ML071200043
| ML071200043 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/20/2007 |
| From: | Susquehanna |
| To: | Gerlach R Document Control Desk, NRC/NRR/ADRO |
| References | |
| 028401, 2007-16181 | |
| Download: ML071200043 (74) | |
Text
/ Apr. 20, 2007 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2007-16181 USER INFORMATION:
Name:GERLACH*ROSE M EMPL#:028401 CA#:0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:
TO: GERLACH*ROSE M 04/20/2007 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
- RORS.
TENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.
TRM2 - TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 04/10/2007 ADD MANUAL TABLE OF CONTENTS DATE: 04/19/2007 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.2.1 REMOVE: REV:6 ADD: REV: 7 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT B3.6.3 REMOVE: REV:0
, D:
CATEGORY:
REV: 1 DOCUMENTS TYPE: TRM2 Aeoi ID: TEXT LOES
Apr. 20, 2007 Page 2 of 2 I
REMOVE: REV:33 ADD: REV: 34 ADD: REV: 35 REMOVE: REV:35 ADD: REV: 36 REMOVE: REV:36 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 MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents Issue Date: 04/19 /2007 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 36 04/19/2007
Title:
LIST OF EFFECT:IVE SECTIONS TEXT TOC 9 12/14/2006
Title:
TABLE OF CONTENTS TEXT 1.1 0 11/19/2002
Title:
USE AND APPLICATION DEFINITIONS TEXT 2.1 1 02/04/20,05\
/
Title:
PLANT PROGRAMS AND SETPOINTS PLANT-PROGRAMS TEXT 2. 2 6 *04/0t9120.O,7
Title:
PLANT PROGRAMS AND SETPOINTS/INSTRUMENT-TRIP SETPOINT TABLE TEXT 3.0 2-> 0.,-/29/2007
Title:
APPLICABILITY TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT 3.1.1 01" 11/19/2002
Title:
REACTIVITY CONTROL'SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT 3.1.2 0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1.3 3 04/09/2007
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT 3.2.1 7 04/19/2007
Title:
CORE OPERATING LIMITS CORE OPERATING LIMITS REPORT (COLR)
Report Date: 04/19/07 Page 11 of of 15 15 Report Date: 04/19/07
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.3.1 0 11/19/2002
Title:
INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 1 04/26/2006
Title:
INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 1 04/26/2006
Title:
INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 2 06/13/2006
Title:
INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0 11/19/2002
Title:
INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK TEXT 3.3.6 2 10/19/2005
Title:
INSTRUMENTATION TRM-ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 0 11/19/2002
Title:
INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 - 1 10/22/2003
Title:
INSTRUMENTATION TRM RPS INSTRUMENTATION TEXT 3.3.9 2 04/09/2007
Title:
INSTRUMENTATION LPRM UPSCALE ALARM INSTRUMENTATION TEXT 3.3.10 1 12/14/2004
Title:
INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1 10/22/2003
Title:
INSTRUMENTATION MVP ISOLATION INSTRUMENTATION TEXT 3.4.1 1 04/26/2006
Title:
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY Report Date: 04/19/07 Page 22 of of 15 15 Report Date: 04/19/07
SSES MANUAL
. Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.4.2 0 11/19/2002
Title:
REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY TEXT 3.4.3 0 11/19/2002
Title:
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM (RCS)
TEXT 3.4.4 1 12/14/2004
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 3.5.1 1 02/04/2005
Title:
ECCS AND RCIC ADS MANUAL INHIBIT TEXT 3.5.2 0 11/19/2002 -
Title:
ECCS AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0 11,/19/2002
Title:
ECCS AND RCIC LONG TERM NITROGEN SUPPLY T7 ADS TEXT 3.6.1 .0 11/19/2002
Title:
CONTAINMENT VENTING OR PURGING TEXT 3.6.2 0 11/19/2002
Title:
CONTAINMENT SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0 11/19/2002
Title:
CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION TEXT 3.6.4 0 11/19/2002
Title:
CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 0 11/19/2002 10
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN Page 3- of 15 Report Date: 04/19/07
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7.2 0 11/19/2002
Title:
PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL TEXT 3.7.3.1 1 04/26/2006
Title:
PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 2 04/26/2006
Title:
PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS TEXT 3.7.3.3 2 08/18/2005
Title:
PLANT SYSTEMS C02 SYSTEMS TEXT 3.7.3.4 1 04/26/2006
Title:
PLANT SYSTEMS HALON SYSTEMS TEXT 3.7.3.5
Title:
1 04/26/2006 PLANT SYSTEMS FIRE HOSE STATIONS 0
TEXT 3.7.3.6 1 04/26/2006
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 6 12/14/2006
Title:
PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION TEXT 3.7.4 1 04/26/2006
Title:
PLANT SYSTEMS SOLID RADWASTE SYSTEM TEXT 3.7.5.1 0 11/19/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT 3.7.5.2 0 11/19/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE Report Date: 04/19/07 4
Page A of of 15 15 Report Date: 04/19/07
SSES MANUJAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7.5.3 1 04/26/2006
Title:
PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 1 03/01/2005
Title:
PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 0 11/19/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT 3.7.8 5 10/12/2006
Title:
PLANT SYSTEMS SNUBBERS TEXT 3.7.9 1 08/28/2006
Title:
PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 1 12/14/2004
Title:
PLANT SYSTEMS SPENT- FUEL STORAGE POOLS (SFSPS)
TEXT 3.8.1 2 02/04/2005
Title:
ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT 3.8.2.1 1 -12/14/2004
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 TEXT 3.8.3 0 11/19/2002
Title:
ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT 3.8.4 1 02/04/2005
Title:
ELECTRICAL POWER 24 VDC ELECTRICAL SUBSYSTEM TEXT 3.8.5 0 11/19/2002
Title:
ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION Report Date: 04/19/07 Page ~
5 of of 15 15 Report Date: 04/19/07
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.8.6 0 11/19/2002
Title:
ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8.7 0 12/14/2006
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 1 "04/26/2006
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT 3.10.4 1 08/28/2006
Title:
MISCELLANEOUS LEADING EDGE FLOW METER (LEFM)
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 Report Date: 04/19/07 Page 6 Page6 of j.~
of 15 Report Date: 04/19/07
SSES MANUAL.
. Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.11.1.4 1 12/14/2004
Title:
RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.1.5 1 12/14/2004
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 3 11/14/2006
Title:
RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3.11.2.6 2 12/14/2004
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 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 Report Date: 04/19/07 Page 27 Page of of 15 15 Report Date: 04/19/07
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.12.1 0 11/19/2002
Title:
LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT 3.12.2 1 10/12/2006
Title:
LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0 11/19/2002
Title:
LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENTS TEXT B3.0 2 01/29/2007
Title:
APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.1.1 0 11/19/2002
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 0 11/19/2002
Title:
CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR)
TEXT B3.3.1 0 11/19/2002
Title:
INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 0 11/19/2002
Title:
INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3. .3 1 02/04/2005
Title:
INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION Report Date: 04/19/07 Page88 Page of of 2.~
15 Report Date: 04/19/07
SSES MANUAL
. Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.3.4 2 06/13/2006
Title:
INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT B3.3.5 1 06/13/2006
Title:
INSTRUMENTATION BASES THIS PAGE INTENTIONALLY LEFT BLANK TEXT B3.3.6 3 10/19/2005
Title:
INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION TEXT B3.3.7 0 11/19/2002
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 2 04/10/2007
Title:
INSTRUMENTATION BASES LPRM UPSCALE ALARM INSTRUMENTATION TEXT B3.3.10 0 11/19/2002
Title:
INSTRUMENTATION BASES REACTOR RECIRCULATION PUMP MG SET STOPS TEXT B3.3.11 .1 10/22/2003
Title:
INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3.4.1 0 11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY TEXT B3.4.2 0 11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES STRUCTURAL INTEGRITY TEXT B3.4.3 0 11/19/2002
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 Page 9 of 15 Report Date: 04/19/07
SSES MANUTAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.4.5 0 11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS TEXT B3.5.1 0 11/19/2002
Title:
ECCS AND RCIC BASES ADS MANUAL INHIBIT TEXT B3.5.2 0 11/19/2002
Title:
ECCS AND RCIC BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT B3.5.3 0 11/19/2002
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 1 04/26/2006
Title:
PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT B3.7.3.2 2 04/26/2006
Title:
PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS Page 10 of 15 Report Date: 04/19/07
SSES MANTIAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.3.3 0 11/19/2002
Title:
PLANT SYSTEMS BASES C02 SYSTEMS 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 I 01/12/2004 -
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 1 03/01/2005
Title:
PLANT SYSTEMS BASES ESSW PUMPHOUSE VENTILATION TEXT B3.7.7 0 11/19/2002 D
Title:
PLANT SYSTEMS MONITORING BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC INSTRUMENTATION RADIATION Page 11 of 15 Report Date: 04/19/07
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.8 2 10/12/2006
Title:
PLANT SYSTEMS BASES SNUBBERS TEXT B3.7.9 1 12/14/2004
Title:
PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1 12/14/2004
Title:
PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.8.1 1 02/04/2005
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 (DM) MAINTENANCE ACTIVITIES TEXT B3.8.4 0 11/19/2002
Title:
ELECTRICAL POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT B3.8.5 0 11/19/2002
Title:
ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B3.8.6 1 02/04/2005
Title:
ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 0 12/14/2006
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT B3.9 .1 0 11/19/2002
Title:
REFUELING OPERATIONS BASES DECAY TIME Report Date: 04/19/07 12 Page 12 of of 25.
15 Report Date: 04/19/07
SSES MANUTAL~
Manual Name: TRM2 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 B3.10.4 0 11/19/2002 _
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 TEXT B3.11.2.1 1 12/14/2004
Title:
RADIOACTIVE EFFLUENTS BASES DOSE RATE Report Date: 04/19/07 Page 1~.
13 of of 15 15 Report Date: 04/19/07
SSES MANUJAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.11.2.2 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES TEXT B3.11.2.3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATES FORM TEXT B3.11.2.4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.11.2.5 4 11/14/2006
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 2 01/06/2006
Title:
RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3.11.4.2 10 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 0 11/19/2002
Title:
LOADS CONTROL PROGRAM BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT B3.12.2 0 11/19/2002
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: 04/19/07 14 Page 14 of of 15 15 Report Date: 04/19/07
SSES MANUAL Manual Name: TRM2 O Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 4.1 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 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT 4.5 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS 0 . 09/27/2003 TEXT 4.6
Title:
ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM TEXT 4.7 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS TRAINING ~
Report Date: 04/19/07 Page 25.
15 of of j~
15 Report Date: 04/19/07
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 36 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date TOC TABLE OF CONTENTS 11/29/2006 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 04/12/1999 Pages TRM / 2.0-6 and TRM / 2.0-7 03/27/2007 Page TRM / 2.0-8 12/03/2004 Pages TRM / 2.0-9 through TRM / 2.0-11 11/15/2004 Page TRM / 2.0-12 03/27/2007 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 / 3.0-21 01/10/2007 Page TRM / 3.0-3 03/15/2002 Page TRM / 3.0-4 11/30/2005 3.1 REACTIVITY CONTROL SYSTEMS Pages 3.1-1 through 3.,1-5, 08/31/1998 Pages TRM / 3.1-6,through TRM /3.1-8 03/27/2007-Pages TRM / 3.1-9 and-TRM/ 3.1-9a 02/18/1999 Page TRM /3 1-1 02/18/1999 3.2 CORE OPERATING LIMITS REPORT Page TRM. /3.2-*1 08/31/1998 Pages TRM /i3.2"2through TRM / 3.2-48 03/30/2007 3.3 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 07/16/1999 Page TRM / 3.3-4 03/31/2006
\Pages 3.3-5 and 3.3-6 08/31/1998 Page TRM 3.3-7 03/31/2006 Page 3.3-8 08/31/1998 Pages TRM / 3.3-9 and TRM / 3.3-9a 12/17/1998 Page TRM / 3.3-10 05/30/2006 Page TRM / 3.3-11 06/02/2005 Page TRM / 3.3-11a 05/30/2006 Page TRM / 3.3-12 03/30/2001 Page TRM / 3.3-13 09/13/2005 Page TRM / 3.3-14 12/14/1998 Page TRM / 3.3-15 10/22/2003 SUSQUEHANNA - UNIT 2 TRM / LOES-1 EFFECTIVE DATE 04/04/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 36 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / 3.3-16 06/27/2001 Pages TRM / 3.3-17 and TRM / 3.3-18 06/14/2002 Pages TRM / 3.3-19 and TRM / 3.3-20 10/22/2003 Page TRM / 3.3-21 03/27/2007 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 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 3.4-6 through 3.4-11 08/31/1998 Page TRM / 3.4-12 12/03/2004 Page TRM / 3.4-13 03/31/2006 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 04/17/2000 Pages 3.5-5 through 3.5-7 08/31/1998 3.6 CONTAINMENT Pages 3.6-1 through- 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 T-RM / 3.6-9 -12/31/2002 3.7 PLANT SYSTEMS Pages TRM / 3.7-1 and TRM / 3.7-2 07/29/1999 Page 3.7-3 08/31/1998 Pages TRM / 3.7-4 and TRM / 3.7-5 03/31/2006 Pages TRM / 3.7-6 through TRM / 3.7-8 08/02/1999 Page TRM / 3.7-9 03/31/2006 Page TRM / 3.7-10 08/16/2005 Page TRM / 3.7-11 01/21/2000 Pages TRM / 3.7-12 and TRM / 3.7-13 08/02/1999 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 03/31/2006 Page TRM / 3.7-18 08/02/1999 Page TRM / 3.7-19 03/31/2006 Pages TRM / 3.7-20 through TRM / 3.7-22 08/02/1999 Pages TRM / 3.7-23 and TRM / 3.7-24 03/31/2006 Pages TRM / 3.7-25 through TRM / 3.7-27 08/02/1999 Page TRM / 3.7-28 11/29/2006 TRM I LOES-2 EFFECTIVE DATE 04/04/2007 SUSQUEHANNA - UNIT SUSQUEHANNA -
UNIT 22 TRM / LOES-2 EFFECTIVE DATE 04/04/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 36 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / 3.7-29 11/16/2001 Page TRM / 3.7-30 11/30/2005 Page TRM / 3.7-31 11/16/2001 Page TRM / 3.7-32 01/09/2004 Page TRM / 3.7-33 10/05/2002 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 Pages TRM / 3.7-40 and TRM / 3.7-40a 02/14/2005 Pages 3.7-41 and 3.7-42 08/31/1998 Pages TRM / 3.7-43 through TRM / 3.7-48 10/05/2006 Pages TRM / 3.7-48a and TRM / 3.7-48b 10/05/2006 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 3.8 ELECTRICAL POWER Page TRM / 3.8-1 04/02/2002 Pages TRM / 3.8-2 and TRM / 3.8-3 01/28/2005 Page TRM / 3.8-4 01/31/2005 Pages TRM / 3.8-5 and TRM / 3.8-6 04/02/2002 Pages TRM / 3.8-7 through TRM / 3.8-10 12/03/2004-Page TRM/3.8-11 --- 08/10/2004 Page TRM / 3.8-12 -12/03/2004 Pages 3.8-13 and 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 through TRM / 3.8-23 06/06/1999 Pages 3.8-24 and 3.8-25 08/31/1998 Pages TRM / 3.8-26 through TRM / 3.8-29 11/29/2006 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 03/31/2006 Page TRM / 3.10-8 08/16/2006 SUSQUEHANNA - UNIT 2 TRM / LOES-3 EFFECTIVE DATE 04/04/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 36 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 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 through 3.11-9 08/31/1998 Page TRM / 3.11-10 12/03/2004 Pages 3.11-11 and 3.11-12 08/31/1998 Page 3.11-13 09/01/1998 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 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 05/13/2005 Page 3.11-25 09/01/1998 Pages TRM /3.11-26 through TRM / 3.11-28 01/21/2004 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 - D3/31/2006 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 09/30/2006 Page TRM / 3.12-5 02/05/1999 4.0 ADMINISTRATIVE CONTROLS Pages 4.0-1 through 4.0-8 08/31/1998 SUSQUEHANNA - UNIT 2 TRM / LOES-4 EFFECTIVE DATE 04/04/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 36 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 3.0-10 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 Pages TRM / B 3.1-1 through TRM / B 3.1-3 07/13/1999 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 / B 3.3-1 04/07/2000 Page B 3.3-2 08/31/1998 Pages TRM / B 3.3-3 and TRM / B 3.3-3A 01/31/2005 Pages TRM / B 3.3-4 through TRM / B 3.3-7 05/30/2006 Pages TRM / B 3.3-8 and TRM / B 3.3-9 03/30/2001 Page B 3.3-10 08/31/1998 Pages TRM / B 3.3-11 and TRM / B 3.3-42 09/13/2005 Page TRM / B 3-3-13 12/03/2004.
Page TRM / B 3.3 06/25/2002 Page TRM / B 3.3-14a -06114/2002 Page TRM / B 3.3-14b 06/14/2002 Page TRM / B 3.3-15 10/22/2003 Page TRM / B 3.3-16 10/22/2003 Page TRM I 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 through TRM / B 3.3-19e 03/27/2007 Pages TRM / B 3.3-20 and TRM / B 3.3-21 05/16/2003 Page TRM / B 3.3-22 10/22/2003 Page TRM / B 3.3-23 05/16/2003 B 3.4 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 through B 3.4-4 08/31/1998 Page TRM / B 3.4-5 10/15/1999 Page B 3.4-6 08/31/1998 B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 through B 3.5-5 08/31/1998 SUSQUEHANNA - UNIT 2 TRM / LOES-5 EFFECTIVE DATE 04/04/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 36 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 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 08/02/1999 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 through TRM / B 3.7-14 08/02/1999 Pages TRM / B 3.7-14a and TRM / B 3.7-14b 01/09/2004 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 Pages TRM / B 3.7-21 and TRM / B3.7-21a 02/14/2005.
Pages TRM / B 3.7-22 and TRM / B 3.7-23 04/07/2000 Pages TRM / B 3.7-24 through TRM / B 3.7-30 10/05/2006 Pages TRM / B 3.7-30a and TRM / B 3.7-30b 10/05/2006 Page TRM / B 3.7-31 12/03/2004 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 B 3.8 ELECTRICAL POWER BASES Page TRM / B 3.8-1 04/02/2002 Pages TRM / B 3.8-2 and TRM I B 3.8-2a 01/28/2005 Page TRM / B 3.8-3 04/02/2002 Page 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 3.8-16 04/02/2002 Page TRM / B 3.8-17 01/28/2005 Pages TRM / B 3.8-18 through TRM / B 3.8-24 11/29/2006 SUSQUEHANNA - UNIT 2 TRM / LOES-6 EFFECTIVE DATE 04/04/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 36 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 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 Pages TRM / B 3.10-6 and TRM / 3.10-7 04/17/2002 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 3.11-11 a 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 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 Page TRM / B 3.11-23a 05/13/2005 Pages TRM / B13.11-24 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 Page TRM / B 3.11-30 12/03/2004 Pages B 3.11-31 through B 3.11-35 08/31/1998 Page TRM / B 3.11-36 02/12/1999 B.3.12 LOADS CONTROL PROGRAM BASES Pages TRM / B 3.12-1 through TRM / B 3.12-3 02/05/1999 LDCN4461 TRM2 text LOES.doc 4/2/07 SUSQUEHANNA - UNIT 2 TRM / LOES-7 EFFECTIVE DATE 04/04/2007
Core Operating Limits Report (COLR)
PPL Rev. 7 3.2,1 3.2 Core Operating Limits Report (COLR) 3.2.1 Core Operating Limits Report (COLR)
TRO 3.2.1 The Core Operating Limits specified in the attached COLR shall be met.
APPLICABILITY: Specified in the referenced Technical Specifications.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core Operating Limits not A.1 Perform action(s) Specified in referenced met. described in referenced Technical Technical Specification. Specifications.
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY NOTE N/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications.
SUSQUEHANNA - UNIT 2 TRM 1 3.2-1 EFFECTIVE DATE 08131/1998
PPL Rev- 7 PL-NF-07-002 Rev. 1 Page 1 of 47 Susquehanna SES Unit 2 Cycle 14 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering March 2007 p
SUSQUEHANNA UNIT 2 'TRM/3.2-2 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 2 of 47 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev. Affected No. Sections Description/Purpose of Revision 0 ALL Issuance of this COLR is in support of Unit 2 Cycle 14 operation.
1 6.0 Figure 6.2-2 changed per AR 855311855311to improve operating margin.
FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 2 TRM/3.2-,3 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 3 of 47 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 14 CORE OPERATING LIMITS REPORT Table of Contents 1.0 INTR ODUCTIO N .................................................................................................... 4 2.0 DEFINITIO NS ...................................................................................................... 5 3.0 SHUTDOWN MARGIN ................................................ 6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ................. 7 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) ............................... 9 6.0 LINEAR HEAT GENERATION RATE-(LHGR) ............................ 21 7.0 ROD-BLOCK MONITOR (RBMI) SETPOINTS AND OPERABILITY REQUIREMENTS ............................................... 29 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION ....................... 31 9.0 POW ER / FLOW MAP ............................................................................................ 43 10.0 OPRM SETPO INTS ................................................................................................ 45 11.0 R E FE R E N C ES ........................................................................................... .............. 46 SUSQUEHANNA UNIT 2 rRM/3,2-4 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 4 of 47
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 14 is prepared in accordance with the requirements of Susquehanna Unit 2, Technical Specification 5.6.5. As required by Technical Specifications 5-6.5, core shutdown margin, the core operating limits, RBM setpoints, and OPRM setpoints presented herein were developed using NRC-approved methods and are established such that all applicable limits of the plant safety analysis are met.
SUSQUEHANNA UNIT 2 TRM!3.2-5 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 5 of 47 2.0 DEFINITIONS Terms used in this COLR but not defined in Section 1.0 of the Technical Specifications or Section 1.1 of the Technical Requirements Manual are provided below.
2.1 The AVERAGE PLANAR EXPOSURE at a specified height shall be equal to the total energy produced per unit length at the specified height divided by the total initial weight of uranium per unit length at that height.
2.2 The PELLET EXPOSURE shall be equal to the total energy produced per unit length of fuel rod at the specified height divided by the total initial weight of uranium per unit length of that rod at that height.
2.3 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR limit for the applicable fuel bundle type.
2.4 LHGRFACr is a multiplier applied to the LHGR limit when operating at less than 108 Mlbmlhr core flow. The LHGRFACf multiplier protects against both fuel centedine melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbmlhr, 2.5 LHGRFACp is a multiplier applied to the LHGR limit when operating at less than 100%
rated power. The LHGRFACp multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from partial power conditions.
2.6 MFLCPR is the ratio of the applicable MCPR operating limit for the applicable fuel bundle type divided by the MCPR calculated by the core monitoring system for each fuel bundle.
2.7 MAPRAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLGHR limit for the applicable fuel bundle type.
2.8 - OPRM is the Oscillation Power Range Monitor. The Oscillation Power Range Moniter-(OPRM) will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence thatthe MCPR safety limit is not violated.
2.9 Np is the OPRM setpoint for the number of consecutive confirmations of oscillation half-cycles that will be considered evidence of a stability related power oscillation.
2.10 Sp is the OPRM trip setpoint for the peak to average OPRM signal, 2.11 Fp is the core flow, in Mlbm / hr. be4ow which the OPRM RPS trip is activated.
SUSQUEHANNA UNJT 2 TRM/3.2-6 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 6 of 47 3.0 SHUTDOWN MARGIN 3.1 Technical Specification Reference Technical Specification 3.1.1 3.2 Description The SHUTDOWN MARGIN shall be equal to or greater than:
a) 0.38% Ak/k with the highest worth rod analytically determined OR b) 0.28% Ak/k with the highest worth rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and poison burnup, Beginning of Cycle (BOO) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, "R". The adder, "R", is the difference between the calculated value of maximum core reactivity (that is, minimum SDM) during the operating cycle and the calculated BOO core reactivity. If the value of 4RR is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOO measured value is required.
The SHUTDOWN MARGIN limits provided in 3.2a and 3.2b are applicable in MODES 1, 2, 3, 4, and-5. This includes core shuffling.
SUSQUEHANNA UNIT 2 TRMI3,2_-7 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 7 of 47 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 Technical Soecification Reference Technical Specification 3.2.1 42 Description The APLHGRs for ATRIUMTM-10 fuel shall not exceed the limit shown in Figure 4.2-1.
The APLHGR limits in Figure 4.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable in Two Loop operation.
The APLHGR limits for Single Loop operation are provided in Section 8.0.
SUSQUEHANNA UNIT 2 TRM/3.2-8 EFFECTIVE OATE 03/30/2007
SSES UNIT 2 CYCLE 14 (16 44 124 44.44 INDETERMINING MAPRAT
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PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 9 of 47 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) 5,1 Technical Specification Reference Technical Specification 3.2.2, 3.7.6, and 3.3.4.1 5.2 Description The MCPR limit is specified as a function of core power, core flow, average scram insertion time per Section 5.3 and plant equipment operability status- The MCPR limits for all fuel types (ATRIUM TM-1O) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a) EOC-RPT and Main Turbine Bypass Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOC to EOG Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOC b) Main Turbine Bypass Inoperable / EOC-RPT Operable Figure 5.2-3: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-4: Power-Dependent MCPR value determined from BOC to -
EOC -
c) EOC-RPT Inoperable / Main Turbine Bypass Operable Figure 5.2-5: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-6: Power-Dependent MCPR value determined from Boc to EOC The MCPR limits in Figures 5.2-1 through 5,2-6 are valid for Two Loop operation.
The MCPR limits for Single Loop operation are provided in Section 8.0.
SUSQUEHANNA UNIT 2 TRMI3.2- 10 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 10 of 47 5.3 Average Scram Time Fraction ifthe average measured scram times are greater than the Realistic Scram times listed in Table 5.3-1 then the MCPR operating limits corresponding to the Maximum Allowable Average Scram Insertion Time must be implemented.
Determining MCPR operating limits based on interpolation between scram insertion times is not permitted. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.
SUSQUEHANNA UNIT 2 IRM/3.2-11 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 11 of 47 EOC-RPT and Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-12 EFFECTIVE DATE 03/3012007
- 4 (A
(A SSES UNIT 2 CYCLE 14 2.2 LEGEND 2.1 CURVE A- MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME
--.4 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1.9 I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR (A 4V1.7 (A CL.1 (50,1.62) 1,.6 1.5 F'1
~~11
~11 ni 1.4
~~~1
-.4 J
REFERENCE:
T.S. 3.2.2 (86.3,1.37) (108,1.37)1 1.3
-1 Ev~
(A 1.2 (A 70 80 90 100 110 30 40 50 60
-u XT N) Total Core Flow (MLB/HR) I z
-n<
6D MCPR OPEFATING LIMIT VERSUS TOTAL CORE FLOW 6
EOC-RPT AND, MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-1
SSES UNIT 2 CYCLE 14
,CD 3.5 3.4 LEGEND 3.3 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM (25,3.15) INSERTION TIME 3.2 3.1
-CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME Nz 3.0 (302.4)..
.... - I .. .. 1 ...-.. 77-2.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.8 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 t 2 .7 E 2.6
.j USED IN DETERMINING MFLCPR 2.5 r-"
CL 0 2.3 a:
2.4 C. 2.2
=E2.1 I- -____________ MFCP I-D 2.0
... i .
1.9 rn v (40,1.76) 1 1.8 -V A--
1.7 I I I 4 4 (40,1.68) l! II
-I w1- 4I m 1.6 a . I
REFERENCE:
T.S. 3.2.21 - (80,1.47) 1.5 I 1 1 (65~1.58)7 (100,1.41) 4 M(100,1.37) 1.4 I 1
- (85.1-.44)-
C> II C0 1.3 ___________ * .. I~ I.
20 30 40 50 60 70 80 90 100 NJ . Core Power (% RATED)
(b Z MCPR OqERATING LIMIT VERSUS CORE POWER -n EOC-RPT AND MAIN TURBINE BYPASS OPERABLE 6~.
TWO LOOP OPERATION (BOC TO EOC) -. N FIGURE 5.2-2
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 14 of 47 Main Turbine Bypass Inoperable / EOC-RPT Operable SUSQUEHANNA UNIT 2 TRM/3.2-15 EFFECTIVE DATE 03/30/2007
VI)
SSES UNIT 2 CYCLE 14 c: 2.3 I - I I V), 2.2 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME K
2.1 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME (30,1.98) rF 2.0 4 4. 4- I SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 f!1 "1 R71 E1.9 4. - U
~ 3 1 -~~I F I USED IN DETERMINING MFLCPR
-- -.- *--.------ -, V
(,~1 N, 1.8 0.
(.1.7 1.6 A (81.8,1.58) (108,1.58)
C-, 1.5 RE FERNCE: T.S. 3.7.6a.d322' ,
1.4-N-)
1.3 30 40 50 60 70 80 90 100 110
-u Total Core Flow (MLBIHR) x 0 (D *: 0
<I MCPR OPEFRATING LIMIT VERSUS TOTAL CORE FLOW . z 0 -71 MAIN TURBINE BYPASS INOPERABLE I EOC.RPT OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-3
SSES UNIT 2 CYCLE 14 0, 3.5 3.4 m
3.3 3.2 3.1 3.0 2.9 2.8 2.7 E
2.6 2.5 C,
2.4 0
2.3 2.2 2.1 2.0 1.9 m
m 1.8 rn 1.7 m 1.6 (100,1.58) 1.5
-1 m 1.4 c~) 1.3 C) 20 30 40 50 60 70 80 90 100 03 xD v C)
Core Power (% RATED) co <
C) (D~
MCPR OIqERATING LIMIT VERSUS CORE POWER 0)
MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-4
PPL Rev. 7 PL-NF-07-002 Rev. I Page 17 of 47 EOC-RPT Inoperable /
Main Turbine Bypass Operable SUSQUEHANNA 'UNIT 2 TRM / 3. 2 -18 EFFECTIVE DATE 03/30/2007
SSES UNIT 2 CYCLE 14 2.2 V) 2.1 2.0 N) 1.9 20 ~1.8 CL 0
Ix 0- 1.6 1.5 1.4 m
m 1.3 1.2 30 40 50 60 70 80 90 100 110 Co Total Core Flow (MLB/HR) z-n MCPR OPEF*ATING LIMIT VERSUS TOTAL CORE FLOW co
-A.
6
-4 EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-5
SSES UNIT 2 CYCLE 14 3.5 rnl 3.4 LEGEND 3.3
-... 5,3.15) , CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 (25,3.15)... INSERTION TIME 3.1 S(30,2.94) CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 2.9 2.8 ___ _ _SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
_ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.7
--4 2.6 USED IN DETERMINING MFLCPR CA) 2.5 -U CL N) 2.4 CD cND 0.
m 2.3 -4 2.2 2.1 2.0 1.9 1.8 (40,1166) - A * .... . .
1.7 1.6 .. B _._.... . .
IRE=ERENCE: T.S. 3.3.4.1 and 3.2.2"l ._ .... .. _. _...
1.5 (100,1.41)
C-)
..... .......... .... (80,1.47) 1.4 1.3 90 100 5o 60 70 80 20 30 40 CID Core Power (% RATED)
-n MCPR OPERATING LIMIT VERSUS CORE POWER 6O EOC-RPT INOP'ERABLE / MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-6
PPL Rev. 7 PL-NF-07-002 Rev, 1 Page 20 of 47 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)
Position 45 0.470 0.520 39 0630 0.860 25 1.500 1.910 5 2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSOUEHANNA UNTT 2 T'RM!3.2-21 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 21 of 47 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3 and 3.7.6 6.2 Description The maximum LHGR for ATRIUMT1-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1. The LHGR limit in Figure 6.2-1 is valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable.
In order to protect against both fuel centerline melting and cladding strain during anticipated system transients initiated from reduced power and flow conditions, power and flow dependent LHGR limit multipliers are provided:
a) Main Turbine Bypass Operable / EOC-RPT Operable and Inoperable Figure 6.2-2: Flow-Dependent LHGR Limit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multiplier b) Main Turbine Bypass Inoperable / EOC-RPT Operable and Inoperable Figure-6.2-4: Flow-Dependent-LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit.Multiplier The LGHR limit and LHGR likit multipliers in Figures 6.2-1 through 6.2-5 are valid for both Two Loop and Single Loop operation.
SUSQUEHANNA UNIT 2 TRM/3,..2-2 EFFECTIVE DATE 03/30/2007
0 SSES UNIT 2 CYCLE 14 o 16 4 4 1 4 4 1 ' 4 I 4 4 i 4 g 4 4 I 4 I i I
..i.
14
REFERENCE:
TS. 3.2.3 0.0,13.4 , : ;18900,13.4 ;3 Nr USED IN DETERMININGFDLRXJ"
_12 2
. . . . .¶.. ...
............... 4 6.
G,
- 0) II I-1 I I I I iI j I i i4 p p I ..11e* i* . ~ t ~ I ~ . 4. ~ 4 .I Ii .1. i .
. .- . 4I i . . .
- r I. - ... I
- I@ I* *.**w.
l l4, I *I@
i4
- - ) .. v , .*4i I . J- I.i..** .*
X 8
. . ....i i.. } ....... .
4 l 4 I I I #
, 4 4I 4*I 1 1 4 , I 4I I 4 4I 4 4 ¶ l l 4 4. 4 i 4 p4 I4 4*
I 4 4i Il 4 4I 4 4 4 4 4 I I
.3
-J m .. . .. . .74400,7.10
- 4 P 4 I 4 4] . ,l4I . ... 4 r 4 4 4 4i 1 4i 4 4 i 1 N) ýc <
CD) 6 m 0 -4 rn I 4 4 4 4 , , ~4I I tI I 1 44I I 4 4 4 4 4 I a 4 4 44 I I 4 4 I I p S
Ir I rn 4 50000 60000 70000 80000 0 10000 20000 30000 40000 0
C) Pellet Exposure (MWD/MTU)
D C EXPOSURE LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET ATRIUMT-10 FUEL FIGURE 6.2-1
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 23 of 47 Main Turbine Bypass Operable I EOC-RPT Operable and Inoperable SUSQUEHANNA UNIT 2 TRM/3. 2 -24 EFFECTIVE DATE 03/30/2007
U0 a SSES UNIT 2 CYCLE 14 O 1.10
... " . ... ... . ... . 1... . *1... . 1a ... 1 ... a ... "1.....
A .... . *I - *......... I ...... ,... ....
....
- I
$_ A A A A a , I
~~7 ,1.001 A A 1 A A 00
.- ..-.. ...-- ..-.... ... . a . * ... .... . .. ..... .] *...
...i .oJ .*..=o*...*................ .. *° 0 o0...
L9 I . . . .. . .
CL 0 .8 o~~. .... .... ....
qj .
- cO* 0,..... ...... . , ... .. .. ... . ..... .. . . . . . . . . . . . . . .
0.70 -- -' - - - -. . .. . . . ... . .
RD................................................................-
Z .. ............... J ........ . . ....
a a A l AA
REFERENCE:
TA$. 3.2.3and3..
C-)
A A A , a a SEDNDEERMINING FDLRX 0.50
--H rn*
C) 0.40 30 40 50 ,60 70 80 90 100 110 C)
A Total Core Flow (MLB/hr)
"4 CD Z t -
FLOWpEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS OPERABLE .
ATRIUMTM-i0 FUEL C)
FIGURE 6.2-2
9*
<SSES UNIT 2 CYCLE 14 i*~aa a i o a a
-- I *Iti I a 1 . 10*a .. ."
a ............ a ...... aa ........ I Ii .........a .. a a a a a a a a ar a a a a (10,1.00
. .. . . . . a a R 3a2 .3 a n a
- o. 0 . ...... ..... ..... ..... .... "'÷.......... "..... I.... 1.......... " *......
... . =..... .+.....
. .. .. I a... .. . .. . a a . I .......
0 .8: .. .. .. . ... . .
.. I o. ...
.. . .. . . .. .. .. r1o rr 0.50 a a a
. a
..
- a
. ...a 0 .70.. 0........*... A P LS......A r - -,,0u.....
(: ... . ~. . '
"' .. . . . . a. . a............. ....... . . .
20 30 40 50 so 70 80 90 100 a0 .40 I*I * ~ .i p liI*.* !i .... i m aing a.. I . 1l J 1 . l
=30 20 4+0,50,7 0 0 0 0.4 a Cor Poe (% USDATEETRINNGD)R o ... . . . 0 , U0M M~ . . .
POWER DEPENDENT LHGR LIMIT MULTPLIER MAIN TURBINE BYPASS OPERABLE R ATRIUMT 01FUEL 4 FIGURE 6.2-3
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 26 of 47 Main Turbine Bypass Inoperable I EOC-RPT Operable and Inoperable SUSQUEHANNA UNIT 2 'TRM/3-2-27 EFFECTIVE DATE 03/30/2007
CSSES UNIT 2 CYCLE 14 1j.1u 4 4 4 4 . a S i a a , 1 I a a 1 a a .
4 4 ,i 4 ii
-r-4 P I 4 I
- a
- a I 1 I I 4 4 t I 1 6 a a I I 4 4 4
- 4 4 , i , 4 3 I 4 1 4 . 4 ~ 1' a
=1.00 . . . . . . . . . ........ (9.... ) .(.. 8...
.)
0.90
- ty 0.80 I 4 4 l 5 4 4 4 I S u-i u 4"1 I I S i SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS
, S i " i.i (D
ARE INOPERABLE PER SR 3.7..1 OR 3.7.62 i 4 SVALVES -4
= 0.70 0 3 4 . .. . . I . . . . . . . . . . . . .
Q. . . . . ~.............E.YPA...
0.
0.60 * ~USED IN DETERMINING FDLRX
.. IN.O. P .A...... .3 .. .
0.50 C=?
S I i 3 44I44I CW 0.40 60 70 80 90 100 110 3O 40 50 (D
N) ,Total Core Flow (MLB!HR) (0<
FLOW PEPENDENT LHGR LIMIT MULTIPLIER 0
MAIN TURBINE BYPASS INOPERABLE 4~o ATRIUMTM-10 FUEL -
FIGURE 6.2-4
t4 SSES UNIT 2 CYCLE 14
- a I a a a b a I a . . . .. .
c1.00 I a ap1 a a a
... . .. . a
............................ ......... a. ... - - - - - - - - - -.......
0.90 a 1 a,0 a (100,0.90) a.
ce 0.80 .. . . ..* .* ." -- -- - ... ... .. ...... ..... I I.. . ... ..
..... ....... ... I..
.SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS
... . r-T (D
-T-L 0.70 ..... ...
- VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 D R
REFERENCE:
T.Sa 3.2.3 andN3.7.6 0l.60 m S a USEDINDETERMININGFDLRX 0.50
.. acaaaAia i a I a a a ia a* a a i CC a... ....... . . . . .... .. .
(25,0.42) - - a30,0.4a
-n,.
c) 0.40 0.6 i 20 30 40 ,0 60 70 8o 90 100 Core Power (% RATED) -0 C-mD Z1o 1
POWqR DEPENDENT L-GR LfMIT MULTIPLIER 00 0 MAIN TURBINE BYPASS INOPERABLE 0 ATRIUM M-10 FUEL 0 FIGURE 6.2.5
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 29 of 47 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS 7.1 Technical Specification Reference Technical Specification 3.3.2.1 7.2 Description The RBM Allowable Value and Trip Setpoints for; a) Low Power Range Setpoint, b) Intermediate Power Range Setpoint, c) High Power Range Setpoint, e) Low Power Range - Upscale, f) Intermediate Power Range - Upscale, and g) High Power Range - Upscale shall be established as specified in Table 7.2-1. The RBM setpoints are valid for Two Loop and Single Loop Operation, Main Turbine Bypass Operable and Inoperable, and EOC-RPT Operable and Inoperable.
The RBM system design objective is to block erroneous control rod withdrawal initiated by the operator before fuel design limits are violated. If the full withdrawal of any control rod would not violate a fuel design limit, then the RBM system is not required to be operable. Table 7.2-2 provides RBM system operability requirements to ensure that fuel design limits are not violated.
SUSQUEHANNA UNIT 2 TRM/3.2-30 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 30 of 47 Table 7-2-1 RBM Setpoints
..... Allowable Nominal Trip Function Value(1' Setpoint Low Power Range Setpoint 28.0 24.9 Intermediate Power Range Setpoint 63.0 61.0 High Power Range Setpoint 83.0 81.0 Low Power Range - Upscale 123.4 123.0 Intermediate Power Range - Upscale 113.6 113.2 High Power Range - Upscale 110.6 110.2 (1) Power setpoint function (Low, Intermediate, and High Power Range Setpoints) determined in percent of rated thermal power. Upscale trip setpoint function (Low, Intermediate, and High Power Range - Upscale) determined in percent of reference level.
Table 7.2-2 RBM System Operability Requirements Thermal Power
(% of Rated) " MCPR (z,3)
_>28 and < 90 < 1-78
>90 < 1.71 (2)
Applicable to Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable.
(3) Applicable to both Two Loop and Single Loop Operation.
SUSQUEHANNA UNIT 2 TRMI3.2,-3]. EFFECTIVE DA!E 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 31 of 47 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 Technical Specification Reference Technical Specification 3.2.1, 3.2.2, 3.2.3, 3.3.4.1, 3.4-1, and 3.7.6 8.2 Description APLHGR The APLHGR limit for ATRIUM'rM-1 0 fuel shall be equal to the APLHGR Limit from Figure 8.2-1.
The APLHGR limits in Figure 8.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable in Single Loop operation.
Minimum Critical Power Ratio Limit The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limits for all fuel types (ATRIUM TM-10) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a) EOC-RPT and Main Turbine Bypass Operable Figure 8.2-2: Flow-Dependent MCPR value determined from BOGC to EOC Figure 8.2-3: Power-Dependent MCPR value determined from BOC to EOC b) Main Turbine Bypass Inoperable / EOC-RPT Operable Figure 8.2-4: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-5: Power-Dependent MCPR value determined from BOC to EOC c) EOC-RPT Inoperable / Main Turbine Bypass Operable Figure 8.2-6: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC SUMIJEHANNA UNIT 2 T-RM/3.2- 32 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 32 of 47 The MCPR limits in Figures 8.2-2 through 8.2-7 are valid only for Single Loop operation.
Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0.
RBM Setpoints and Operability Requirements The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0.
SUSQUEHANNA UNIT 2 TRMi3.2-.33 EFFECTIVE DATE 03/30/2007
o SSES UNIT 2 CYCLE 14 16
- a. .. . . .. . . .
M
-T" 5 a,1 a.0: 1 a . REEEC
. as T.S.3.4 a , s 11
~ an3.1 a
T.S. 3.41.and 3.2.
0.,00a s a~ ~ ~~~ ......
a REFERENCE ......... .
a aRA 14 I IN DETERMINING t-4
-\) ' I' i, ~USE:D IN DETERMINING MAPRAT a r a l u , I . dl a
- . t . a a . a a1a
.E 12 a a a ,a., a a a aa ,.a , a a a araa
............ a-! i
-U
-U3
.tz a' a* a, , I--
N~ o210 Cu Jia a a . . a a a a ' a 1 . a a *
<8 ca I..
(-U.
-,ri (D z
-H- T 6
- a ~ a .,. r a~ a a a ~ ah h S a i , . 67000,5.6 m .. ' ...... .1 6005
. . . . . . a a a . . . .
aa.
ýi I
LI)
. 30000 40000 50000 60000 70000 I 10000 20000 Average Planar Exposure (MWDIMTU) -. "
0 a*
-:4 VERSUS AVERAGE PLANAR EXPOSURE AVERAGE PLANAR LINEAR HEAT GINERATION RATE LIMIT .I) C:
SINGLE LOOP OPERATION
'--4 I'O)
ATRIUMT"-10 FUEL FIGURE 8.2-1
PPL Rev. 7 PL-NF-07-002 Rev. I Page 34 of 47 EOC-RPT and Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-35 EFFECTIVE. DATE 03/30/2007
0 (f~ SSES UNIT 2 CYCLE 14
(~l 2.3 I I I I I !
m tLEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.2 -(30,2.18) I ...
-4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
+ -.---------.- ' -
2.1 4 -
'Y ANALYSES ASSUME THAT FOUR BYPASS VALVES E ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 (50,2.08)
IN) 2.0
]
I USED INDETERMINING MFLCPR T 0
I.i.... I*" I I ot, a.
1.9 m 1.8 3.4.1 and
REFERENCE:
S
REFERENCE:
T S 3.4.1 and 3.2.2I
_ _ L
--4 1.7 110 70 so 90 100 30 40 50 60 ;TJ "U
. Total Core Flow (MLB/HR) -T
~0 FLOW 6 MCPR OPERATING LIMIT VERSUS TOTAL CORE 0 EOC-RPT AND MAIN TURBINE BYPASS OPERABLE 0 4-I~
SINGLE LOOP OPERATION (BOC to EOC) 4 FIGURE 8.2-2
SSES UNIT 2 CYCLE 14 (A
4.1 rn 3.9 3.7
-1 3.5 3.3 Em
-H
-J 3.1
' 2,9 0
2.7 2.5 rn 2.3 rn
~11 m
C-,
2.1 nfl 1.9
-H m 1.7 -L- -"
20 30 40 50 60 70 80 90 100 I-Core Power (% RATED) i--
~-1 C MCPR OPERATING LIMIT VERSUS CORE POWER -4 EOC.RPTJAND MAIN TURBINE BYPASS OPERABLE C SINGLE LOOP OPERATION (BOC to EOC) 0
-4 N, FIGURE 8.2-3
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 37 of 47 Main Turbine Bypass Inoperable I EOC-RPT
-Operable SUSQUEHANNA UNIT 2 TRM/3.2--38 EFFECTIVE DATE 03/30/2007
SSES UNIT 2 CYCLE 14 (A
2.6 rrl 2.5 N) 2,4
-_E2.3
-1
-U N) 2 2.2 0
-4 C.
~2.1 rn 2.0
-fl ni C-)
-H 1.9
-H m
(A 70 80 90 100 110 (A 30 40 50 60 (0 x~
N) Total Core Flow (MLBIHR) z Tn CD MCPR OPEFATING LIMIT VERSUS TOTAL CORE FLOW 0~
0 MAIN TURBINE BYPASS INOPERABLE ! EOC-RPT OPERABLE -4x SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-4
- W~ I ELI t~ - ~ I~E ~ I
- '* *;bb-..5 UINI I Z L;YJLI:: 14 4.3 (25,4.25)
M
- LEGEND 41~
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3INSERTION TIME 3.9 (30,3.74) ICURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3,7 E E
3.5 3 3 I SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
-73 USED IN DETERMINING MFLCPR
- .* .- 3.1 ... . "-
0X C3 02.9 02.7 n\
2.5 .
2.3 -(40,2.32) --
--IA __-_ _ _ _ _(100,2 ... ...
2.1
_.4,D, ] ("72.9,2.03) 1.9 !
REFERENCE:
T.S. 3.4.1 3.7.6, and 3.2.2 1.7 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
MCPR OFERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE o SINGLE LOOP OPERATION (BOC to EOC) C0
" )
FIGURE 8.2-5
PPL Rev. 7 PL-NF-07-002 Rev- 1 Page 40 of 47 EOC-RPT Inoperable I Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-41 EFFECTIVE DATE 03/30/2007
SSES UNIT 2 CYCLE 14 4Dr 2.3 i I I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.2 I I CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.1 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES;
--4 -i ARE OPERABLE PER SR 3,7.6.1 AND 3.7.6.2 (50,2.08) ... . ... .. .
"V F-'
E 2,02.0 USED IN DETERMINING MFLCPR L..
0.
0:
IL 0
1.9
=* (108,1 .81) m-ii
.B -- - -A - .. -..
-T-1.8
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.22 m
1.7 !d, 3 2I CD, I 70 80 90 100 110 3( 40 5o
- u
.Total Core Flow (MLBIHR)
C) z MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW -4 EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE 0
-.,4 SINGLE LOOP OPERATION (BOC to EOC) to3 FIGURE 8.2-6
SSES UNIT 2 CYCLE 14 4.1 m
3.9 3.7 3.5 3.3 Co 'D 3.1 r-(~0 0
~2.7 2,5 m 2.3 rn m
C-)
-9 2.1 m
1.9 rn C)
Co 1.7 Co C) 20 30 40 s0 60 70 80 90 100 N) Core Power (% RATED)
Co<
C)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOERABLE / MAIN TURBINE BYPASS OPERABLE 0
SINGLE LOOP OPERATION (BOC to EOC) -4 NJ FIGURE 8.2-7
PPL Rev- 7 PL-NF-07-002 Rev. 1 Page 43 of 47 9.0 POWER / FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and II of the Power/ Flow map, Figure 9.1.
If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power / Flow map is considered an immediate exit region.
If the OPRM Instrumentation is inooerable per TS 3.3.1.1, Region I of the Power I Flow map is considered an immediate scram region.
Region II of the Power / Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation.
SUSQUEHANNA UNIT 2 I"RM/3.2-44 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 44 of 47 120: UNIT 2120 Purpose AP T* MIdS.t.Mn POWVER I FLOW MAP 110 initial I Date: TripSIoint IFORM PeOFIERABE 00MEDIATE ar/z",,*("7 ,
- IF OPR 2a~AE~MDM I1OSRMLA00200 Budr 0 EXITlAW ON.2M04O2 L A IjwoIeATELY F)T IAWOl.-7O0j_2 90 r I J, t I 1 - 90
-As ,*hlrd In Ar1*Jmnl G toI IF ABOVE MLJ.LA BMNIDAR.T. -1 J RodLine L IMMMDIAT'L'Y FXIT LAWON-22AI,002 11.CI ii 1
-, = -1 Tr-,
k---
.... ..AJ '- 1.L7 L --- 0 0-7a i t I Lu-g 9.1 I t I ; 44 7
0,- r '1'-t- -" 1 z' . :- . '1 2 ( SfUit
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r Fo r I"'
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1-1 E C n
-14R33D-
/2 50 J--*-*,** - --- J *- Approx .... '.. ,5
"% r 7 "" ' iJ'"
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- 30 P, J-.:
-1, J-1-If >2.25% and <40%
30%S
-i hermnal power, comply with LCO 1.2.2 MCPR 20 . 20 i'3 " * '3N I "t "I" 0 10 20 30 40 so 60 70 so so 100 Ila Total Core Flow (Mlbm/hr)
(for SLO <75% PUMP Speed Use Form GO-200-009-2)
Figure 9.1 SSES Unit 2 Cycle 14 Power/ Flow Map SUSQUEHANNA UNIT 2 TRM/3.2-45 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev, 1 Page 45 of 47 10.0 OPRM SETPOINTS 10.1 Technical Specification Reference Technical Specification 3.3.1.1 10.2 Description Setpoints for the OPRM Instrumentation are established that will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR Safety limit is not violated. The setpoints are described in Section 2.0 and are listed below:
Sp 1.12 Np = 16 F = 60 Mlbm / hr SUSQUEHANNA UNIT 2 TRM/3. 2.- 46 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 46 of 47
11.0 REFERENCES
11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. XN-NF-81-58(P)(A}, Revision 2 and Supplements I and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model." Exxon Nuclear Company, March 1984.
- 2. EMF-2361(P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model,"
Framatome ANP, May 2001.
- 3. EMF-2292(PXA), Revision 0, "ATRIUM'M .-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.
- 4. XN-NF-84-105(P)(A), Volume 1 and Volume I Supplements 1 and 2, "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," Exxon Nuclear Company, February 1987.
- 5. XN-NF-80-19(P)(A), Volume I and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983.
- 6. XN-NF-80-19(PXA), Volumes 2, 2A. 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECGS Evaluation Model," Exxon Nuclear Compsany, September 1982.
-7. XN-NF-80-19(PXA), Volume 3 Revision 2 "Exxon Nuclear Methodology for--
Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987.
- 8. XN-NF-80-1 9(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, June 1986.
- 9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc-,
September 1986.
- 10. ANF-524(P)(A), Revision 2 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors,"
November 1990.
- 11. NE-092-001A, Revision 1, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993).
SUSQUEHANNA UNIT 2 TRM/3.2- 47 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 47 of 47
- 12. ANF-89-98(P)(A) Revision I and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.
- 13. EMF-2209(P)(A), Revision 2, "SPCB Critical Power Correlation," Framatome ANP, September 2003.
- 14. Caldon, Inc., "TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM"T' System," Engineering Report - 80P, March 1997.
- 15. Caldon, Inc., "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFM' or LEFM CheckPlusTM System," Revision 0, Engineering Report ER-160P, May 2000.
- 16. EMF-85-74(P)(A). Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A),
"RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model,"
Siemens Power Corporation, February 1998.
- 17. EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microburn-B2," Siemens Power Corporation, October 1999.
- 18. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis -
Assessment of STAIF with Input from MICROBURN-B2," Siemens Power Corporation, August 2000.
- 19. NEDO-32465-A; "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Ap~plications," August 1996_
- 20. ANF-913(P)(A), Volume 1 Revisioni and Volume 1 Supplements 2, 3, and -4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation, August 1990.
- 21. ANF-1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005.
SUSQUEHANNA UNIT 2 TRM/3.2-48 EFFECTIVE DATE 03/30/2007
Suppression Pool Alarm Instrumentation PPL Rev. 1 B 3.6.3 B 3.6.3 Suppression Pool Alarm Instrumentation BASES TRO The function of the Suppression Pool Instrumentation is to provide continuous monitoring of the suppression pool temperature and level. This monitoring function supplements the Operator observations and periodic Technical Specification Surveillance Requirements which require observation of the monitored parameters.
The suppression pool alarm instrumentation is designed to warn the control room operator that a limit has been reached and some compensatory action may be required. The setpoints are chosen to be consistent with the limits defined in the Technical Specifications.
Each channel of suppression pool narrow range level instrumentation consists of a transmitter, indicator and alarm circuit. This TRO only requires the alarm function to be maintained. The indicator is not required to support this function but can be used to support the performance of TRS 3.6.3.1, "Channel Check," and can be used to perform Surveillance Requirement (SR) 3.6.2.2.1.
Each channel of suppression pool temperature consists of 8 temperature detectors, as described in the Basis for SR 3.6.2.1.1, associated indicators and alarm circuits.
The four alarm functions, as specified in Table 3.6.3-1, are displayed by monitors located both on the-electronic unit (TX-25751 for Div. I, TX-25752 for Div 11)and on the main control board (TIAH-25751 for Div. I, TIAH-25752 for Div. II). The alarm displays on both the electronic unit and main control board must be surveilled.
Annunciators, tripped by the-plant computer at a calculated .bulk pool temprature of 880 F and by the electronic unit at or below the 1050 F, I 10°F and 120°F limits, enhance the operator's monitoring capability but are not required to be surveilled.
This TRO only requires the alarm function to be maintained. The indicators are not required to support this function but can be used to support the performance of TRS 3.6.3.1, "Channel Check" and can be used to perform SR 3.6.2.1.1.
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.6-4 EFFECTIVE DATE 03/27/2007
Suppression Pool Alarm Instrumentation PPL Rev. 1 B 3.6.3 B 3.6.3 Suppression Pool Alarm Instrumentation BASES (continued)
TRS The TRSs are defined to be performed at the specified Frequency to ensure that the Suppression Pool Alarm Instrumentation Function is maintained OPERABLE.
TRS 3.6.3.1 Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation 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 instrumentation continues to operate properly between each CHANNEL CALIBRATION.
Agreement criteria which are determined 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.-.
TRS 3.6.3.2 -
A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.
The Frequency of 92 days is based on the reliability analysis of Reference 1.
REFERENCES (1) EWR 365129, Evaluation of extending SPOTMOS alarm functional test from 31 days to 92 days.
SUSQUEHANNA - UNIT 2 TRM / B 3.6-5 EFFECTIVE DATE 04/04/2007