ML25101A038
| ML25101A038 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/03/2025 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML25101A038 (1) | |
Text
{{#Wiki_filter:1-1..1:.u.. U..::> 1 L.UL.:J MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2025-2749 USER INFORMATION: GERLACH*ROSEY M Address: NUCSA2 Phone#: 542-3194 EMPL#: 028401 CA#: 0363 TRANSMITTAL INFORMATION: TO: GERLACH*ROSEY M 04/03/2025 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 11///A.ROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ~ RORS. ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material. TRM2 - TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 03/24/2025 ADD MANUAL TABLE OF CONTENTS DATE: 04/02/2025 CATEGORY: DOCUMENTS TYPE: TRM2 of 2
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ID: TEXT 3.2.1 ADD: REV: 22 REMOVE: REV: 21 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT B3.10.3 REMOVE: REV:3 ADD: REV: 4 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: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents Issue Date: 04/02/2025 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 99 01/03/2019
Title:
LIST OF EFFECTIVE SECTIONS TEXT TOC 29 11/27/2023
Title:
TABLE OF CONTENTS TEXT 1.1 1 11/27/2023
Title:
USE AND APPLICATION DEFINITIONS TEXT 2.1 1 02/04/2005
Title:
PLANT PROGRAMS AND SETPOINTS PLANT PROGRAMS TEXT 2.2 13 06/29/ 2023
Title:
PLANT PROGRAMS AND SETPOINTS I NSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 8 03/1 8/2021
Title:
APPLICABILITY TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT 3.1.1 2 01/15/2025
Title:
REACTIVITY CONTROL SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS -ARI ) I NSTRUMENTATION TEXT 3.1.2 0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1. 3 5 12/18/2017
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 1 10/12/2020
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT 3.2.1 22 04/02/2025
Title:
CORE OPERATING LIMITS REPORT (COLR) Page 1 of 15 Report Date: 04/03/25
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.3.1 0 11/19/2002
Title:
INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 3 03/31/2011
Title:
INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 2 11/09/2007
Title:
INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 11 07/21/2017
Title:
INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0 11/19/2002
Title:
INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK TEXT 3.3.6 6 06/29/2023
Title:
INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 6 04/16/2024
Title:
INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 1 10/22/2003
Title:
INTENTIONALLY LEFT BLANK TEXT 3.3.9 3 05/14/2009
Title:
INSTRUMENTATION LPRM UPSCALE ALARM INSTRUMENTATION TEXT 3.3.10 1 12/14/2004
Title:
INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1 10/22/2003
Title:
INSTRUMENTATION MVP ISOLATION INSTRUMENTATION TEXT 3.3.12 2 04/02/2019
Title:
WATER MONITORING INSTRUMENTATION Page 2 of 15 Report Date: 04/03/25
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 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:
INTENTIONALLY LEFT BLANK TEXT 3.4.3 1 11/09/2007
Title:
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM (RCS) TEXT 3.4.4 2 05/14/2009
Title:
REACTOR COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT 3.4.5 1 04/26/2006
Title:
REACTOR COOLANT SYSTEM REACTOR VESSEL MATERIALS TEXT 3.4.6 1 04/25/2013
Title:
REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT 3.5.1 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 RCIC SYSTEM LONG TERM NITROGEN SUPPLY TO ADS TEXT 3.6.1 1 11/27/2023
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 11/19/2002
Title:
CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION Page 3 of 15 Report Date: 04/03/25
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.6.4 1 11/27/2023
Title:
CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 0 11/19/2002
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN TEXT 3.7.2 1 11/27/2023
Title:
PLANT SYSTEMS ULTIMATE HEAT SINK (URS) AND GROUND WATER LEVEL TEXT 3.7.3.1 7 04/21/2022
Title:
PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 3 04/16/2009
Title:
PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS TEXT 3.7.3.3 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 15 08/02/2021
Title:
PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION TEXT 3.7.4 2 11/27/2023
Title:
PLANT SYSTEMS SOLID RADWASTE SYSTEM Page 4 of 15 Report Date: 04/03/25
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7.5.1 1 03/05/2015
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT 3.7.5.2 0 11/19/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS 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
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT 3. 7. 8 9 03/05/2015
Title:
PLANT SYSTEMS SNUBBERS TEXT 3.7. 9 2 03/05/2019
Title:
PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7. 10 2 04/29/2014
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS) TEXT 3.7. 11 2 11/01/2018
Title:
PLANT SYSTEMS TEXT 3.8.1 4 08/02/2021
Title:
ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT 3.8.2.1 3 09/19/2023
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION - CONTINUOUS TEXT 3.8.2.2 3 06/23/2021
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION - AUTOMATIC Page 5 of 15 Report Date: 04/03/25
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.8.3 4 01/28/2020
Title:
ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT 3.8.4 2 11/27/2023
Title:
ELECTRICAL POWER 24 VDC ELECTRICAL SUBSYSTEM TEXT 3.8.5 1 11/14/2013
Title:
ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION TEXT 3.8.6 3 03/05/2019
Title:
ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8.7 3 02/25/2021
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT 3.9.1 0 11/19/2002
Title:
REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0 11/19/2002
Title:
REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 1 03/12/2019
Title:
REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 2 11/27/2023
Title:
MISCELLANEOUS SEALED SOURCE CONTAMINATION TEXT 3.10.2 1 04/09/2007
Title:
MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 4 10/05/2022
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) TEXT 3.10. 4 2 04/17/2009
Title:
INTENTIONALLY LEFT BLANK Page 6 of 15 Report Date: 04/03/25
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3. 11. 1. 1 2 11/27/2023
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION TEXT 3.11.1.2 2 11/27/2023
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE TEXT 3.11.1.3 2 11/27/2023
Title:
RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM TEXT 3.11.1.4 3 11/27/2023
Title:
RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.1.5 4 11/27/2023
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT 3.11.2.1 5 11/27/2023
Title:
RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3.11.2.2 2 11/27/2023
Title:
RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES TEXT 3.11.2.3 2 11/27/2023
Title:
RADIOACTIVE EFFLUENTS DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM TEXT 3.11.2.4 1 11/27/2023
Title:
RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3.11.2.5 5 11/27/2023
Title:
RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3. 11. 2. 6 9 11/27/2023
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11. 3 2 11/27/2023
Title:
RADIOACTIVE EFFLUENTS TOTAL DOSE Page 7 of 15 Report Date: 04/03/25
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.11.4.1 7 06/27/2024
Title:
RADIOACTIVE EFFLUENTS MONITORING PROGRAM TEXT 3.11.4.2 3 11/27/2023
Title:
RADIOACTIVE EFFLUENTS LAND USE CENSUS TEXT 3.11.4.3 2 11/27/2023
Title:
RADIOACTIVE EFFLUENTS INTERLABORATORY COMPARISON PROGRAM TEXT 3.12.1 0 11/19/2002
Title:
LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT 3.12.2 4 04/17/2008
Title:
LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0 11/19/2002
Title:
LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENTS TEXT 4.1 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 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 2 11/27/2023
Title:
ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS TEXT 4.6 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM Page 8 of 15 Report Date: 04/03/25
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 4.7 1 12/13/2022
Title:
ADMINISTRATIVE CONTROLS TRAINING TEXT B3.0 7 03/18/2021
Title:
APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.1. 1 2 04/29/2014
Title:
REACTIVITY CONTROL SYSTEM BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.1.2 0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT B3.1.3 4 12/18/2017
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT B3.1.4 1 10 /12/2020
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.1 0 11/19/2002
Title:
CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR) TEXT B3.3.1 1 01/3 1/2014
Title:
INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 2 03/31/2011
Title:
INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 2 11/09/2007
Title:
INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 8 11/27/2023
Title:
INSTRUMENTATION BASES TRM POST ACCIDENT MONI TORING (PAM) INSTRUMENTATION TEXT B3.3.5 2 11/09/2007
Title:
INSTRUMENTATION BASES THIS PAGE INTENTIONALLY LEFT BLANK Page 9 of 15 Report Date: 04/03/25
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.3.6 7 06/29/2023
Title:
INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION TEXT B3.3.7 6 04/16/2024
Title:
INSTRUMENTATION BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT B3.3.8 1 10/22/2003
Title:
INTENTIONALLY BLANK TEXT B3.3.9 4 01/03/2019
Title:
INSTRUMENTATION BASES LPRM UPSCALE ALARM INSTRUMENTATION TEXT B3.3.10 3 02/22/2012
Title:
INSTRUMENTATION BASES REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 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 B3.4.1 0 11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY TEXT B3.4.2 1 04/16/2009
Title:
REACTOR COOLANT SYSTEM BASES STRUCTURAL INTEGRITY TEXT B3. 4. 3 1 11/09/2007
Title:
REACTOR COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR TEXT B3.4.4 1 01/03/2019
Title:
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 15 Report Date: 04/03/25
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.4.6 2 01/03/2019
Title:
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 1 11/27/2023
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 1 04/19/2007
Title:
CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION TEXT B3.6.4 2 11/27/2023
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 1 11/27/2023
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 15 Report Date: 04/03/25
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.3.3 0 11/19/2002
Title:
PLANT SYSTEMS BASES CO2 SYSTEMS TEXT B3.7.3.4 3 06/19/2019
Title:
PLANT SYSTEMS BASES HALON 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 TEXT B3.7.3.8 3 09/27/2012
Title:
PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION TEXT B3.7. 4 1 11/27/2023
Title:
PLANT SYSTEMS BASES SOLID RADWASTE SYSTEM TEXT B3.7.5.l 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 15 Report Date: 04/03/25
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 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 3 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 TEXT B3.8.2.l 1 09/19/2023
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION - CONTINUOUS TEXT B3.8.2.2 2 06/23/2021
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION - AUTOMATIC TEXT B3.8.3 0 11/19/2002
Title:
ELECTRICAL POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT B3.8.4 1 11/27/2023
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 4 03/05/2019
Title:
ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 3 02/25/2021
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM Page 13 of 15 Report Date: 04/03/25
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.9.l 0 11/19/2002
Title:
REFUELING OPERATIONS BASES DECAY TIME TEXT B3.9.2 0 11/19/2002
Title:
REFUELING OPERATIONS BASES COMMUNICATIONS TEXT B3.9.3 1 03/12/2019
Title:
REFUELING OPERATIONS BASES REFUELING PLATFORM TEXT B3.10.l 1 11/27/2023
Title:
MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 1 04/10/2007
Title:
MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT B3.10.3 4 04/02/2025
Title:
MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
- TEXT B3.11.l.l 2
11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3.11.1. 2 1 11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3. 11. 1. 3 1 11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3.11.l.4 1 11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.1. 5 1 11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.ll.2.l 3 10/15/2024
Title:
RADIOACTIVE EFFLUENTS BASES DOSE RATE Page 14 of 15 Report Date: 04/03/25
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.ll.2.2 1 11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES TEXT B3.11.2.3 1 11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATES FORM TEXT B3.ll.2.4 1 11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.11.2.5 6 11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3.11.2.6 3 11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11. 3 1 11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES TOTAL DOSE TEXT B3.11.4.1 8 06/27/2024
Title:
RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3.11.4.2 1 11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES LAND USE CENSUS TEXT B3.11. 4. 3 1 11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAM TEXT B3.12.1 1 10/04/2007
Title:
LOADS CONTROL PROGRAM BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT B3.12.2 1 12/03/2010
Title:
LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS TEXT B3.12.3 0 11/19/2002
Title:
LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Page 15 of 15 Report Date: 04/03/25
Rev. 22 .3.2 Core Operating Limits Report (COLR) 3.2.1 Core Operating Limits Report (COLR) COLR 3.2.1 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 A.1 Perform action(s) described in referenced Technical Specification. TECHNICAL REQUIREMENT SURVEILLANCE COMPLETION TIME Specified in referenced Technical Specifications. SURVEILLANCE FREQUENCY
NOTE-------------------------------------------
N/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications. SUSQUEHANNA - UNIT 2 TRM / 3.2-1
Rev. 22 Susquehanna SES Unit 2 Cycle 23 PL-NF-25-004 Rev. 0 Page 1 of 69 CORE OPERA TING LIMITS - REPORT SUSQUEHANNA UNIT 2 TRM / 3.2-2 Nuclear Fuels Engineering March 2025
REV AFFECTED NO. SECTIONS Rev. 22 PL-NF-25-004 Rev. 0 Page 2 of 69 CORE OPERA TING LIMITS REPORT REVISION DESCRIPTION INDEX DESCRIPTION / PURPOSE OF REVISION 0 ALL Issuance of this COLR is in support of Unit 2 Cycle 23 operation. FORM NFP-QA-008-2, Rev. 2 SUSQUEHANNA UNIT 2 TRM / 3.2-3
1.0 2.0 3.0 4.0 5.0 6.0 7.0 Rev. 22 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 23 CORE OPERA TING LIMITS REPORT Table of Contents PL-NF-25-004 Rev. 0 Page 3 of 69 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......................................................................................................... 45 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION.......................................... 47 9.0 POWER/ FLOW MAP.................................................................................................. 65 10.0 OPRM SETPOINTS...................................................................................................... 67
11.0 REFERENCES
.............................................................................................................. 68 SUSQUEHANNA UNIT 2 TRM / 3.2-4
1.0 Rev. 22 INTRODUCTION PL-NF-25-004 Rev. 0 Page 4 of 69 This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 23 is prepared in accordance with the requirements of Susquehanna Unit 2, 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 2 TRM / 3.2-5
2.0 Rev. 22 PL-NF-25-004 Rev. 0 Page 5 of 69 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 LHGRFACr is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFACr 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. 2.7 MCPRss.s% is the cycle-specific safety limit MCPR that ensures at least 99.9% of fuel rods are not susceptible to boiling transition. 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 2 TRM / 3.2-6
3.0 Rev.22 PL-NF-25-004 Rev. 0 Page 6 of 69 SHUTDOWN MARGIN 3.1 References 3.2 Technical Specification 3.1.1 Description The SHUTDOWN MARGIN shall be equal to or greater than: a) 0.38% Llk/k with the highest worth rod analytically determined OR b) 0.28% Llk/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 between 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 2 TRM / 3.2-7
Rev. 22 PL-NF-25-004 Rev. 0 Page 7 of 69 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 References 4.2 Technical Specification 3.2.1 Description The APLHGRs for ATRIUM 11 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 2 TRM / 3.2-8
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- AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE -TWO LOOP OPERATION FIGURE 4.2-1 60000 70000
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5.0 Rev. 22 PL-NF-25-004 Rev. 0 Page 9 of 69 MINIMUM CRITICAL POWER RATIO (MCPR) 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 MCPRee.9% Safety Limit is 1.07 for Two Loop operation and 1.09 for Single Loop operation. 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 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 EOC Figure 5.2-10: Power-Dependent MCPR value determined from BOC to EOC 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. SUSQUEHANNA UNIT 2 TRM / 3.2-10
5.3 Rev. 22 Average Scram Time Fraction PL-NF-25-004 Rev. 0 Page 10 of 69 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 UNIT 2 TRM / 3.2-11
Rev. 22 PL-NF-25-004 Rev. 0 Page 11 of 69 Main Turbine Bypass/ EOC-RPT / Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 TRM / 3.2-12
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REFERENCE:
T.S. 3.2.2 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 OPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-1 I 108.0, 1.20 I 110 -0 -0 ru r (C I CD z "Tl I N ::0 N 0 CD Cf < 0
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1.8 1.6 1.4 1.2 SSES UNIT 2 CYCLE 23 I I I -i -i I 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 CURVE A: ALL SCRAM INSERTION TIMES 26, 2.81 23, 2.85 A B CURVE B: SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE 26, 2.81 PER SR 3.7.6.1 AND 3.7.6.2 I-23, 2.85 - I-C CURVE C: 26, 2.72 USED IN DETERMINING MFLCPR r 23, 2.75 126.01, 2.09 140, 1.91 I-H5o, 1.91: 60, 1.81 I A ~.......... *------- 70, 1.81 1 I 26.01, 2.02 I 80, 1.66 I 40, 1.19 I I 5o, 1.18 I 190, 1.551 I 50, 1.10 ---, ~------- 1100, 1.551 1100, 1.401 W
REFERENCE:
T.S. 3.2.2 I B I 70, 1.54 I l 80, 1.53 I 10 20 30 40 50 60 70 80 Core Power (% RA TED) MCPR OPERA TING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-2 I 9o, 1.50 I 90 100
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REFERENCE:
T.S. 3.7.6 and 3.2.2 I 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 ~ - I 108.0, 1.35 I 110 -0 -0 m r (0 I CD z,, ~ ::o N 0 CD 'f -+, < 0 O')
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C: Cl) "C w C: 2.5 N Cl) I C. Cl) --.J C 2.3 Cl) 3: 0 2.1 a.. 1.9 1.7 1.5 1.3 SSES UNIT 2 CYCLE 23 LEGEND CURVE A: CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 26, 3.25 INSERTION TIME 23, 3.39 CURVE 8: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE B: CURVE C: CORE POWER :s: 26% AND CORE FLOW :S: 50 MLBM/HR 26, 3.25 A MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 23, 3.39 B CURVE D: CORE POWER :s: 26% AND CORE FLOW :S: 50 MLBM/HR ~ REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: ___ C D I I I I I I 26, 3.25 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE - 23, 3.25 INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 CURVED: 26, 3.25 USED IN DETERMINING MFLCPR ~ 23, 3.25 I 26.01, 2.15 I 140, 1.951 I so, 1.91 , so, 1.85 A H 10, 1.a1: I -f 90, 1.68 ~ I 26.01, 2.04 l4o, 1.aa I ,so, 1.681 60, 1.76 I.............._ 100, 1.68
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REFERENCE:
T.S. 3.7.6 and 3.2.21 n10, 1.s2, I so, 1.s1 I I 95, 1.571 10 20 30 40 50 60 70 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-4 l 9o, 1.ss I 80 90 100 -0 -0 tu r (0 I CD z ~ 71
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REFERENCE:
T.S. 3.3.4.1 and 3.2.2 : 30 40 50 60 70 80 90 100 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-5 L I 108.0, 1.20 I 110
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2.7
- 0 s:
C: Cl) "C w C: 2.5 N Cl) I C. N Cl) 0 C 2.3 Cl) 3: 2.1 0 c.. 1.9 1.7 1.5 1.3 CURVE A: 26, 2.81 23, 2.85 .. CURVE B: ._ 26, 2.81 .. 23, 2.85 .. CURVE C: .. 26, 2.72 23, 2.75 .._CURVED: ._ 26, 2.72 23, 2.75 I-SSES UNIT 2 CYCLE 23 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWERS 26% AND CORE FLOWS 50 MLBM/HR MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME I-CURVE D: CORE POWER s 26% AND CORE FLOWS 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME A SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE
_8 PER SR 3.7.6.1 AND 3.7.6.2
~i--- I I I t C_o USED IN DETERMINING MFLCPR 126.01, 2.14 1 140, 1.941 1150, 1.941160, 1.94 1 A -.... r---......_ I 70, 1.817 I 26.01, 2.03 I 80, 1.71 L H9o, 1.111-- 140, 1.821 50, 1.18: 1 L 60, 1.70 B I 100, 1.71 I I 100, 1.551
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 I 70, 1.571 I 80, 1.51 I I 9o, 1.55 I 10 20 30 40 50 60 70 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-6 80 90 100 -a -a ru r CQ I CD z '"Tl I CO :::0 N 0 CD 'f < 0 0). 0 (0 0 .i:,.
- 0 CD N
N
i Rev. 22 PL-NF-25-004 Rev. 0 Page 20 of 69 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM / 3.2-21
CJ) 2.4 C CJ) 0 2.3 C m I )> 2.2 z z )> C 2.1 z =i N
- !: E 2.0
- J C)
C: 1.9 ns... Cl) c.. 1.8 0 ~
- a.
{.) 1.7 -f
- 0 s:
C: Cl) 1.6 "C ~ C: N Cl) I c.. 1.5 N Cl) N C
- s:
0 1.4 U:: 1.3 1.2 1.1 1.0 SSES UNIT 2 CYCLE 23 I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I I I I --130.0, 1.96: SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 "\\ I 35.0, 1.84 I I I I I USED IN DETERMINING MFLCPR j 35.1, 1.531
r------_
A B 30
r------_
REFERENCE:
T.S. 3.7.8 and 3.2.21 I I 40 50 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-7 100 ~ 108.0, 1.20 I 110
- 0 CD <
N N
(/) 4.0 C (/) 0 3.8 C m I )> 3.6 z z )> C 3.4 z =i N E 3.2
- i en C:
3.0 cu... Q) C. 2.8 0 0:::
- a. u 2.6
-l ~
- 0 s;:
C: Q) 2.4 "C (,) C: N Q) I C. 2.2 N Q) (,) 0... Q) 3: 0 2.0
- a.
1.8 1.6 1.4 1.2 SSES UNIT 2 CYCLE 23 I I I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE A: CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 26, 2.81 ~ 23, 2.85 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR ALL SCRAM INSERTION TIMES CURVE B: 26, 2.81 A I I 8 23, 2.85 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 ... CURVE C: 26, 2.72 C 23, 2.75 USED IN DETERMINING MFLCPR ~ 126.01, 2.091 I 40, 1.91 I
- 50, 1.91:
l6o, 1.81 I A ~ ~ 70, 1.811 I 26.01, 2.02 I 80, 1.66 I 40, 1.791 I 90, 1.57 I
- 50, 1.78:
160, 1.11 -... ii-------- 8 I
REFERENCE:
T.S. 3.7.8 and 3.2.2 1
- 70, 1.55 r-i 80, 1.53 I ------
I 9o, 1.50 I I 100, 1.s5 I 1100, 1.401 10 20 30 40 50 60 70 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-8 80 90 100 "'O "'O i:u r (0 I CD z N "71 N ::0 N 0 CD 'f ...... < 0 0). 0 coo~
- 0 CD <
N N
Rev.22 One TSV or TCV Closed SUSQUEHANNA UNIT 2 TRM / 3.2-24 PL-N F-25-004 Rev. O Page 23 of 69
2.4 (/) C 2.3 (/) 0 C m 2.2 I )> z z 2.1 )> C
- t
- ::
z =i E 2.0 N
- i Cl C:
1.9 cu... Cl) C. 1.8 0 0:::
- a.
(.)
- i:
1.7 C: ~ Cl) 1.6
- a "C
~ C: Cl) C. 1.5 w Cl) N C I 3: N (J1 0 1.4 U:: 1.3 1.2 1.1 1.0 SSES Ul. 2 CYCLE 23 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM I 30.0, 2.19 I INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 140.0, 1.961 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 30 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I I USED IN DETERMINING MFLCPR I A 8 140.1, 1.59 1 I
REFERENCE:
T.S. 3.2.2 and TRM 3.3.71 40 50 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED* TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-9 100
- Operation with one TSV or TCV closed is only supported at power levels :5 75% rated power I
- I 108.0, 1.37 I 110 ""'CJ ""'CJ w r (Q I CD z N 7l ~ :::0 N 0 CD 'f -<o 0) 0 C.00~
- a CD N
N
(/) 4.0 C (/) 0 3.8 C m I )> 3.6 z z )> C 3.4 z =i N E 3.2
- J C')
C: 3.0 ca... Cl) Cl. 2.8 0 It: ll. () 2.6 -I
- 0 s;::
C: Cl) 2.4 "O (.v C: N Cl) I Cl. 2.2 N Cl)
- 0)
C... Cl) 3= 0 2.0 ll. 1.8 1.6 1.4 1.2 SSES UNIT 2 CYCLE 23 I I I I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE A: 26, 2.81 CURVE C: CORE POWER :S 26% AND CORE FLOW :S 50 MLBM/HR 23, 2.85 ALL SCRAM INSERTION TIMES CURVE B: 26, 2.81 A-B-23, 2.85 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 CURVE C: C 26, 2.72 I USED IN DETERMINING MFLCPR r 23, 2.75 126.01, 2.09 I I 40, 1.91 I A_ J 50, 1.911 I 60, 1.81 I
- 70, 1.81:
I 26.01, 2.021
175, 1.741 I 40, 1.791 B
50, 1.78 I 60, 1.70 I
- 15, 1.54 I H
REFERENCE:
T.S. 3.2.2 and TRM 3.3.7: I 70, 1.541 I 10 20 I 30 40 50 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-10 60 70 80 7J 7J w r (0 I CD z N 7l o, ::0 N 0 CD 'f -<o 0). 0 CO 0~
- 0 CD N
N
Rev. 22 Table 5.3-1 PL-NF-25-004 Rev. 0 Page 26 of 69 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 2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 2 TRM / 3.2-27
6.0 Rev. 22 PL-NF-25-004 Rev. 0 Page 27 of 69 LINEAR HEAT GENERATION RATE (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 11 fuel shall not exceed the LHGR limits determined from Figure 6.2-1. The LHGR limits in Figure 6.2-1 are 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 Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier c) EOC-RPT Inoperable Figure 6.2-6: Flow-Dependent LHGR Limit Multiplier Figure 6.2-7: Power-Dependent LHGR Limit Multiplier d) Backup Pressure Regulator Inoperable Figure 6.2-8: Flow-Dependent LHGR Limit Multiplier Figure 6.2-9: Power-Dependent LHGR Limit Multiplier e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 6.2-10: Flow-Dependent LHGR Limit Multiplier Figure 6.2-11 : Power-Dependent LHGR Limit Multiplier SUSQUEHANNA UNIT 2 TRM / 3.2-28
Rev. 22 PL-NF-25-004 Rev. O Page 28 of 69 The LHGR limits and LHGR limit multipliers in Figures 6.2-1 through 6.2-11 are valid for both Two Loop and Single Loop operation. SUSQUEHANNA UNIT 2 TRM / 3.2-29
(/) C (/) D C m I )> z z )> C z =i N --j
- 0 s:
vJ N I vJ 0 f - E
- J Q)
{}_ C: 0 ~ Q) C: Q) (!) nl Q)
- c...
nl Q) C:
- J 16.0 14.0 12.0 10.0 8.0 6.0 4.0 2.0 0
I I I SSES UNIT 2 CYCLE 23 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I --~--+--1/4--~---~--~---~--~--+--+--+--~--~---~--~---~--~--+--1/4--~---~--~---~--~---~--+--+--~--~---~--4---~--~--+--1/4--~---~--~---~-- I I I I I I I I I I I I I I 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
- ~-----~ I 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 0.0, 13.6 +--H-++-: 2:0~0, 13.6 -r--1---r--i--t--n--1--1 : : : :R~F~R~N~E:: T~S.: 3.~.3:
- : : r--
1 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 --r-T--r--r--r--1---r--rT--r-T--r- -: --1--r-1--T--r--r--r--1---r--1--T--r-1 usED IN DETERMINING FDLRX i-- I 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--T--,---r--~---r--T---r---T*--,---r--,---r--,---r--T-- --T--,---r--,---r--T---r---T---r--T--,---r--,---r--T---r--T--,---r--,---r-- 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 I I I I I I I I I I I I I I I I I 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 H 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 --r-T--r--T--r-T--r--r-r-r--T--r--rT-r--:---1--T--r--T--r--r, --.. ---, 53000, 1 o.2 -r--r--:---r--T--r---:---r--1---r-- I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 --T---r--T--~---r--,---r--T---r---T---r--T--,---r--,---r--T---r--T--~---r--,---r--T---r--T-- --r--,---r--,---r--T---r--T--~---r--,---r-- 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I --7---r--T--~---r--1---r--1---r---T*--,---~--,---r--,---r--T---,---T--~---r--,---r--1---r--T---r--r-- ---r--,---r--T---r---T--,---r--,---r-- 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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--..,..--T--1---r--,---r--T---~--T---,---~--1---r--,---r--7--..,..--T--~---r--,---r--1---r--T--..,..--r--,---r-- ---r--T--..,..--T--,---r--,---r-- 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 --T---t---T--1---r--,---r--T---r--*---,---~--,---r--1---~--T--..,..--T--1---r--,---~--1---~--*---t---r--1---r--1---r- ---r--T--1---r--,---r-- 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 1 I I I I I I I I I I I I 1 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 --*--..,..--T--1---r--,---r--1--~--*--~--~--1---~--1---~--*---t---T--~---r-- ---~--1---1---*---1---~--,---r--1---~--1---t-- --~---~--1---~-- 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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---+--1--- -- ---~--1---~--*--~--~--1---~--1---~--+---t---+--1---~-- ---~--1---~--*--~--+-- --- --1---~--+---t---+-- --
~--
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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 --+---t---+-- --- -- -----1---r--+---t---~-- --- -- ---~--+---t---+-- --- -- --- --1---r--+--..... --~--1--- -- ---~--+---t---+-- --- -- --- -- 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 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 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 80000, 3.5 I 10000 20000 30000 40000 50000 60000 70000 80000 Pellet Exposure (MWD/MTU) LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE FIGURE 6.2-1 7J 7J w r (0 I CD z N 7l CO ;oN 0 CD Cf ...... < 0 0). 0 coo~
- 0 CD <
N N
Rev. 22 PL-N F-25-004 Rev. 0 Page 30 of 69 Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 TRM / 3.2-31
(/) C (/) 0 C m I }> z z }> C z =i tv -~ C. E
- l
- l!:
0:: (!) J: .J s:: -i Cl)
- a "C
s: s:: Cl) C2. (;J Cl) N C 3:: (;J tv .2 LI. 1.10 SSES UNIT 2 CYCLE 23 I I I I I I I I I I I I I I I I I I I
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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 1.00
1--------r-------+-------1--------r-------1--------t-------+-------1--------r-------..:-.:;,-,,..-"""'!':----:!""'"--"""'!':---""!": --11 os.o, 1.00 0.90 0.80 0.70 0.60 0.50 0.40 I
I I I 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 ________ l _______ _t _______ 1 ________ L _______ J ________ 1 _______ 1 _______ J ________ : ______ JJ86.9, 1.ool ___ L _______ J ________ t ______ _ I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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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+--------~-------~--------+-------..... ------- --------~---------------+--------~------- --------~-------
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 4
1-------, -------:-------:--------r-------1--------:-------:-------1--------r-------1-----
1
REFERENCE:
r.s. 3.2.3 ~ ~,---~,---~,----,~-~ I I I I I I I I I I I I I I I
~ ------r------r-------r-------r-------r-------r------r-------r-------r------1 USED; IN DET~ERMIN;ING FD;LRX
--------t-------+-------t--------~-------~--------t-------+-------t--------t------- ~----~---------~----~---~
I I I I I I I I I I I I I I I I I I I I I I I I 30.0, 0.48 ---~-------+-------1/2--------~-------~------ I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
,--------r--------.--------T--------~-------,------
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7.0 Rev.22 PL-NF-25-004 Rev. O Page 45 of 69 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 Valve (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 2 TRM / 3.2-46
Function Rev. 22 Table 7.2-1 RBM Setpoints Allowable Value(1l PL-NF-25-004 Rev. 0 Page 46 of 69 Nominal Trip 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) (2) (3) Power setpoint function (Low, Intermediate, and High Power Range Setpoints) determined in percent of RA TED 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 (2,3l (% of Rated) ~ 28 and< 90 < 1.79 ~ 90 and< 95 < 1.47 .:::, 95 < 1.68 Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and one TCV/TSV closed. Applicable to both Two Loop and Single Loop Operation. SUSQUEHANNA UNIT 2 TRM / 3.2-47
8.0 Rev. 22 PL-N F-25-004 Rev. 0 Page 47 of 69 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 11 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 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 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 2 TRM / 3.2-48
Rev. 22 PL-N F-25-004 Rev. 0 Page 48 of 69 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, and support power levels up to 67.1 % RA TED THERMAL POWER and core flows up to 52 Mlbm/hr. These conditions conservatively bound Single Loop Operation in accordance with Technical Specification 3.4.1. Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0. RBM Setpoints and Operability Requirements The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0. SUSQUEHANNA UNIT 2 TRM / 3.2-49
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- 0 CD N
N
Rev.22 PL-NF-25-004 Rev. 0 Page 50 of 69 Main Turbine Bypass/ EOC-RPT / Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 TRM / 3.2-51
(/) 3.0 C (/) 0 C m 2.8 I )> z z )> C 2.6 z =i N ~ E 2.4
- J C)
C: ca 2.2 Q) C. 0 0:: Cl. 2.0 -l (.)
- 0
~ s: C: Q) w "C 1.8 N C: I Q) C]1 C. N Q) C 1.6 0 u::: 1.4 1.2 1.0 SSES UNIT 2 CYCLE 23 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 -I 30.0, 1.961 I USED IN DETERMINING MFLCPR I I I ~ 135.0, 1.841 30 A-8 I 52.0, 1.45 I I I I 35.1, 1.53 I
REFERENCE:
T.S. 3.4.1 and 3.2.21 35 40 45 50 55 60 65 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC TO EOC) FIGURE 8.2-2 70 "'CJ "'CJ ru r (0 I CD z CJl -;n _,. ::0 N 0 CD 'f -<o O') 0 COO -l).
- 0 CD <
N N
(/) 4.0 C (/) 0 C 3.8 m I )> z 3.6 z )> C z 3.4 =1 N .E
- i 3.2 C,
C:.. ns 3.0 a,
- a.
0 0::: ll. 2.8 u -i
- 0 2.6 C:
s a, "C (.,J C: N a, 2.4
- a.
I a, CJ1 (.,J C... a, 2.2
== 0 ll. 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 23 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE A: CURVE C: CORE POWER ::5: 26% AND CORE FLOW~ 50 MLBM/HR - 26, 2.83 23, 2.87 ALL SCRAM INSERTION TIMES I I I - CURVE B: SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 26, 2.83 A R ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 23, 2.87 USED IN DETERMINING MFLCPR CURVE C: C I 26, 2.74 - 23, 2.77 126.01, 2.11, 40, 2.07: A 150, 2.07 I ISO, 2.07 I I 67.1, 2.07 I I 26.01, 2.07 I 140, 2.07 I 8 150, 2.071 1 so, 2.01 r l 67.1, 2.071 ~
REFERENCE:
T.S. 3.4.1 and 3.2.2 ! 10 I 20 30 40 50 60 70 Core Power(% RATED) 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 ~ 80
- 0 CD N
N
Rev.22 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 TRM / 3.2-54 PL-NF-25-004 Rev. 0 Page 53 of 69
(/) 3.0 C (/) 0 C m 2.8 I ~ z z ~ C 2.6 z =i N .E 2.4
- i Cl C:..
cu 2.2 Q) C. 0 0::
- a.
2.0 -I (.)
- 0
~ s:: C: Q) (;) "C 1.8 N C: I Q) c.n C. c.n Q) C 3: 1.6 ..2 LL 1.4 1.2 1.0 SSES UNIT 2 CYCLE 23 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 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 3o, 2.10 I ~ I USED IN DETERMINING MFLCPR ~ 140, 1.so I A-s 140.1, 1.541 I 52, 1.51 I I
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 I 30 35 40 45 50 55 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 60 65 70 -0 -0 Ill r (Q I CD z 0, 71 ,1:,,.::0N 0 CD Cf -<o
- 0)
- 0 c.o O
,I:,.
- 0 CD N
N
(J) 4.4 C (J) 0 4.2 C m I )> 4.0 z z )> C 3.8 z =i N
- e 3.6
...I Cl 3.4 C: ra... 3.2 Cl) C2. 0 0::: 3.0 0.. (.J -i 2.8
- 0 C:
s: Cl) 'O w C: 2.6 i-v Cl) C2. I Cl) (.J1
- 0)
C 2.4 Cl) ~ 0 2.2 0.. 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 23 I I I I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM CURVE A: INSERTION TIME 26, 3.27 23, 3.41 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER::; 26% AND CORE FLOW::; 50 MLBM/HR CURVE 8: A MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 26, 3.27 B 23, 3.41 CURVE D: CORE POWER ::; 26% AND CORE FLOW::; 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME C D I I I .,. CURVE C: 26, 3.27 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS """23, 3.27 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 CURVED: USED IN DETERMINING MFLCPR 26, 3.27 23, 3.27 126.01, 2.171 140, 2.07 ~--- A-H 5o, 2.011 , so, 2.071 I 67.1, 2.07 I I
- 26.01, 2.07:
I 4o, 2.01 l B 150, 2.071 160, 2.01ns1.1, 2.071 H
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2: 10 20 30 40 50 60 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC) FIGURE 8.2-5 70 r 80 ""O ""O m r (C I <D z u, 71 u, :::0 N 0 <D Cf .... < 0 0). 0 coo~
- 0 CD <
N N
SUSQUEHANNA UNIT 2 Rev. 22 EOC-RPT Inoperable TRM / 3.2-57 PL-NF-25-004 Rev. 0 Page 56 of 69
(/) 3.0 C (/) 0 C m 2.8 I )> z z )> C 2.6 z =i I\\.) ~ E 2.4
- i C>
s:: ns 2.2 Cl) C. 0 0::
- a.
2.0 L)
- o
- i1!:
~ s:: Cl) (;) 'O 1.8 N s:: I Cl) CJl C. co Cl) C 3: 1.6 0 U: 1.4 1.2 1.0 SSES UNIT 2 CYCLE 23 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION 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 _J 30, 1.961 I USED IN DETERMINING MFLCPR ~ I 35, 1.84 I A B I 35.1, 1.53 I I 52, 1.45 I I
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 30 35 40 45 50 55 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 60 65 70 -0 -0 tu r (Q I CD z 01 T' -..J ::0 N 0 CD 'f -<o 0). 0 CD O .j:,,.
- o (1) <
I\\.) I\\.)
(/) 4.4 C (/) 0 4.2 C m I )> 4.0 z z )> C 3.8 z =i N 3.6
- §
...J C, 3.4 C: nl... 3.2 Cl) C. 0 0::: 3.0
- a.
u -I
- 1!:
2.8
- 0 s:
C: Cl) "C w C: 2.6 N Cl) I C. CJ1 Cl) co C 2.4 Cl) 0 2.2
- a.
2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 23 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE A: CURVE C: CORE POWER :s: 26% AND CORE FLOW :s: 50 MLBM/HR 26, 2.83 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 23, 2.87 CURVED: CORE POWER :S: 26% AND CORE FLOW :S: 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME ,_ CURVE B: 26, 2.83 '""23, 2.87 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES A-8 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 CURVE C: I I I 26, 2.74 USED IN DETERMINING MFLCPR 23, 2.77 - - C D CURVED: 26, 2.74 23, 2.77 126.01, 2.161 40, 2.01LA- ~ 50, 2.07 I 160, 2.071 I 67.1, 2.07 I ~--- 1----- I I 67.1, 2.07 j 126.01, 2.071 40, 2.07 LJ 50, 2.01 I 160, 2.01 I 8-I
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 I I 10 20 30 40 50 60 Core Power (% RA TED) MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC) FIGURE 8.2-7 70 80 "U "U o.> r (0 I CD z CJ1 71 CX> ::0 N 0 CD Cf1 < 0 (j)
- 0 coo~
- 0 co N
N
Rev. 22 PL-NF-25-004 Rev. 0 Page 59 of 69 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM / 3.2-60
(J) 3.0 C (/) 0 C m 2.8 I )> z z )> C 2.6 z =i N
- t
- :
E 2.4
- J C'I r::
cu 2.2 Q) Q. 0 0::: Cl. 2.0 -j 0
- u
- l!:
s: r:: Q) vJ 't:I 1.8 N r:: I Q) (J) Q. Q) C 3:: 1.6 ..2 LL 1.4 1.2 1.0 SSES UNIT 2 CYCLE 23 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 USED IN DETERMINING MFLCPR J 30, 1.96 I ~ I 35, 1.84 I A B I 35.1, 1.53 I 152, 1.45 I I
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 30 35 40 45 50 55 60 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 65 70 "U "U Ill r (C I CD z
- 0) 71 0 :;o N 0
CD Cf -<a 0). 0 coo~
- u CD <
N N
(/) 4.0 C (/) 0 C 3.8 m I )> z 3.6 z )> C z 3.4 =i N .E
- J 3.2 C)
C: cu 3.0 Q) Q. 0 0::: 2.8 a.. (.) -I ~ 2.6
- o s
C: Q) 'C (,.) C: 2.4 N Q) I Q.
- 0)
Q) N C.. 2.2 Q) 3: 0 a.. 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 23 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I-- CURVE A: - 26, 2.83 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 23, 2.87 ALL SCRAM INSERTION TIMES CURVE B: -26, 2.83 A-8 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES - 23, 2.87 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I I -cuRVE C: C _ 26, 2.74 USED IN DETERMINING MFLCPR 23, 2.77 A 150, 2.011 126.01, 2.111 140, 2.07 160, 2.071 167.1, 2.071 I I I 26.01, 2.071 140, 2.071 150, 2.071 160, 2.01r-767.1, 2.071 8 H
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 ! 10 20 30 40 50 60 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC) FIGURE 8.2-9 70 80 lJ lJ ru r (0 I (D z
- 0) 71
.....,. :::0 N 0 CD Cf -<o 0) 0 c.o O .j::..
- o CD
- <
N N
Rev. 22 One TSV or TCV Closed SUSQUEHANNA UNIT 2 TRM / 3.2-63 PL-NF-25-004 Rev. 0 Page 62 of 69
CJ) 3.0 C CJ) 0 C m 2.8 I )> z z )> C 2.6 z =i N E 2.4
- J C)
C: 2.2 Ill.. (1) C. 0 0:::
- a.
2.0 -I u
- o
~ C: (1) w "Cl 1.8 N C: I (1)
- 0)
C. .j:>. (1) C
- s:
1.6 0 U:: 1.4 1.2 1.0 SSES UNIT 2 CYCLE 23 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 130,2.191 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 ~ ~ 140, 1.96 1 I USED IN DETERMINING MFLCPR I I I A 8 140.1, 1.59 I I 52, 1.55 I I
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I 30 35 40 45 50 55 60 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (BOC TO EOC) FIGURE 8.2-10 65 70
- o CD
~ N N
(/) 4.0 C (/) 0 C 3.8 m I )> z 3.6 z )> C z 3.4
- j N
E
- J 3.2 C)
C: cu 3.0 Q) C. 0 ~ 2.8 D. u --l ~ 2.6
- 0 s::
C: Q) 't:I w C: 2.4 N Q) I C.
- 0)
Q) u, C... 2.2 Q)
== 0 D. 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 23 I I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE A: CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 26, 2.83 23, 2.87 ALL SCRAM INSERTION TIMES I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES CURVE B: 26, 2.83 A 8 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 23, 2.87 USED IN DETERMINING MFLCPR CURVE C: C I 26, 2.74 23, 2.77 I A-150, 2.011 126.01, 2.111 140, 2.07 160, 2.071 I 67.1, 2.07 I ~ I I 26.01, 2.07 I 140, 2.0718 - l 5o, 2.011 160, 2.01n61.1, 2.071 -j
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7: I 10 20 I I 30 40 50 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (BOC TO EOC) FIGURE 8.2-11 60 70 80 -a -a ID r CQ I CD z
- 0) 71
~ ::U N 0 CD 'f -<o 0) 0 coo~
9.0 Rev. 22 PL-NF-25-004 Rev. 0 Page 65 of 69 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 I Flow map, Figure 9.1. If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power I Flow map is considered an immediate exit region. If the OPRM Instrumentation is inoperable per TS 3.3.1.1, Region I of the Power I Flow map is considered an immediate scram region. Region II of the Power I Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation. SUSQUEHANNA UNIT 2 TRM / 3.2-66
0 UJ ~ ~ 0 -... (LI 3: 0 a. cu E... (LI .c I-Rev. 22 PL-NF-25-004 Rev. 0 Page 66 of 69 120.,--,;:-_::-.:::.:::r.r.:::.:::::.:::r.r.:::.:::r.:.:::r.r:.:::r.:.:::.:::r.:::-.:::.:::..::-.:::.:::r.:::r.:::..:::-~:-..-r,~.~. ~.-..-r:~:-============.-
- -~- -~-*:-~--,- --,-~--
UNIT 2 120 110 100 90 60 50 40 30 20 10 0
Purpose:
-..!-- -*!--!--!.-~- -~-~---------------1 Initial/ Date: 10 20 30 1 I I I I I I 40 50 60 70 Total Core Flow (Mlbm/hr) Figure 9.1 80 SSES Unit 2 Cycle 23 Power/ Flow Map 90 100 110 100 90 80 70 60 40 SUSQUEHANNA UNIT 2 TRM / 3.2-67
Rev. 22 10.0 OPRM SETPOINTS 10.1 References Technical Specification 3.3.1.1 10.2 Description PL-NF-25-004 Rev. 0 Page 67 of 69 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 listed below: = = = SUSQUEHANNA UNIT 2 1.12 16 60 Mlbm / hr TRM / 3.2-68
Rev. 22
11.0 REFERENCES
PL-NF-25-004 Rev. 0 Page 68 of 69 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-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.
- 5. 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.
- 6. 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.
- 7. 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.
- 8. ANF-89-98(P)(A) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.
- 9. EMF-2209(P)(A), Revision 3, "SPCB Critical Power Correlation," AREVA NP, September 2009.
- 10. EMF-85-7 4(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. 11. EMF-2158(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.
- 12. 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. SUSQUEHANNA UNIT 2 TRM / 3.2-69
Rev.22 PL-NF-25-004 Rev. 0 Page 69 of 69
- 13. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.
- 14. ANF-1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005.
- 15. BAW-10247PA, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors," AREVA, Inc., April 2008.
- 16. ANP-10340P-A, Revision 0, "Incorporation of Chromia-Doped Fuel Properties in AREVA Approved Methods," Framatome Inc., May 2018.
- 17. ANP-10335P-A, Revision 0, "ACE/ATRIUM-11 Critical Power Correlation,"
Framatome Inc., May 2018.
- 18. ANP-10300P-A, Revision 1, "AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios,"
Framatome Inc., January 2018.
- 19. ANP-10332P-A, Revision 0, "AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Loss of Coolant Accident Scenarios,"
Framatome Inc., March 2019.
- 20. ANP-10333P-A, Revision 0, "AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA),"
Framatome Inc., March 2018. 21. ANP-10307PA, Revision 0, "AREVA MCPR Safety Limit Methodology for Boiling Water Reactors," AREVA, Inc., June 2011.
- 22. BAW-10247P-A Supplement 1 P-A, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, Supplement 1:
Qualification of RODEX4 for Recrystallized Zircaloy-2 Cladding," AREVA Inc., April 2017.
- 23. BAW-10247P-A Supplement 2P-A, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, Supplement 2:
Mechanical Methods," Framatome Inc., August 2018. SUSQUEHANNA UNIT 2 TRM / 3.2-70
Rev. 4 ISFSI B 3.10.3 B 3.10 MISCELLANEOUS B 3.10.3 Independent Spent Fuel Storage Installation (ISFSI) BASES TRO The SSES Independent Spent Fuel Storage Installation utilizes two systems: NUHOMS Horizontal Modular System and Holtec HI-STORM FW System. The standardized NUHOMS system is a horizontal canister system composed of a steel dry shielded canister (DSC) and a reinforced concrete horizontal storage module (HSM). The DSC provides confinement and criticality control for the storage and transfer of irradiated fuel. The HSM houses the DSC and provides for heat removal. An HSM is considered loaded when it houses a DSC containing spent fuel. The HSM is a reinforced concrete unit with penetrations located at the top and bottom of the HSM side walls for air flow. The HSM penetrations are protected from debris intrusions by wire mesh screens during storage operation. Decay heat from the stored fuel bundles is removed by air flow through the penetrations in the HSM. Air enters vents near the bottom of the HSM, circulates and rises around the DSC, and exits through the opening near the top of the HSM. Excessive temperatures can adversely affect the HSM concrete's strength and durability. The TRO ensures that each HSM has adequate heat removal capability to assure the strength and durability characteristics of each HSM is maintained. An HSM is considered FUNCTIONAL as long as it meets the requirements of Reference 1. HSMs loaded in accordance with Amendments O and 4 require that the air flow-path inlets and outlets are not completely blocked and capable of maintaining concrete temperature < 350°F for HSM FUNCTIONALITY. HSMs loaded in accordance with all other applicable amendments require either that the air flow-path inlets and outlets are not completely blocked or concrete temperature < 350°F for HSM FUNCTIONALITY. The SSES ISFSI utilizes the Holtec HI-STORM FW system as well. The HI-STORM Heat Removal System is a passive, air-cooled, convective heat transfer system that ensures heat from the Multi-Purpose Canister (MPC) is transferred to the environs by the chimney effect. Relatively cool air is drawn into the annulus between the OVERPACK and the MPC through the inlet air ducts. The MPC transfers its heat from the canister surface to the air via natural convection. The buoyancy created by the heating of the air creates a chimney effect and the air is forced back into the environs through the outlet air ducts at the top of the OVER PACK. SUSQUEHANNA - UNIT 2 TRM / B 3.10-4
Rev. 4 BASES TRO ( continued) ACTIONS ISFSI B 3.10.3 The HI-STORM Heat Removal System must be verified to be FUNCTIONAL to preserve the assumptions of the thermal analyses (Section 4.6.2.4, Reference 3). FUNCTIONALITY is defined as at least 50% of the inlet air ducts available for air flow (i.e., unblocked). FUNCTIONALITY of the heat removal system ensures that the decay heat generated by the stored fuel assemblies is transferred to the environs at a sufficient rate to maintain fuel cladding and other HI-STORM component temperatures within design limits. The intent of this TRO is to address those occurrences of air duct blockage that can be reasonably anticipated to occur from time to time at the ISFSI (i.e., Design Event I and II class events per Reference 4). These events are of the type where corrective actions can usually be accomplished within one 8-hour operating shift to restore the heat removal system to FUNCTIONAL status (e.g., removal of loose debris). The TRO is applicable during storage operations of the HI-STORM FW system. Once an OVERPACK containing an MPC loaded with spent fuel has been placed in storage, the heat removal system must be FUNCTIONAL to ensure adequate dissipation of the decay heat from the fuel assemblies. This TRO implements the surveillance requirements required by Reference 1 and Reference 5. A.1 Action A.1 requires that blockage be removed within 40 hours. The 40 hours as delineated in reference 1 is based on a conservative analysis assuming complete blockage of all air inlets and outlets that indicates that the HSM concrete can reach 350°F. 40 hours is also deemed to be sufficient time to restore cooling to the affected HSM. 8.1 Action 8.1 is provided to address NON-FUNCTIONAL conditions of the HSM which are not related to heat removal. Actions to restore the HSM to a FUNCTIONAL condition should start immediately and proceed in a time frame commensurate with the evaluation of the condition. C.1 and C.2 Actions C.1 and C.2 address excessive temperature conditions that could affect the HSM strength and durability by immediately initiating actions to remove the DSC from the HSM. No time requirement for removal is specified in reference 1, however the vendor recommends the DSC be SUSQUEHANNA - UNIT 2 TRM / B 3.10-4a
Rev.4 BASES ACTIONS ( continued) ISFSI B 3.10.3 removed within 60 days. Taking immediate action to move the DSC from the HSM is intended to ensure the DSC is removed within the recommended 60 days. A note has been added to the ACTIONS which states that, for this TRO, separate Condition entry is allowed for each HI-STORM. This is acceptable since the Required Actions for each Condition provide appropriate compensatory measures for each HI-STORM not meeting the TRO. Subsequent HI-STORM OVERPACKs that do not meet the TRO are governed by subsequent Condition entry and application of associated Required Actions. 0.1 If the heat removal system has been determined to be NON-FUNCTIONAL, it must be restored to FUNCTIONAL status within eight hours. Eight hours is a reasonable period of time (typically, one operating shift) to take action to remove the obstructions in the air flow path. If the heat removal system cannot be restored to FUNCTIONAL status within eight hours, the innermost portion of the OVERPACK concrete may experience elevated temperatures. Therefore, dose rates are required to be measured to verify the effectiveness of the radiation shielding provided by the concrete. This Action must be performed immediately and repeated every twelve hours thereafter to provide timely and continued evaluation of the effectiveness of the concrete shielding. As necessary, the system user shall provide additional radiation protection measures such as temporary shielding. The Completion Time is reasonable considering the expected slow rate of deterioration, if any, of the concrete under elevated temperatures. In addition to Required Action E.1, efforts must continue to restore cooling to the HI-STORM. Efforts must continue to restore the heat removal system to FUNCTIONAL status by removing the air flow obstruction(s) unless optional Required Action E.2.2 is being implemented. This Required Action must be complete in 24 hours. The Completion Time is consistent with the thermal analyses of this event (Section 4.6.2.4, Reference 3), which show that all component temperatures remain below their short-term temperature limits up to 32 hours after event initiation. SUSQUEHANNA - UNIT 2 TRM / B 3.10-5
Rev. 4 BASES ACTIONS ( continued) TRS E.2.1 (continued) The Completion Time reflects the 8 hours to complete Required ISFSI B 3.10.3 Action D.1 and the appropriate balance of time consistent with the applicable analysis results (Section 4.6.2.4, Reference 3). The event is assumed to begin at the time the HI-STORM heat removal system is declared NON-FUNCTIONAL. This is reasonable considering the low probability of all inlet ducts becoming simultaneously blocked by trash or debris. E.2.2 In lieu of implementing Required Action E.2.1, transfer of the MPC into a TRANSFER CASK will place the MPC in an analyzed condition and ensure adequate fuel cooling until actions to correct the heat removal system NON-FUNCTIONALITY can be completed. Transfer of the MPC into a TRANSFER CASK removes the HI-STORM from the TRO Applicability since storage operations does not include times when the MPC resides in the TRANSFER CASK. An engineering evaluation must be performed to determine if any concrete deterioration has occurred in the OVERPACK which prevents it from performing its design function. If the evaluation is successful and the air flow obstructions have been cleared, the OVERPACK heat removal system may be considered FUNCTIONAL and the MPC transferred back into the OVERPACK. Compliance with TRO 3.10.3 is then restored. If the evaluation is unsuccessful, the user must transfer the MPC into a different, fully qualified OVERPACK to resume storage operations and restore compliance with TRO 3.10.3. In lieu of performing the engineering evaluation, the user may opt to proceed directly to transferring the MPC into a different, fully qualified OVERPACK or place the TRANSFER CASK in the spent fuel pool and unload the MPC. The Completion Time of 24 hours reflects the Completion Time from Required Action E.2.1 to ensure component temperatures remain below their short-term temperature limits for the respective decay heat loads. The Surveillance Requirements 3.10.3.1 and 3.10.3.2 are intended to monitor the parameters that ensure that each HSM has adequate heat removal capability so to assure the strength and durability characteristics of each HSM is maintained. The Surveillance Requirements were obtained from reference 1 attachment A. SUSQUEHANNA - UNIT 2 TRM / B 3.10-5a
Rev. 4 BASES TRS ( continued) ISFSI B 3.10.3 Performance of TRS 3.10.3.1 and TRS 3.10.3.2 is dependent upon which Certificate of Compliance Number 1004 Amendment the HSM is loaded in accordance with. Amendments O and 4 require that both surveillances be performed. All other applicable Amendments allow for the performance of TRS 3.10.3.1 or TRS 3.10.3.2 to verify thermal performance. Surveillance Requirement 3.10.3.3 is intended to monitor the ability of the HI-STORM to reject heat from the MPC to the environment to assure long-term integrity of the stored fuel. This Surveillance Requirement was obtained from Reference 5 Appendix A. There are two options for implementing TRS 3.10.3.3, either of which is acceptable for demonstrating that the heat removal system is FUNCTIONAL. Visual observation that all inlet and outlet air ducts are unobstructed ensures that air flow past the MPC is occurring and heat transfer is taking place. Greater than 50% blockage of the total inlet or outlet air duct area renders the heat removal system NON-FUNCTIONAL and this TRO is not met. 50% or less blockage of the total inlet or outlet air duct area does not constitute NON-FUNCTIONALITY of the heat removal system. However, corrective actions should be taken promptly to remove the obstruction and restore full flow through the affected duct(s). As an alternative, for an OVERPACK with air temperature monitoring instrumentation installed in the outlet air ducts, the temperature rise between ambient and the OVERPACK air outlet may be monitored to verify FUNCTIONALITY of the heat removal system. Blocked inlet or outlet air ducts will reduce air flow and increase the temperature rise experienced by the air as it removes heat from the MPC. Based on the analyses of Section 4.6.2.4 of Reference 3, provided the air temperature rise is less than the limit stated in the TRS, adequate air flow and, therefore, adequate heat transfer is occurring to provide assurance of long-term fuel cladding integrity. The reference ambient temperature used to perform this Surveillance shall be measured at the ISFSI facility. The Frequency of 24 hours is reasonable based on the time necessary for HI-STORM components to heat up to unacceptable temperatures assuming design basis heat loads, and allowing for corrective actions to take place upon discovery of blockage of air ducts. SUSQUEHANNA - UNIT 2 TRM / B 3.10-Sb
Rev. 4 BASES REFERENCES ISFSI B 3.10.3
- 1. Dry Spent Fuel Storage Cask Certificate Of Compliance Number 1004
- 2. Safety Evaluation NL-96-055
- 3. Holtec International HI-STORM FW CSAR Hl-2114830
- 4. ANSI/ANS 57.9-1992
- 5. Certificate of Compliance and Technical Specification Evaluation for Certificate No. 1032 Amendment 5
- 6. NUH-003, CSAR, Safety Analysis Report for the Standardized NUHOMS Horizontal Modular System for Irradiated Nuclear Fuel SUSQUEHANNA - UNIT 2 TRM / B 3.10-5c}}