* ASSUME THAT FOUR BYPASS VALVES 3*° C ~ J 26, 2.96 I ARE OPERABLE PER SR 3.7.6.1 AND 3;7.6.2. 2.8 J 2s, 2.86 USED IN DETERMINING MFLCPR 2.6 2.4 2.2 1 26.01, 2.00 I 2.0 ~ 140,1.76 A 1.8 -s --+- 'so, 1.61 ! 1.6 H
REFERENCE:
T.S. 3.4.1 and 3.2.2: I
- 1. 4 20 30 40 50 60 70 Core Power(% RATED) 80 90 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-3 .....l,. c:o I 100, 1.611 100
Rev. 19 Main Turbine Byp*ass Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-47 PL-NF-18-003 Rev. 1 Page 46 of 62
(/) 3.0 C (/) 0 C m 2.8 I )> z z 2.6 )> C z -I 2.4 '§ 2.2
- i C')
r: I'll .... 2.0 -I a, Q.
- a 0
s:: ~ w C. N (.) 1.8 I ~ ~ co 1.6 11.4 1.2 1.0 SSES UNIT 1 CYCLE 21 LEGEND CURVE A; MAXIMUM ALLOWABLE AVERAGE SCRAM t-INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I I. I I SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 I USED IN DETERMINING MFLCPR 130, 1.781 A 8 I 108, 1.391 I REFERIENCE: T.S. 3A.1, 3.7.6, and 3.2.2 I 30 40 50 60 70 80 90 . Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-4 100 110
(J') C (J') 0 C m I )> z z )> C z ~ E
- J Cl C:
~ a> C.
- 0 0
~ ~
- a.
w N 0 I ~ .i::,.. co . SSES UNIT 1 CYCLE 21 40 I I I I I LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.6 ~23,3.45 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 \\ \\ CURVE C: CORE POWER::;; 26% AND CORE FLOW::;; 50 MLBM/HR \\ 3.2
- 126, 3.181 123, 3.061 \\
3.0 \\ SAFETY ANALYSES ASSUME THAT TWO OR.MORE BYPASS - -c VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 2.8 I 26, 2.86 I 2.6 USED IN DETERMINING MFLCPR C 2.4 co 2.2 i 26.01, 2.06 : 2.0 ~ 140, 1.80 i 1.8 ........ I A s* I 60, 1.66 I 1.6 J
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 \\ I 100, 1.661 1.4 20 30 40 50 60 70 80 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-5 90 100
SUSQUEHANNA UNIT 1 Rev. 19 EOC-RPT Inoperable TRM/3.2-50 PL-NF-18-003 Rev. 1 Page 49 of 62
(/') C (/')
- o C m I
)> z z )> C z -I E
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C
- i ca...
-I Cl) Q.
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- 2.4 2.2 2.0 1.8 *
- 1.s 1.4 1.2 1.0 30 SSES UNIT 1.CYCLE 21-LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM I-INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM !NS_ERTION TIME I
I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I USED IN DETERMINING MFLCPR I 130, 1.56 I A B j 1os, 1.25 j
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 I 40 50 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING UMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-6 100 110 c.o -u -u m r (0 I CD z 0, 71 o;a~ 0 CD 1 --,, < 0 a,. 0 1')->.(.,.)
Cl) C Cl) 0 C m
- c
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- i C)
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- ....i (I)
C.
- o 0
~ ~ w
- a.
N 0 I ~ CJ1 N SSES UNIT 1 CYCLE 21 40. 3.3 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.6 INSERTION TIME 3.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 13*2 ~ 23, 3.09 CURVE C: CORE POWER :s: 26% AND CORE FLOW :s; 50 MLBM/HR 23,3.06,~ 3*0 "-;: I 26, 2.961 C . I 2.8 26, 2.861 SAFETY ANAL YS!=S ASSl)ME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.6 I I I I I I USED IN DETERMINING MFLCPR 2.4 2.2
- 2s.01, 2.00 1 2.0 1.8
~ 140,1.76 A 1 so, 1.61: B 1.6 1.4 l
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.21 1.2 20 30 40 50 60 70 80 Core Power(% RATED) MCPR OPERA TING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-7 90
r
.....l,, co I 100~ 1.611 100
- Rev. 19 PL-NF-18-003 Rev. 1 Page 52 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-53
(/) C (/) 0 C m I )> z z )> C z -I ....lo. -*a
- i C)
C ;; ell.. -I (I) C.
- 0 0
~ c::: ll. c.,;, N (.) I ~ 0, ~ SSES UNIT 1 CYCLE 21 3.0 LEGEND 2.8 CURVE A: MAXIMUM AllOWABllE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.4 SAFETY ANALYSES. ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.2 USED IN DETERMINING MFLCPR 2.0 1.8 1.6 130, 1.561 ~ 1.4 A B I 108, 1.2s I 1.2 --j
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 1 1.0 30 40
- 50 60 70 80 90 Total Core _Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-8 100 110
(./) C (./) 0 C m I )>
- z z
)> C z -I SSES UNIT 1 CYCLE 21 38 LEGEND 3.S CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.2 =-----I 23, 3.09 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 123, 3.os: ~ 3.o ~ I
- 1 C
26, 2.96 ~ 2.8 '2s, 2.s6' SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.6 I I I I USED IN DETERMINING MFLCPR 2.4 I 26.01, 2.33 I -- r--,.......__ I 40, 2.12 I 2.2 --..........__ A 2.0 B 1.8 1.6 1.4 -- I'-,...__
- 60, 1.82:
W
REFERENCE:
T.S. 3.4.1, 3.7.8, cJJnd 3.2.2 I 20 30 40 50 .. so 70 80 Core Power (% RA TED) MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-9 90 co I 100, 1.s2 I 100
Rev. 19 One TSV or TCV Closed SUSQUEHANNA UNIT 1 TRM/3.2-56 PL-NF-18-003 Rev. 1 Page 55 of 62
I. en C en 0 C m
- c
)> z z )> C. z -I "§
- J C,
C f! -I Ql C.
- a 0
s: a!: w
- a.
N (.) I 2E 0, -...J SSES UNIT 1 CYCLE 21 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.4 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.0 I USED IN DETERMINING MFLCPR I I I 1.8 -j 30, 1.75: 1.6 1.4 A B I 1os, 1.401 1.2
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I 1.0 30 40 50 60 70 80 90 100 Total Core Flow (MLB/HR) MCPR OPERATING UMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED* SINGLE LOOP OPERATION (BOC to EOC) . FIGURE 8.2-1 O
- Operation with one TSV or TCV closed is only supported at power levels S 75% rated power.
110 (0
(/) C (/) 0 C I.m I )>" z z )> C z --l '§
- i C) c*
C'CS.. --l a) Q.
- 0 0
~ a::: ll. w N (.) I aE 0,
- 0)
SSES UNIT 1 CYCLE 21 38. LEGEND 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTIQN TIME 3.2 123, 3.091 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 123,3.061 ~ 3.0 ""'..,,., : 26, 2.96 : -c '126,2.861 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.8 2.6 2.4 2.2 2.0 1.8 1.6
- 1. 4
- ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I
I I USED IN DETERMINING MFLCPR I 26.01, 2.00 I 140, 1.76 I A*-~s I 60, 1.61 I H
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.71 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 ~ 175, 1.61 80 co
Rev. 19 PL-NF-18-003 Rev. 1 Page 58 of 62 9.0 POWER/ FLOW MAP 9.1 References 9.2 Technical Specification 3.3.1.1 Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and II of the Power/ Flow map, Figure 9.1. If the OPRM l_nstrumentation 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 per TS 3.3.1.1, Region I of the Power / 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. SUSQUEHANNA UNIT 1 TRM/3.2-59
a w ~ ~ ~ - Q) ~ 0.., <-!-,"'l-+--i--l--,i-~~....,............. -i--i--!--+'............
- .;,* '>-1.....;.'.........,'-+'-J.-t-' _'.....,'.....;.' -!--'-+'-+'.....;.' -!-+' -'-+'-+'-!--+' -+' -';',.-,' '-1--+' -*.-'.,*,...,,~. 0 0
10 20 30 40 50 60 70 80 190 .fio Total Core Flow (Mihm/hr) Figure 9.1 SSES Unit 1 Cycle 21 Power/ Flow Map SUSQUEHANNA UNIT 1 TRM/3.2-60
Rev. 19 10.0 OPRM SETPOINTS 10.1 References Technical Specification 3.3.1.1 10.2 Description PL-NF-18-003 Rev. 1 Page 60 of 62 Setpoints for tt:ie 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 listed below: = = . Fp = SUSQUEHANNA UNIT 1 1.11 15 60 Mlbm / hr TRM/3.2-61
Rev. 19
11.0 REFERENCES
PL-NF-18-003 Rev. 1 Page 61 of 62 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 1 and 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, "ATRIUM'-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.
- 4. XN-NF-84-105(P)(A), Volume 1 and Volume 1 Supplements 1 and 2, "XCOBRA-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 1 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, 28, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," 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-80-19(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,"
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 UNIT 1 TRM/3.2-62
Rev. 19 PL-NF-18-003 Rev. 1 Page 62 of 62
- 13. EMF-2209(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),
"RODEX2A (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 CASM0-4/Microburn-B2," Siemens Power Corporation, October 1999.
- 16. EMF-CC-07 4(P)(A), Volume 4, Revision 0, "BWR Stability Analysis -
Assessment of STAIF with Input from MICROBURN-B2," Siemens Power Corporation, August 2000.
- 17. NED0-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.
- 18. ANF-913(P)(A), Volume 1 Revision 1 and Volume 1 Supplements 2, 3, and 4, "COTRANSA2: A Com put.er 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 1 TRM/3.2-63
Rev.2 B 3.5 B 3.5.1 BASES TRO ADS Manual Inhibit B 3.5.1 Emergency Core Cooling Systems (ECCS), Reactor Pressure Vessel (RPV) Water Inventory Control, and Reactor Core Isolation Cooling (RCIC) System Automatic Depressurization System (ADS) Manual Inhibit The ADS Manual Inhibit function is provided to permit overriding ADS actuation in the event that the actuation signals are due to an Anticipated Transient Without a Scram (ATWS). The function supports operation of the SLCS Function (LCO 3.1. 7) (ADS Inhibit) and ADS Function (LCO 3.5.1) (ADS Permissive), and is required to be OPERABLE when those functions are required. The purpose of the ADS Manual Inhibit Function is to disable the ADS system to prevent a blowdown in the event of an Anticipateq Transient Without a Reactor Scram (ATWS), when boron injection is required. ADS Manual Inhibit is required by procedure any time SLCS injection is initiated for reactivity control. The ADS Manual Inhibit function supports SLCS operation for mitigation of an ATWS event, which ties its Operability requirement to that of SLCS. If the ATWS transient results in a sustained reactor water level below the Level 1 ADS initiation setpoint (-129"), the SLCS Function can be defeated by failure of one ADS Manual Inhibit channel in either the ADS A or B logic control systems. Because its actuation could result in the injection of a large amount of unborated water into the core under A TWS conditions, preventing ADS is appropriate whenever boron injection is required. The ADS Manual Inhibit "passive" function must be Operable to support actuation of the ADS initiation function, which ties its Operability requirement to that of ADS. One ADS Manual Inhibit Switch is provided for each Division. (Reference 1) SUSQUEHANNA - UNIT 1 TRM / B 3.5-1
Rev. 2 BASES ACTIONS TRS ADS Manual Inhibit B 3.5.1 The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components. The REQUIRED ACTIONS are based on the ATWS mitigation Function and on the need to preserve the ADS ECCS function. The allowed out of service time for the Inhibit function is commensurate with the Function's importance to safety, relative to ATWS functional requirements. While the ADS Manual Inhibit is a desirable function for the ATWS mitigation scenarios, it is not a necessary function for plant shutdown with Standby Liquid Control injection under the ATWS emergency operating procedures when high pressure injection systems are available. High pressure injection systems are used to control RPV water level above -129" in an ATWS. SSES plant specific analyses do not show RPV level falling below-129" in an MSIV closure ATWS (the limiting water level event) if HPCI and RCIC are available. Failure of the ADS Manual Inhibit Function to reset to the "permissive" mode when returned to "normal" can affect the ADS system's ability to perform its ECCS safety function. The ADS Manual Inhibit "permissive" function assures there is appropriate switch contact continuity such that the automatic and manual ADS initiation trip channels can function in accordance with the ECCS design basis. Failure of the switch to support the ADS ECCS Function causes the ADS trip channel to become inoperable. The TRSs are defined to be performed at the specified Frequency to ensure that the ADS Manual Inhibit Switch is maintained OPERABLE. REFERENCES . 1. FSAR Section 7.3.1.1a SUSQUEHANNA - UNIT 1 TRM / B 3.5-2.}}