ML19011A057
| ML19011A057 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/07/2019 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19011A057 (40) | |
Text
UUJ.J.* U / / .e...V..LJ Page 1 of 3 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2019-383 USER INFORMATION:
GERLACH*ROSEY M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 542-3194 TRANSMITTAL INFORMATION:
TO: GERLACH*ROSEY M 01/07/2019 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ON THIS TRANSMITTAL. WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF
~.RRORS.
1rTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no
, , __ . ,he will be issued with the updated material.
TRM2 - TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 12/03/2018
. ADD MANUAL TABLE OF CONTENTS DATE: 01/04/2019 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.10.4 ADD: REV: 2 ADD: REV: 1
VI I tLo V.J...J Page 2 of 3 REMOVE: REV:l CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.6.2 REMOVE : REV: 2 ADD: REV: 3 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 4.2 REMOVE: REV: 0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 4.3 REMOVE: REV: 0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT B3.3.9 REMOVE : REV: 3 OD: REV: 4 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT B3.4.4 REMOVE : REV: 0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT B3.4.6 ADD: REV: 2 REMOVE : REV: 1 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT LOES REMOVE: REV:98
U UJ.J.
- V I I .e.. V ..1.-1 Page 3 of 3 ADD: REV: 99 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT TOC ADD: REV,: 26 REMOVE: REV:25 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS@ X3107 OR X3171 FOR ASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents Issue Date: 01/04/2019 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 99 01/03/2019
Title:
LIST OF EFFECTIVE SECTIONS TEXT TOC 26 01/03/2019 /~'\
Title:
TABLE OF CONTENTS
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TEXT 1.1
Title:
USE AND APPLICATION DEFINITIONS 0 11/19/2002 A;
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PLANT PROGRAMS AND SETPOINTS PLANT PROG~S
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REACTIVITY CONTROL I .--.., \. '-. *,
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Title:
REACTIVIT¥ CON~ROL SYSTEMS CONTROL ROD DRIVE* (CRD) HOUSING SUPPORT
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TEXT 3 .1. 3 5 12/18/2017
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3 .1.4 0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT 3.2.1 13 03/26/2017
Title:
CORE OPERATING LIMITS REPORT (COLR)
Page_! of 15 Report Date: 01/07/19
SSES MANUAL Manual Name: TRM2 f
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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 4 04/29/2014
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: 01/07/19
SSES MANUAL
, Manual Name: TRM2
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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 1
- ._ - /
Title:
REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT 3.5.1 1 02/04/2005
Title:
ECCS AND RCIC ADS MANUAL INHIBIT TEXT 3.5.2 1 11/09/2007
Title:
ECCS AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0 11/19/2002
Title:
ECCS AND RCIC 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: 01/07/19
SSES MANUAL Manual Name: TRM2 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 W~TER SYSTEM (ESW) SHUTDOWN TEXT 3.7.2 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 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 14 12/18/2017
Title:
PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION TEXT 3.7.4 1 04/26/2006
Title:
PLANT SYSTEMS SOLID RADWASTE SYSTEM Page! of 15 Report Date: 01/07/19
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 1 08/28/2006
Title:
PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 2 04/29/2014
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS}
TEXT 3.7.11 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
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV} THERMAL OVERLOAD PROTECTION -
AUTOMATIC Page i of 15 Report Date: 01/07/19
SSES MANUAL Manual Name: TRM2
(_ Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.8.3 2 06/20/2012
Title:
ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT 3.8.4 1 02/04/2005
Title:
ELECTRICAL POWER 24 VDC ELECTRICAL SUBSYSTEM TEXT 3.8.5 1 11/14/2013
Title:
ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION TEXT 3.8.6 2 12/14/2006
Title:
ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8.7 2 10/22/2009
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT 3.9.1 0 11/19/2002
Title:
REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0 11/19/2002
Title:
REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 0 11/19/2002*
Title:
REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 1 04/26/2006
Title:
MISCELLANEOUS SEALED SOURCE CONTAMINATION TEXT 3.10.2 1 04/09/2007
Title:
MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 2 06/15/2010
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT 3.10.4 2 04/17/2009
Title:
MISCELLANEOUS LEADING EDGE FLOW METER (LEFM)
Page .§. of -15 Report Date: 01/07/19
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 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. 11.1. 3 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM TEXT 3.11.1.4 2 10/09/2012
Title:
RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT 3 .11.1. 5 3 03/05/2015 *
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT 3.11.2.1 3 04/26/2006
Title:
RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3 . 11. 2. 2 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES TEXT 3 .11. 2. 3 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM TEXT 3 . 11. 2 . 4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3.11.2.5 4 07/03/2013
Title:
RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3 . 11. 2 . 6 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 J_ of 15 Report Date: 01/07/19
SSES MANUAL Manual Name: TRM2
(_ 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 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 0 09/27/2003
Title:
ADMINISTRATIVE.CONTROLS REPORTING REQUIREMENTS TEXT 4.6 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM Page.§.. of 15 Report Date: 01/07/19
SSES MANUAL Manual Name: TRM2 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 B3.1.2 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 r' 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 Ti tl.e: 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 i of 15 Report Date: 01/07/19
SSES MANUAL I Manual Name: TRM2
\.
Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.3.6 5 01/31/2014
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 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.l 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: 01/07/19
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 0 11/19/2002
Title:
ECCS AND RCIC BASES ADS MANUAL INHIBIT TEXT B3.5.2 1 11/09/2007
Title:
ECCS AND RCIC BASES LONG TERM NITROGEN SUPPLY TO ADS TEXT B3.6.1 0 11/19/2002
Title:
CONTAINMENT BASES VENTING OR PURGING TEXT B3.6.2 0 11/19/2002
Title:
CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 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 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: 01/07/19
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 ~LON 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.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: 01/07/19
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 2 12/08/2011
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 0 11/19/2002
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
CONTINUOUS TEXT B3.8.2.2 1 09/17/2004
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD' PROTECTION -
AUTOMATIC TEXT B3.8.3 0 11/19/2002
Title:
ELECTRICAL POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT B3.8.4 0 11/19/2002
Title:
ELECTRICAL POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT B3.8.5 1 11/14/2013
Title:
ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B3.8.6 3 06/20/2012
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: 01/07/19
SSES MANUAL Manual Name: 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 0 11/19/2002
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.ll.l.l 1 05/10/2016
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3. 11.1. 2 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3 . 11. 1. 3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3. 11.1. 4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.ll.1.5 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.ll.2.l 1 12/14/2004
Title:
RADIOACTIVE EFFLUENTS BASES DOSE RATE Page 14 of 15 Report Date: 01/07/19
SSES MANUAL Manual Name: TRM2 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 IN PARTICULATES FORM TEXT B3 .11. 2. 4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3 .11.2. 5 5 07/03/2013
Title:
RADIOACT~VE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3 .11. 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 . 11. 4 . 1 5 03/05/2015
Title:
RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3.11.4.2 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LAND USE. CENSUS TEXT B3 .11.4. 3 0 11/19/2002
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 PROGR.AN BASES LIGHT LOADS REQUIREMENTS Page 15 of 15 Report Date: 01/07/19
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 99 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL) -
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SUSQUEHANNA - UNIT 2 LOES-1
SUSQUEHANNA STEAM ELECTRIC STATION Rev.26 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION TITLE PAGE 1.0 USE AND APPLICATION ............................................................................... 1.0-1 1.1 Definitions ................................................................................................. 1.0-1 2.0 PLANT PROGRAMS AND SETPOINTS ........................................................ 2.0-1 2.1 Plant Programs ......................................................................................... 2.0-1 2.2 Instrument Trip Setpoint Table ................................................................. 2.0-5 3.0 APPLICABILITY .......................................................*..................................... 3.0-1 3.0 Technical Requirement for Operation (TRO) Applicability ........................ 3.0-1 3.0 Technical Requirement Surveillance (TRS) Applicability ......................... 3.0-3 3.1 REACTIVITY CONTROL SYSTEMS .............................................................. 3.1-1 3.1.1 Anticipated Transient Without Scram Alternate Rod Injection (ATWS-ARI) Instrumentation .................................................................... 3.1-1 3.1.2 Control Rod Drive (CRD) Housing Support .............................................. 3.1-4 3.1.3 Control Rod Block Instrumentation ........................................................... 3.1-5 3.1.4 Control Rod Scram Accumulators Instrumentation and Check Valve ............................................................................................. 3.1-9 3.2 CORE OPERATING LIMITS REPORT .......................................................... 3.2-1 3.2.1 Core Operating Limits Report ................................................................... 3.2-1 3.3 INSTRUMENTATION ..................................................................................... 3.3-1 3.3.1 Radiation Monitoring Instrumentation ....................................................... 3.3-1 3.3.2 Seismic Monitoring Instrumentation ......................................................... 3.3-4 3.3.3 Meteorological Monitoring Instrumentation .............................................. 3.3-7 3.3.4 TRM Post-Accident Monitoring Instrumentation ....................................... 3.3-9 3.3.5 Section Not Used ..................................................................................... 3.3-12 3.3.6 TRM Isolation Actuation Instrumentation ................................................. 3.3-13 3.3.7 Main Turbine Overspeed Protection System ............................................ 3.3-17 3.3.8 Section Not Used ..................................... ,............................................... 3.3-19 3.3.9 OPRM Instrumentation Configuration ....................................................... 3.3-21 3.3.10 Reactor Recirculation Pump MG Set Stops ............................................. 3.3-22 3.3.11 MVP Isolation Instrumentation ................................................................. 3.3-24 3.3.12 Water Monitoring Instrumentation ............................................................ 3.3-26 3.4 REACTOR COOLANT SYSTEM .................................................................... 3.4-1 3.4.1 Reactor Coolant System Chemistry ......................................................... 3.4-1 3.4.2 Not Used .................................................................................................. 3.4-6 3.4.3 High/Low Pressure Interface Leakage Monitors ...................................... 3.4-9 3.4.4 Reactor Recirculation Flow and Rod Line Limit ....................................... 3.4-12 3.4.5 Reactor Vessel Materials ........................................................................ 3.4-13 3.4.6 Reactor Recirculation Single Loop Operation (SLO)
Flow Rate Restriction ............................................................................... 3.4-14 SUSQUEHANNA - UNIT 2 TOC-1
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 26 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL) t-SECTION TITLE PAGE 3.5 EMERGENCY CORE COOLING AND RCIC ................................................. 3.5-1 3.5.1 ADS Manual Inhibit. .................................................................................. 3.5-1 3.5.2 ECCS and RCIC System Monitoring Instrumentation .............................. 3.5-3 3.5.3 Long Term Nitrogen Supply to ADS ......................................................... 3.5-6 3.6 CONTAINMENT ............................................................................................. 3.6-1 3.6.1 Venting or Purging .................................................................................... 3.6-1 3.6.2 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication .................................................................................................. 3.6-3 3.6.3 Suppression Pool Alarm Instrumentation ................................................. 3.6-4 3.6.4 Primary Containment Closed System Boundaries ................................... 3.6-7 3.7 PLANT SYSTEMS ........................................................................................... 3.7-1 3.7.1 Emergency Service Water System (ESW) Shutdown .............................. 3.7-1 3.7.2 Ultimate Heat Sink (UHS) and Ground Water Level. ................................ 3.7-3 3.7.3 Fire Protection .......................................................................................... 3. 7-4 3.7.3.1 Fire Suppression Water Supply System ................................................... 3. 7-4 3.7.3.2 Spray and Sprinkler Systems ................................................................... 3. 7-8 3.7.3.3 CO2 systems ............................................................................................ 3.7-12 3.7.3.4 Halon Systems ......................................................................................... 3.7-16 3.7.3.5 Fire Hose Stations ...................*................................................................ 3.7-18 3.7.3.6 Yard Fire Hydrants and Hydrant Hose Houses ........................................ 3.7-22 3.7.3.7 Fire Rated Assemblies ............................................................................. 3. 7-24 3.7.3.8 Fire Detection Instrumentation ................................................................. 3.7-26 3.7.4 Solid Radwaste System ............................................................................ 3. 7-34 3.7.5 Explosive Gas and Storage Tank Radioactivity Monitoring Program .................................................................................. 3. 7-37 3.7.5.1 Main Condenser Offgas Hydrogen Monitor .............................................. 3. 7-37 3.7.5.2 Main Condenser Offgas Explosive Gas Mixture ....................................... 3. 7-38 3.7.5.3 Liquid Holdup Tanks ................................................................................. 3.7-39 3.7.6 ESSW Pumphouse Ventilation ................................................................. 3.7-40 3.7.7 Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation ....................................................................... 3. 7-41 3.7.8 Snubbers .................................................................................................. 3.7-43 3.7.9 Control Structure HVAC ........................................................................... 3.7-49 3.7.10 Spent Fuel Storage Pools (SFSPs) .......................................................... 3.7-51 3.7.11 Structural Integrity .................................................................................... 3.7-54 3.8 ELECTRICAL POWER ................................................................................... 3.8-1 3.8.1 Primary Containment Penetration Conductor Overcurrent Protective Devices ................................. : .................................................. 3.8-1 3.8.2 Motor Operated Valves Thermal Overload Protection .............................. 3.8.5 3.8.2.1 Motor Operated Valves (MOV) Thermal Overload Protection -
Continuous ............................................................................................... 3.8-5 3.8.2.2 Motor Operated Valves (MOV) Thermal Overload Protection -
Automatic ................................................................................................. 3.8-11 3.8.3 Diesel Generator (DG) Maintenance Activities ......................................... 3.8-13 SUSQUEHANNA - UNIT 2 TOC-2
SUSQUEHANNA STEAM ELECTRIC STATION Rev.26 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL) i-SECTION PAGE 3.8.4 24 voe Electrical Power Subsystem ....................................................... 3.8-15 3.8.5 Degraded Voltage Protection ................................................................... 3.8-21 3.8.6 Emergency Switchgear Room Cooling ..................................................... 3.8-24 3.8.7 Battery Monitoring and Maintenance Program ......................................... 3.8-26 3.9 REFUELING OPERATIONS .......................................................................... 3.9-1 3.9.1 Decay Time ....................................................................... :...................... 3.9-1 3.9.2 Communications ....................................................................................... 3.9-2 3.9.3 Refueling Platform .................................................................................... 3.9-3 3.10 MISCELLANEOUS ......................................................................................... 3.10-1 3.10.1 Sealed Source Contamination .................................................................. 3.10-1 3.10.2 Shutdown Margin Test RPS In.strumentation ........................................... 3.10-4 3.10.3 Independent Spent Fuel Storage Installation (ISFSI) ............................... 3.10-7 3.10.4 Section Not Used ..................................................................................... 3.10-8 3.11 RADIOACTIVE EFFLUENTS ......................................................................... 3.11-1 3.11.1 Liquid Effluents ......................................................................................... 3.11-1 3.11.1.1 Liquid Effluents Concentration ................................................................. 3.11-1 3.11.1.2 Liquid Effluents Dose ............................................................................... 3.11-4 3.11.1.3 Liquid Waste Treatment System .............................................................. 3.11-6 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation .............................. 3.11-8 3.11.1.5 Radioactive Liquid Process Monitoring Instrumentation .......................... 3.11-13 3.11.2 Gaseous Effluents .................................................................................... 3.11-17 3.11.2.1 Dose Rate ................................................................................................ 3.11-17 3.11.2.2 Dose - Noble Gases ................................................................................. 3.11-20 3.11.2.3 Dose - Iodine, Tritium, and Radionuclides in Particulate Form ....................................................................................... 3.11-21 3.11.2.4 Gaseous Radwaste Treatment System .................................................... 3.11-22 3.11.2.5 Ventilation Exhaust Treatment System .................................................... 3.11-23 3.11.2.6 Radioactive Gaseous Effluent Monitoring Instrumentation ......................................................................................... 3.11-25 3.11.3 Total Dose ................................................................................................ 3.11-33 3.11.4 Radiological Environmental Monitoring .................................................... 3.11-35 3.11.4.1 Monitoring Program .................................................................................. 3.11-35 3.11.4.2 Land Use Census ..................................................................................... 3.11-45 3.11.4.3 lnterlaboratory Comparison Program ....................................................... 3.11-47 3.12 LOADS CONTROL PROGRAM ..................................................................... 3.12-1 3.12.1 Crane* Travel - Spent Fuel Storage Pool .................................................. 3.12-1 3.12.2 Heavy Loads Requirements ..................................................................... 3.12.3 3.12.3 Light Loads Requirements ....................................................................... 3.12-5 SUSQUEHANNA - UNIT 2 TOC-3
SUSQUEHANNA STEAM ELECTRIC STATION Rev.26 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION 4.0 ADMINISTRATIVE CONTROLS .................................................................... 4.0-1 4.1 Organization ............................................................................................. 4.0-1 4.2 Reportable Event Action ........................................................................... 4.0-2 4.3 Safety Limit Violation ................................................................................ 4.0-3 4.4 Procedures and Programs ....................................................................... 4.0-4 4.5 Reporting Requirements .......................................................................... 4.0-5 4.5.1 Startup Reports ........................................................................................ 4.0-5 4.5.2 Annual Reports .................. :...................................................................... 4.0-6 4.5.3 Special Reports ........................................................................................ 4.0-6 4.6 Radiation Protection Program .................................................................. 4.0-7 4.7 Training .................................................................................................... 4.0-8 SUSQUEHANNA - UNIT 2 TOC-4
SUSQUEHANNA STEAM ELECTRIC STATION Rev.26 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL) f__
\-
SECTION B 3.0 Technical Requirement for Operation (TRO) Applicability ....................... B 3.0-1 B 3.0 Technical Requirement Surveillance (TRS) Applicability ........................ 8 3.0-9 B 3.1.1 Anticipated Transient Without Scram Alternate Rod Injection (ATWS-ARI) lnstrumentation ................................................................... B 3.1-1 B 3.1.2 Control Rod Drive (CRD) Housing Support ............................................. B 3.1-4 B 3.1.3 Control Rod Block lnstrumentation .......................................................... B 3.1-5 B 3.1.4 Control Rod Scram Accumulators Instrumentation and Check Valve ..................................................................................... 8 3.1-8 B 3.2.1 Core Operating Limits Report (COLR) .................................................... 8 3.2-1 B 3.3.1 Radiation Monitoring lnstrumentation ...................................................... B 3.3-1 B 3.3.2 Seismic Monitoring Instrumentation ........................................................ 8 3.3-2 B 3.3.3 Meteorological Monitoring Instrumentation ............................................. 8 3.3-3 B 3.3.4 TRM Post-Accident Monitoring Instrumentation ...................................... 8 3.3-4 B 3.3.5 Section Not Used ....................................................................................8 3.3-9 B 3.3.6 TRM Isolation Actuation Instrumentation ................................................ 8 3.3-10 B 3.3.7 Turbine Overspeed Protection System .................................................... B 3.3-14 B 3.3.8 Section Not Used .................................................................................... 8 3.3-15 B 3.3.9 OPRM Instrumentation ............................................................................ 8 3.3-18 B 3.3.10 Reactor Recirculation Pump MG Set Stops ............................................ 8 3.3-20 B 3.3.11 MVP Isolation Instrumentation ................................................................ 8 3.3-22 B 3.3.12 Water Monitoring Instrumentation ........................................................... 8 3.3-24 B 3.4.1 Reactor Coolant System Chemistry ........................................................ 8 3.4-1 B 3.4.2 . Not Used .................................................................................................8 3.4-2 B 3.4.3 High/Loy.., Pressure Interface Leakage Monitor ....................................... 8 3.4-4 B 3.4.4 Reactor Recirculation Flow and Rod Line Limit ...................................... 8 3.4-5 B 3.4.5 Reactor Vessel Materials ........................................................................ 8 3.4-6 B 3.4.6 Reactor Recirculation Single Loop Operation (SLO)
Flow Rate Restriction ..............................................................................8 3.4-7 B 3.5.1 ADS Manual lnhibit.. ................................................................................ B 3.5-1 B 3.5.2 ECCS and RCIC System Monitoring Instrumentation ............................. 8 3.5-3 B 3.5.3 Long Term Nitrogen Supply to ADS ........................................................ 8 3.5-4 B 3.6.1 Venting or Purging ...................................................................................B 3.6-1 B 3.6.2 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication .................................................................................................8 3.6-3 B 3.6.3 Suppression Pool Alarm Instrumentation ................................................ 8 3.6-4 B 3.6.4 Primary Containment Closed System Boundaries .................................. 8 3.6-6 B 3.7.1 Emergency Service Water System (Shutdown) ...................................... 8 3.7-1 B 3.7.2 Ultimate Heat Sink (UHS) Ground Water Level.. ..................................... B 3.7-2 B 3.7.3.1 Fire Suppression Water Supply System .................................................. B 3.7-3 SUSQUEHANNA - UNIT 2 TOC-5
SUSQUEHANNA STEAM ELECTRIC STATION Rev.26 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
I r-~
SECTION PAGE 8 3.7.3.2 Spray and Sprinkler Systems .................................................................. 8 3.7-5 8 3.7.3.3 CO2 Systems ..................................................................................:....... 8 3.7-7 8 3.7.3.4 Halon Systems ........................................................................................ 8 3.7-8 8 3.7.3.5
- Fire Hose Stations ................................................................................... 8 3.7-10 8 3.7.3.6 Yard Fire Hydrants and Hydrant Hose Houses ....................................... 8 3.7-11 8 3.7.3.7 Fire Rated Assemblies ............................................................................8 3.7-12 8 3.7.3.8 Fire Detection Instrumentation ................................................................ 8 3.7-14 8 3.7.4 Solid Radwaste System ........................................................................... 8 3.7-15 8 3.7.5.1 Main Condenser Offgas Hydrogen Monitor ............................................. 8 3.7-17 8 3.7.5.2 Main Condenser Offgas Explosive Gas Mixture ...................................... 8 3.7-19 8 3.7.5.3 Liquid Holdup Tanks ................................................................................B 3.7-20 8 3.7.6 ESSW Pumphouse Ventilation ................................................................ B 3.7-21 8 3.7.7 Main_ Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation ...................................................................... 8 3. 7-22 8 3.7.8 Snubbers .................................................................................................8 3.7-24 8 3.7.9 Control Structure HVAC .......................................................................... 8 3.7-31 B 3.7.10 Spent Fuel Storage Pools .............................. ; ........................................ B 3.7-33 B 3.7.11 Structural Integrity ................................................................................... 8 3.7-36 B 3.8.1 Primary Containment Penetration Conductor Overcurrent Protective Devices ...................................................................................B 3.8-1 B 3.8.2.1 Motor Operated Valves (MOV) Thermal Overload Protection -
Continuous ..............................................................................................8 3.8-3 B 3.8.2.2 Motor Operated Valves (MOV) Thermal Overload Protection -
Automatic ................................................................................................8 3.8-4 B 3.8.3 Diesel Generator (DG) Maintenance Activities ........................................ B 3.8-5 B 3.8.4 24 voe Electrical Power Subsystem ...................................................... 8 3.8-6 8 3.8.5 Degraded Voltage Protection .............................~ .................................... 8 3.8-16 8 3.8.6 Emergency Switchgear Room Cooling .................................................... B 3.8-17 8 3.8.7 Battery Monitoring and Maintenance Program ........................................ 8 3.8-18 B.3.9.1 Decay Time .............................................................................................8 3.9-1 B 3.9.2 Communications ......................................................................................B 3.9-2 B 3.9.3 Refueling Platform ...................................................................................8 3.9-3 83.10.1 Sealed Source Contamination .................................................................B 3.10-1 B 3.10.2 Shutdown Margin Test RPS Instrumentation .......................................... 8 3.10-2 B 3.10.3 Independent Spent Fuel Storage Installation (ISFSI) .............................. 8 3.10-4 B 3.11.1.1 Liquid Effluents Concentration .................................. :............................. 8 3.11-1 B 3.11.1.2 Liquid Effluents Dose ..............................................................................B 3.11-4 B 3.11.1.3 Liquid Waste Treatment System ............................................................. 8 3.11-6 8 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation ............................. 8 3.11-7 8 3.11.1.5 Radioactive Liquid Process Monitoring Instrumentation ......................... 8 3.11-10 SUSQUEHANNA - UNIT 2 TOC-6
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 26 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION PAGE 8 3.11.2.1 Dose Rate ...............................................................................................8 3.11-12 8 3.11.2.2 Dose - Noble Gases ................................................................................8 3.11-16 8 3.11.2.3 Dose - Iodine, Tritium, and Radionuclides in Particulates Form ...... ,............................................................................. 8 3.11-18 8 3.11.2.4 Gaseous Radwaste Treatment System ................................................... 8 3.11-20 8 3.11.2.5 Ventilation Exhaust Treatment System .. ,................................................ 8 3.11-21 8 3.11.2.6 Radioactive Gaseous Effluent Monitoring lnstrumentation ........................................................................................8 3.11-24 8 3.11.3 Total Dose ...............................................................................................8 3.11-26 8 3.11.4.1 Monitoring Program .................................................................................. 8 3.11-28 8 3.11.4.2 Land Use Census .................................................................................... 8 3.11-34 8 3.11.4.3 lnterlaboratory Comparison Program ... ~ ................................................. 8 3.11-36 8.3.12.1 Crane Travel - Spent Fuel Storage Pool ................................................ 8 3.12-1 8.3.12.2 Heavy Loads Requirements .................................................................... 8 3.12-2 8.3.12.3 Light Loads Requirements ...................................................................... 8 3.12-3 SUSQUEHANNA - UNIT2 TOC-7
Suppression Chamber-to-Drywell Vacuum Breaker Position Indication Rev. 3
- 3.6.2 3.6 Containment 3.6.2 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication TRO 3.6.2 The Suppression Chamber-to-Drywell Vacuum Breaker Position Indication sh~II be OPERABLE APPLICABILITY: MODES 1, 2, and 3 ACTIONS
*------- -- NOTE--------------------------------------------------------
Separate condition entry is allowed for each instrument.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more position A.1.1 Verify that the associated 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> indicators of any suppression chamber -
suppression chamber - drywell vacuum breaker is drywell vacuum breaker closed.
inoperable Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter A.1.2 Enter CONDITION B of Immediately LCO 3.6.1.6 (continued)
SUSQUEHANNA - UNIT 2 3.6-3
Suppression Chamber-to-Drywell Vacuum Breaker Position Indication Rev. 3 3.6.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A.2 Restore the suppression 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> chamber - drywell vacuum breaker indication to OR OPERABLE status.
At the next outage with containment entry, not to exceed the next refueling outage for in-accessible containment components.
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.6.2.1 Observe expected actuation of both valve As required by SR 3.6.1.6.2 position during the Technical Specification Functional cycling.
TRS 3.6.2.2 Perform a CHANNEL CALIBRATION on each 24 months vacuum breaker position indicator.
SUSQUEHANNA - UNIT 2 3.6-3a
Not Used Rev. 2 3.10.4 3.10.4 Section Not Used THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 3.10-8
ADMINISTRATIVE CONTROLS Rev. 1 4.0 4.2 Reportable Event Action 4.2.1 The following actions shall be taken for REPORTABLE EVENTS:
- a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and,
- b. Each REPORTABLE EVENT shall be reviewed by the PORC and submitted to the Nuclear Safety Review Board (NSRB) and a specified corporate officer.
SUSQUEHANNA - UNIT 2 4.0-2
ADMINISTRATIVE CONTROLS Rev. 1 4.0
[--
4.3 Safety Limit Violation 4.3.1 The following actions shall be taken in the event a Safety Limit is violated:
4.3.1.1 Nuclear Safety Review Board (NSRB) and a specified corporate officer shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.3.1.2 A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PORC.
4.3.1.3 The Safety Limit Violation Report shall be submitted to the NSRB and a specified corporate officer within 14 days of the violation.
4.3.1.4 Critical operation of the unit shall not be resumed until authorized by the Commission.
SUSQUEHANNA - UNIT 2 4.0-3
OPRM Instrumentation Rev. 4 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRO The OPRM system configuration governs its operation in accordance with the licensing analysis. Several configuration parameters are intrinsic to the trip function safety setpoint bases or provide settings for defense-in-depth algorithm features that are not assumed in the basis for the protection system safety analysis (Reference 2, Reference 3).
Each of the setting values may be used as the process setpoint or device setting without further adjustment for uncertainties .
. Setpoints and Settings Bases TOL{E) Period Tolerance The specified range of values for the period tolerance has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability. A range of values is provided to allow system tuning to avoid spurious alarms on period confirmations. Limiting the setpoiht adjustment range provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability.
fg Conditioning Filter Cutoff Frequency The specified value for the Conditioning Filter Cutoff Frequency has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability. Setting minimizes impact on signal amplitude and provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability.
Tmin Oscillation Period Lower Time Limit Tmax Oscillation Period Upper Time Limit The Oscillation Period Time Limit parameters establish the range of detectable oscillation periods of OPRM cell signals for signal oscillations associated with reactor core thermal-hydraulic instability.
(continued)
SUSQUEHANNA - UNIT 2 B 3.3-18
OPRM Instrumentation Rev. 4 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRO LPRMmin (continued)
This value determines the availability and resulting sensitivity of cells in the reactor core in the event of LPRM channel failures. The minimum LPRM per cell parameter is an assumption of the OPRM trip setpoint (Sp) basis calculation.
Amplitude and Growth Rate Based Algorithm Parameters S1 Peak Threshold Setpoint/ABA & GRBA Valley Threshold Setpoint/ABA & GRBA Amplitude Trip Setpoint/ABA Growth Rate Factor Setpoint/GRBA These parameters calibrate the Amplitude and Growth Rate Based Algorithm, described in References 2 and 3, which provides an OPRM trip output to the Reactor Protection System. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algorithm.
The algorithm is provided as a defense-in-depth feature in the event of unanticipated power oscillations. These Amplitude and Growth Rate Based Algorithm Parameters are considered sufficient to provide backup protection and to avoid spurious trips by maximizing margin to expected operating conditions and transients.
ACTIONS The required actions assure that the system settings that support the Period Based Algorithm setpoint analysis, and those parameters that define the Amplitude and Growth Rate Based Algorithm are returned in a timely manner to the values assumed in the analysis (Reference 2, Reference 3) or that the affected channel is declared inoperable and the applicable Required Action of LCO 3.3.1.1 is then entered, or an alternate method to detect and suppress thermal hydraulic instability oscillations is employed.
(continued)
SUSQUEHANNA - UNIT 2 B 3.3-19
OPRM Instrumentation Rev. 4 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS Note 1 has been provided to modify the ACTIONS related to affected OPRM (continued) channels. Technical Specification Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits will not result in separate entry into the Condition. Technical Specification Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for affected OPRM channels provide appropriate compensatory measures. As such, a Note has been provided that allows separate Condition entry for each affected OPRM channel.
Several parameter settings are essential for the proper operation of the OPRM period-based trip algorithm. The permissible values of Period Confirmation Tolerance, Averaging Filter time constant, Conditioning Filter Cutoff Frequency, and minimum operable LPRM per cell parameters are limited by the setpoint basis calculations and system transient response analysis. The Minimum and Maximum Oscillation Period settings limit the algorithm window to the cell signal resonances that can be associated with unstable thermal-hydraulic conditions.
Because the ability of the OPRM channel to perform its safety function is affected by these parameter settings, the affected OPRM channel must be considered inoperable when these conditions are not met.
Operability is evaluated for each inoperable channel and Required Actions taken in accordance with LCO 3.3.1.1.
The design objective for the Amplitude and Growth Rate Based Algorithms is to provide automatic action to limit the size of these unanticip~ted oscillations, thereby preventing fuel cladding damage. Several parameter settings define the .function of the Amplitude and Growth Rate Based Algorithm. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algorithm, which is provided as a defense-in-depth feature in the event of unanticipated oscillations.
(continued)
SUSQUEHANNA - UNIT 2 B 3.3-19a
OPRM Instrumentation Rev.4 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS C.1 (continued)
Because the ability of the OPRM channel to perform its safety function is not affected by these parameter settings, the affected OPRM channel need not be immediately considered inoperable when these conditions are not met.
These parameters are to be maintained for conformance with the licensing requirement of a defense-in-depth feature in addition to the licensed OPRM trip function. This is corrected by returning the parameters to conformance within 120 days of identification.
Since the Amplitude and Growth Rate Based parameters affect only the defense-in-depth response within each channel, failure to maintain the proper parameters in the channel affects only the operability of that channel.
This Action is to be taken if the Period Based Detection Algorithm trip function is not available in accordance with LCO 3.3.1.1, and initiation of an alternate method to Detect and Suppress thermal hydraulic instability oscillations is required by the referenced LCO Required AGtions. The applicable Conditions are entered as required.
As directed from Required Action 0.1, this Action provides preemptive protection through Power/Flow Map operating restrictions.
When operating in Region I of the Power / Flow map specified in the COLR, or when operating in Region II of the Power/ Flow map specified in the COLR with less than 50% of the required LPRM upscale alarms OPERABLE, the potential for thermal-hydraulic oscillations is greatly increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. Therefore, the reactor mode switch must be immediately placed in the shutdown position. Action is taken immediately to place the plant in a condition where any potential for thermal-hydraulic instabilities will be terminated.
Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/
alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors .
.(continued)
SUSQUEHANNA - UNIT 2 B 3.3-19b
- As directed from Required Action 0.1, this Action provides guidance for Operator action in response to thermal-hydraulic instability oscillations.
When operating in Region II of the Power/Flow map specified in the COLR immediate response is necessary when there are indications that thermal hydraulic oscillations are occurring as defined in the CONDITION.
LPRM upscale alarms are required to detect reactor core thermal-hydraulic instability events. The criteria for determining which LPRM upscale alarms are required is based on assignment of these alarms to designated core zones. These core zones consist of the level A, B, and C alarms in 4 or 5 adjacent LPRM strings. The number and location of LPRM strings in each zone assure that with 50% or more of the associated LPRM upscale alarms OPERABLE sufficient monitoring capability is available to detect core wide and regional oscillations. Operating plant instability data is used to determine the specific LPRM strings assigned to each zone.
Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/
alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors.
As directed from Required Action 0.1, this Action provides guidance for Operator action in response to operation in conditions that may lead to thermal-hydraulic instability oscillations.
When operating in Region II of the Power/Flow map specified in the COLR, the potential for thermal-hydraulic oscillations is increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. Therefore, action must be initiated immediately to restore operation outside of Regions II of the Power/Flow map specified in the COLR. This can be accomplished by either decreasing THERMAL POWER with control rod insertion or increasing core flow by increasing recirculation pump speed. The starting of a recirculation pump will not be used as a means to exit the excluded Regions because the starting of a recirculation pump with the plant operating above the 70% rod line is prohibited due to potential instability problems.
(continued)
SUSQUEHANNA - UNIT 2 B 3.3-19c
OPRM Instrumentation Rev.4 8 3.3.9 8 3.3.9 OPRM Instrumentation BASES ACTIONS H.1 (continued)
The LPRMs provide a capability to monitor power in selected locations of the reactor core. The LPRM Upscale Alarm Instrumentation provides information concerning local power oscillations. Condition F requires a reactor scram when operating in Region II of the Power/Flow map specified in the COLR with indications that thermal hydraulic oscillations are occurring. The number and location of LPRM strings in each zone assures that with 50% or more of the associated LPRM upscale alarms OPERABLE any power oscillations which could occur would be detected and proper actions can be taken.
Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/
alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors.
A sign is posted in the Control Room to ensure that plant operators are aware of the system condition if a plant transient results in the plant entering into the instability region.
TRS TRS 3.3.9.1 Required only when the OPRM trip function is not available, this TRS ensures the combination of core flow and THERMAL POWER are within required limits to prevent uncontrolled thermal hydraulic oscillations by ensuring the recirculation loops are within the limits established by the Power I Flow map specified in the COLR. At low recirculation flows and high reactor power,' the reactor exhibits increased susceptibility to thermal-hydraulic instability. The Power I Flow map specified in the COLR is based on guidance provided in References 7, 8, and 9 which also provided the guidance on how to respond to operation in these conditions. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is based on operating experience and the operator'$ inherent knowledge of the current reactor status, including significant changes in THERMAL POWER and core flow to ensure the requirements are constantly met.
TRS 3.3.9.2 This TRS is to be performed at the specified Frequency to ensure that the LPRM Upscale Alarm Instrumentation are maintained OPERABLE.
(continued)
SUSQUEHANNA - UNIT 2 8 3.3-19d
OPRM Instrumentation Rev. 4 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRS TRS 3.3.9.3 (continued)
The parameter setpoint verification surveillance compares the desired settings and setpoints to the values contained in the processor memory.
This surveillance is required to assure that the settings are maintained in accordance with the setpoint analysis. The frequency is based on the OPRM CALIBRATION frequency per SR 3.3.1.1.18.
REFERENCES 1. NED0-31960-A, BWROG Long Term Solution Licensing Methodology
- 2. NED0-31960-A, Supp. 1, BWROG Long Term Solution Licensing Methodology
- 3. NED0-32465-A, BWROG Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications
- 4. Deleted
- 5. Generic Letter 94-02, Long-Term Solutions and Upgrade Of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in Boiling Water Reactors
- 6. LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation
- 7. GE Service Information Letter No. 380, "BWR Core Thermal Hydraulic Stability," Revision 1, February 10, 1984
- 8. Letter, L. A. England to M. J. Virgilio, "BWR Owner's Group Guidelines for Stability Interim Corrective Action," June 6, 1994
- 9. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis:
Assessment of STAIF with Input from MICROBURN-82," November 1999
- 10. NEDC-3241 OP-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option Ill Stability Trip Function" SUSQUEHANNA - UNIT 2 B 3.3-19e
Reactor Recirculation Flow and Rod Line Limit Rev. 1 B 3.4.4
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B 3.4.4 Reactor Recirculation Flow and Rod Line Limit BASES TRO TRO 3.4.4 requires that the operating loop flow rate be maintained below 50% rated loop flow during an idle recirculation loop startup. This restriction minimizes core power spikes during the startup of an idle recirculation loop and assures operation in accordance with the assumptions of FSAR 15.4.4. In addition, the flow restriction avoids excessive vibration of reactor vessel internals (i.e., jet pump risers). For the purpose of this TRO, loop flow refers to recirculation drive flow.
Reactor operating rod line limitation is in place to maintain operation within the analysis assumptions of FSAR Section 15.4.4, and outside the region of potential core instability from the power to flow map.
APPLICABILITY This Requirement is applicable whenever an idle recirculation loop is started while not in refueling.
ACTIONS The Actions assure that the Requirement is met prior to the idle pump start in order to assure that design considerations and licensing criteria are met.
TRS The required surveillance provides the necessary test to assure the required conditions are in place prior to the idle loop pump start.
REFERENCES 1. FSAR Section 15.4.4 SUSQUEHANNA - UNIT 2 B 3.4-5
Rev. 2 Reactor Recirculation Single Loop Operation (SLO) Flow Rate Restriction B 3.4.6
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B 3.4.6 Reactor Recirculation Single Loop Operation (SLO) Flow Rate Restriction BASES TRO TRO 3.4.6 requires that the operating loop flow rate be maintained less than or equal to 54.0 Mlbm/hr during single loop operation. Single loop operation includes events that require a recirculation loop to be declared "not in operation" due to Technical Specification 3.4.1 Condition B. Note that the parameter of concern is the 3 minute average recirculation system loop flow (e.g., Plant Process Computer (PPC) point NJF02B and NJF03B) not core flow. This restriction avoids excessive vibration of jet pump components.
Fatigue usage can be accumulated when loop flow rates are above 54 Mlbm/hr if large gaps are present. Excessive vibration can lead to cracking of the jet pump riser brace welds. The limitation contained in this TRO will provide nuclear safety assurance in that jet pump integrity will be maintained and thus the FSAR Chapter 15 analysis assumption of maintaining 2/3 core height will be met. Additionally, these measures will assure asset preservation and avoid lengthy repairs due to potential riser brace cracking. The required action to place the reactor mode switch in shutdown will assure the flow rate is established within limits. The time frame of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> is required to avoid excessive vibrations that occur at higher loop flow rates and the subsequent impact on jet pump riser brace.
APPLICABILITY This Requirement is applicable whenever in reactor recirculation single loop operation in Modes 1 and 2. Single loop operation includes events that require a recirculation loop to be declared "not in operation" due to Technical Specification 3.4.1 Condition B.
ACTIONS The Actions assure excessive jet pump vibration can not occur when in single loop operation.
TRS The required surveillance assures that the maximum loop flow rate is not exceeded.
REFERENCES 1. FSAR Section 15.6 SUSQUEHANNA - UNIT 2 B 3.4-7