ML19106A159
| ML19106A159 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/28/2019 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19106A159 (79) | |
Text
{{#Wiki_filter:HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2019-3*191 USER INFORMATION: Name:GERLACH*ROSEY M Address : NUCSA2 Phone#: 542-3194 TRANSMITTAL INFORMATION: TO: GERLACH*ROSEY M LOCATION: USNRC EMPL#:028401 CA#:0363 02/28/2019 FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2) Mar. 28, 2019 THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE rHE 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 FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS. ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material. '*~
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TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 02/21/2019 ADD MANUAL TABLE OF CONTENTS DATE: 02/27/2019 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.2.1 ADD: REV: 14 REMOVE: REV:13 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS@ X3171 OR X3'194 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, E.LECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
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Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Content~ Issue Date: 03/12/2019 Procedure Name Rev Issue Date TEXT LOES 99 01/03/2019
Title:
LIST OF EFFECTIVE SECTIONS TEXT TOC 27 03/05/2019
Title:
TABLE OF CONTENTS TEXT 1.1 0 11/19/2002
Title:
USE AND APPLICATION DEFINITIONS TEXT 2.1 1 02/04/2005
Title:
PLANT PROGRAMS AND SETPOINTS PLANT PROG . TEXT 2,2 t ;.* li
Title:
PLANT PROGRAMS AND
- --=J TEXT 3.0 11 7
Change ID Change Number SETPOINT TABLE
Title:
APPLICABILITY TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILl:TY TEXT 3.1.1 1 11/09/2007
Title:
REACTIVITY CONTROL SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRA,M ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT 3.1.2 0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1.3 5 12/18/2017
Title:
REACTIVITY CONTROL SYSTEMS CONT~OL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 0 11/19/2002
Title:
REACTIVITY CO~TROL SYSTEMS CONTROL ROD SCRAM ~CCUMULA~ORS INSTRUMENTATION AND CHECK VALVE TEXT 3.2.1 14 02/27/2019
Title:
CORE OPERATING LIMITS ~EPORT (COLR) Page.!. of 15 Report Date: 03/28/19
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, Manual Name : TRM2 SSES MANUAL ~ f - - 1. *.~.} 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 I TEXT 3.3.6 5 03/05/2019 i..
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:
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 1 03/05/2015
Title:
WATER MONITORING INSTRUMENTATION Page£ of 15 Report Date: 03/28/19
SSES MANUAL Manual Name: TRM2 \\_~ Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.4.1 1 Ot/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 0 11/19/2002
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 11/19/2002
Title:
CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION Pagel of 15 Report Date: 03/28/19
SSES MANUAL Manual Name: TRM~ , __ )
- .::,**** Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.6.4 0 11/19/2002
Title:
CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 0 11/19/2002
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN TEXT3.7.2 0 11/19/2002
Title:
PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND-GROUND WATER LEVEL TEXT 3.7.3.1 5 . 02/16/2017
Title:
PLANT SYSTEMS FIRE SUPPRESSION WATER SUPP~Y 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 14 12/18/2017
Title:
.PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION rEXT 3.7.4 1 04/26/2006
Title:
PLANT SYSTEMS SOLID RADWASTE SYSTEM Page_! of 15 Report Date: 03/28/19
$SES.MANUAL Manual Name: TRM2 l I j} '*--:I 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 '.DEXT 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 SNUBB~RS 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 3 06/20/2012
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 2.
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION - AUTOMATIC of 15 Report Date: 03/28/19
SSES MANUAL Manual Name: TRM2 I i!
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Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.8.3 3 03/05/2019
Title:
ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT 3.8.4 1 02/04/2005
Title:
ELECTRICAL POWER 24 VDC ELECTRICAL SUBSYSTEM TEXT 3.8.5 1 11/14/2013
Title:
ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION TEXT 3.8.6 3 03/05/2019
Title:
ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8.7 2 10/22/2009
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT 3.9.1 0 11/19/2002
Title:
REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0 11/19/2002
Title:
REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 1 03/12/2019
Title:
REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 1 04/26/2006
Title:
MISCELLANEOUS SEALED SOURCE CONTAMINATION TEXT 3.10.2 1 04/09/2007
Title:
MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 2 06/15/2010
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) TEXT 3.10.4 2 04/17/2009
Title:
MISCELLANEOUS LEADING EDGE FLOW METER (LEFM) Page.§_ 1of 15 Report Date: 03/28/19
SSES MANUAL Manual Name: TRM2 , _ _J
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Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2
- 1
.,*i' TEXT 3.11.1.1 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION TEXT 3. 11. 1. 2 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE TEXT 3.11'.l.3 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM TEXT 3.11.1.4 2 10/09/2012
Title:
RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT 3. 11. 1. 5 3 03/05/2015
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT 3.11.2.1 4 03/12/2019
Title:
RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3. 11. 2. 2 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES TEXT 3.11.2.3 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM TEXT 3.11.2.4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3. 11. 2. 5 4 07/03/2013
Title:
RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3.11. 2. 6 8 07/21/2017
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.3 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS TOTAL DOSE Page 1 of 15 Report Date: 03/28/19
SSES MANUAL
- Manual Name
TRM2 t . 1 ~ Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.11.4.1 4 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 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 ;R.EQUIREMENT.s I,... ) 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 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS TEXT 4.6 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM ~J*
- Page~
of 15 Report Date: 03/28/19
SSES MANUAL Manual Name: TRM2 '*...:.5/ Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 4.7 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS TRAINING TEXT B3.0 6 03/05/2015
Title:
APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.1.1 2 04/29/2014
Title:
REACTIVITY CONTROL SYSTEM BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION. TEXT B3.l.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
- /
0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.1 0 11/19/2002
Title:
CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR) TEXT B3.3.1 1 01/31/2014
Title:
INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 2 03/31/2011
Title:
INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 2 11/09/2007
Title:
INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION. TEXT B3.3.4 7 07/21/2017
Title:
INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT B3.3.5 2 11/09/2007
Title:
INSTRUMENTATION BASES THIS PAGE INTENTIONALLY LEFT BLANK Page~ of 15 Report Date: 03/28/19
SSES MANUAL Manual *Name: TRM2 jj 1 **-* Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3. 3. 6 \\ 6 03/05/2019
Title:
INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION TEXT B3.3.7 2 11/10/2015
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 j TEXT B3. 3. 11 ..,:/ 1 10/22/2003
Title:
INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3.3.12 0 04/16/2009
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: 03/28/19
SSES MANUAL Manual Name: TRM2 1
- ca./\\ 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 B3.5.1 1 03/05/2019
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.S.3 2 03/05/2019
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM LONG TERM NITROGEN SUPPLY TO ADS TEXT B3.6.1 0 11/19/2002
Title:
CONTAINMENT BASES VENTING OR PURGING TEXT B3.6.2 0 11/19/2002
Title:
CONTAINMENT BASES SUPPRESSION CHAMB~R-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 1 12/14/2004
Title:
CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM.BOUNDARIES TEXT B3.7.1 0 11/19/2002
Title:
PLANT SYSTEMS BASES EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN) TEXT B3.7.2 0 11/19/2002
Title:
PLANT SYSTEMS BASES ULTIMATE HEAT SINK (UHS) GROUND WATER L~VEL 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: 03/28/19
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 2 04/29/2014
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 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 15 Report Date: 03/28/19
SSES MANUAL Manual Name: TRM2 ) '._--:0:=l 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 B3.7.11 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 B3.8.2.1 0 11/19/2002
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Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION - CONTINUOUS TEXT B3.8.2.2 1 09/17/2004
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION - AUTOMATIC TEXT B3.8.3 0 11/19/2002
Title:
ELECTRICAL POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT B3.8.4 0 11/19/2002
Title:
ELECTRICAL POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT B3.8.5 1 11/14/2013
Title:
ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B3.8.6 4 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 15 Report Date: 03/28/19
SSES MANUAL Manual Naine: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.9.1 0 11/19/2002
Title:
REFUELING OPERATIONS BASES DECAY TIME TEXT B3.9.2 0 11/19/2002
Title:
REFUELING OPERATIONS BASES COMMUNICATIONS TEXT B3.9.3 1 03/12/2019
Title:
REFUELING OPERATIONS BASES REFUELING PLATFORM TEXT B3.10.l 0 11/19/2002
Title:
MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 1 04/10/2007
Title:
MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT B3.10.3 0 11/19/2002
Title:
MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION {ISFSI) TEXT B3. 11.1. 1 1 05/10/2016
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT !33. 11. 1. 2 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3.11.1. 3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3. 11. 1. 4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3. 11. 1. 5 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS. MONITORING INSTRUMENTATION TEXT B3.ll.2.1 1 12/14/2004
Title:
RADIOACTIVE EFFLUENTS BASES DOSE RATE Page 14 of 15 Report Date: 03/28/19
SSES MANUAL Manual Name: TRM2 il \\.--,,/ Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.11. 2. 2 0 11/19/2002.
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES TEXT B3.11.2.3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - IODINE, TRITIUM, AND RADIONUCLIDES PARTICULATES FORM TEXT B3.11.2.4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.ll.2.5 5 07/03/2013.
Title:
RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3.ll.2.6 2 09/08/2016
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT B3. 11. 3 0 11/19)2002
Title:
RADIOACTIVE EFFLUENTS BASES TOTAL DOSE TEXT B3.ll.4.1 5 03/05/2015
Title:
RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3.ll.4.2 0 11/19/2002
Title:
RADIOAC'.I'IVE EFFLUENTS BASES LAND USE CENSUS TEXT B3.ll.4.3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAM TEXT B3.12.l 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 IN Page 15 of 15 Report Date: 03/28/19
Rev. 14 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 REQUIRED ACTION A. Core Operating Limits not A.1 Perform action(s) met. described in referenced Technical Specification. TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANGE
NOTE------------------------------------
No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications. SUSQUEHANNA - UNIT 2 3.2-1 COMPLETION TIME Specified in referenced
- Technical Specifications.
FREQUENCY N/A
Rev. 14 Susquehanna SES Unit 2 Cycle 19 PL-NF-17~001 Rev. 1 Page 1 of 62 CORE OPERA TING LIMITS - REPORT SUSQUEHANNA UNIT 2 3.2-2 Nuclear Fuels Engineering February 2019
Rev. Affected No. Sections 0 ALL 1 6.0 ALL Rev. 14 PL-NF-17-001 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 2 Cycle 19 operation. Figures 6.2-2 through 6.2-4 (editorial) and 6.2-5 (technical) are revised to account for the cycle achieving a greater core average exposure than what was assumed to initially analyze Unit 2 Cycle 19 (U2C19). Updated U2C19 licensing analysis results (Framatome, formerly AREVA, report ANP-3536, Rev. 3) at a bounding core average exposure only affect the power-dependent, eq~ipment out-of-service Linear Heat Generation Rate (LHGR) multipliers. On pages 27, 29, and 32, text supporting these Figures is also updated. Removed page count prefix TRM/ and Effective Date from footer to align formatting with the new process. FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 2 3.2-3
Rev. 14 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 19 CORE OPERATING LIMITS REPORT Table of Contents PL-NF-17-001 Rev. 1 Page 3 of 62
1.0 INTRODUCTION
......................................................................................................... 4 2.0 DEFINITIONS............................................................................................................. 5 3.0 SHUTDOWN MARGIN................................................................................................ 6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)....................... 7 5.0 MINIMUM CRITICAL POWER RATIO (MCPR)........................................................... 9 6.0 LINEAR HEAT GENERATION RATE (LHGR)............................................................. 27 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS........................................................................................................ 38 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION.........................................40 9.0 POWER/ FLOW MAP................................................................................................ 58 10.0 OPRM SETPOINTS.................................................................................................... 60
11.0 REFERENCES
............................................................................................................ 61 SUSQUEHANNA UNIT 2 3.2-4
Rev. 14
1.0 INTRODUCTION
PL-NF-17-001 Rev. 1 Page 4 of 62 This CORE OPERATING LIMITS REPORT for Susquehanna Unit.2 Cycle 19 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 3.2-5
Rev. 14 2.0 DEFINITIONS PL-NF-17-001 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 LHGRFACr is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFACt 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 RA TED 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 MAPRA T 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 3.2-6
Rev. 14 PL-NF-17-001 Rev. 1 Page 6 of 62 3.0 SHUTDOWN MARGIN 3.1 Technical Specification Reference Technical Specification 3.1.. 1 3.2 Description The SHUTDOWN MARGIN shall be equal to or greater than: a) 0.38% Lik/k with the. highest worth rod analytically determined OR b) 0.28% Lik/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 (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM 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 SDM) 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 3.2-7
Rev. 14 PL-NF-17-001 Rev. 1 Page 7 of 62 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RA TE (APLHGR) 4.1 Technical Specification Reference Technical Specification 3.2.1 4.2 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 for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable a*nd Inoperable in Two Loop operation. The APLHGR limits for Single Loop operation are provided in Section 8.0. SUSQUEHANNA UNIT 2 3.2-8
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Rev. 14 PL-NF-17-001 Rev. 1 Page 9 of 62 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) 5.1 Technical Specification Reference Technical Specification 3.2.2, 3.3.4.1, 3.7.6, and 3.7.8 5.2 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 5.3 Description The 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 (ATRI UM'-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 EOC Figure 5.2-10:Power-Dependent MCPR value determined from BOC to EOC SUSQUEHANNA UNIT 2 3.2-10
Rev. 14 PL-NF-17-001 Rev. 1 Page 10 of 62 The MCPR limits in Figures 5.2-1 through 5.2-10 are valid for Two Loop operation. The MCPR limits for Single Loop operation are provided in Section 8.0. 5.4 Average Scram Time Fraction If the average measured scram times are greater than the Realistic Scram times listed in Table 5.3-1 then the MCPR operating limits corresponding to the* Maximum Allowable Average Scram Insertion Time must be implemented. Determining MCPR operating limits based on interpolation between scram insertion times is not permitted. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures. SUSQUEHANNA UNIT 2 3.2-11
Rev. 14 PL-NF-17-001 Rev. 1 Page 11 of 62 Main Turbine Bypass/ EOC-RPT / Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 3.2-12
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REFERENCE:
T.S. 3.2.2
........ ~
30 40 ~ I 108, 1.21 I 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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E SSES UNIT 2 CYCLE 19 36 I I I I 3.4 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.2 ---123, 3.0911--+---------1 t----.-----+-------t----iCURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 ~'\\L..: 12:.:.6!.,:, 2:.:.:.9::5:...rl------r----i I 23, 3.041\\. CURVE C: CORE POWER :s:: 26% AND CORE FLOW :s:: 50 MLBM/HR ' 126, 2.841 2.8 ~ 2.6 _ C _1-------l1-------+-----1SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE c PER SR 3.7.6.1 AND 3.7.6.2 ~ Cll 2.4 Q. 0 w 0::: ~. '-----~-------.----~-----,------.----~ 1------11----+----------lUSED IN DETERMINING MFLCPR ";.J ~ 2.2 t: 5!: 2.0 I 26.01, 1.99 I 1.8 140, 1.70 126.01, 1.891 A I---L--__:._-__.i+--~:::--....3.t-,.....-::::-----+--- -+----------l,-----------------1 ~ ------------ 1.6 I 80, 1.44 I I 40, 1.62 194.46, 1.37 I
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REFERENCE:
T.S. 3.2.2 I I 80, 1.41 L 1.2 I I 85, 1.39 I 94.46, 1.34 1100, 1.321 L__ __ __JL__ ___ L_ ___ L_ ___ L_ ___ ..1._ ___ ..1..._____::====~~'..!......'...:=..J-.J 20 30 40 ~ 60 ro 80 90 Core Power(% RATED) MCPR OPERA TING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-2 100
Rev. 14 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 3.2-15 PL-NF-17-001 Rev. 1 Page 14 of 62
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REFERENCE:
T.S. 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 TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-3 1108, 1.36 I 100 110
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C I!! Cl) C. 0 UJ 0::: N C.. I 0 ~ :l!: SSES UNIT 2 CYCLE 19 36 23, 3.431 3.4 \\. LEGEND \\ \\ CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 INSERTION TIME 123, 3.041 I 26, 3.15 I CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME \\. 3.0 c\\ CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 2.8 ' I 26, 2.841 2.6 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 2.4 2.2 USED IN DETERMINING MFLCPR i 126.01, 2.03 I 2.0 1.8 40, 1.741 ~ A B I 80, 1.54 I 1100, 1.54 I 1.6 -J
REFERENCE:
T.S. 3.7.6 and 3.2.21 1.4 1.2 20 30 40 50 60 70 80 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC to EOC) FIGURE 5.2-4 90 100
SUSQUEHANNA UNIT 2 Rev. 14 EOC-RPT Inoperable 3.2-18 PL-NF-17-001 Rev. 1 Page 17 of 62
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1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 19 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 USED IN DETERMINING MFLCPR i 130, 1.541 A ~ B I
REFERENCE:
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I 108, 1.21 I ~ 60 70 80 90 100 110 Total Core Flow (MLB/HR) MCPR OPERA TING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-5
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1----t---+------+----l SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE,.. PER SR 3.7.6.1 AND 3.7.6.2 C ~ I I I I I O (l)c. 2.4 1------1--+------+----r--~---~-----'-----....__--------'----1-1[ 2.0 1.8 1.6 1.4 1.2 USED IN DETERMINING MFLCPR 126.01, 1.991 140, 1.701 A Bi-----+----------------1 ~
REFERENCE:
T.S. 3.3.4.1 and 3.2.2! 180, 1.441 20 30 ~ ~ M ro ~ Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC to EOC) FIGURE 5.2-6 194.46, 1.43 L 1100, 1_43 ! 90 100
Rev. 14 PL-NF-17-001 Rev. 1 Page 20 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 3.2-21
l/l C 2.2 l/l 0 C m I
- t>
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1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 19 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 I I I USED IN DETERMINING MFLCPR r 130, 1.54 I r-----.__ A B I
REFERENCE:
T.S. 3.7.8 and 3.2.21 r---------....____ 30 40 50 1108, 1.211 ~ 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 5.2-7 100 110 "'O "'O D> r (0 I CD z N 7' ...... ;a...... 0 CD -;J .... < 0 0). 0 'I\\.)....>.....>.
(./l C (./l 0 C m I )> z z )> C z =i 36 3.4 3.2 -123, 3.091 N 3 ~ .0 \\" 1 26, 2.95 1 123, 3.041 I .8 I 26, 2.841 2 -c .6 .4
- 26.01, 2.30 :
.............. ~ 140, 2.08 I .2 2.0 ~ 1.8 1.6 SSES UNIT 2 CYCLE 19 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I I USED IN DETERMINING MFLCPR [ A B -..... r--,.....__ I 80, 1.461 ~
REFERENCE:
T.S. 3.7.8 and 3.2.2! I 94.46, 1.37 L 1.4 1.2 20 30 40 50 60 70 80 Core Power(% RATED) MCPR OPERA TING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC to EOC) FIGURE 5.2-8 I 100, 1.351 90 100
Rev. 14 One TSV or TCV Closed SUSQUEHANNA UNIT 2 3.2-24 PL-NF-17-001 Rev. 1 Page 23 of 62
l/l C l/l 0 C m I )> z z )> C z =i N E
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- E SSES UNIT 2 CYCLE 19 2.2 LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
- INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I
I I 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, 1.74 I USED IN DETERMINING MFLCPR r 1.7 1.6 ~ -~ ~ A .............. 8 1.5 1.4 .... ~ ~ ~ I 108, 1.371
- 1.3 I
REFERENCE:
T.S. 3.2.2 and TRM 3.3.7 I 1.2 30 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 s 75% rated power 110
(/l C (/l 0 C m I )> z z )> C z 3.6
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0 w 0::: N C.. 2 I (.) ~ :l!: .2 '\\ ,__ C I 26, 2.841 .2.o I 26.01, 1.99 I ~ SSES UNIT 2 CYCLE 19 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 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR 1.8 140, 1.10 I I 26.01, 1.89 I A ~ .6 175, 1.471 I 40, 1.62 I 1 1.4 1.2 20 B I
REFERENCE:
T.S. 3.2.2 and TRM 3.3.7 I 30 40 50 60 Core Power (% RA TED) MCPR OPERA TING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED* TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-10 I 75, 1.43 I 70
- Operation with one TSV or TCV closed is only supported at power levels s; 75% rated power 80
Rev. 14 Table 5.3-1 PL-NF-17-001 Rev. 1 Page 26 of 62 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 3.2-27
Rev. 14 PL-NF-17-001 Rev. 1 Page 27 of 62 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 6.2 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 6.3 Descriptio*n 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 2 3.2-28
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REFERENCE:
T.s. 3.2.3 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 --l---f---~--~---l.--l--...:..--~--~---:..-- -.:..--i--~---l.--J--..:..--~--~---l.--~--..:...--i--~---l.--J-- USED IN DET*ERMINING FDLRX 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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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I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I --*--~---~--~---~--*--...... --~--~---~--*--...... --~--~---~ *--...... --~--~---~--*--...... --*--~---~--*---+---*--~---~--~---+---*--~---~--~---+---*--~--- I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I' I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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--J---~--~---'---L--J---~--~---'---L--J---~--~---'---L--J-- --~---'---~--J---~--~--..L.--~--J---~--J--..L.--~--J---~--J--..&..--~--J--- 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 I I I I I I I I I I I I 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---t--~---r--t--t---t--1---r--t---t--t--1---r--1---:---t--1---~--f---:---t--. -L--f---:---t--1---~--1--1---t--1---~--1---t--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
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Rev. 14 PL-NF-17-001 Rev. 1 Page 29 of 62 Main Turbine Bypass/ EOC-RPT / Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 3.2-30
(/) C (/) 0 C m I )> z z )> C z -I N w N I w 1.10 1.00 0.90 0.80 0.70 0.60 0.50 0.40 0.30 I I I SSES UNIT 2 CYCLE 19 I I I 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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REFERENCE:
T.S. 3.2.3 I I I I I I I 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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SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3. 7.6.1 AND 3. 7.6.2 30 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 . l 40 50 60 70 80 90 100 Total Core Flow (MLB/hr) FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE A TRIUM'-1 O FUEL FIGURE 6.2-2 110
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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 I I I I I I I I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES I I I I I s1 r r r 1 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
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REFERENCE:
T.S. 3.2.3, 3.3.4.1, 3. 7.6 and 3. 7.8 I I I I I I I
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30 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 40 50 60 70 80 90 100 Total Core Flow (MLB/HR) FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS OR EOC-RPT OR BACKUP PRESSURE REGULATOR INOPERABLE ATRIUM'-10 FUEL FIGURE 6.2-4 110
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____ J _______ J _______ J 94.46, 1.00 L_~! ___.. I I I I LEGEND CURVE A: BASE CURVE I I I I I I I I I I I I I I I I I I I I CURVE B: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR
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REFERENCE:
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Rev. 14 One TSV or TCV Closed SUSQUEHANNA UNIT 2 3.2-36 PL-NF-17-001 Rev. 1 Page 35 of 62
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REFERENCE:
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- Operation with one TSV or TCV closed is only supported at power levels ~ 75% rated power 110
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REFERENCE:
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~--~*~ I I I I I I I I I I I I I I I I I I I I 26, 0.43 I I I I I I I I I I ---~-----------~----------~-----------~----------1-----------~----------~-----------~----------1-----------~----------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 --,23, 0.40--------~----------~-----------~----------~-----------~----------~-----------~----------~-----------~----------~----------- I I I I I I I I I I 20 I I I I I I I I I I I I I 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 30 40 50 60 Core Power (% RA TED) POWER DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED" ATRIUM'-10 FUEL FIGURE 6.2-7 70
- Operation with one TSV or TCV closed is only supported at power levels s 75% rated power 80
Rev. 14 PL-NF-17-001 Rev. 1 Page 38 of 62 7.0 ROD BLOCK MONITOR {RBM) SETPOINTS AND OPERABILITY REQUIREMENTS 7.1 Technical Specification Reference Technical Specification 3.3.2.1 7.2 Description The RBM Allowable Value and Trip Setpoints for; a) Low Power Range Setpoint, b) Intermediate Power Range Setpoint, c) High Power Range Setpoint, d) Low Power Range - Upscale, e) Intermediate Power Range - Upscale, and f) High Power Range - Upscale shall be established as specified in Table 7.2-1. The RBM setpoints are valid for Two Loop and Single Loop Operation, Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable. The RBM system design objective is to block erroneous control rod withdrawal initiated by the operator before fuel design limits are violated. If the full withdrawal of any control rod would not violate a fuel design limit, then the RBM system is not required to be operable. Table 7.2-2 provides RBM system operability requirements to ensure that fuel design limits are not violated. SUSQUEHANNA UNIT 2 3.2-39
Rev. 14 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 83.0 123.4 117.4 107.6 PL-NF-17-001 Rev. 1 Page 39 of 62 Nominal Trip Setpoint 24.9 61.0 81.0 123.0 117.0 107.2 <1J 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 <2,3l (% of Rated) 2: 28 and< 90 < 1.76 2: 90 and< 95 < 1.47 ~95 < 1.68 <2l Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable. <3l Applicable to both Two Loop and Single Loop Operation. SUSQUEHANNA UNIT 2 3.2-40
Rev. 14 PL-NF-17-001 Rev. 1 Page 40 of 62 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 Technical Specification Reference Technical Specification 3.2.1, 3.2.2, 32.3, 3.3.4.1, 3.4.1, 3.7.6, and 3.7.8 8.2 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 8.3 Description APLHGR The APLHGR limit for ATRIUM'-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1. The APLHGR limits in Figure 8.2-1 are valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable in Single Loop operation. 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 / 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 SUSQUEHANNA UNIT 2 3.2-41
Rev. 14 d) Backup Pressure Regulator Inoperable PL-NF-17-001 Rev. 1 Page 41 of 62 Figure 8.2-8: Flow-Dependent MCPR value determined from BOC to EOG Figure 8.2-9: Power-Dependent MCPR value determined from BOC to EOG e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 8.2-10:Flow-Dependent MCPR value determined from BOC to EOG Figure 8.2-11 :Power-Dependent MCPR value determined from BOC to EOG The MCPR limits in Figures 8.2-2 through 8.2-11 are valid only for Single Loop operation. Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0. RBM Setpoints and Operability Requirements The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0. SUSQUEHANNA UNIT 2 3.2-42
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Rev. 14 PL-NF-17-001 Rev. 1 Page 43 of 62 Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 3.2-44
Vl C 3.6 Vl 0 C m I 3.4 )> z z )> C z 3.2 =i N 3.0 2.8
- e
- i C)
C: 2.6 ns... Cl) C. 0 2.4 c..u 0::: N
- a.
I (.) .j:::,, (J1 a: 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 19 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 USED IN DETERMINING MFLCPR I 130, 1.871 A B I I
REFERENCE:
T.S. 3.4.1 and 3.2.21 I 108, 1.48 ~ 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 SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-2 110
l/l C l/l 0 C m I )> z z )> C z =i N w N I .j:::,, Cl'l E
- J Cl C:
Ill... Cl) C. 0 0:: a.. () ~ 46 4.4 4.2 4.0 1-------+---------l SSES UNIT 2 CYCLE 19 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 I 23, 3.711
,...---+--------1---1 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 3.6
,.._ I I 123, 3.65 F\\ 26, 3.55 I I I 3.4 126, 3.42 11--------1-----~---I ,__ C --l-==:::::::::i:=:!..._-----l--------1----l SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2. 3.2 3.0 USED IN DETERMINING MFLCPR 2.8 2.6 I 26.01, 2.40 I 2.4 2.2 I 61 140, 2.0 I A - 8 160, 1.901 2.0 1.8 1.6 ]
REFERENCE:
T.S. 3.4.1 and 3.2.21 1.4 20 30 40 50 60 70 Core Power(% RATED) 80 90 MCPR OPERA TING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-3 100, 1.90 I 100
Rev. 14 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 3.2-47 PL-NF-17-001 Rev. 1 Page 46 of 62
Vl C V, 0 C m
- r:
)> z z )> C z =i N ~ E
- J
. C) C:
- l ns...
Q) C. 0 w 0:: N ll. I () ~ 00 :e SSES UNIT 2 CYCLE 19 4.2 4.0 LEGEND CUR.VE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.8 INSERTION TIME 3.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME ~-4. 3.2 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS - VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 3.0 I I I 2.8 I USED IN DETERMINING MFLCPR 2.6 2.4 2.2 130, 2.111 2.0 A B 1.8 H
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 I I 108, 1.65 I-1.6 1.. 4 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
V'l ~ 44 o* C m I )> z z )> C z ~ f',..J
- t::
E
- i C)
C ra.. Cl) C. 0 w ~ f',..J Cl. I 0 .i::,. lO
- !E 4.2 W23, 4.121
\\ 4.0 \\ 3.8 C - 126, 3.78 I I 23, 3.651 \\ 3.6 \\ \\ '26, 3.42' 3.4 3.2 3.0 2.8 2.6 I 26.01, 2.45 I 2.4 "'...... "'--. : 40, 2.11 : 2.2 SSES UNIT 2 CYCLE 19 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 :s;; 26% AND CORE FLOW :s;; 50 MLBM/HR SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 USED IN DETERMINING MFLCPR 160, 1.961 A B 2.0 I
REFERENCE:
T *. s. 3.4.1, 3.7.6, and 3.2.21 1.8 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 C 100, 1.96 I 100 "U "U ru r (C I CD z 71 CX) ::a...>. 0 CD -;-J -<o 0). 0 N...>....>.
SUSQUEHANNA UNIT 2 Rev. 14 EOC-RPT Inoperable 3.2-50 PL-NF-17-001 Rev. 1 Page 49 of 62
(./l C 4.0 (./l 0 C m
- I:
)> 3.8 z z )> 3.6 C z =l N 3.4 3.2 E 3.0
- J Cl C
2.8 n:s... Cl) C. 0 2.6 w 0:: N
- a.
I (.) u, I-'
- a:
2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 19 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 USED IN DETERMINING MFLCPR I
- l 30, 1.871 A
B
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 !
- 108, 1.48 I 30 40 50 60 70 80 90 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-6 100 110
CJ') C CJ') § m I )> z z )> C z =i N 4.6 4.4 4.2 4.0 SSES UNIT 2 CYCLE 19 t-------1,------+---1CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME r;:::==:::;---t-------t---1CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8...j 23, 3.71 li----------t CURVE C: CORE POWER~. 26% AND CORE FLOW~ 50 MLBM/HR 3.6 "-..,_ I I I 23, 3.65 l\\.t""t"'t""l-\\-2.....:6,_3_.5_5...J-----;----;.___----r_~-----r-----~----~----~-- .E 3.4 1 1 1 1
- J
_ C _ .JL..:2:.:::6!....:, 3~.4:::!2:..Jlr----r-----11 g> 3.2 - ~ a, 3.0 Q. 0 I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I I I I I I I w 0::: 2.8 N C.. USED IN DETERMINING MFLCPR t= I (.) ~ :;E 2.6 2.4 2.2 2.0 1.8 i------+---1 126.01, 2.40 :------------------+---------------- 1------+-.;;:,o,,,,i:::---1: 40, 2.06 11------------------+---------- I I A B 11 oo, 1.90 I 60, 1.90 ----- ---+-------!:===,---' H
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.21------------------+----- 1.6 1.4 20 30 40 50 60 70 80 Core Power (%.RATED) MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-7 90 100
- a CD
- =:::
~
Rev. 14 PL-NF-17-001 Rev. 1 Page 52 of 62 Backup Pressure Regulator. Inoperable SUSQUEHANNA UNIT 2 3.2-53
<.n C 4.0 <.n 0 C m
- c 3.8
)> 2 z )> 3.6 C z =i N 3.4 3.2 ~ E 3.0
- i C)
C 2.8 cu... Cl) C. 0 2.6 w Cr! N C. I u u, .j:::,,
- al:
2.4 2.2 2.0 1.8 1.6 1.4 . SSES UNIT 2 CYCLE 19 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, 1.87 I A 8 I
REFERENCE:
T.s~ 3.4.1, 3.7.8, and 3.2.2 30 40 50 60 70 80 90 Total C~re 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 I 108, 1.48 I 110
(./l C (./l 0 C m I )> z z )> C z =i 46 4 4 4 .4 .2 .o N 3.8 I 23, 3.711 w N I u, u, E
- J en C:
ns... (I) C. 0 0:: ll. (.) ~ 3 3 3 3 2 2 2 2 2 6 I I '""' I 26, 3.55 I I 23, 3.65 : '\\
- 4 - c -n2s, 3.421
.2 .0
- 26.01, 2.77:
.8 .6 .4 .2 .0 SSES UNIT 2 CYCLE 19 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER ~ 26% AND CORE FLOW ~ 50 MLBM/HR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I I I I I USED IN DETERMINING MFLCPR 140, 2.51 \\ A B , so, 2.141 ~ 1.8 ~
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.21 .6 1 1.4 20 30 40 50 60 70 80 Core Power (% RA TED) MCPR OPERA TING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-9 90 I 100, 2.141 100 "U "U tu r (Q I CD z CJ1 71 .j:>. ::0....>. 0 CD -;-J --h < 0 O'). 0 N->-->-
Rev. 14 One TSV or TCV Closed SUSQUEHANNA UNIT 2 3.2-56 PL-NF-17-001 Rev. 1 Page 55 of 62
l/l C 4.0 l/l 0 C m I 3.8 )> z z )> 3.6 C z =i N 3.4 3.2 E 3.0
- J C)
C: 2.8 cu... Cl) C. 0 2.6 w 0::: N ll.. I (.) lJ1 '-I
- !E 2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 19 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 LJ 30, 2.11 I A 8 J
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I 30 40 50 60 70 80 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 90 100
- Operation with one TSV or TCV closed is only supported at power levels :;;; 75% rated power 1108, 1.67 I 110
Vl C 4.6 Vl 0 C m 4.4 I )> z 4.2 z )> C 4.0 z =i N 3.8 3.6 3.4 E
- J C) 3.2 C:
C'CI... 3.0 Q) C. 0 c..u a: 2.8 N 0.. I (.) u, CX) a=: 2.6 2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 19 I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
- 23, 3.71:
CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR ~ I I I 23, 3_65'"p--~ I 26, 3.55 I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 126, 3.421 -c ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR I 26.01, 2.40 I
- 40, 2.06 I A
B ~
- 60, 1.90:
J
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I 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
- Operation with one TSV or TCV closed is only supported at power levels :,; 75% rated power
- 75, 1.90 80
Rev. 14 PL-NF-17-001 Rev. 1 Page 58 of 62
- 9.0 POWER/ FLOW MAP 9.1 Technical Specification Reference Technic~I Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER/ core flow outside of Stability Regions I and II of the Power/ 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 / 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 3.2-59
";F. - ~
- a.
iii E Q) ..c: I-110 100 90 80 70 60 50 40 30 20 10 Rev. 14
Purpose:
Initial/ Date: I STABILITY REGION II IMMEDIAlELY EXITIAW APPLICABLE T..:: PROCEDURE. ~ RESJRICTED REGION IF ABOVE MELLLA BOUNDARY, IMMEDIA lEL Y EXITIAW APPLICABLE PROCEDURE. I I I I I I I I I I I I IHJJ:: J(<- ..J.J=:=:=: =: =-==,=,=, =,==,=.=.=,==: =: =:=:4-1., _L_' -r-r-r-r- *t-rt*t -r-t*;--1-- --i--tl*r- --:-
- r-r*r*r- --1-*rT*r *r-T*rr* *r-r-T*r- -
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-~--:- ~- --~--;--~-~-- -:--1--~- --:--~--:--~- I I Approx,,,,,****,,,, One Pump :- --:-:--:-:-- -:--r-1--r- --i--:--i--t-PL-NF-17-001 Rev. 1 Page 59 of 62 120 110 100 90 80 70 60 50 I I I I I I I -..1--1,.-..1-- 1 I I I I I I I I I I I I I -l--'--l.-.J-- -..I--L-.J-- 1 I I I I I I I I I I I I I -:-:--t-:-- -:--:-:-- -t-t-t-1-- -r-1-- I I I I 40 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-- --tl-t-i-- --1--r-l- -r-+-r-+- -+-f-+- 30 -r-+-+-+- -+-r-+- -t-+-t-t- -+-r-+- -+--:--t--:-- --:--t--:-- 1 j j I I 1 1 20 +-+,-+,-+, -+, -+-+-+-+-+-i-,k:-i,,11-+-I--+-+-+-+#-+-+, --+-1: 80°k Speed. : I I I I I I I I I I I I 10 --t-+-~-~-- -+-~-~-+- --~-1-+-1-- -~-+-~-+- -+-!-+-!- -j--r-t--r- }t[{ J}~} JH+ JfjJ: J}}{ :_-f:.~-t:.*:_~:.'.;:*_J:.*- __ : -_J:.*_-__ :*.f:,:--~:.*:_--_: 0.... ~:.:...-i-l-~=::.i-i--l--i--i-~:.j....+--i--i-i----<-,l-i-' _j.' -i-' -*~~'_j.' -i-' -i-'..j'_j.' -i-' -i-' -i'~'~'-i-' -i-' -'i-i'i-i'-,l-i--i--i--+--l-+--i-i-J~ 0 110 0 10 20 30 40 50 60 70 80 90 Total Core Flow (Mlbm/hr) (for SLO <75% Pump Speed Use Form G0-200-009-2) Figure 9.1 SSES Unit 2 Cycle 19 Power I Flow Map 100 SUSQUEHANNA UNIT 2 3.2-60
Rev. 14 10.0 OPRM SETPOINTS 10.1 Technical Specification Reference Technical Specification 3.3.1.1 10.2 Description PL-NF-17-001 Rev. 1 Page 60 of 62 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 3.2-61
Rev. 14
11.0 REFERENCES
PL-NF-17-001 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 NRG, 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. 1 O. 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 NRG SER (November 30, 1993).
SUSQUEHANNA UNIT 2 3.2-62
Rev. 14 PL-NF-17-001 Rev. 1 Page 62 of 62
- 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.
- 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-074(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 Computer Program for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation, August 1990.
- 19. ANF-1358(P)(A), Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005.
SUSQUEHANNA UNIT 2 3.2-63}}