ML14042A176
| ML14042A176 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/03/2014 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2014-4612 | |
| Download: ML14042A176 (110) | |
Text
Feb. 03, 2014 Page 1 of 3 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2014-4612 USER INFORMATION:
GERLACH*ROSEY M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:
TO: GERLACH*ROSEY M 02/03/2014 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 ERRORS.
ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.
TRMI - TECHNICAL REQUIREMENTS MANUAL UNIT 1 REMOVE MANUAL TABLE OF CONTENTS DATE: 11/14/2013 ADD MANUAL TABLE OF CONTENTS DATE: 01/31/2014 CATEGORY: DOCUMENTS TYPE: TRMI
Feb. 03, 2014 Page 2 of 3 ID: TEXT 1.1 ADD: REV: 1 REMOVE: REV:0 CATEGORY: DOCUMENTS TYPE: TRMI ID: TEXT 2.2 ADD: REV: 10 REMOVE: REV:9 CATEGORY: DOCUMENTS TYPE: TRMI ID: TEXT 3.7.9 REMOVE: REV:1 ADD: REV: 2 CATEGORY: DOCUMENTS TYPE: TRMI ID: TEXT B3.3.1
- REMOVE: REV:O ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM1 ID: TEXT B3.3.6 ADD: REV: 5 REMOVE: REV:4 CATEGORY: DOCUMENTS TYPE: TRMI ID: TEXT B3.7.8 ADD: REV: 4 REMOVE: REV:3
Feb. 03, 2014 Page 3 of 3 CATEGORY: DOCUMENTS TYPE: TRM1 ID: TEXT LOES ADD: REV: 79 REMOVE: REV:78 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 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 MANTTAIZ O Manual Name:
Manual
Title:
TRMI TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date: 0'1/31/2014 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 79 01/31/2014
Title:
LIST OF EF:FECTIVE SECTIONS TEXT TOC 22 10/09/2012
Title:
TABLE OF CONTENTS TEXT 1.1 1 01/31/2014
Title:
USE AND APPLICATION DEFINITIONS TEXT 2.1 1 02/04/2005
Title:
PLANT PROGRAMS AND SETPOINTS PLANT PROGRAMS TEXT 2.2 10 01/31/2014
Title:
PLANT PROGRAMS AND SETPOINTS INSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 4 05/23/2008
Title:
TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY & SURVEILLANCE (TRS)
APPLICABILITY TEXT 3.1.1 1 11/09/2007
Title:
REACTIVITY CONTROL SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT 3.1.2 0 11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1.3 5 04/16/2009
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 0 11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION &
CHECK VALVE TEXT 3.2.1 13 04/10/2012
Title:
CORE OPERATING LIMITS REPORT (COLR)
Report Date: 01/31/14 Page 11 Page of of 16 16 Report Date: 01/31/14
SSES MANUAL
. Manual Name: TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.3.1 0 11/18/2002
Title:
INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 3 03/31/2011
Title:
INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 2 11/09/2007
Title:
INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 6 07/09/2010
Title:
INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0 11/18/2002
Title:
INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK 0 TEXT 3.3.6 3 01/13/2011
Title:
INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 1 11/09/2007
Title:
INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 1 10/22/2003
Title:
INSTRUMENTATION TRM RPS INSTRUMENTATION TEXT 3.3.9 3 04/17/2008
Title:
OPRM INSTRUMENTATION CONFIGURATION TEXT 3.3.10 1 12/14/2004
Title:
INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1 10/22/2003
Title:
INSTRUMENTATION MVP ISOLATION INSTRUMENTATION
- TEXT 3.3.12 0 04/16/2009
Title:
WATER MONITORING INSTRUMENTATION Page 2 of 16 Report Date: 01/31/14
SSES MAN~TEA-L Manual Name: TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.4.1 1 04/26/2006
Title:
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY TEXT 3.4.2 1 04/16/2009
Title:
REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY TEXT 3.4.3 1 11/09/2007
Title:
REACTOR COOLANT SYSTEM HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITORS TEXT 3.4.4 2 04/17/2008
Title:
REACTOR COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT 3.4.5 1 04/26/2006
Title:
REACTOR COOLANT SYSTEM REACTOR VESSEL MATERIALS TEXT 3.4.6
Title:
2 04/25/2013 REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION 0
TEXT 3.5.1 1 02/04/2005
Title:
EMERGENCY CORE COOLING AND RCIC ADS MANUAL INHIBIT TEXT 3.5.2 1 11/09/2007
Title:
EMERGENCY CORE COOLING AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0 11/18/2002
Title:
EMERGENCY CORE COOLING AND RCIC LONG TERM NITROGEN SUPPLY TO ADS TEXT 3.6.1 0 11/18/2002
Title:
CONTAINMENT VENTING OR PURGING TEXT 3.6.2 1 08/23/2011
Title:
SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0 11/18/2002
Title:
CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION Report Date: 01/31/1~
Page33.
Page of 16 16 Report Date: 01/31/14
SSES MANUAL Manual Name: TRMI O Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.6.4 0 11/18/2002
Title:
CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 0 11/18/2002
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN TEXT 3.7.2 0 11/18/2002
Title:
PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL TEXT 3,7.3.1 2 04/16/2009
Title:
PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 3 04/16/2009
Title:
PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS O TEXT 3,7.3.3 3 04/16/2009
Title:
PLANT SYSTEMS C02 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 10 09/27/2012
Title:
PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION O TEXT 3.7.4 1 04/26/2006
Title:
PLANT SYSTEMS SOLID RADWASTE SYSTEM Report Date: 01/31/14 Page 44 of 16 16 Report Date: 01/31/14
SSES MANUAL Manual Name: TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.5.1 0 11/18/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT 3.7.5.2 0 11/18/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT 3.7.5.3 1 04/26/2006
Title:
PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 3 06/04/2012
Title:
PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 2 09/05/2008
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING TEXT 3. 7. 8
Title:
PLANT SYSTEEMS SNUBBERS 4 06/21/2007 0 TEXT 3.7.9 2 01/31/2014
Title:
PLANT SYST~:MS CONTROL STRUCTURE HVAC TEXT 3.7.10 1 12/14/2004
Title:
PLANT SYSTIEMS SPENT FUEL STORAGE POOLS (SFSPS)
TEXT 3.7.11 0 04/16/2009
Title:
STRUCTURAL INTEGRITY TEXT 3.8.1 2 04/05/2010
Title:
ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT 3.8.2.1 2 11/09/2007
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
CONTINUOUS TEXT 3.8.2.2 2 12/14/2004
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
AUTOMATIC Report Date: 01/31/1'~
Page ~5 of of 16 16 Report Date: 01/31/14
SSES MANUAL Manual Name: TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.8.3 1 04/05/2010
Title:
ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT 3.8.4 0 11/18/2002
Title:
ELECTRICAL POWER 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT 3.8.5 1 11/14/2013
Title:
ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION TEXT 3.8.6 1 12/08/2011
Title:
ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8.7 1 06/15/2009
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM
. TEXT 3.9.1
Title:
0 11/18/2002 REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0 11/18/2002
Title:
REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 0 11/18/2002
Title:
REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 1 04/26/2006
Title:
MISCELLANEOUS SEAL SOURCE CONTAMINATION TEXT 3.10.2 2 08/08/2006
Title:
MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 2 06/15/2010
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
- TEXT 3.10.4 2 04/17/2008
Title:
MISCELLANEOUS LEADING EDGE FLOW METER (LEFM)
Page 6 of 16 Report Date: 01/31/14
SSES MANUAL Manual Name: TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 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 2 05/02/2007
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 11/18/2002
Title:
RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3.11.2.5 4 07/03/2013
Title:
RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3.11.2.6 4 09/16/2009
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.3 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS TOTAL DOSE 4 Report Date: 01/31/14 Page 71 Page off o 16 L6 Report Date: 01/31/14
SSES MANUAL
. Manual
Title:
Manual Name: TRMI TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.4.1 4 08/08/2006
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 POOL STORAGE POOL TEXT 3.12.2 4 04/17/2008
Title:
LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0 11/19/2002
Title:
LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENT TEXT 4.1 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION TEXT 4.3 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION TEXT 4.4 1 12/18/2008
Title:
ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT 4.5 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS TEXT 4.6 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM Report Date: 01/31/14 Page 88 Page of of 16 16 Report Date: 01/31/14
SSES MANUAL Manual Name: TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 4.7 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS TRAINING TEXT B3.0 4 05/23/2008
Title:
APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.1.1 1 11/09/2007
Title:
REACTIVITY CONTROL SYSTEMS BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.1.2 0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT B3.1.3 3 03/31/2006
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT B3.1.4 0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.1 0 11/19/2002
Title:
CORE OPERATING L IMITS 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 3 12/18/2008
Title:
INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 4 07/09/2010
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 Report Date: 01/31/14 Page .2 9 of of 16 16 Report Date: 01/31/14
SSES MANUAL Manual Name: TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.3.6 5 01/31/2014
Title:
INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION TEXT B3.3.7 1 11/09/2007
Title:
INSTRUMENTATION BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT B3.3.8 1 10/22/2003
Title:
INSTRUMENTATION BASES TRM REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT B3.3.9 3 04/17/2008
Title:
OPRM INSTRUMENTATION TEXT B3.3.10 3 08/09/2010
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 B3.4.1 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 0 11/19/2002
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 Report Date: 01/31/14 Page 10 Page 10 of of 16 16 Report Date: 01/31/14
SSES MANUAL Manual Name: TRlJl Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.4.6 2 04/25/2013
Title:
REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT B3.5.1 0 11/19/2002
Title:
ECCS AND RCIC BASES ADS MANUAL INHIBIT TEXT B3.5.2 1 11/09/2007
Title:
ECCS AND RCIC BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT B3.5.3 1 11/09/2007
Title:
ECCS AND RCIC BASES LONG TERM NITROGEN SUPPLY TO ADS TEXT B3.6.1 0 11/19/2002
Title:
CONTAINMENT BASES VENTING OR PURGING TEXT B3.6.2 0 11/19/2002
Title:
CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 2 04/17/2008
Title:
CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION TEXT 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 3 06/15/2010
Title:
PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM 0
TEXT B3.7.3.2 2 04/26/2006
Title:
PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS Pageii f 16Reprt ate:01/1/1 Page 11 of 16 Report Date: 01/31/14
SSES MANUAL Manual Name: TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.3.3 0 11/19/2002
Title:
PLANT SYSTEMS BASES C02 SYSTEMS TEXT B3,7.3.4 2 06/04/2013
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
Title:
3 09/27/2012 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 Am0 TEXT B3.7.7 2 01/31/2008 WF
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION Page 12 of 16 Report Date: 01/31/14
SSES MANUAL Manual Name: TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 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 B3.7.11 1 04/14/2010
Title:
STRUCTURAL INTEGRITY TEXT B3.8.1 2 03/10/2010
Title:
ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT B3.8.2.1 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 2 12/08/2011
Title:
ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 2 06/04/2013
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM Report Date: 01/31/id Page 13 Page 13 of of 16 16 Report Date: 01/31/14
SSES MANUAL Manual Name: TRMI1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.9.1 0 11/19/2002
Title:
ASES DECAY TIME REFUELING OPEl RATIONS B.
TEXT B3.9.2 0 11/19/2002
Title:
REFUELING OPEl RATIONS BASES COMMUNICATIONS TEXT B3.9.3 0 11/19/2002
Title:
REFUELING OPEl RATIONS BASES REFUELING PLATFORM TEXT B3.10.1 0 11/19/2002
Title:
MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 1 03/31/2006
Title:
MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT B3.10.3 0 11/19/2002
Title:
MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT B3.10.4 1 04/17/2008
Title:
MISCELLANEOUS BASES LEADING EDGE FLOW METER (LEFM)
TEXT B3.11.1.1 0 11/19/2002
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 B3.11.1.5 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION Report Date: 01/31/14 Page 14 14 of of 16
.16 Report Date: 01/31/14
SSES MANUAL Manual Name: TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.11.2.1 1 12/14/2004
Title:
RADIOACTIVE EFFLUENTS BASES DOSE RATE 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:
RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3.11.2.6
Title:
1 01/27/2004 RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING 0
INSTRUMENTATION TEXT B3.11.3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES TOTAL DOSE TEXT B3.11.4.1 4 06/04/2013
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 Report Date: 01/31/1~
Page i~
Page 15 of of 16 16 Report Date: 01/31/14
SSES MANUAL Manual Name: TRMI1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.12.3 0 11/19/2002
Title:
LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Report Date: 01/31/14 Page 14 16 0off 2~6 1-k Report Date: 01/31/14
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 79 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date TOC TABLE OF CONTENTS 10/09/2012 1.0 USE AND APPLICATION Page TRM / 1.0-1 10/04/2002 Page TRM / 1.0-2 01/21/2014 Page TRM / 1.0-3 10/04/2002 2.0 PLANT PROGRAMS Page 2.0-1 08/31/1998 Pages TRM / 2.0-2 and TRM / 2.0-3 01/28/2005 Page TRM / 2.0-4 06/25/2002 Page TRM / 2.0-5 01/21/2014 Page TRM / 2.0-6 03/27/2008 Page TRM / 2.0-7 05/15/2008 Pages TRM / 2.0-8 and TRM / 2.0-9 01/07/2011 Page TRM / 2.0-10 02/02/2010 Page TRM / 2.0-11 11/15/2004 Page TRM / 2.0-12 03/27/2008 Pages TRM / 2.0-13 and TRM / 2.0-14 11/15/2004 Page TRM / 2.0-15 11/15/2005 3.0 APPLICABILITY Page TRM / 3.0-1 04/14/2008 Page TRM / 3.0-2 04/12/2007 Page TRM / 3.0-3 03/15/2002 Page TRM / 3.0-4 11/30/2005 3.1 REACTIVITY CONTROL SYSTEMS Page TRM / 3.1-1 10/31/2007 Pages TRM / 3.1-2 through TRM / 3.1-5 08/31/1998 Page TRM / 3.1-6 03/22/2006 Page TRM / 3.1-7 04/07/2009 Page TRM / 3.1-8 03/27/2008 Pages TRM / 3.1-9 and TRM / 3.1-9a 02/18/1999 Page TRM / 3.1-10 02/18/1999 3.2 CORE OPERATING LIMITS REPORT Page TRM / 3.2-1 07/07/1999 Pages TRM / 3.2-2 through TRM / 3.2-54 04/09/2012 3.3 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 07/16/1999 Page TRM / 3.3-4 and TRM / 3.3-5 10/31/2007 Page TRM / 3.3-6 03/10/2011 TRM/LOES-1 EFFECTIVE DATE 01/21/2014 SUSQUEHANNA - UNIT SUSQUEHANNA -
UNIT I 1 TRM / LOES-1 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 79 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / 3.3-7 10/31/2007 Page 3.3-8 08/31/1998 Pages TRM / 3.3-9 and TRM / 3.3-9a 06/30/2010 Page TRM / 3.3-10 10/31/2007 Pages TRM / 3.3-11 and TRM / 3.3-11 a 06/30/2010 Page TRM / 3.3-12 03/30/2001 Page TRM / 3.3-13 01/07/2011 Page TRM / 3.3-14 12/14/1998 Pages TRM / 3.3-15 and TRM / 3.3-16 01/07/2011 Page TRM / 3.3-17 06/14/2002 Page TRM / 3.3-18 10/31/2007 Pages TRM / 3.3-19 through TRM / 3.3-21 10/22/2003 Page TRM / 3.3-22 03/27/2008 Page TRM / 3.3-22a 11/15/2004 Pages TRM / 3.3-22b through TRM / 3.3-22d 03/22/2006 Page TRM / 3.3-23 12/03/2004 Pages TRM / 3.3-24 and TRM / 3.3-25 05/16/2003 Page TRM / 3.3-26 10/22/2003 Pages TRM / 3.3-27 and TRM / 3.3-28 04/07/2009 3.4 REACTOR COOLANT SYSTEM Page TRM / 3.4-1 03/31/2006 Pages 3.4-2 through 3.4-5 10/23/1998 Pages TRM / 3.4-6 through TRM / 3.4-8 04/01/2009 Page TRM / 3.4-9 08/31/1998 Page TRM / 3.4-10 10/31/2007 Page TRM / 3.4-11 08/31/1998 Page TRM / 3.4-12 03/27/2008 Page TRM / 3.4-13 03/31/2006 Pages TRM / 3.4-14 and TRM / 3.4-15 04/25/2013 3.5 EMERGENCY CORE COOLING AND RCIC Page TRM / 3.5-1 01/28/2005 Pages 3.5-2 and 3.5-3 08/31/1998 Pages TRM / 3.5-4 and TRM / 3.5-5 10/31/2007 Pages 3.5-6 and 3.5-7 08/31/1998 3.6 CONTAINMENT Page 3.6-1 08/31/1998 Pages TRM / 3.6-2 and TRM / 3.6-2a 08/11/2Oll Page 3.6-3 08/31/1998 Page TRM / 3.6-4 01/07/2002 Page 3.6-5 08/31/1998 Pages TRM / 3.6-6 through TRM / 3.6-8 12/31/2002 SUSQUEHANNA - UNIT 1 TRM / LOES-2 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 79 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.7 PLANT SYSTEMS Pages 3.7-1 through 3.7-3 08/31/1998 Page TRM / 3.7-4 03/31/2006 Pages TRM / 3.7-5 04/07/2009 Pages TRM / 3.7-6 through TRM / 3.7-8 08/02/1999 Pages TRM / 3.7-9 and TRM / 3.7-10 04/07/2009 Page TRM / 3.7-11 12/29/1999 Page TRM / 3.7-12 08/02/1999 Page TRM / 3.7.13 04/07/2009 Page TRM / 3.7-14 08/09/2005 Pages TRM / 3.7-15 and TRM / 3.7-16 08/02/1999 Page TRM / 3.7-17 04/07/2009 Page TRM / 3.7-18 08/02/1999 Page TRM / 3.7-19 04/07/2009 Pages TRM / 3.7-20 through TRM / 3.7-22 08/02/1999 Page TRM / 3.7-23 04/07/2009 Page TRM / 3.7-24 03/31/2006 Page TRM / 3.7-25 08/02/1999 Page TRM / 3.7-26 09/25/2012 Page TRM / 3.7-27 11/24/2011 Pages TRM / 3.7-28 through TRM / 3.7-34a 09/25/2012 Page TRM / 3.7-35 03/31/2006 Pages TRM / 3.7-36 and TRM / 3.7-37 02/01/1999 Pages 3.7-38 and 3.7-39 08/31/1998 Page TRM / 3.7-40 03/31/2006 Page TRM / 3.7-41 05/24/2012 Pages TRM / 3.7-41a through TRM / 3.7-41c 05/24/2012 Page TRM / 3.7-42 09/04/2008 Page TRM / 3.7-43 08/31/1998 Pages TRM / 3.7-44 through TRM / 3.7-46 10/05/2006 Page TRM / 3.7-47 06/07/2007 Page TRM / 3.7-48 10/05/2006 Page TRM / 3.7-49 06/07/2007 Page TRM / 3.7-50 01/21/2014 Page TRM / 3.7-51 08/16/2006 Page TRM / 3.7-52 12/03/2004 Page TRM / 3.7-53 04/15/2003 Page TRM / 3.7-54 07/29/1999 Pages TRM / 3.7-55 through TRM / 3.7-57 04/01/2009 TRM/LOES-3 EFFECTIVE DATE 01/21/2014 SUSQUEHANNA - UNIT SUSQUEHANNA -
UNIT I1 TRM / LOES-3 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 79 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.8 ELECTRICAL POWER Page TRM / 3.8-1 04/02/2002 Page TRM / 3.8-2 01/28/2005 Pages TRM / 3.8-3 and TRM /3.8-4 03/25/2010 Pages TRM / 3.8-5 and TRM / 3.8-6 04/02/2002 Page TRM / 3.8-7 10/31/2007 Pages TRM / 3.8-8 through TRM / 3.8-10 12/03/2004 Page TRM / 3.8-11 09/03/2004 Page TRM / 3.8-12 12/03/2004 Page TRM / 3.8-13 03/25/2010 Page TRM / 3.8-14 08/31/1998 Pages TRM / 3.8-15 through TRM / 3.8-17 04/02/2002 Page 3.8-18 08/31/1998 Page TRM / 3.8-19 04/02/2002 Page 3.8-20 08/31/1998 Pages TRM / 3.8-21 and TRM / 3.8-22 06/06/1999 Page TRM / 3.8-23 11/07/2013 Pages TRM / 3.8-24 and TRM / 3.8-25 11/30/2011 Page TRM / 3.8-26 05/28/2009 Page TRM / 3.8-27 11/29/2006 Pages TRM / 3.8-28 and TRM / 3.8-29 05/28/2009 3.9 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 08/31/1998 3.10 MISCELLANEOUS Page TRM / 3.10-1 03/31/2006 Pages 3.10-2 and 3.10-3 08/31/1998 Pages 3.10-2 and 3.10-3 08/31/1998 Page TRM / 3.10-4 08/01/2006 Pages TRM / 3.10-5 and TRM / 3.10-6 03/22/2006 Page TRM / 3.10-7 06/10/2010 3.11 RADIOACTIVE EFFLUENTS Page TRM / 3.11-1 03/31/2006 Pages 3.11-2 and 3.11-3 08/31/1998 Page TRM / 3.11-4 03/31/2006 Page 3.11-5 08/31/1998 Page TRM / 3.11-6 03/31/2006 Pages TRM / 3.11-7 and TRM / 3.11-8 08/31/1998 Pages TRM / 3.11-9 and TRM / 3.11-10 10/09/2012 Pages TRM / 3.11-11 and TRM / 3.11-12 08/31/1998 Page TRM / 3.11-13 04/12/2007 SUSQUEHANNA - UNIT 1 TRM / LOES-4 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 79 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / 3.11-14 12/03/2004 Pages 3.11-15 and 3.11-16 09/01/1998 Page TRM / 3.11-17 03/31/2006 Page 3.11-18 08/31/1998 Page TRM / 3.11-19 08/15/2005 Pages TRM / 3.11-20 and TRM / 3.11-21 03/31/2006 Page TRM / 3.11-22 04/02/2002 Page TRM / 3.11-23 11/14/2006 Page TRM / 3.11-24 06/18/2013 Page TRM / 3.11-25 04/12/2007 Pages TRM / 3.11-26 and TRM / 3.11-27 01/21/2004 Page TRM / 3.11-28 09/08/2009 Page TRM / 3.11-29 12/03/2004 Pages TRM / 3.11.30 through TRM / 3.11.32 01/21/2004 Page TRM / 3.11-33 03/31/2006 Page 3.11-34 08/31/1998 Page TRM / 3.11-35 03/31/2006 Pages TRM / 3.11-36 through TRM / 3.11-39 11/30/2005 Pages 3.11-40 through 3.11-43 08/31/1998 Page TRM / 3.11-44 08/01/2006 Page TRM / 3.11-45 03/31/2006 Page 3.11-46 08/31/1998 Page TRM / 3.11-47 03/31/2006 LOADS CONTROL PROGRAM 3.12 Pages TRM / 3.12-1 through TRM / 3.12-3 02/05/1999 Page TRM / 3.12-4 03/14/2008 Page TRM / 3.12-5 02/05/1999 4.0 ADMINISTRATIVE CONTROLS Pages TRM / 4.0-1 through TRM / 4.0-3 08/31/1998 Page TRM / 4.0-4 12/11/2008 Pages TRM / 4.0-5 through TRM / 4.0-8 08/31/1998 SUSQUEHANNA - UNIT 1 TRM / LOES-5 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 79 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date B 3.0 APPLICABILITY BASES Pages TRM / B 3.0-1 through TRM / B 3.0-3 08/31/1998 Page TRM / B 3.0-4 01/10/2007 Page TRM / B 3.0-5 04/14/2008 Page TRM / B 3.0-6 08/31/1998 Page TRM / B 3.0-7 04/12/2007 Pages TRM / B 3.0-8 through TRM / B 3.0-10 08/31/1998 Pages TRM / B 3.0-11 and TRM / B 3.0-12 03/15/2002 Pages TRM / B 3.0-13 and TRM / B 3.0-14 11/30/2005 Page TRM / B 3.0-15 03/15/2002 B 3.1 REACTIVITY CONTROL SYSTEMS BASES Page TRM / B 3.1-1 07/13/1999 Pages TRM / B 3.1-2 and TRM / B 3.1-3 10/31/2007 Page B 3.1-4 08/31/1998 Page TRM / B 3.1-5 11/15/2005 Pages TRM / B 3.1-6 and TRM / B 3.1-7 03/22/2006 Page TRM / B 3.1-8 02/18/1999 B 3.2 CORE OPERATING LIMITS BASES Page B 3.2-1 08/31/1998 B 3.3 INSTRUMENTATION BASES Page TRM / B 3.3-1 01/21/2014 Page TRM / B 3.3-2 03/10/2011 Page TRM / B 3.3-2a 10/31/2007 Page TRM / B 3.3-3 12/11/2008 Page TRM / B 3.3-3a 10/31/2007 Page TRM / B 3.3-4 06/30/2010 Page TRM / B 3.3-5 05/30/2006 Page TRM / B 3.3-6 06/30/2010 Page TRM / B 3.3-7 10/30/2007 Page TRM / B. 3.3-8 06/30/2010 Page TRM I B 3.3-9 10/31/2007 Pages TRM / B 3.3-10 through TRM / B 3.3-12 01/07/2011 Page TRM / B 3.3-13 01/21/2014 Page TRM / B 3.3-14 06/25/2002 Page TRM / B 3.3-14a 10/31/2007 Page TRM / B 3.3-14b 10/31/2007 Pages TRM / B 3.3-15 and TRM / B 3.3-16 10/22/2003 Page TRM / B 3.3-17 03/22/2006 Pages TRM / B 3.3-17a through TRM / B 3.3-17c 03/22/2006 Page TRM / B 3.3-17d 03/27/2008 SUSQUEHANNA - UNIT 1 TRM / LOES-6 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 79 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Pages TRM / B 3.3-17e and TRM / B 3.3-17f 03/22/2006 Pages TRM / B 3.3-18 and TRM / B 3.3-19 08/03/2010 Page TRM / B 3.3-20 10/22/2003 Page TRM / B 3.3-21 05/16/2003 Pages TRM / B 3.3-22 and TRM / B 3.3-23 04/07/2009 B 3.4 REACTOR COOLANT SYSTEM BASES Page B 3.4-1 08/31/1998
.Pages TRM / B 3.4-2 and TRM / B 3.4-3 04/01/2009 Pages TRM / B 3.4-4 and TRM / B 3.4-4a 10/31/2007 Page TRM / B 3.4-5 10/15/1999 Page B 3.4-6 08/31/1998 Pages TRM / B 3.4-7 and TRM / B 3.4-8 04/25/2013 B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 08/31/1998 Pages TRM / B 3.5-3 through TRM / B 3.5-5 10/31/2007 B 3.6 CONTAINMENT BASES Page TRM / B 3.6-1 07/26/2001 Page TRM / B 3.6-2 02/01/1999 Page B 3.6-3 08/31/1998 Page TRM / B 3.6-4 03/27/2008 Page TRM / B 3.6-5 04/04/2007 Page TRM / B 3.6-6 12/03/2004 Pages B.3.6-7 through TRM / B 3.6-11 12/31/2002 B 3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 08/31/1998 Page TRM / B 3.7-3 06/10/2010 Page TRM / B 3.7-3a 12/27/2007 Page TRM / B 3.7-4 03/31/2006 Page TRM / B 3.7-5 08/02/1999 Page TRM / B 3.7-6 03/31/2006 Pages TRM / B 3.7-7 and TRM / B 3.7-7a 08/02/1999 Pages TRM / B 3.7-8 and TRM / B 3.7-9 05/29/2013 Page TRM / B 3.7-10 08/02/1999 Page TRM / B 3.7-10a 03/31/2006 Page TRM / B 3.7-11 08/02/1999 Page TRM / B 3.7-11a 03/31/2006 Pages TRM / B 3.7-12 and TRM / B 3.7-13 08/02/1999 Pages TRM / B 3.7-14 and TRM / B 3.7-14a 09/25/2012 SUSQUEHANNA - UNIT 1 TRM / LOES-7 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 79 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / B 3.7-14b 11/24/2011 Pages TRM / B 3.7-15 and TRM / B 3.7-16 02/01/1999 Pages B 3.7-17 through B 3.7-20 08/31/1998 Page TRM / B 3.7-21 05/29/2013 Pages TRM / B 3.7-21a through TRM / B 3.7-21d 05/24/2012 Pages TRM / B 3.7-21e through TRM / B 3.7-21g 05/29/2013 Page TRM / B 3.7-22 and TRM / B 3.7-23 01/30/2008 Page TRM / B 3.7-24 10/05/2006 Page TRM / B 3.7-25 01/21/2014 Pages TRM / B 3.7-26 through TRM / B 3.7-28 10/05/2006 Pages TRM / B 3.7-29 and TRM / B 3.7-30 06/07/2007 Page TRM / B 3.7-30a 10/05/2006 Page TRM / B 3.7-30b 01/21/2014 Page TRM / B 3.7-31 11/30/2011 Page TRM / B 3.7-32 03/09/2001 Page TRM / B 3.7-33 04/15/2003 Page TRM / B 3.7-34 12/03/2004 Page TRM / B 3.7-35 07/05/2000 Pages TRM / B 3.7-36 through TRM / B 3.7-39 04/01/2009 Page TRM / B 3.7-40 04/08/2010 B 3.8 ELECTRICAL POWER BASES Page TRM / B 3.8-1 04/02/2002 Pages TRM / B 3.8-2 and TRM / B 3.8-2 01/28/2005 Page TRM / B 3.8-2a 03/01/2010 Page TRM / B 3.8-3 04/02/2002 Page TRM / B 3.8-3a 04/02/2002 Page TRM / B 3.8-4 08/10/2004 Page TRM / B 3.8-4a 04/02/2002 Page TRM / B 3.8-5 08/31/1998 Pages TRM / B 3.8-6 through TRM / B 3.8-15 04/02/2002 Page TRM / B 3.8-16 11/07/2013 Page TRM / B 3.8-17 11/30/2011 Pages TRM / B 3.8-17a and TRM / B 3.8-17b 11/30/2011 Pages TRM / B 3.8-18 through TRM / B 3.8-20 05/29/2013 Pages TRM / B 3.8-21 and TRM / B 3.8-22 05/28/2009 Page TRM / B 3.8-23 05/29/2013 Page TRM / B 3.8-24 05/28/2009 B.3.9 REFUELING OPERATIONS BASES Pages B 3.9-1 through B 3.9-7 08/31/1998 SUSQUEHANNA - UNIT I TRM / LOES-8 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 79 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date B 3.10 MISCELLANEOUS BASES Page B 3.10-1 08/31/1998 Pages TRM / B 3.10-2 and TRM / B 3.10-3 03/22/2006 Pages TRM / B 3.10-4 and TRM / B 3.10-5 08/23/1999 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 08/30/1998 Page TRM / B 3.11 02/01/1999 Pages TRM/B 3.11-11 and TRM/B 3.11-1 Ia 04/07/2000 Pages TRM/B 3.11-12 and TRM/B 3.11-13 02/01/1999 Page TRM / B 3.11-14 12/03/2004 Page TRM / B 3.11-15 02/01/1999 Pages B 3.11-16 through B 3.11-19 08/30/1998 Page TRM / B 3.11-20 04/02/2002 Page TRM / B 3.11-20a 04/02/2002 Page TRM / B 3.11-21 05/13/2005 Pages TRM / B 3.11-22 and TRM / B 3.11-23 11/14/2006 Pages TRM / B 3.11-23a and TRM / B 3.11-23b 06/18/2013 Pages TRM / B 3.11-24 and TRM / B 3.11-25 01/21/2004 Pages B 3.11-26 and B 3.11-27 08/30/1998 Pages TRM / B 3.11-28 and TRM / B 3.11-29 11/30/2005 Pages TRM / B 3.11-30 and TRM / B 3.11-31 05/29/2013 Page TRM/ B 3.11-32 08/30/1998 Page TRM/ B 3.11-33 06/30/2010 Pages TRM / B 3.11-34 and TRM / B 3.11-35 08/30/1998 Page TRM / B 3.11-36 02/12/1999 B.3.12 LOADS CONTROL PROGRAM BASES Page TRM / B 3.12-1 09/19/2007 Page TRM / B 3.12-2 11/29/2010 Page TRM / B 3.12-3 02/05/1999 TRM1 text LOES 1/21/14 SUSQUEHANNA - UNIT 1 TRM / LOES-9 EFFECTIVE DATE 01/21/2014
Definitions PPL Rev. 1 1.1 1.0 USE AND APPLICATION 1.1 Definitions
NOTE ----------------------------------------------------------
- 1. The defined terms of this section and the Technical Specifications appear in capitalized type and are applicable throughout these Technical Requirements and Bases.
- 2. Terms used in these Technical Requirements are as defined in the Technical Specifications or as defined below.
Term Definition GASEOUS RADWASTE A GASEOUS RADWASTE TREATMENT SYSTEM TREATMENT SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
MEMBERS OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.
PROCESS CONTROL PROGRAM The PROCESS CONTROL PROGRAM (PCP) shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured.
PURGE - PURGING PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
(continued)
SUSQUEHANNA - UNIT 1 TRM / 1.0-1 EFFECTIVE DATE 10/04/2002
Definitions PPL Rev. 1 1.1 1.0 USE AND APPLICATION 1.1 Definitions (continued)
SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee. See FSAR Section 2.1.1.2.
SOLIDIFICATION SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).
SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the site boundary used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. See FSAR Section 2.1.1.3.
VENTILATION EXHAUST A VENTILATION EXHAUST TREATMENT SYSTEM TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
(continued)
SUSQUEHANNA - UNIT 1 TRM / 1.0-2 EFFECTIVE DATE 01/21/2014
Definitions PPL Rev. 1 1.1 1.0 USE AND APPLICATION 1.1 Definitions (continued)
VENTING VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during venting. Vent, used in system names, does not imply a VENTING process.
SUSQUEHANNA - UNIT 1 TRM / 1.0-3 EFFECTIVE DATE 10/04/2002
Instrument Trip Setpoint Program PPL Rev. 10 2.2 2.0 PLANT PROGRAMS AND SETPOINTS 2.2 Instrument Trip Setpoint Table The Instrument Trip Setpoint Limits in Table 2.2-1 are the Trip Setpoint value limits that were contained in the Instrumentation Setpoint tables for protection systems and other functions important to safety that were included in the scope of the original Standard Technical Specifications. Actual instrument setpoints are established utilizing the Allowable Values specified in the Technical Specifications and Technical Requirements. Allowable Values are established in the Reference LCOs and TROs identified in this Table. TRO references are enclosed in square brackets.
Instrumentation process setpoints for the listed subsystems and trip functions are set consistent with the Trip Setpoint Limit Column of Table 2.2-1. Actual setpoints are established in accordance with engineering procedures.
Alarm setpoints and other non-protection system trip settings as may be found in the Technical Specifications or in the Technical Requirements are not included in this table.
Reference:
MFP-QA-1220, Engineering Change Process Handbook SUSQUEHANNA - UNIT 1 TRM / 2.0-5 EFFECTIVE DATE 01/21/2014
Instrument Trip Setpoint Program PPL Rev. 10 2.2 TABLE 2.2-1 (Page 1 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO [TRO] TRIP FUNCTION TRIP SETPOINT 2.2.1 Reactor Protection 2.2.1.1 3.3.1.1 Intermediate Range Monitor, Neutron Flux- _120/125 divisions of full scale High 2.2.1.2 3.3.1.1 Average Power Range Monitor, Neutron Flux *18% of RATED THERMAL POWER
- High (Setdown) 2.2.1.3 3.3.1.1 Average Power Range Monitor, Simulated 0.55 W + 58.7%
Thermal Power- High, Two Loop Operation 2.2.1.4 3.3.1.1 Average Power Range Monitor, Simulated 0.55 (W- AW) + 58.7%""
Thermal Power- High, Single Loop Operation 2.2.1.5 3.3.1.1 Average Power Range Monitor, Simulated < 113.5% of RATED THERMAL Thermal Power-High, Clamp POWER 2.2.1.6 3.3.1.1 Average Power Range Monitor, Neutron Flux - < 118% of RATED THERMAL High POWER 2.2.1.7 3.3.1.1 Reactor Vessel Steam Dome Pressure - High < 1087 psig 2.2.1.8 3.3.1.1 Reactor Vessel Water Level - Low, Level 3 > 13.0 inches (a) 2.2.1.9 3.3.1.1 Main Steam Isolation Valve - Closure _<10% closed 2.2.1.10 This Section Not Used 2.2.1.11 3.3.1.1 Drywell Pressure- High *1.72 psig 2.2.1.12 3.3.1.1 Scram Discharge Volume Water Level - High -
- 65 gallons Level Transmitter 2.2.1.13 3.3.1.1 Scram Discharge Volume Water Level - High -
- 61 gallons Float Switch 2.2.1.14 3.3.1.1 Turbine Stop Valve - Closure
- 5.5% closed 2.2.1.15 3.3.1.1 Turbine Control Valve Fast Closure, Trip > 500 psig Oil Pressure - Low (continued)
(a)See Figure 2.2-1 (b)For Single loop operation, the value of AW = 8.7 SUSQUEHANNA - UNIT 1 TRM / 2.0-6 EFFECTIVE DATE 03/27/2008
Instrument Trip Setpoint Program PPL Rev. 10 2.2 TABLE 2.2-1 (Page 2 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO [TRO] TRIP FUNCTION TRIP SETPOINT 2.2.1.16 OPRM Instrumentation 2.2.1.16.1 3.3.1.1 Sp PBA Amplitude Trip See COLR - TRO 3.2 2.2.1.16.2 3.3.1.1 Np PBA Successive Confirmation Count Trip See COLR -TRO 3.2 2.2.1.16.3 [3.3.9] TOL (e) Period Tolerance 0.10 sec 2.2.1.16.4 [3.3.9] fc Conditioning Filter Cutoff Frequency 1.50 Hz 2.2.1.16.5 [3.3.9] Tmin Oscillation Period Lower Time Limit 1.00 sec 2.2.1.16.6 [3.3.9] Tmax Oscillation Period Upper Time Limit 3.50 sec 2.2.1.16.7 [3.3.9] LPRMmin Minimum LRPMs/Cell Required for 2 Cell Operability 2.2.1.16.8 [3.3.9] S1 Peak Threshold Setpoint/ABA & GRBA 1.20 2.2.1.16.9 [3.3.9] S2 Valley Threshold Setpoint/ABA & GRBA 0.85 2.2.1.16.10 [3.3.9] Smax Amplitude Trip SetpointIABA 1.50 2.2.1.16.11 [3.3.9] DR3 Growth Rate Factor Setpoint/GRBA 1.60 2.2.2 Isolation Actuation Instrumentation 2.2.2.1 Primary Containment Isolation 2.2.2.1.1 3.3.6.1 Reactor Vessel Water Level Low, Level 3 > 13.0 inches(a) 2.2.2.1.2 3.3.6.1 Reactor Vessel Water Level Low Low, Level 2 _-38.0 inches(a) 2.2.2.1.3 3.3.6.1 Reactor Vessel Water Level Low Low Low, > -129 inches(a)
Level 1 2.2.2.1.4 3.3.6.1 Drywell Pressure - High < 1.72 psig 2.2.2.1.5 3.3.6.1 SGTS Exhaust Radiation - High _<23.0 mR/hr 2.2.2.1.6 [3.3.6] Main Steam Line Radiation - High High < 15 x full power background without hydrogen injection (continued)
(a)See Figure 2.2-1 SUSQUEHANNA - UNIT 1 TRM / 2.0-7 EFFECTIVE DATE 05/15/2008
Instrument Trip Setpoint Program PPL Rev. 10 2.2 TABLE 2.2-1 (Page 3 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.2.2 Secondary Containment Isolation 2.2.2.2.1 3.3.6.2 Reactor Vessel Water Level - Low Low, -38.0 inches(a)
Level 2 2.2.2.2.2 3.3.6.2 Drywell Pressure - High _<1.72 psig 2.2.2.2.3 3.3.6.2 Refuel Floor High Exhaust Duct Radiation - _<18 mR/hr High 2.2.2.2.4 3.3.6.2 Railroad Access Shaft Exhaust Duct _<5 mR/hr Radiation - High 2.2.2.2.5 3.3.6.2 Refuel Floor Wall Exhaust Duct Radiation - < 21 mR/hr High 2.2.2.3 Main Steam Line Isolation 2.2.2.3.1 3.3.6.1 Reactor Vessel Water Level - Low Low Low, _-129 inches(a)
Level 1 2.2.2.3.2 3.3.6.1 Main Steam Line Pressure - Low _>861 psig 2.2.2.3.3 3.3.6.1 Main Steam Line Flow - High < 173 psid 2.2.2.3.4 3.3.6.1 Condenser Vacuum - Low > 9.0 inches Hg vacuum 2.2.2.3.5 3.3.6.1 Reactor Building Main Steam Line Tunnel < 1771F Temperature - High 2.2.2.3.6 This Section Not Used 2.2.2.3.7 This Section is not used.
2.2.2.3.8 [3.3.6] Turbine Building Main Steam Tunnel < 1970F Temperature - High 2.2.2.4 Reactor Water Cleanup System Isolation 2.2.2.4.1 3.3.6.1 Reactor Vessel Water Level - Low Low, -38 inches(a)
Level 2 2.2.2.4.2 3.3.6.1 RWCU A Flow - High < 59 gpm 2.2.2.4.3 3.3.6.1 RWCU Flow- High < 462 gpm 2.2.2.4.4 3.3.6.1 RWCU Penetration Area Temperature - High <131°F 2.2.2.4.5 This Section is not used.
2.2.2.4.6 3.3.6.1 RWCU Pump Area Temperature - High <147°F 2.2.2.4.7 This Section is not used.
2.2.2.4.8 3.3.6.1 RWCU Heat Exchanger Area Temperature - <147°F High 2.2.2.4.9 This Section is not used.
(continued)
(a)See Figure 2.2-1 SUSQUEHANNA - UNIT 1 TRM / 2.0-8 EFFECTIVE DATE 01/07/2011
Instrument Trip Setpoint Program PPL Rev. 10 2.2 TABLE 2.2-1 (Page 4 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.2.5 Reactor Core Isolation Cooling System Isolation 2.2.2.5.1 3.3.6.1 RCIC Steam Line A Pressure - High < 188 inches H20 2.2.2.5.2 3.3.6.1 RCIC Steam Supply Line Pressure - Low >_60 psig 2.2.2.5.3 3.3.6.1 RCIC Turbine Exhaust Diaphragm Pressure < 10.0 psig
- High 2.2.2.5.4 3.3.6.1 RCIC Equipment Room Temperature - High <1671F 2.2.2.5.5 3.3.6.1 RCIC Pipe Routing Area Temperature - High <1671F 2.2.2.5.6 3.3.6.1 RCIC Emergency Area Cooler Temperature - <1670 F High 2.2.2.5.7 3.3.6.1 Drywell Pressure - High < 1.72 psig 2.2.2.5.8 This section is not used.
2.2.2.5.9 This section is not used.
2.2.2.6 High Pressure Coolant Injection System Isolation 2.2.2.6.1 3.3.6.1 HPCI Steam Line A Pressure - High < 370 inches H 2 0 2.2.2.6.2 3.3.6.1 HPCI Steam Supply Line Pressure - Low > 104 psig 2.2.2.6.3 3.3.6.1 HPCI Turbine Exhaust Diaphragm Pressure - < 10 psig High 2.2.2.6.4 3.3.6.1 HPCI Equipment Room Temperature - High < 1671F 2.2.2.6.5 3.3.6.1 HPCI Emergency Area Cooler Temperature - < 167OF High 2.2.2.6.6 3.3.6.1 HPCI Pipe Routing Area Temperature - High < 1671F 2.2.2.6.7 3.3.6.1 Drywell Pressure - High
- 1.72 psig 2.2.2.6.8 This section is not used.
2.2.2.6.9 This section is not used.
2.2.2.7 Shutdown Cooling/System Isolation 2.2.2.7.1 3.3.6.1 Reactor Vessel Water Level - Low, Level 3 13.0 inches(a) 2.2.2.7.2 3.3.6.1 Reactor Vessel Steam Dome Pressure - High < 98 psig 2.2.2.7.3 [3.3.6] RHR Flow - High < 25,000 gpm 2.2.3 ECCS Actuaton 2.2.3.1 Core Spray System 2.2.3.1.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, >-129 inches(a)
Level 1 2.2.3.1.2 3.3.5.1 Drywell Pressure - High < 1.72 psig 2.2.3.1.3 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low > 413, _<427 psig injection permissive (continued)
(a) See Figure 2.2-1 SUSQUEHANNA - UNIT 1 TRM / 2.0-9 EFFECTIVE DATE 01/07/2011
Instrument Trip Setpoint Program PPL Rev. 10 2.2 TABLE 2.2-1 (Page 5 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.3.2 LPCI Mode of RHR System 2.2.3.2.1 3.3.5.1 Reactor Vessel Water'Level - Low Low Low, -129 inches(a)
Level 1 2.2.3.2.2 3.3.5.1 Drywell Pressure - High < 1.72 psig 2.2.3.2.3 3.3.5.1 Reactor Vessel Steam Dome Pressure - >413, < 427 psig Low, injection permissive 2.2.3.2.4 3.3.5.1 Reactor Vessel Steam Dome Pressure - > 236 psig, decreasing Low, Recirculation Discharge Valve permissive 2.2.3.3 HPCI System 2.2.3.3.1 3.3.5.1 Reactor Vessel Water Level - Low Low, >-38 inches(a)
Level 2 2.2.3.3.2 3.3.5.1 Drywell Pressure - High < 1.72 psig 2.2.3.3.3 3.3.5.1 Condensate Storage Tank Level - Low > 40.5 inches above tank bottom 2.2.3.3.4 3.3.5.1 Reactor Vessel Water Level - High, Level 8 < 54 inches 2.2.3.4 Automatic Depressurization System (ADS) 2.2.3.4.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, > -129 inches Level 1 2.2.3.4.2 3.3.5.1 Drywell Pressure - High _<1.72 psig 2.2.3.4.3 3.3.5.1 ADS Timer _<102 seconds 2.2.3.4.4 3.3.5.1 Core Spray Pump Discharge Pressure - High > 135, _ 155 psig 2.2.3.4.5 3.3.5.1 Low Pressure Coolant Injection Pump > 121, < 129 psig Discharge Pressure - High 2.2.3.4.6 3.3.5.1 Reactor Vessel Water Level - Low, Level 3 >_13 inches Confirmatory 2.2.3.4.7 3.3.5.1 ADS Drywell Pressure Bypass Timer < 420 seconds 2.2.3.5 Loss of Power - ECCS Actuation 2.2.3.5.1 4.16kv ESS Bus Undervoltage (Loss of Voltage < 20%)
2.2.3.5.1.1 3.3.8.1 Bus Undervoltage S823.2. 856.8 Volts
(
2.2.3.5.1.2 3.3.8.1 Time delay >0.4, <0.6 seconds (continued)
(a)See Figure 2.2-1 SUSQUEHANNA - UNIT 1 TRM / 2.0-10 EFFECTIVE DATE 02/02/2010
Instrument Trip Setpoint Program PPL Rev. 10 2.2 TABLE 2.2-1 (Page 6 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.3.5.2 4.16kV ESS Bus Undervoltage (Degraded Voltage < 65%)
2.2.3.5.2.1 3.3.8.1 Bus Undervoltage > 2641.1, _2748.9 Volts 2.2.3.5.2.2 3.3.8.1 Time delay > 2.7, < 3.3 seconds 2.2.3.5.3 4.16kV ESS Bus Undervoltage (Degraded Voltage, < 93%)
2.2.3.5.3.1 3.3.8.1 Bus Undervoltage > 3829.3, < 3906.7 Volts 2.2.3.5.3.2 3.3.8.1 Time Delay (Non-LOCA) _Ž4 minute, 30 seconds
< 5 minute, 30 seconds 2.2.3.5.3.4 3.3.8.1 Time Delay (LOCA) > 9, < 11 seconds 2.2.3.5.4 480V ESS Bus 0B565 Undervoltage (Degraded Voltage, < 65%)
2.2.3.5.4.1 [3.8.5] 480V Basis > 308.9, *315.1 Volts 2.2.3.5.4.2 [3.8.5] Time Delay > 4.5, < 5.5 seconds 2.2.3.5.5 480V ESS Bus 0B565 Undervoltage (Degraded Voltage, < 92%)
2.2.3.5.5.1 [3.8.5] 480V Basis >_437.6,
- 446.4 Volts 2.2.3.5.5.2 [3.8.5] Time Delay Ž 9, < 11 seconds 2.2.4 ATWS Alternate Rod Injection and Recirculation Pump Trip 2.2.4.1 3.3.4.2/[3.1.1] Reactor Vessel, Water Level - Low Low, >-38 inches(a)
Level 2 2.2.4.1 3.3.4.2J[3.1.1] Reactor Vessel Steam Dome Pressure- High <1135 psig 2.2.5 End of Cycle Recirculation Pump Trip 2.2.5.1 3.3.4.1 Turbine Stop Valve-Closure < 5.5% closed 2.2.5.2 3.3.4.1 Turbine Control Valve - Fast Closure >_500 psig 2.2.6 Reactor Core Isolation Cooling System Actuation 2.2.6.1 3.3.5.2 Reactor Vessel Water Level - Low Low, >!-38 inches(a)
Level 2 2.2.6.2 3.3.5.2 Reactor Vessel Water Level - High, Level 8 < 54 inches(a) 2.2.6.3 3.3.5.2 Condensate Storage Tank Level - Low > 36.0 inches above tank bottom (continued)
(a)See Figure 2.2-1 SUSQUEHANNA - UNIT 1 TRM / 2.0-11 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Program PPL Rev. 10 2.2 TABLE 2.2-1 (Page 7 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.7 Control Rod Block 2.2.7.1 Rod Block Monitor 2.2.7.1.1 3.3.2 Low Power Range - Upscale See COLR TRO 3.2 3.3.2 Intermediate Power Range - Upscale See COLR TRO 3.2 3.3.2 High Power Range - Upscale See COLR TRO 3.2 2.2.7.1.2 3.3.2 Low Power Range Setpoint See COLR TRO 3.2 3.3.2 Intermediate Power Range Setpoint See COLR TRO 3.2 3.3.2 High Power Range Setpoint See COLR TRO 3.2 2.2.7.2 APRM
'2.2.7.2.1 [3.1.3] Simulated Thermal Power-High 0.55W + 54.2%
- Two Loop Operation 2.2.7.2.2 [3.1.3] Simulated Thermal Power-High 0.55 (W-AW) + 54.2% 'c)
- Single Loop Operation 2.2.7.2.3 [3.1.3] Simulated Thermal Power-High - Clamp _108% of RATED THERMAL POWER 2.2.7.2.4 [3.1.3] Downscale >_5% of RATED THERMAL POWER 2.2.7.2.5 [3.1.3] Neutron Flux - High (Setdown) < 12% of RATED THERMAL POWER 2.2.7.3 Source Range Monitors 2.2.7.3.1 [3.1.3] Upscale < 2E5 cps 2.2.7.3.2 [3.1.3] Downscale > 3.0 cps(b) 2.2.7.4 Intermediate Range Monitors 2.2.7.4.1 [3.1.3] Upscale < 108/125 divisions of full scale 2.2.7.4.2 [3.1.3] Downscale > 5/125 divisions of full scale 2.2.7.5 Scram Discharge Volume 2.2.7.5.1 [3.1.3] Water Level - High < 35.9 gallons 2.2.7.6 Reactor Coolant System Recirculation Flow 2.2.7.6.1 [3.1.3] Upscale 114%
(continued) b)With a signal-to-noise ratio >_2, or within the limits of Figure 2.2-2.
(c)For single loop operation, the value of AW = 8.7 SUSQUEHANNA - UNIT 1 TRM / 2.0-12 EFFECTIVE DATE 03/27/2008
Instrument Trip Setpoint Program PPL Rev. 10 2.2 TABLE 2.2-1 (Page 8 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.8 CREOASS 2.2.8.1 3.3.7.1 Main Control Room Outside Air Intake <5 mR/hr Radiation Monitor 2.2.8.1.1 3.3.7.1 Reactor Vessel Water Level - Low Low, >-38.0 inches(a)
Level 2 2.2.8.1.2 3.3.7.1 Drywell Pressure - High < 1.72 psig 2.2.8.1,.3 3.3.7.1 Refuel Floor High Exhaust Duct Radiation < 18 mR/hr
- High 2.2.8.1.4 3.3.7.1 Railroad Access Shaft Exhaust Duct <5 mR/hr Radiation - High 2.2.8.1.5 3.3.7.1 Refuel Floor Wall Exhaust Duct Radiation < 21 mR/hr
- High 2.2.9 Feedwater/Main Turbine Trip System Actuation 2.2.9.1 3.3.2.2 Reactor Vessel Level - High < 54.0 inches(a) 2.2.10 MVP Isolation 2.2.10.1 [3.3.11] Main Steam Line Radiation - High High < 15 x full power background without hydrogen injection (a)See Figure 2.2-1 SUSQUEHANNA - UNIT 1 TRM / 2.0-13 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Table PPL Rev. 10 2.2 FIGURE 2. 2-1 REACTOR VESSEL WATER LEVEL SUSQUEHANNA - UNIT 1 TRMV / 2.0-14 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Table PPL Rev. 10 2.2 Instrument Trip Setpoint Table 2.2 3
2.8 . . . . . . . . . . . . . .
2.6 2.4 2.2 2
1.8 1.6 I.-
1.4 -- Acceptable i-z 1.2 0
0 1 0.8 0.6 Not Acceptable 0.4 0.2 0
2 6 10 14 18 22 26 30 Signal-to-Noise Ratio Figure 2.2-2 Minimum SRM Trip Setpoint Versus Signal-to-Noise Ratio SUSQUEHANNA - UNIT 1 TRM / 2.0-15 EFFECTIVE DATE 11/15/2005
Control Structure HVAC PPL Rev. 2 3.7.9 3.7 Plant Systems 3.7.9 Control Structure HVAC TRO 3.7.9 The following Control Structure HVAC Subsystems shall be OPERABLE:
- a. Control Structure Heating and Ventilating System
- b. Computer Room Floor Cooling System
- c. Control Structure Chilled Water
- d. Battery Room Exhaust System
- e. SGT Equipment Room Ventilation System (Heating)
- f. SGT Equipment Room Ventilation System (Cooling)
APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment.
During CORE ALTERATIONS.
During operations with a potential for draining the reactor vessel (OPDRVs).
NOTE----------------.-.-----.-.------ .......---------------
- 1. If Conditions and Required Actions for this TRO that direct entry into LCOs are not completed. LCO 3.0.3 should be entered not TRO 3.0.3.
- 2. Enter applicable Conditions and Required Actions of LCO 3.7.3 "Control Room Emergency Outside Air Supply (CREOAS) System" and LCO 3.7.4 "Control Room Floor Cooling System" for Technical Specification Functions made inoperable by the inoperable Control Structure HVAC Subsystems.
- 3. Control Structure and Computer Room Ventilation fans are also governed by LCO 3.7.3 "Control Room Emergency Outside Air Supply (CREOAS) System."
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. A single division of A.1 Restore all affected 30 days subsystems a-e inoperable subsystems to OPERABLE for its cooling or heating status mode (continued)
SUSQUEHANNA - UNIT 1 TRM / 3.7-50 EFFECTIVE DATE 01/21/2014
Control Structure HVAC PPL Rev. 2 3.7.9 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. A single division of B.1 Restore the affected cooling 30 days subsystem f inoperable unit to OPERABLE status C. Both divisions of any C.1 Declare affected equipment Immediately subsystem inoperable for inoperable and enter all the cooling or heating appropriate LCOs/TROs mode D. Required Action and D.1 Be in MODE 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A, or B AND not met D.2 Be in MODE 4 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.7.9.1 Administratively verify that the Control Structure 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> HVAC Subsystems are available SUSQUEHANNA - UNIT 1 TRM / 3.7-51 EFFECTIVE DATE 08/16/2006
Radiation Monitoring Instrumentation PPL Rev. 1 B 3.3.1 B 3.3.1 Radiation Monitoring Instrumentation BASES TRO The OPERABILITY of the radiation monitoring instrumentation ensures that:
(1) the radiation levels are continually measured in the areas served by the individual channels; (2) the alarm is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of NUREG-0737, "Clarification of TMI Action Plan Requirements," November 1980.
(Reference 1 and 2)
Table 3.3.1-1 identifies two criticality monitoring functions-new fuel storage vault and spent fuel storage pool. Both functions have two redundant monitors. Each instrument is positioned and setpoint established to detect a criticality event for the function monitored.
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components.
TRS The TRSs are defined to be performed at the specified Frequency to ensure that the Radiation Monitoring Function is maintained OPERABLE.
Performance of the CHANNEL CHECK ensures that a gross failure of the instrument has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel against a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value.
Significant deviations between instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrument continues to operate properly between each CHANNEL CALIBRATION.
Agreement criteria, which are developed by the plant staff based on an investigation of a combination of the channel instrument uncertainties, may be used to support this parameter comparison and include indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit and does not necessarily indicate the channel is inoperable.
REFERENCES 1. FSAR Section 12.3.4
- 2. NUREG-0737, "Clarification of TMI Action Plan Requirements,"
November 1980 SUSQUEHANNA - UNIT I TRM / B 3.3-1 EFFECTIVE DATE 01/21/2014
TRM Isolation Actuation Instrumentation PPL Rev. 5 B 3.3.6 B 3.3.6 TRM Isolation Actuation Instrumentation BASES TRO The TRM Actuation instrumentation automatically initiates closure of appropriate primary containment isolation valves (PCIVs). The function of the PCIVs, in combination with other accident mitigation systems, is to limit fission product release during and following postulated Design Basis Accidents (DBAs) (Reference 1). The TRM Isolation Actuation Instrument has been relocated from the Technical Specifications because the identified Function is not credited in the plant design basis to mitigate any plant event, but does provide a diverse means to initiate an Isolation Actuation.
The isolation instrumentation includes the sensors, relays, and instruments that are necessary to cause initiation of primary containment and Reactor Coolant Pressure Boundary (RCPB) isolation. When the setpoint is reached, the sensor actuates, which then outputs an isolation signal to the isolation logic. Monitoring a wide range of independent parameters provides functional diversity. The input parameters to the isolation logic are:
(a) Main steam line radiation, (b) Turbine Building Main Steam Line Tunnel Temperature - High, and (c) RHR Flow- High.
The valves associated with these trip channels are identified in Table B 3.3.6-1. Each of these valves is also associated with other trip channels as identified in LCO Bases B 3.6.1.3.
The trips occur after a one second delay. See Tech Spec Basis B 3.3.6-1.
(continued)
SUSQUEHANNA - UNIT I TRM / B 3.3-10 EFFECTIVE DATE 01/07/2011
TRM Isolation Actuation Instrumentation PPL Rev. 5 B 3.3.6 B 3.3.6 TRM Isolation Actuation Instrumentation BASES (continued)
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components. The ACTIONS are modified by two Notes. Note 1 allows penetration flow path(s) to be unisolated intermittently under administrative controls. These controls consist of stationing a dedicated operator at the controls of the valve, who is in continuous communication with the control room. In this way, the penetration can be rapidly isolated when a need for primary containment isolation is indicated.
Note 2 is provided to modify the ACTIONS for separate Condition entry, consistent with similar Note in the TS 3.3.6.1 Actions.
Condition C applies if the channel is not restored to OPERABLE status or placed in trip, or isolation capability is not restored, within the allowed Completion Time. If inoperable channels should not be placed in trip (e.g., might result in a undesirable transient) Action C may be intentionally entered as a result of not meeting Required Action A.1 in its required Completion Time. Required Action C.1 requires appropriate compensatory measures be in place within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Examples of appropriate compensatory measures may consist of verifying that diverse isolation functions remain OPERABLE. Furthermore, isolating the penetration (e.g., as may be required by TS Actions for an inoperability affecting both the TRM Function and a required TS Function) also provides adequate compensatory actions since isolating the affected penetration flow path(s) accomplishes the safety function of the inoperable channels. If it is not desired to isolate the affected penetration flow path(s) (e.g., as in the case where isolating the penetration flow path(s) could result in a reactor scram or disabling RHR-SDC), alternate compensatory measures should be pursued.
The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time is acceptable due to the fact that these Functions are not assumed in any accident or transient analysis in the FSAR.
TRS The TRSs are defined to be performed at the specified Frequency to ensure that the TRM Isolation Actuation Instrumentation Functions are maintained OPERABLE. TRM Isolation Actuation Instrumentation Surveillances are performed consistent with the Bases for LCO 3.3.6.1 "Isolation Activation Instrumentation."
(continued)
SUSQUEHANNA - UNIT 1 TRM / B 3.3-11 EFFECTIVE DATE 01/07/2011
TRM Isolation Actuation Instrumentation PPL Rev. 5 B 3.3.6 B 3.3.6 TRM Isolation Actuation Instrumentation BASES (continued)
TRS 3.3.6.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel. The system functional testing performed on PCIVs in LCO 3.6.1.3 overlaps this surveillance to provide complete testing of the assumed safety function. The 24 month Frequency is based on the need to perform portions of this surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the surveillance when performed at the 24 month Frequency.
TRS 3.3.6.6 The response time testing of Function 2.a is per FSAR Table 7.3-29.
REFERENCES 1. FSAR Section 7.3.1
- 2. NRC Inspection and Enforcement Manual, Part 9900: Technical Guidance, Standard Technical Specification Section 1.0 Definitions, Issue dated 12/8/96.
SUSQUEHANNA - UNIT 1 TRM / B 3.3-12 EFFECTIVE DATE 01/07/2011
TRM Isolation Actuation Instrumentation PPL Rev. 5 B 3.3.6 Table B 3.3.6-1 Primary Containment Isolation Valves (Page 1 of 1)
Isolation Signal Function No.
Plant systems Valve Number Valve Description (Table 3.3.6-1)
Nuclear HV-141FO22A MSIV l.a Boiler HV-141FO22B MSIV l.a HV-141F022C MSIV l.a HV-141FO22D MSIV l.a HV-141FO28A MSIV 1.a HV-141FO28B MSIV 1.a HV-141F028C MSIV 1.a HV-141F028D MSIV 1.a HV-141F016 MSL Drain Isolation Valve 1.a HV-141F019 MSL Drain Isolation Valve 1.a Reactor HV-143F019 Reactor Coolant Sample Valve 2.a Recirculation HV-143F020 Reactor Coolant Sample Valve 2.a RHR HV-151F022 RHR - Reactor Vessel Head Spray Valve 3.a HV-151F023 RHR - Reactor Vessel Head Spray Valve 3.a HV-151F008 RHR Shutdown Cooling Valve 3.a HV-151F009 RHR Shutdown Cooling Valve 3.a SUSQUEHANNA - UNIT 1 TRM / [] 3.3-13 EFFECTIVE DATE 01/21/2014
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES TRO All snubbers are required to be OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on non-safety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
Snubbers are required to be OPERABLE whenever they are considered necessary to support equipment for the systems on which they are installed.
Technical Specification LCO 3.0.8 has been added to the Technical Specifications to allow snubbers to be inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if the inoperable snubber affects one subsystem or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if it affects multiple subsystems.
The generic NRC Safety Evaluation which approved the use of LCO 3.0.8 requires that certain conditions be met before LCO 3.0.8 can be entered.
TRM 3.7.8 provides guidance on meeting these conditions.
"Type" of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity. For example, mechanical snubbers utilizing the same design features of the 2-kip, and 100-kip capacity manufactured by Company "A" are of the same type. The same design mechanical snubbers manufactured by company "B" for the purposes of this Technical Requirement would be of a different type, as would hydraulic snubbers from either manufacturer.
A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR part 50. The controlled list of plant snubbers is maintained by the ISl Program. The addition or deletion of any snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
(continued)
SUSQUEHANNA - UNIT 1 TRM / B 3.7-24 EFFECTIVE DATE 10/05/2006
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES TRO The following are examples of conditions that require a snubber to be (continued) declared inoperable:
- Snubber not attached to piping system or support plate,
- Snubber missing,
- Snubber locked in position,
- Snubber excessively bent.
The following are examples of conditions that require an evaluation to confirm whether or not the snubber is inoperable:
- Dent(s) in snubber case,
- Thread engagement not per design,
- Missing bolt(s) on support plate,
- Snubber slightly bent.
As stated in NRC's Safety Evaluation Condition 2, the LCO 3.0.8 requirement to assess and manage risk is met by licensee programs to comply with the requirements of paragraph (a)(4) of the Maintenance Rule, 10 CFR 50.65, to assess and manage risk resulting from maintenance activities. Since the 10 CFR 50.65(a) (4) guidance, the revised (May 2000)
Section 11 of NUMARC 93-01, does not address seismic risk, licensees must qualitatively integrate the use of LCO 3.0.8 into their 10 CFR 50.65(a) (4) program to assess and manage risk.
As described in the Bases of LCO 3.0.8, "LCO 3.0.8 should be considered with respect to other plant maintenance activities, and integrated into the existing Maintenance Rule process to the extent possible so that maintenance on any unaffected train or subsystem is properly controlled, and emergent issues are properly addressed. The risk assessment need not be quantified, but may be a qualitative awareness of the vulnerability of systems and components when one or more snubbers are not able to perform their associated support function."
The inservice inspection and testing program for snubbers will be performed in accordance with Subsection ISTD of the ASME OM Code and applicable addenda as required by 10 CFR Part 50.55a(b)(3)(v) except where specific written relief has been granted by the NRC. (Reference 2)
(continued)
SUSQUEHANNA - UNIT 1 TRM / B 3.7-25 EFFECTIVE DATE 01/21/2014
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES (continued)
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components and the implementation of LCO 3.0.8. The NRC's 4/27/2005 Safety Evaluation lists the conditions that must be followed to adopt and utilize LCO 3.0.8. The ACTIONS provide the guidance for the implementation of these conditions and therefore the implementation of LCO 3.0.8.
Conditions A and B Condition A applies when one or more snubbers are not capable of providing their associated support function(s) to a single subsystem of a multiple subsystem supported system or to a single subsystem supported system.
Condition B applies when one or more snubbers are not able to perform their associated support function(s) are associated with more than one subsystem of a multiple subsystem supported system.
The wording of these Conditions allow for confirmation of snubber inoperability. This allows for input from snubber knowledgeable parties to review the condition. The intent is to obtain this confirmation in an expeditious manner and not delay declaring a snubber or support system inoperable. If confirmation of snubber inoperability is delayed, the snubber should be considered inoperable and appropriate actions of this TRO applied.
Required Action A.1.1 or B.1.1 When a snubber is to be rendered incapable of performing its related support function (i.e., nonfunctional) for testing or maintenance or is discovered to not be functional, it must be determined whether any Technical Specification (TS) system(s) require the affected snubber(s) for system OPERABILITY, and whether the plant is in a MODE or specified condition in the Applicability that requires the supported TS system(s) to be OPERABLE.
- 1. If an analysis determines that the supported TS system(s) do not require the snubber(s) to be functional in order to support the OPERABILITY of the system(s), LCO 3.0.8 is not needed.
- 2. If the LCO(s) associated with any supported TS system(s) are not currently applicable (i.e., the plant is not in a MODE or other specified condition in the Applicability of the LCO), LCO 3.0.8 is not needed.
(continued)
SUSQUEHANNA - UNIT 1 TRM / B 3.7-26 EFFECTIVE DATE 10/05/2006
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES ACTIONS 3. If the supported TS system(s) are inoperable for reasons other than (continued) snubbers, LCO 3.0.8 cannot be used.
LCO 3.0.8 is an allowance, not a requirement. When a snubber is nonfunctional, any supported TS system(s) may be declared inoperable instead of using LCO 3.0.8.
The NRC Safety Evaluation only considered the loss of the ability of a snubber to respond to a seismic event. However, some snubbers have design functions other than response to a seismic event. The inability to perform these non-seismic design functions were not considered or justified. Therefore, when a snubber is to be rendered nonfunctional for testing or maintenance or is discovered to not be functional, the design function of the snubber must be determined in order to determine if LCO 3.0.8 may be used.
- 1. If the design function of the snubber is to react to only seismic loads, LCO 3.0.8 may be applied.
- 2. If the design function of the snubber includes both seismic loads and non-seismic loads (e.g., thrust loads, blowdown loads, waterhammer loads, steamhammer loads, LOCA loads, and pipe rupture loads),
any TS systems supported by the nonfunctional snubber must be able to remain OPERABLE if subjected to the non-seismic loads with the snubber removed. If the supported TS system will remain OPERABLE when subjected to non-seismic loads, LCO 3.0.8 may be applied. Otherwise, LCO 3.0.8 may not be applied to TS systems supported by the nonfunctional snubber.
- 3. If the design function of the snubber includes only non-seismic loads (e.g., thrust loads, blowdown loads, waterhammer loads, steam-hammer loads, LOCA loads, and pipe rupture loads), LCO 3.0.8 cannot be applied to the TS systems supported by the nonfunctional snubber. However, if it can be confirmed that snubber is not needed for OPERABILITY of the TS system, LCO 3.0.8 is not needed.
Note: Snubbers located in the Diesel Generator Buildings only have seismic loads as their design function loads. Snubbers located elsewhere in the plant have both seismic and non-seismic loads as their design function loads.
(continued)
SUSQUEHANNA - UNIT 1 TRM / B 3.7-27 EFFECTIVE DATE 10/05/2006
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES ACTIONS Required Action A. 1.2 or B. 1.2 (continued)
This Required Action ensures that when LCO 3.0.8 is entered there are sufficient OPERABLE subsystems (not associated with the inoperable snubber) to provide makeup and heat removal in the event of a LOOP.
The NRC does not require any other accidents or events such as LOCA, DBA or transients to be accounted for. The subsystems that can be use to meet this condition are:
- a. At least one OPERABLE high pressure subsystem (e.g., HPCI or RCIC) and OPERABLE heat removal capability (e.g., suppression pool cooling), or
- b. At least one OPERABLE low pressure subsystem (e.g., LPCI or CS) and OPERABLE heat removal capability (e.g., suppression pool cooling or shutdown cooling).
The NRC's Safety Evaluation Condition 1.(d) is met by these required actions.
Required Action A.1.3 or B.1.3 The NRC's Safety Evaluation requires that subsystem(s) associated with inoperable snubber (s) must be capable of performing their required safety or support function when subjected to the postulated non-seismic design function loads.
NRC's Safety Evaluation also requires that every time LCO 3.0.8 is used for TS systems supported by nonfunctional snubbers whose design loads include non-seismic loads, licensees must be able to produce a record of the design function of the nonfunctional snubber (i.e., seismic vs. non-seismic). This record does not have to be created prior to or following use of LCO 3.0.8, but must be able to be created or produced if requested.
For example, if a system engineer knows from previous experience that a particular snubber is only designed for seismic loads, it is not necessary to collect existing design documents or create design documents or calcula-tions to demonstrate that fact prior to using LCO 3.0.8. However, if asked to demonstrate the design basis of the snubber, the licensee must be able to produce or create appropriate documentation to support that position.
Required Action A.1.4 or B.1.4 Required Action A. 1.4 or B. 1.4 provide for the entry into LCO 3.0.8 provided the requirements for entry are verified.
(continued)
SUSQUEHANNA - UNIT 1 TRM / B 3.7-28 EFFECTIVE DATE 10/05/2006
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES ACTIONS Required Action A.1.5 or B.1.5 (continued)
The completion time is consistent with the time used to evaluate the risk of having an inoperable snubber and not declaring the system LCO.
Condition E Snubbers are required to be OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Evaluating their service life and replacing them before the end of their service life ensures that the snubbers will remain OPERABLE.
TRS The TRSs are defined to be performed at the specified Frequency to ensure that the snubbers are maintained OPERABLE. Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, ifapplicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the completion of their fabrication or at a subsequent date. Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.
TRS 3.7.8.1 The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Generic Letter 90-09 provides a method for determining the next interval for the visual inspection of snubbers based upon the number of unacceptable snubbers found during the previous inspection, the total population or category size for each snubber type, and the previous inspection interval.
The visual inspection interval for a snubber population shall be determined based upon previous inspections and the number of unacceptable snubbers found during that interval. The visual inspection interval for snubbers shall be determined based upon the criteria provided in the ISI Program Plan.
(continued)
SUSQUEHANNA - UNIT I TRM / B 3.7-29 EFFECTIVE DATE 06/07/2007
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES TRS TRS 3.7.8.1 (continued)
Visual inspections shall verify that (1) the snubber has no visible indications of damage or impaired OPERABILITY, and (2) fasteners for the attachment of the snubber to the component, and to the snubber anchorage are functional.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per TRS 3.7.8.2. A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber. If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.
(continued)
SUSQUEHANNA - UNIT I TRM / B 3.7-30 EFFECTIVE DATE 06/07/2007
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES TRS TRS 3.7.8.2 (continued)
A representative sample of snubbers shall be tested for each type of snubber. The representative sample selected for the functional test sample plans shall be randomly selected from the snubbers of each type and reviewed before beginning the testing. The review shall ensure as far as practical that they are representative of the various configurations, operating environments, range of size, and capacity of snubbers of each type.
Functional Test Acceptance Criteria The snubber functional test shall verify that:
- 1) Activation (restraining action) is achieved within the specified range in both tension and compression;
- 2) Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range;
- 3) Where required, the force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel; and
- 4) For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement.
Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.
TRS 3.7.8.3 The maximum expected service life for various seals, springs, and other critical parts shall be determined and established based on engineering information and shall be extended or shortened based on monitored test results and failure history. Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be OPERABLE. The parts replacements shall be documented and the documentation shall be retained in accordance with FSAR 17.2.17.
(continued)
SUSQUEHANNA - UNIT 1 TRM / B 3.7-30a EFFECTIVE DATE 10/05/2006
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES TRS TRS 3.7.8.3 (continued)
The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.
TRS 3.7.8.5 The required inspection consists of the following elements:
- 1. Perform a visual inspection of all affected snubbers,
- 3. Verify freedom of motion of mechanical snubbers by evaluation of in-place snubber piston setting, or
- 4. Verify freedom of motion of mechanical snubbers by stroking the mechanical snubber through its full range of travel.
REFERENCES 1. Generic Letter 90-09
- 2. 10CFRPart50 SUSQUEHANNA - UNIT 1 TRM / B 3.7-30b EFFECTIVE DATE 01/21/2014
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USE AND APPLICATION DEFINITIONS TEXT 2.1 1 02/04/2005
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INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 2 11/09/2007
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INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 6 07/09/2010
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INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0 11/19/2002
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INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK TEXT 3.3.6 3 01/13/2011
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INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 1 11/09/2007
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INSTRUMENTATION LPRM UPSCALE ALARM INSTRUMENTATION TEXT 3.3.10 1 12/14/2004
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INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1 10/22/2003
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REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM (RCS)
TEXT 3.4.4 2 05/14/2009
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REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT 3.5.1 1 02/04/2005
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ECCS AND RCIC ADS MANUAL INHIBIT TEXT 3.5.2 1 11/09/2007
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ECCS AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0 11/19/2002
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PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL TEXT 3.7.3.1 2 04/16/2009
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PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 3 04/16/2009
Title:
PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS
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3 PLANT SYSTEMS C02 SYSTEMS 04/16/2009 TEXT 3.7.3.4 2 04/16/2009
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PLANT SYSTEMS HALON SYSTEMS TEXT 3.7.3.5 2 04/16/2009
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PLANT SYSTEMS FIRE HOSE STATIONS TEXT 3.7.3.6 2 04/16/2009
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PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION
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PLANT SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT 3.7.5.3 1 04/26/2006
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PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 3 06/04/2012
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PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 2 09/05/2008
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PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT 3.7.8 8 09/13/2012
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PLANT SYSTEMS SNUBBERS TEXT 3.7.9 1 08/28/2006
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PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 1 12/14/2004
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PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)
TEXT 3.7.11 1 10/02/2009
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 PROTECTICON -
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ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTI( ON -
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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 06/20/2012
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 3.11.1.1 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION Page6 of 15 Report Date: 01/31/14
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 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 2 05/02/2007
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 4 09/16/2009
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.3 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS TOTAL DOSE TEXT 3.11.4.1 3 04/26/2006
Title:
RADIOACTIVE EFFLUENTS MONITORING PROGRAM Report Date: 01/31/14 Page 77 of of 15 15 Report Date: 01131114
SSES MAiNUAL1
. Manual Namne: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 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 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION TEXT 4. 3 0 09/27/2003
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 TEXT 4. 7 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS TRAINING Report Date: 01/31/14 Page Page .~
8 of of 15 15 Report Date: 01/31/14
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 4 TEXT B3.0 5 06/20/2012
Title:
APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.1.1 1 11/09/2007
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 3 04/10/2007
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
Title:
0 11/19/2002 CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR)
E 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 4 07/09/2010
Title:
INSTRUMENTATION BASES TRE POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT B3.3.5 2 11/09/2007
Title:
INSTRUMENTATION BASES THIS PAGE INTENTIONALLY LEFT BLANK TEXT B3.3.6 5 01/31/2014
Title:
INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION Report Date: 01/31/id Pages Page 9 of of 15
.15 Report Date: 0113111d
SSES MANUAL
. Name: TECHNICAL Manual
Title:
TRM2 REQUIREMENTS MANUAL UNIT 2 TEXT B3.3,7 1 11/09/2007
Title:
INSTRUMENTATION BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT B3.3.8 1 10/22/2003
Title:
INSTRUMENTATION BASES TRM RPS INSTRUMENTATION TEXT B3.3.9 3 05/14/2009
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 B3.4.1 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 0 11/19/2002
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 TEXT B3.4.6 1 04/25/2013
Title:
REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION Report Date: 01/31/14 10 Page 10 of of 15 15 Report Date: 01/31/14
SSES MANUJAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.5.1 0 11/19/2002
Title:
ECCS AND RCIC BASES ADS MANUAL INHIBIT TEXT B3.5.2 1 11/09/2007
Title:
ECCS AND RCIC BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT B3.5.3 1 11/09/2007
Title:
ECCS AND RCIC BASES LONG TERM NITROGEN SUPPLY TO ADS TEXT B3.6.1 0 11/19/2002
Title:
CONTAINMENT BASES VENTING OR PURGING TEXT B3.6.2 0 11/19/2002
Title:
CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 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 3 06/15/2010
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 TEXT B3.7.3.3 0 11/19/2002
Title:
PLANT SYSTEMS BASES C02 SYSTEMS Report Date: 01/31/14 Page .12.
Page 11 of of 15 15 Report Date: 01/31/14
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.3.4 1 04/26/2006
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
- TEXT B3.7.8 4 01/31/2014
Title:
PLANT SYSTEMS BASES SNUBBERS Page 12 of .15 Report Date: 01/31/14
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 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 B3.7.11 2 04/14/2010
Title:
STRUCTURAL INTEGRITY TEXT B3.8.1 2 03/10/2010
Title:
ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT B3.8.2.1 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 O
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 I TEXT B3.9.1 0 11/19/2002
Title:
REFUELING OPERATIONS BASES DECAY TIME Report Date: 01/31/14 PageI~
Page 13 of of 15 15 Report Date: 01/31/14
SSES MANUAL Manual Name: TFM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 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 B3.10.1 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 0 11/19/2002
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 B3.11.1.5 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.11.2.1 1 12/14/2004
Title:
RADIOACTIVE EFFLUENTS BASES DOSE RATE TEXT B3.11.2.2 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES Report Date: 01/31/14 Page 14 Page 14 of of 15 15 Report Date: 01/31/14
SSES MANUJAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 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:
RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3.11.2.6 1 01/27/2004
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 4 06/04/2013
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 PROGRAM BASES LIGHT LOADS REQUIREMENTS Report Date: 01/31/1'~
Page i5~
Page 15 of of 15
.15 Report Date: 01/31/14
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 82 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date TOC TABLE OF CONTENTS 10/09/2012 1.0 USE AND APPLICATION Page TRM / 1.0-1 08/31/1998 Page TRM / 1.0-2 10/04/2002 Page TRM / 1.0-3 08/31/1998 2.0 PLANT PROGRAMS Page 2.0-1 08/31/1998 Pages TRM / 2.0-2 and TRM 2.0-3 01/28/2005 Page TRM / 2.0-4 06/25/2002 Page TRM / 2.0-5 01/21/2014 Page TRM / 2.0-6 04/15/2009 Page TRM / 2.0-7 05/15/2008 Pages TRM / 2.0-8 and TRM / 2.0-9 01/07/2011 Page TRM / 2.0-10 02/02/2010 Page TRM / 2.0-11 11/15/2004 Page TRM / 2.0-12 04/15/2009 Pages TRM / 2.0-13 and TRM / 2.0-14 11/15/2004 Page TRM / 2.0-15 11/15/2005 3.0 APPLICABILITY Pages TRM / 3.0-1 and TRM / 3.0-2 06/12/2012 Page TRM / 3.0-3 03/15/2002 Page TRM / 3.0-4 11/30/2005 3.1 REACTIVITY CONTROL SYSTEMS Page TRM / 3.1-1 10/31/2007 Pages TRM / 3.1-2 through TRM / 3.1-5 08/31/1998 Page TRM / 3.1-6 03/27/2007 Page TRM / 3.1-7 04/15/2009 Page TRM / 3.1-8 03/27/2007 Pages TRM / 3.1-9 and TRM / 3.1-9a 02/18/1999 Page TRM / 3.1-10 02/18/1999 3.2 CORE OPERATING LIMITS REPORT Page TRM / 3.2-1 08/31/1998 Pages TRM / 3.2-2 through TRM / 3.2-55 04/25/2013 3.3 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 07/16/1999 Pages TRM / 3.3-4 and TRM / 3.3-5 10/31/2007 Page TRM / 3.3-6 03/10/2011 Page TRM 3.3-7 10/31/2007 Page 3.3-8 08/31/1998 TRM / LOES-1 EFFECTIVE DATE 01/21/2014 SUSQUEHANNA - UNIT SUSQUEHANNA -
UNIT 2 2 TRM / LOES-1 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 82 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Pages TRM / 3.3-9 and TRM / 3.3-9a 06/30/2010 Page TRM / 3.3-10 10/31/2007 Pages TRM / 3.3-11 and TRM / 3.3-11 a 06/30/2010 Page TRM / 3.3-12 03/30/2001 Page TRM / 3.3-13 01/07/2011 Page TRM / 3.3-14 12/14/1998 Pages TRM / 3.3-15 and TRM / 3.3-16 01/07/2011 Page TRM / 3.3-17 06/14/2002 Page TRM / 3.3-18 10/31/2007 Pages TRM / 3.3-19 and TRM / 3.3-20 10/22/2003 Page TRM / 3.3-21 04/15/2009 Page TRM / 3.3-21a 11/15/2004 Pages TRM /3.3-21b through TRM / 3.3-21d 03/27/2007 Page TRM / 3.3-22 12/03/2004 Pages TRM / 3.3-23 and TRM / 3.3-24 05/16/2003 Page TRM / 3.3-25 10/22/2003 Pages TRM / 3.3-26 and TRM / 3.3-27 04/07/2009 3.4 REACTOR COOLANT SYSTEM Page TRM / 3.4-1 03/31/2006 Pages 3.4-2 through 3.4-5 10/23/1998 Pages TRM / 3.4-6 through TRM / 3.4-8 04/01/2009 Page 3.4-9 08/31/1998 Page 3.4-10 10/31/2007 Page 3.4-11 08/31/1998 Page TRM / 3.4-12 04/17/2009 Page TRM / 3.4-13 03/31/2006 Page TRM / 3.4-14 04/25/2013 3.5 EMERGENCY CORE COOLING AND RCIC Page TRM / 3.5-1 01/28/2005 Pages 3.5-2 and 3.5-3 08/31/1998 Page TRM / 3.5-4 10/31/2007 Pages 3.5-5 through 3.5-7 08/31/1998 3.6 CONTAINMENT Pages 3.6-1 and 3.6-2 08/31/1998 Pages TRM / 3.6-3 and TRM / 3.6-3a 08/11/2011 Page 3.6-4 08/31/1998 Page TRM / 3.6-5 01/07/2002 Page 3.6-6 08/31/1998 Pages TRM / 3.6-7 through TRM / 3.6-9 12/31/2002 SUSQUEHANNA - UNIT 2 TRIM / LOES-2 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 82 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.7 PLANT SYSTEMS Pages TRM / 3.7-1 and TRM / 3.7-2 07/29/1999 Page 3.7-3 08/31/1998 Page TRM / 3.7-4 03/31/2006 Page TRM / 3.7-5 04/07/2009 Pages TRM / 3.7-6 through TRM / 3.7-8 08/02/1999 Pages TRM / 3.7-9 and TRM / 3.7-10 04/07/2009 Page TRM / 3.7-11 01/21/2000 Page TRM / 3.7-12 08/02/1999 Page TRM / 3.7-13 04/07/2009 Page TRM / 3.7-14 08/09/2005 Pages TRM / 3.7-15 and TRM / 3.7-16 08/02/1999 Page TRM / 3.7-17 04/07/2009 Page TRM / 3.7-18 08/02/1999 Page TRM / 3.7-19 04/07/2009 Pages TRM / 3.7-20 through TRM / 3.7-22 08/02/1999 Page TRM / 3.7-23 04/07/2009 Page TRM / 3.7-24 03/31/2006 Page TRM / 3.7-25 08/02/1999 Page TRM / 3.7-26 09/25/2012 Page TRM / 3.7-27 11/24/2011 Pages TRM / 3.7-28 through TRM / 3.7-33 09/25/2012 Page TRM / 3.7-34 03/31/2006 Pages TRM / 3.7-35 and TRM / 3.7-36 02/01/1999 Pages 3.7-37 through 3.7-38 08/31/1998 Page TRM / 3.7-39 03/31/2006 Page TRM / 3.7-40 05/24/2012 Pages TRM / 3.7-40a through TRM / 3.7-40c 05/24/2012 Page TRM / 3.7-41 09/04/2008 Page TRM / 3.7-42 08/31/1998 Pages TRM / 3.7-43 through TRM / 3.7-45 10/05/2006 Page TRM / 3.7-46 06/07/2007 Page TRM / 3.7-47 09/05/2012 Page TRM / 3.7-48 06/07/2007 Page TRM / 3.7-49 03/09/2001 Page TRM / 3.7-50 08/16/2006 Page TRM / 3.7-51 12/03/2004 Page TRM / 3.7-52 04/15/2003 Page TRM / 3.7-53 07/29/1999 Page TRM / 3.7-54 04/01/2009 Page TRM / 3.7-55 09/25/2009 Page TRM / 3.7-56 04/01/2009 SUSQUEHANNA - UNIT 2 TRM / LOES-3 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 82 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.8 ELECTRICAL POWER Page TRM / 3.8-1 04/02/2002 Page TRM / 3.8-2 01/28/2005 Pages TRM / 3.8-3 and TRM / 3.8-4 06/12/2012 Pages TRM / 3.8-5 and TRM / 3.8-6 04/02/2002 Pages TRM / 3.8-7 through TRM / 3.8-10 10/31/2007 Page TRM / 3.8-11 08/10/2004 Page TRM / 3.8-12 12/03/2004 Page TRM / 3.8-13 06/12/2012 Page TRM / 3.8-14 08/31/1998 Page TRM / 3.8-15 01/28/2005 Pages TRM / 3.8-16 and TRM / 3.8-17 04/02/2002 Page 3.8-18 02/01/1999 Page TRM / 3.8-19 04/02/2002 Page TRM / 3.8-20 02/01/1999 Pages TRM / 3.8-21 and TRM / 3.8-22 06/06/1999 Page TRM / 3.8-23 11/07/2013 Page TRM / 3.8-24 11/30/2011 Page TRM / 3.8-25 06/11/2012 Pages TRM / 3.8-25a and TRM / 3.8-25b 11/30/2011 Page TRM / 3.8-26 05/28/2009 Page TRM / 3.8-27 11/29/2006 Page TRM / 3.8-28 05/28/2009 Page TRM / 3.8-29 10/20/2009 3.9 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 08/31/1998 3.10 MISCELLANEOUS Page TRM / 3.10-1 03/31/2006 Pages 3.10-2 through 3.10-4 08/30/1998 Pages TRM / 3.10-5 and TRM / 3.10-6 03/27/2007 Page TRM / 3.10-7 06/10/2010 3.11 RADIOACTIVE EFFLUENTS Page TRM / 3.11-1 03/31/2006 Pages 3.11-2 through 3.11-3 08/31/1998 Page TRM/, 3.11-4 03/31/2006 Page 3.11-5 08/31/1998 Page TRM / 3.11-6 03/31/2006 Pages 3.11-7 and TRM/3.11-8 08/31/1998 Pages TRM / 3.11-9 and TRM / 3.11-10 10/09/2012 Pages TRM / 3.11-11 and TRM / 3.11-12 08/31/1998 Page TRM / 3.11-13 04/12/2007 Page TRM / 3.11-14 12/03/1004 Pages 3.11-15 and 3.11-16 09/01/1998 Page TRM / 3.11-17 03/31/2006 TRM I LOES-4 EFFECTIVE DATE 01/21/2014 SUSQUEHANNA - UNIT SUSQUEHANNA -
UNIT 2 2 TRM / LOES-4 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 82 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page 3.11-18 08/31/1998 Page TRM / 3.11-19 08/15/2005 Pages TRM / 3.11-20 and TRM / 3.11-21 03/31/2006 Page TRM / 3. 11-22 04/02/2002 Page TRM / 3.11-23 11/14/2006 Page TRM / 3.11-24 06/18/2013 Page TRM / 3.11-25 04/12/2007 Pages TRM / 3.11-26 and TRM / 3.11-27 01/21/2004 Page TRM / 3.11-28 09/08/2009 Page TRM / 3.11-29 12/03/2004 Pages TRM 3.11-30 through TRM / 3.11-32 01/21/2004 Page TRM / 3.11-33 03/31/2006 Page 3.11-34 08/31/1998 Page TRM / 3.11-35 03/31/2006 Pages TRM / 3.11-36 through TRM / 3.11-39 11/30/2005 Pages 3.11-40 through 3.11-44 08/31/1998 Page TRM / 3.11-45 03/31/2006 Page 3.11-46 08/31/1998 Page TRM / 3.11-47 03/31/2006 3.12 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-3 02/05/1999 Page TRM / 3.12-4 03/14/2008 Page TRM / 3.12-5 02/05/1999 4.0 ADMINISTRATIVE CONTROLS Pages TRM / 4.0-1 through TRM / 4.0-3 08/31/1998 Page TRM / 4.0-4 12/11/2008 Pages TRM / 4.0-5 through TRM / 4.0-8 08/31/1998 TRM / LOES-5 EFFECTIVE DATE 01/21/2014 SUSQUEHANNA - UNIT SUSQUEHANNA -
UNIT 2 2 TRM / LOES-5 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 82 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date B 3.0 APPLICABILITY BASES Pages TRM / B 3.0-1 through TRM / B 3.0-3 08/31/1998 Page TRM / B 3.0-4 01/10/2007 Pages TRM / B 3.0-5 through TRM / B 3.0-7 06/12/2012 Pages TRM / B 3.0-8 through TRM / B 3.0-10 08/31/1998 Pages TRM / B 3.0-11 and TRM / B 3.0-12 03/15/2002 Pages TRM / B 3.0-13 and TRM / B 3.0-14 11/30/2005 Page TRM / B 3.0-15 03/15/2002 B 3.1 REACTIVITY CONTROL SYSTEMS BASES Page TRM / B 3.1-1 07/13/1999 Pages TRM / B 3.1-2 and TRM / B 3.1-3 10/31/2007 Page B 3.1-4 08/31/1998 Pages TRM / B 3.1-5 through TRM / B 3.1-7 03/27/2007 Page TRM / B 3.1-8 02/18/1999 B 3.2 CORE OPERATING LIMITS BASES Page B 3.2-1 08/31/1998 B 3.3 INSTRUMENTATION BASES Page TRM I B 3.3-1 01/21/2014 Page TRM / B 3.3-2 03/10/2011 Page TRM / B-3.3-2a 10/31/2007 Pages TRM / B 3.3-3 and TRM / B 3.3-3a 10/31/2007 Page TRM / B 3.3-4 06/30/2010 Page TRM / B 3.3-5 05/30/2006 Page TRM / B 3.3-6 06/30/2010 Page TRM / B 3.3-7 10/31/2007 Page TRM / B 3.3-8 06/30/2010 Page TRM / B 3.3-9 10/31/2007 Page TRM / B 3.3-10 01/07/2011 Page TRM / B 3.3-11 01/21/2014 Pages TRM / B 3.3-12 and TRM / B 3.3-13 01/07/2011 Page TRM / B 3.3-14 06/25/2002 Page TRM / B 3.3-14a 10/31/2007 Page TRM / B 3.3-14b 06/14/2002 Pages TRM / B 3.3-15 through TRM / B 3.3-17 10/22/2003 Pages TRM / B 3.3-18 and TRM / B 3.3-19 03/27/2007 Pages TRM / B 3.3-19a and TRM / B 3.3-19b 03/27/2007 Page TRM / B 3.3-19c 04/17/2009 Pages TRM / B 3.3-19d and TRM / B 3.3-19e 03/27/2007 Page TRM / B 3.3-20 02/16/2012 Page TRM / B 3.3-21 08/03/2010 Page TRM / B 3.3-22 10/22/2003 Page TRM / B 3.3-23 05/16/2003 Pages TRM / B 3.3-24 and TRM / B 3.3-25 04/07/2009 TRM / LOES-6 EFFECTIVE DATE 01/21/2014 SUSQUEHANNA - UNIT SUSQUEHANNA -
UNIT 2 2 TRM / LOES-6 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 82 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date B 3.4 REACTOR COOLANT SYSTEM BASES Page TRM / B 3.4-1 08/31/1998 Pages TRM / B 3.4-2 and TRM / B3.4-3 04/01/2009 Pages TRM / B 3.4-4 and TRM / B 3.4-4a 10/31/2007 Page TRM / B 3.4-5 10/15/1999 Page B 3.4-6 08/31/1998 Page TRM / B 3.4-7 04/25/2013 B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 08/31/1998 Pages TRM / B 3.5-3 and TRM / B 3.5-3a 10/31/2007 Page B 3.5-4 08/31/1998 Page TRM / B 3.5-5 10/31/2007 B 3.6 CONTAINMENT BASES Page TRM / B 3.6-1 07/26/2001 Page TRM / B 3.6-2 02/01/1999 Page B 3.6-3 08/31/1998 Page TRM / B 3.6-4 03/29/2007 Page TRM / B 3.6-5 04/04/2007 Page TRM / B 3.6-6 12/03/2004 Pages TRM / B 3.6-7 through TRM / B 3.6-11 12/31/2002 B 3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 08/31/1998 Page TRM / B 3.7-3 06/10/2010 Page TRM / B 3.7-3a 12/27/2007 Page TRM / B 3.7-4 03/31/2006 Page TRM / B 3.7-5 08/02/1999 Pages TRM / B 3.7-6 and TRM / B 3.7-6a 03/31/2006 Pages TRM / B 3.7-7 and TRM / B 3.7-7a 08/02/1999 Page TRM / B 3.7-8 08/02/1999 Page TRM / B 3.7-9 03/31/2006 Page TRM / B 3.7-10 08/02/1999 Pages TRM / B 3.7-10a through TRM / B 3.7-11a 03/31/2006 Pages TRM / B 3.7-12 and TRM / B 3.7-13 08/02/1999 Pages TRM / B 3.7-14 through TRM / B 3.7-14b 09/25/2012 Pages TRM / B 3.7-15 and TRM / B 3.7-16 02/01/1999 Pages B 3.7-17 through B 3.7-20 08/31/1998 Page TRM / B 3.7-21 05/29/2013 Pages TRM / B 3.7-21 a through TRM / B 3.7-21d 05/24/2012 Pages TRM / B 3.7-21e through TRM / B 3.7-21g 05/29/2013 Pages TRM / B 3.7-22 and TRM / B 3.7-23 01/30/2008 SUSQUEHANNA - UNIT 2 TRM / LOES-7 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 82 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / B 3.7-24 10/05/2006 Page TRM / B 3.7-25 01/21/2014 Pages TRM / B 3.7-26 through TRM / B 3.7-29 10/05/2006 Page TRM / B 3.7-30 06/07/2007 Page TRM / B 3.7-30a 10/05/2006 Page TRM / B 3.7-30b 01/21/2014 Page TRM / B 3.7-31 11/30/2011 Page TRM / B 3.7-32 03/09/2001 Page TRM / B 3.7-33 04/15/2003 Page TRM / B 3.7-34 12/03/2004 Page TRM / B 3.7-35 07/05/2000 Pages TRM / B 3.7-36 and TRM / B 3.7-37 04/01/2009 Page TRM / B 3.7-38 09/25/2009 Page TRM / B 3.7-39 04/01/2009 Page TRM / B 3.7-40 04/08/2010 B 3.8 ELECTRICAL POWER BASES Page TRM / B 3.8-1 04/02/2002 Pages TRM / B 3.8-2 and TRM / B 3.8-2 01/28/2005 Page TRM / B 3.8-2a 03/01/2010 Pages TRM / B 3.8-3 and TRM / B 3.8-3a 04/02/2002 Page TRM / B 3.8-4 04/02/2002 Page TRM / B 3.8-4a 08/10/2004 Page TRM / B 3.8-5 08/31/1998 Pages TRM / B 3.8-6 through TRM / B 3.8-15 04/02/2002 Page TRM / B 3.8-16 11/07/2013 Page TRM / B 3.8-17 11/30/2011 Page TRM / B 3.8-17a 06/11/2012 Page TRM / B 3.8-17b 11/30/2011 Pages TRM / B 3.8-18 through TRM / B 3.8-20 05/29/2013 Pages TRM / B 3.8-21 and TRM / B 3.8-22 05/28/2009 Page TRM / B 3.8-23 05/29/2013 Page TRM / B 3.8-24 05/28/2009 B.3.9 REFUELING OPERATIONS BASES Pages B 3.9-1 and B 3.9-2 08/31/1998 Pages B 3.9-3 through B 3.9-7 10/23/1998 B 3.10 MISCELLANEOUS BASES Page B 3.10-1 08/31/1998 Pages TRM / B 3.10-2 and TRM / B 3.10-3 03/27/2007 Pages TRM / B 3.10-4 and TRM / B 3.10-5 08/23/1999 SUSQUEHANNA - UNIT 2 TRM / LOES-8 EFFECTIVE DATE 01/21/2014
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 82 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 08/31/1998 Page TRM / B 3.11-10 02/01/1999 Pages TRM / B 3.11-11 and TRM / B 3.11-11a 04/07/2000 Pages TRM / B 3.11-12 and TRM / B 3.11-13 02/01/1999 Page TRM / B 3.11-14 12/03/2004 Page TRM / B 3.11-15 02/01/1999 Pages B 3.11-16 through B 3.11-19 08/31/1998 Pages TRM / B 3.11-20 and TRM / B 3.11-20a 04/02/2002 Page TRM / B 3.11-21 05/13/2005 Pages TRM / B 3.11-22 and TRM / B 3.11-23 11/14/2006 Pages TRM / B 3.11-23a and TRM / B 3.11-23b 06/18/2013 Pages TRM / B 3.11-24 and TRM / B 3.11-25 01/21/2004 Pages B 3.11-26 through B 3.11-27 08/31/1998 Pages TRM / B 3.11-28 and TRM / B 3.11-29 11/30/2005 Pages TRM / B 3.11-30 and TRM / B 3.11-31 05/29/2013 Page TRM / B 3.11-32 08/31/1998 Page TRM / B 3.11-33 06/30/2010 Pages TRM / B 3.11-34 and TRM / B 3.11-35 08/31/1998 Page TRM / B 3.11-36 02/12/1999 B.3.12 LOADS CONTROL PROGRAM BASES Page TRM / B 3.12-1 09/19/2007 Page TRM / B 3.12-2 11/29/2010 Page TRM / B 3.12-3 02/05/1999 TRM2 text LOES.doc 1/22/2014 TRM I LOES-9 EFFECTIVE DATE 01/21/2014 SUSQUEHANNA-- UNIT SUSQUEHANNA UNIT 22 TRM / LOES-9 EFFECTIVE DATE 01/21/2014
Instrument Trip Setpoint Program PPL Rev. 11 2.2 2.0 PLANT PROGRAMS AND SETPOINTS 2.2 Instrument Trip Setpoint Table The Instrument Trip Setpoint Limits in Table 2.2-1 are the Trip Setpoint value limits that were contained in the Instrumentation Setpoint tables for protection systems and other functions important to safety that were included in the scope of the original Standard Technical Specifications. Actual instrument setpoints are established utilizing the Allowable Values specified in the Technical Specifications and Technical Requirements. Allowable Values are established in the Reference LCOs and TROs identified in this Table. TRO references are enclosed in square brackets.
Instrumentation process setpoints for the listed subsystems and trip functions are set consistent with the Trip Setpoint Limit Column of Table 2.2-1. Actual setpoints are established in accordance with engineering procedures.
Alarm setpoints and other non-protection system trip settings as may be found in the Technical Specifications or in the Technical Requirements are not included in this table.
Reference:
MFP-QA-1220, Engineering Change Process Handbook SUSQUEHANNA - UNIT 2 TRM / 2.0-5 EFFECTIVE DATE 01/21/2014
Instrument Trip Setpoint Program PPL Rev. 11 2.2 TABLE 2.2-1 (Page 1 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO [TRO] TRIP FUNCTION TRIP SETPOINT 2.2.1 Reactor Protection 2.2.1.1 3.3.1.1 Intermediate Range Monitor, Neutron Flux - < 120/125 divisions of full scale High 2.2.1.2 3.3.1.1 Average Power Range Monitor, Neutron Flux - _18% of RATED THERMAL POWER High (Setdown) 2.2.1.3 3.3.1.1 Average Power Range Monitor, Simulated 0.55 W + 58.7%
Thermal Power - High Two Loop Operation 2.2.1.4 3.3.1.1 Average Power Range Monitor, Simulated 0.55 (W - AW) + 5 8 . 7 %101 Thermal Power - High Single Loop Operation 2.2.1.5 3.3.1.1 Average Power Range Monitor, Simulated < 113.5% of RATED THERMAL Thermal Power - High Flow Clamp POWER 2.2.1.6 3.3.1.1 Average Power Range Monitor, Neutron Flux - < 118% of RATED THERMAL High POWER 2.2.1.7 3.3.1.1 Reactor Vessel Steam Dome Pressure - High < 1087 psig 2.2.1.8 3.3.1.1 Reactor Vessel Water Level - Low, Level 3 >_ 13.0 inches(a) 2.2.1.9 3.3.1.1 Main Steam Isolation Valve - Closure < 10% closed 2.2.1.10 This Section Not Used 2.2.1.11 3.3.1.1 Drywell Pressure- High _ 1.72 psig 2.2.1.12 3.3.1.1 Scram Discharge Volume Water Level - High - <65 gallons Level Transmitter 2.2.1.13 3.3.1.1 Scram Discharge Volume Water Level - High -
- 61 gallons Float Switch 2.2.1.14 3.3.1.1 Turbine Stop Valve - Closure *5.5% closed 2.2.1.15 3.3.1.1 Turbine Control Valve Fast Closure, Trip Oil _>500 psig Pressure - Low (continued)
(a) See Figure 2.2-1.
(b) For single loop operation, the value of AW = 8.7.
SUSQUEHANNA - UNIT 2 TRM / 2.0-6 EFFECTIVE DATE 04/15/2009
Instrument Trip Setpoint Program PPL Rev. 11 2.2 TABLE 2.2-1 (Page 2 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO [TRO] TRIP FUNCTION TRIP SETPOINT 2.2.1.16 OPRM Instrumentation 2.2.1.16.1 3.3.1.1 Sp PBA Amplitude Trip See COLR - TRO 3.2 2.2.1.16.2 3.3.1.1 Np PBA Successive Confirmation Count Trip See COLR - TRO 3.2 2.2.1.16.3 [3.3.9] TOL (-) Period Tolerance 0.10 sec 2.2.1.16.4 [3.3.9] fc Conditioning Filter Cutoff Frequency 1.50 Hz 2.2.1.16.5 [3.3.9] Tmin Oscillation Period Lower Time Limit 1.00 sec 2.2.1.16.6 [3.3.9] Tmax Oscillation Period Upper Time Limit 3.50 sec 2.2.1.16.7 [3.3.9] LPRMmin Minimum LRPMs/Cell Required for 2 Cell Operability 2.2.1.16.8 [3.3.9] S1 Peak Threshold Setpoint/ABA &GRBA 1.20 2.2.1.16.9 [3.3.9] S2 Valley Threshold Setpoint/ABA & GRBA 0.85 2.2.1.16.10 [3.3.9] Smax Amplitude Trip Setpoint/ABA 1.50 2.2.1.16.11 [3.3.9] DR3 Growth Rate Factor Setpoint/GRBA 1.60 2.2.2 Isolation Actuation Instrumentation 2.2.2.1 Primary Containment Isolation 2.2.2.1.1 3.3.6.1 Reactor Vessel Water Level Low, Level 3 > 13.0 inches(a) 2.2.2.1.2 3.3.6.1 Reactor Vessel Water Level Low Low, Level 2 _-38.0 inches(a) 2.2.2.1.3 3.3.6.1 Reactor Vessel Water Level Low Low Low, 2!-129 inches(a)
Level 1 2.2.2.1.4 3.3.6.1 Drywell Pressure - High _ 1.72 psig 2.2.2.1.5 3.3.6.1 SGTS Exhaust Radiation - High < 23.0 mR/hr 2.2.2.1.6 [3.3.6] Main Steam Line Radiation - High High _<15 x full power background without hydrogen injection (continued)
(a)See Figure 2.2-1.
SUSQUEHANNA - UNIT 2 TRM / 2.0-7 EFFECTIVE DATE 05/15/2008
Instrument Trip Setpoint Program PPL Rev. 11 2.2 TABLE 2.2-1 (Page 3 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.2.2 Secondary Containment Isolation 2.2.2.2.1 3.3.6.2 Reactor Vessel Water Level - Low Low, >-38.0 inches(a)
Level 2 2.2.2.2.2 3.3.6.2 Drywell Pressure - High < 1.72 psig 2.2.2.2.3 3.3.6.2 Refuel Floor High Exhaust Duct Radiation - < 18 mR/hr High 2.2.2.2.4 3.3.6.2 Railroad Access Shaft Exhaust Duct < 5 mR/hr Radiation - High 2.2.2.2.5 3.3.6.2 Refuel Floor Wall Exhaust Duct Radiation - < 21 mR/hr High 2.2.2.3 Main Steam Line Isolation 2.2.2.3.1 3.3.6.1 Reactor Vessel Water Level - Low Low Low, _>-129 inches(a)
Level I 2.2.2.3.2 3.3.6.1 Main Steam Line Pressure - Low > 861 psig 2.2.2.3.3 3.3.6.1 Main Steam Line Flow - High < 173 psid 2.2.2.3.4 3.3.6.1 Condenser Vacuum - Low _ 9.0 inches Hg vacuum 2.2.2.3.5 3.3.6.1 Reactor Building Main Steam Line Tunnel <177°F Temperature - High 2.2.2.3.6 This Section Not Used 2.2.2.3.7 This section is not used.
2.2.2.3.8 [3.3.6] Turbine Building Main Steam Tunnel <197°F Temperature - High 2.2.2.4 Reactor Water Cleanup System Isolation 2.2.2.4.1 3.3.6.1 Reactor Vessel Water Level - Low Low, >:-38 inches(a)
Level 2 2.2.2.4.2 3.3.6.1 RWCU A Flow - High < 59 gpm 2.2.2.4.3 3.3.6.1 RWCU Flow- High <462 gpm 2.2.2.4.4 3.3.6.1 RWCU Penetration Area Temperature - High < 131°F 2.2.2.4.5 This section is not used.
2.2.2.4.6 3.3.6.1 RWCU Pump Area Temperature - High < 1471F 2.2.2.4.7 This section is not used.
2.2.2.4.8 3.3.6.1 RWCU Heat Exchanger Area Temperature - < 147 0F High 2.2.2.4.9 This section is not used.
(continued)
(a)See Figure 2.2-1.
SUSQUEHANNA - UNIT 2 TRM / 2.0-8 EFFECTIVE DATE 01/07/2011
Instrument Trip Setpoint Program PPL Rev. 11 2.2 TABLE 2.2-1 (Page 4 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.2.5 Reactor Core Isolation Cooling System Isolation 2.2.2.5.1 3.3.6.1 RCIC Steam Line A Pressure - High < 138 inches H20 2.2.2.5.2 3.3.6.1 RCIC Steam Supply Line Pressure - Low > 60 psig 2.2.2.5.3 3.3.6.1 RCIC Turbine Exhaust Diaphragm Pressure < 10.0 psig
- High 2.2.2.5.4 3.3.6.1 RCIC Equipment Room Temperature - High < 1671F 2.2.2.5.5 3.3.6.1 RCIC Pipe Routing Area Temperature - High < 1671F 2.2.2.5.6 3.3.6.1 RCIC Emergency Area Cooler Temperature - < 167OF High 2.2.2.5.7 3.3.6.1 Drywell Pressure - High < 1.72 psig 2.2.2.5.8 This section is not used.
2.2.2.5.9 This section is not used.
2.2.2.6 High Pressure Coolant Injection System Isolation 2.2.2.6.1 3.3.6.1 HPCI Steam Line A Pressure - High < 370 inches H20 2.2.2.6.2 3.3.6.1 HPCI Steam Supply Line Pressure - Low > 104 psig 2.2.2.6.3 3.3.6.1 HPCI Turbine Exhaust Diaphragm Pressure - < 10 psig High 2.2.2.6.4 3.3.6.1 HPCI Equipment Room Temperature - High <1670 F 2.2.2.6.5 3.3.6.1 HPCI Emergency Area Cooler Temperature - <167°F High 2.2.2.6.6 3.3.6.1 HPCI Pipe Routing Area Temperature - High <1670 F 2.2.2.6.7 3.3.6.1 Drywell Pressure - High _!1.72 psig 2.2.2.6.8 This section is not used.
2.2.2.6.9 This section is not used.
2.2.2.7 Shutdown Cooling/System Isolation 2.2.2.7.1 3.3.6.1 Reactor Vessel Water Level - Low, Level 3 > 13.0 inches(a) 2.2.2.7.2 3.3.6.1 Reactor Vessel Steam Dome Pressure - High < 98 psig 2.2.2.7.3 [3.3.6] RHR Flow - High < 25,000 gpm 2.2.3 ECCS Actuation 2.2.3.1 Core Spray System 2.2.3.1.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, >-129 inches(a)
Level 1 2.2.3.1.2 3.3.5.1 Drywell Pressure - High _<1.72 psig 2.2.3.1.3 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low >413, _ 427 psig injection permissive (continued)
(a)See Figure 2.2-1.
SUSQUEHANNA - UNIT 2 TRM / 2.0-9 EFFECTIVE DATE 01/07/2011
Instrument Trip Setpoint Program PPL Rev. 11 2.2 TABLE 2.2-1 (Page 5 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.3.2 LPCI Mode of RHR System 2.2.3.2.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, _>-129 inches(a)
Level 1 2.2.3.2.2 3.3.5.1 Drywell Pressure - High < 1.72 psig 2.2.3.2.3 3.3.5.1 Reactor Vessel Steam Dome Pressure - >413, < 427 psig Low, injection permissive 2.2.3.2.4 3.3.5.1 Reactor Vessel Steam Dome Pressure - > 236 psig, decreasing Low, Recirculation Discharge Valve permissive 2.2.3.3 HPCI System 2.2.3.3.1 3.3.5.1 Reactor Vessel Water Level - Low Low, >-38 inches(a)
Level 2 2.2.3.3.2 3.3.5.1 Drywell Pressure - High _<1.72 psig 2.2.3.3.3 3.3.5.1 Condensate Storage Tank Level - Low > 40.5 inches above tank bottom 2.2.3.3.4 3.3.5.1 Reactor Vessel Water Level - High, Level 8 < 54 inches 2.2.3.4 Automatic Depressurization System (ADS) 2.2.3.4.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, >-129 inches Level 1 2.2.3.4.2 3.3.5.1 Drywell Pressure - High < 1.72 psig 2.2.3.4.3 3.3.5.1 ADS Timer *102 seconds 2.2.3.4.4 3.3.5.1 Core Spray Pump Discharge Pressure - High _>135, < 155 psig 2.2.3.4.5 3.3.5.1 Low Pressure Coolant Injection Pump _>121, < 129 psig Discharge Pressure - High 2.2.3.4.6 3.3.5.1 Reactor Vessel Water Level - Low, Level 3 > 13 inches Confirmatory 2.2.3.4.7 3.3.5.1 ADS Drywell Pressure Bypass Timer < 420 seconds 2.2.3.5 Loss of Power - ECCS Actuation 2.2.3.5.1 4.16kv ESS Bus Undervoltage (Loss of Voltage < 20%)
2.2.3.5.1.1 3.3.8.1 Bus Undervoltage > 823.2, : 856.8 Volts 2.2.3.5.1.2 3.3.8.1 Time delay > 0.4, < 0.6 seconds (continued)
(a)See Figure 2.2-1.
SUSQUEHANNA - UNIT 2 TRM / 2. 0-10 EFFECTIVE DATE 02/02/2010
Instrument Trip Setpoint Program PPL Rev. 11 2.2 TABLE 2.2-1 (Page 6 of 8) I .
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.3.5.2 4.16kV ESS Bus Undervoltage (Degraded Voltage < 65%)
2.2.3.5.2.1 3.3.8.1 Bus Undervoltage > 2641. 1, 2748.9 Volts 2.2.3.5.2.2 3.3.8.1 Time delay _>
2.7, !<3.3 seconds 2.2.3.5.3 4.16kV ESS Bus Undervoltage (Degraded Voltage, < 93%)
2.2.3.5.3.1 3.3.8.1 Bus Undervoltage > 3829.3, <3906.7 Volts 2.2.3.5.3.2 3.3.8.1 Time Delay (Non-LOCA) > 4 minute, 30 seconds
< 5 minute, 30 seconds 2.2.3.5.3.4 3.3.8.1 Time Delay (LOCA) > 9, < 11 seconds 2.2.3.5.4 480V ESS Bus 0B565 Undervoltage (Degraded Voltage, < 65%)
2.2.3.5.4.1 [3.8.5] 480V Basis >308.9, <315.1 Volts 2.2.3.5.4.2 [3.8.5] Time Delay > 4.5, < 5.5 seconds 2.2.3.5.5 480V ESS Bus 0B565 Undervoltage (Degraded Voltage, < 92%)
2.2.3.5.5.1 [3.8.5] 480V Basis > 437.6, < 446.4 Volts 2.2.3.5.5.2 [3.8.5] Time Delay > 9, < 11 seconds 2.2.4 ATWS Alternate Rod Injection and Recirculation Pump Trip 2.2.4.1 3.3.4.243.1.11 Reactor Vessel, Water Level - Low Low, >-38 inches(a)
Level 2 2.2.4.1 3.3.4.2J3.1.1] Reactor Vessel Steam Do'me Pressure - High < 1135 psig 2.2.5 End of Cycle Recirculation Pump Trip 2.2.5.1 3.3.4.1 Turbine Stop Valve-Closure _<5.5% closed 2.2.5.2 3.3.4.1 Turbine Control Valve - Fast Closure 2! 500 psig 2.2.6 Reactor Core Isolation Cooling System Actuation 2.2.6.1 3.3.5.2 Reactor Vessel Water Level - Low Low, _>-38 inches(a)
Level 2 2.2.6.2 3.3.5.2 Reactor Vessel Water Level - High, Level 8 <54 inches(a) 2.2.6.3 3.3.5.2 Condensate Storage Tank Level - Low > 36.0 inches above tank bottom (continued)
(8)See Figure 2.2-1.
SUSQUEHANNA - UNIT 2 TRM / 2.0-11 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Program PPL Rev. 11 2.2 TABLE 2.2-1 (Page 7 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.7 Control Rod Block 2.2.7.1 Rod Block Monitor 2.2.7.1.1 3.3.2 Low Power Range - Upscale See COLR - TRO 3.2 3.3.2 Intermediate Power Range - Upscale See COLR - TRO 3.2 3.3.2 High Power Range - Upscale See COLR - TRO 3.2 2.2.7.1.2 3.3.2 Low Power Range Setpoint See COLR - TRO 3.2 3.3.2 Intermediate Power Range Setpoint See COLR - TRO 3.2 3.3.2 High Power Range Setpoint See COLR - TRO 3.2 2.2.7.2 APRM 2.2.7.2.1 [3.1.3] Simulated Thermal Power-High - Two Loop 0.55 W + 54.2%
Operation 2.2.7.2.2 [3.1.3] Simulated Thermal Power-High - Single 0.55 (W - AW) + 54.2%(cl Loop Operation 2.2.7.2.3 [3.1.3] Simulated Thermal Power-High Clamp _ 108% of RATED THERMAL POWER 2.2.7.2.4 [3.1.3] Downscale >5% of RATED THERMAL POWER 2.2.7.2.5 [3.1.3] Neutron Flux - High (Setdown) _<12% of RATED THERMAL POWER 2.2.7.3 Source Range Monitors 2.2.7.3.1 [3.1.3] Upscale _ 2E5 cps 2.2.7.3.2 [3.1.3] Downscale _3.0 cps(b) 2.2.7.4 Intermediate Range Monitors 2.2.7.4.1 [3.1.3] Upscale < 108/125 divisions of full scale 2.2.7.4.2 [3.1.3] Downscale >5/125 divisions of full scale 2.2.7.5 Scram Discharge Volume 2.2.7.5.1 [3.1.3] Water Level- High _35.9 gallons 2.2.7.6 Reactor Coolant System Recirculation Flow 2.2.7.6.1 [3.1.3] Upscale 114%
(continued)
(b)With a signal-to-noise ratio _>2, or within the limits of Figure 2.2-2.
(c)For single loop operation, the valve of AW = 8.7.
SUSQUEHANNA - UNIT 2 TRM / 2.0-12 EFFECTIVE DATE 04/15/2009
Instrument Trip Setpoint Program PPL Rev. 11 2.2 TABLE 2.2-1 (Page 8 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.8 CREOASS 2.2.8.1 3.3.7.1 Main Control Room Outside Air Intake <5 mR/hr Radiation Monitor 2.2.8.1.1 3.3.7.1 Reactor Vessel Water Level - Low Low, -38.0 inches(a)
Level 2 2.2.8.1.2 3.3.7.1 Drywell Pressure - High < 1.72 psig 2.2.8.1.3 3.3.7.1 Refuel Floor High Exhaust Duct Radiation - < 18 mR/hr High 2.2.8.1.4 3.3.7.1 Railroad Access Shaft Exhaust Duct <5 mR/hr Radiation - High 2.2.8.1.5 3.3.7.1 Refuel Floor Wall Exhaust Duct Radiation - *21 mR/hr High 2.2.9 Feedwater/Main Turbine Trip System Actuation 2.2.9.1 3.3.2.2 Reactor Vessel Level - High *54.0 inches(a) 2.2.10 MVP Isolation 2.2.10.1 [3.3.11] Main Steam Line Radiation - High High _ 15 x full power background without hydrogen injection (a)See Figure 2.2-1 SUSQUEHANNA - UNIT 2 TRM / 2.0-13 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Table PPL Rev. 11 2.2 FIGURE 2. 2-1 REACTOR VESSEL WATER LEVEL SUSQUEHANNA - UNIT 2 TRMV / 2.0-14 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Table PPL Rev. 11 2.2 Instrument Trip Setpoint Table 2.2 3
2.8 2.6 2.4 2.2 2
LO_ 1.8 I.-
1.6 1.4 - -A Acceptable I-z Z) 1.2 0
C-) 1 W
U) 0.8 0.6 Not Acceptable 0.4 0.2 0
2 6 10 14 18 22 26 30 Signal-to-Noise Ratio Figure 2.2-2 Minimum SRM Trip Setpoint Versus Signal-to-Noise Ratio SUSQUEHANNA - UNIT 2 TRM / 2.0-15 EFFECTIVE DATE 11/15/2005
Radiation Monitoring Instrumentation PPL Rev. 1 B 3.3.1 B 3.3.1 Radiation Monitoring Instrumentation BASES TRO The OPERABILITY of the radiation monitoring instrumentation ensures that: (1) the radiation levels are continually measured in the areas served by the individual channels; (2) the alarm is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of NUREG-0737, "Clarification of TMI Action Plan Requirements," November 1980. (Reference 1 and 2)
Table 3.3.1-1 identifies two criticality monitoring functions-new fuel storage vault and spent fuel storage pool. Both functions have two redundant monitors. Each instrument is positioned and setpoint established to detect a criticality event for the function monitored.
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components.
TRS The TRSs are defined to be performed at the specified Frequency to ensure that the Radiation Monitoring Function is maintained OPERABLE.
Performance of the CHANNEL CHECK ensures that a gross failure of the instrument has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel against a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrument continues to operate properly between each CHANNEL CALIBRATION.
Agreement criteria, which are developed by the plant staff based on an investigation of a combination of the channel instrument uncertainties, may be used to support this parameter comparison and include indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit and does not necessarily indicate the channel is inoperable.
REFERENCES 1. FSAR Section 12.3.4
- 2. NUREG-0737, "Clarification of TMI Action Plan Requirements,"
November 1980 SUSQUEHANNA - UNIT 2 TRM/B 3.3-1 EFFECTIVE DATE 01/21/2014
TRM Isolation Actuation Instrumentation PPL Rev. 5 B 3.3.6 B 3.3.6 TRM Isolation Actuation Instrumentation BASES TRO The TRM Actuation instrumentation automatically initiates closure of appropriate primary containment isolation valves (PCIVs). The function of the PCIVs, in combination with other accident mitigation systems, is to limit fission product release during and following postulated Design Basis Accidents (DBAs)
(Reference 1). The TRM Isolation Actuation Instrument has been relocated from the Technical Specifications because the identified Function is not credited in the plant design basis to mitigate any plant event, but does provide a diverse means to initiate an Isolation Actuation.
The isolation instrumentation includes the sensors, relays, and instruments that are necessary to cause initiation of primary containment and Reactor Coolant Pressure Boundary (RCPB) isolation. When the setpoint is reached, the sensor actuates, which then outputs an isolation signal to the isolation logic. Monitoring a wide range of independent parameters provides functional diversity. The input parameters to the isolation logic are:
(a) Main steam line radiation, (b) Turbine Building Main Steam Line Tunnel Temperature - High, and (c) RHR Flow - High.
The valves associated with these trip channels are identified in Table B 3.3.6-1.
Each of these valves is also associated with other trip channels as identified in LCO Bases B 3.6.1.3.
The trips occur after a one second delay. See Tech Spec Basis B 3.3.6-1.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.3-10 EFFECTIVE DATE 01/07/2011
TRM Isolation Actuation Instrumentation PPL Rev. 5 B 3.3.6 B 3.3.6 TRM Isolation Actuation Instrumentation BASES (continued)
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components. The ACTIONS are modified by two Notes. Note 1 allows penetration flow path(s) to be unisolated intermittently under administrative controls. These controls consist of stationing a dedicated operator at the controls of the valve, who is in continuous communication with the control room. In this way, the penetration can be rapidly isolated when a need for primary containment isolation is indicated. Note 2 is provided to modify the ACTIONS for separate Condition entry, consistent with similar Note in the TS 3.3.6.1 Actions.
Condition C applies ifthe channel is not restored to OPERABLE status or placed in trip, or isolation capability is not restored, within the allowed Completion Time. If inoperable channels should not be placed in trip (e.g., might result in a undesirable transient) Action C may be intentionally entered as a result of not meeting Required Action A.1 in its required Completion Time. Required Action C.1 requires appropriate compensatory measures be in place within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Examples of appropriate compensatory measures may consist of verifying that diverse isolation functions remain OPERABLE. Furthermore, isolating the penetration (e.g., as may be required by TS Actions for an inoperability affecting both the TRM Function and a required TS Function) also provides adequate compensatory actions since isolating the affected penetration flow path(s) accomplishes the safety function of the inoperable channels. If it is not desired to isolate the affected penetration flow path(s) (e.g., as in the case where isolating the penetration flow path(s) could result in a reactor scram or disabling RHR-SDC), alternate compensatory measures should be pursued. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time is acceptable due to the fact that these Functions are not assumed in any accident or transient analysis in the FSAR.
TRS The TRSs are defined to be performed at the specified Frequency to ensure that the TRM Isolation Actuation Instrumentation Functions are maintained OPERABLE. TRM Isolation Actuation Instrumentation Surveillances are performed consistent with the Bases for LCO 3.3.6.1 "Isolation Activation Instrumentation."
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.3-11 EFFECTIVE DATE 02/21/2014
TRM Isolation Actuation Instrumentation PPL Rev. 5 B 3.3.6 B 3.3.6 TRM Isolation Actuation Instrumentation BASES (continued)
TRS 3.3.6.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel. The system functional testing performed on PCIVs in LCO 3.6.1.3 overlaps this surveillance to provide complete testing of the assumed safety function. The 24 month Frequency is based on the need to perform portions of this surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient ifthe surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the surveillance when performed at the 24 month Frequency.
TRS 3.3.6.6 The response time testing of Function 2.a is per FSAR Table 7.3-29.
REFERENCES 1. FSAR Section 7.3.1
- 2. NRC Inspection and Enforcement Manual, Part 9900: Technical Guidance, Standard Technical Specification Section 1.0 Definitions, Issue dated 12/8/96.
SUSQUEHANNA - UNIT 2 TRM / B 3.3-12 EFFECTIVE DATE 01/07/2011
TRM Isolation Actuation Instrumentation PPL Rev. 5 B 3.3.6 Table B 3.3.6-1 Primary Containment Isolation Valves (Page 1 of 1)
Plant systems Valve Number Valve Description Isolation Signal Function No.
(Table 3.3.6-1)
Nuclear Boiler HV-241 F022A MSIV l.a HV-241F022B MSIV l.a HV-241F022C MSIV l.a HV-241F022D MSIV l.a HV-241 F028A MSIV 1.a HV-241F028B MSIV l.a HV-241F028C MSIV l.a HV-241F028D MSIV 1.a HV-241FO16 MSL Drain Isolation Valve l.a HV-241F019 MSL Drain Isolation Valve l.a Reactor HV-243F019 Reactor Coolant Sample Valve 2.a Recirculation HV-243F020 Reactor Coolant Sample Valve 2.a RHR HV-251 F022 RHR - Reactor Vessel Head Spray Valve 3.a HV-251 F023 RHR - Reactor Vessel Head Spray Valve 3.a, HV-251 F008 RHR - Shutdown Cooling Valve 3.a HV-251 F009 RHR - Shutdown Cooling Valve 3.a SUSQUEHANNA - UNIT 2 TRM / B 3.3-13 EFFECTIVE DATE 01/07/2011
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES TRO All snubbers are required to be OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on non-safety-related systems and then only iftheir failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
Snubbers are required to be OPERABLE whenever they are considered necessary to support equipment for the systems on which they are installed.
Technical Specification LCO 3.0.8 has been added to the Technical Specifications to allow snubbers to be inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ifthe inoperable snubber affects one subsystem or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if it affects multiple subsystems.
The generic NRC Safety Evaluation which approved the use of LCO 3.0.8 requires that certain conditions be met before LCO 3.0.8 can be entered. TRM 3.7.8 provides guidance on meeting these conditions.
"Type" of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity. For example, mechanical snubbers utilizing the same design features of the 2-kip, and 100-kip capacity manufactured by Company "A"are of the same type. The same design mechanical snubbers manufactured by company "B" for the purposes of this Technical Requirement would be of a different type, as would hydraulic snubbers from either manufacturer.
A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR part 50. The controlled list of plant snubbers is maintained in by the ISI Program. The addition or deletion of any snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.7-24 EFFECTIVE DATE 10/05/2006
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES TRO The following are examples of conditions that require a snubber to be (continued) declared inoperable:
- Snubber not attached to piping system or support plate,
- Snubber missing,
- Snubber locked in position,
- Snubber excessively bent.
The following are examples of conditions that require an evaluation to confirm whether or not the snubber is inoperable:
- Dent(s) in snubber case,
- Thread engagement not per design,
- Missing bolt(s) on support plate,
- Snubber slightly bent.
As stated in NRC's Safety Evaluation Condition 2, the LCO 3.0.8 requirement to assess and manage risk is met by licensee programs to comply with the requirements of paragraph (a)(4) of the Maintenance Rule, 10 CFR 50.65, to assess and manage risk resulting from maintenance activities. Since the 10 CFR 50.65(a) (4) guidance, the revised (May 2000) Section 11 of NUMARC 93-01, does not address seismic risk, licensees must qualitatively integrate the use of LCO 3.0.8 into their 10 CFR 50.65(a) (4) program to assess and manage risk.
As described in the Bases of LCO 3.0.8, "LCO 3.0.8 should be consid-ered with respect to other plant maintenance activities, and integrated into the existing Maintenance Rule process to the extent possible so that maintenance on any unaffected train or subsystem is properly controlled, and emergent issues are properly addressed. The risk assessment need not be quantified, but may be a qualitative awareness of the vulnerability of systems and components when one or more snubbers are not able to perform their associated support function."
The inservice inspection and testing program for snubbers will be performed in accordance with Subsection ISTD of the ASME OM Code and applicable addenda as required by 10 CFR Part 50.55a(b)(3)(v) except where specific written relief has been granted by the NRC.
(Reference 2)
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.7-25 EFFECTIVE DATE 01/21/2014
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES (continued)
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components and the implementa-tion of LCO 3.0.8. The NRC's 4/27/2005 Safety Evaluation lists the conditions that must be followed to adopt and utilize LCO 3.0.8.
The ACTIONS provide the guidance for the implementation of these conditions and therefore the implementation of LCO 3.0.8.
Conditions A and B Condition A applies when one or more snubbers are not capable of providing their associated support function(s) to a single subsystem of a multiple subsystem supported system or to a single subsystem supported system.
Condition B applies when one or more snubbers are not able to perform their associated support function(s) are associated with more than one subsystem of a multiple subsystem supported system.
The wording of these Conditions allow for confirmation of snubber inoperability. This allows for input from snubber knowledgeable parties to review the condition. The intent is to obtain this confirmation in an expeditious manner and not delay declaring a snubber or support system inoperable. If confirmation of snubber inoperability is delayed, the snubber should be considered inoperable and appropriate actions of this TRO applied.
Required Action A.1.1 or B.1.1 When a snubber is to be rendered incapable of performing its related support function (i.e., nonfunctional) for testing or maintenance or is discovered to not be functional, it must be determined whether any Technical Specification (TS) system(s) require the affected snubber(s) for system OPERABILITY, and whether the plant is in a MODE or specified condition in the Applicability that requires the supported TS system(s) to be OPERABLE.
- 1. If an analysis determines that the supported TS system(s) do not require the snubber(s) to be functional in order to support the OPERABILITY of the system(s), LCO 3.0.8 is not needed.
- 2. If the LCO(s) associated with any supported TS system(s) are not currently applicable (i.e., the plant is not in a MODE or other specified condition in the Applicability of the LCO), LCO 3.0.8 is not needed.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.7-26 EFFECTIVE DATE 10/05/2006
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES ACTIONS 3. If the supported TS system(s) are inoperable for reasons other (continued) than snubbers, LCO 3.0.8 cannot be used.
LCO 3.0.8 is an allowance, not a requirement. When a snubber is nonfunctional, any supported TS system(s) may be declared inoperable instead of using LCO 3.0.8.
The NRC Safety Evaluation only considered the loss of the ability of a snubber to respond to a seismic event. However, some snubbers have design functions other than response to a seismic event. The inability to perform these non-seismic design functions were not considered or justified. Therefore, when a snubber is to be rendered nonfunctional for testing or maintenance or is discovered to not be functional, the design function of the snubber must be determined in order to determine if LCO 3.0.8 may be used.
- 1. If the design function of the snubber is to react to only seismic loads, LCO 3.0.8 may be applied.
- 2. If the design function of the snubber includes both seismic loads and non-seismic loads (e.g., thrust loads, blowdown loads, waterhammer loads, steamhammer loads, LOCA loads, and pipe rupture loads), any TS systems supported by the nonfunctional snubber must be able to remain OPERABLE if subjected to the non-seismic loads with the snubber removed. If the supported TS system will remain OPERABLE when subjected to non-seismic loads, LCO 3.0.8 may be applied. Otherwise, LCO 3.0.8 may not be applied to TS systems supported by the nonfunctional snubber.
- 3. If the design function of the snubber includes only non-seismic loads (e.g., thrust loads, blowdown loads, waterhammer loads, steamhammer loads, LOCA loads, and pipe rupture loads),
LCO 3.0.8 cannot be applied to the TS systems supported by the nonfunctional snubber. However, if it can be confirmed that snubber is not needed for OPERABILITY of the TS system, LCO 3.0.8 is not needed.
Note: Snubbers located in the Diesel Generator Buildings only have seismic loads as their design function loads. Snubbers located else-where in the plant have both seismic and non-seismic loads as their design function loads.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.7-27 EFFECTIVE DATE 10/05/2006
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES ACTIONS Required Action A.1.2 or B.1.2 (continued)
This Required Action ensures that when LCO 3.0.8 is entered there are sufficient OPERABLE subsystems (not associated with the inoperable snubber) to provide makeup and heat removal in the event of a LOOP.
The NRC does not require any other accidents or events such as LOCA, DBA or transients to be accounted for. The subsystems that can be used to meet this condition are:
- a. At least one OPERABLE high pressure subsystem (e.g., HPCI or RCIC) and OPERABLE heat removal capability (e.g., suppression pool cooling), or
- b. At least one OPERABLE low pressure subsystem (e.g., LPCI or CS) and OPERABLE heat removal capability (e.g., suppression pool cooling or shutdown cooling).
The NRC's Safety Evaluation Condition 1.(d) is met by these required actions.
Required Action A.1.3 or B.1.3 The NRC's Safety Evaluation requires that subsystem(s) associated with inoperable snubber (s) must be capable of performing their required safety or support function when subjected to the postulated non-seismic design function loads.
NRC's Safety Evaluation also requires that every time LCO 3.0.8 is used for TS systems supported by nonfunctional snubbers whose design loads include non-seismic loads, licensees must be able to produce a record of the design function of the nonfunctional snubber (i.e., seismic vs. non-seismic). This record does not have to be created prior to or following use of LCO 3.0.8, but must be able to be created or produced if requested. For example, if a system engineer knows from previous experience that a particular snubber is only designed for seismic loads, it is not necessary to collect existing design documents or create design documents or calculations to demonstrate that fact prior to using LCO 3.0.8. However, if asked to demonstrate the design basis of the snubber, the licensee must be able to produce or create appropriate documentation to support that position.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.7-28 EFFECTIVE DATE 10/05/2006
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES ACTIONS Required Action A.1.4 or B.1.4 (continued)
Required Action A.1.4 or B.1.4 provides for the entry into LCO 3.0.8 provided the requirements for entry are verified.
Required Action A.1.5 or B.1.5 The completion time is consistent with the time used to evaluate the risk of having an inoperable snubber and not declaring the system LCO.
Condition E Snubbers are required to be OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Evaluating their service life and replacing them before the end of their service life ensures that the snubbers will remain OPERABLE.
TRS The TRSs are defined to be performed at the specified Frequency to ensure that the snubbers are maintained OPERABLE. Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the completion of their fabrication or at a subsequent date.
Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.
TRS 3.7.8.1 The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Generic Letter 90-09 provides a method for determining the next interval for the visual inspection of snubbers based upon the number of unacceptable snubbers found during the previous inspection, the total population or category size for each snubber type, and the previous inspection interval.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.7-29 EFFECTIVE DATE 10/05/2006
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES TRS TRS 3.7.8.1 (continued)
The visual inspection interval for a snubber population shall be determined based upon the previous inspections and the number of unacceptable snubbers found during that interval. The visual inspection interval snubbers shall be determined based upon the criteria provided in the ISI Program Plan.
Visual inspections shall verify that (1) the snubber has no visible indications of damage or impaired OPERABILITY, and (2) fasteners for the attachment of the snubber to the component, and to the snubber anchorage are functional.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined (continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.7-30 EFFECTIVE DATE 06/07/2007
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES TRS TRS 3.7.8.1 (continued)
OPERABLE per TRS 3.7.8.2. A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber. If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.
TRS 3.7.8.2 A representative sample of snubbers shall be tested for each type of snubber. The representative sample selected for the functional test sample plans shall be randomly selected from the snubbers of each type and reviewed before beginning the testing. The review shall ensure as far as practical that they are representative of the various configurations, operating environments, range of size, and capacity of snubbers of each type.
Functional Test Acceptance Criteria The snubber functional test shall verify that:
- 1. Activation (restraining action) is achieved within the specified range in both tension and compression;
- 2. Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range;
- 3. Where required, the force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel; and
- 4. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement.
Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.7-30a EFFECTIVE DATE 10/05/2006
Snubbers PPL Rev. 4 B 3.7.8 B 3.7.8 Snubbers BASES TRS TRS 3.7.8.3 (continued)
The maximum expected service life for various seals, springs, and other critical parts shall be determined and established based on engineering information and shall be extended or shortened based on monitored test results and failure history. Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be OPERABLE. The parts replacements shall be documented and the documentation shall be retained in accordance with FSAR 17.2.17.
The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statistical bases for future consideration of snubber service life.
TRS 3.7.8.5 The required inspection consists of the following elements:
- 1. Perform a visual inspection of all affected snubbers,
- 3. Verify freedom of motion of mechanical snubbers by evaluation of in-place snubber piston setting, or
- 4. Verify freedom of motion of mechanical snubbers by stroking the mechanical snubber through its full range of travel.
REFERENCES 1. Generic Letter 90-09
- 2. 10 CFR Part 50 SUSQUEHANNA - UNIT 2 TRM / B 3.7-30b EFFECTIVE DATE 01/21/2014