ML071070403
| ML071070403 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/04/2007 |
| From: | Susquehanna |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| 028401 | |
| Download: ML071070403 (72) | |
Text
Apr. 04, 2007 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2007-13346 USER INFORMATIO EMPL#:028401 CA#: 0363 AddrJCSA2 n~e#:2N194 TRANSMITTAL INFORMATION:
TO: "R ... 'iW - 04/04/2007 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 ERRORS.
ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.
TRM2 - TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 03/28/2007 ADD MANUAL TABLE OF CONTENTS DATE: 04/03/2007 CATEGORY: DOCUMENTS TYPE: TRM2 AoC~i
Apr. 04, 2007 Page 2 of 2 ID: TEXT 3.2.1 REMOVE: REV:5 ADD: REV: 6 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT LOES REMOVE: REV:31 ADD: REV: 32 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.
I SSES MADUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents Issue Date: 0)4/03/2007 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 32 04/03/2007
Title:
LIST OF EF FECTIVE SECTIONS TEXT TOC 9 12/14/2006
Title:
TABLE OF CONTENTS K' /\
TEXT 1.1 0 11/19/2002
Title:
USE AND APPLICATION DEFINITIONS /
TEXT 2.1 1 02/04/2005\\ \ N',,
Title:
PLANT PROGRAMS AND SETPOINTS PLANT,-PROGRAMS' /
TEXT 2.2 5 1112212,005 /
Title:
PLANT PROGRAMS AND SETPOINTS//INSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 '2
- PCBI/ T 01/29/2007 N F, APPLICABILITY TECHNICAL REQU~IREMENT FOR OPERATION (TRO) APPLICABILITY
Title:
TEXT 3.1.1 0- 11/19/2002
Title:
REACTIVITYtONTRObL -SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION ,(ATWS"ARI) INSTRUMENTATION TEXT 3.1.2 . / 0 0/ 11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS* CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1.3 2 11/22/2005
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 6 04/03/2007
Title:
CORE OPERATING LIMITS CORE OPERATING LIMITS REPORT (COLR) eor ae 0/30 Pae1 of1 Page -1 of 15 Report Date: 04/03/07
SSES MANUJAL IManual Manual Name: TRM2
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 1 11/22/2004
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: 04/03/07 Page 22 of of 15
.15 Report Date: 04/03/07
SSES MANUAL
'Manual Manual Name: TRM2
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 TO 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
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN Page 3 of 15 Report Date: 04/03/07
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 1 04/26/2006
Title:
PLANT SYSTEMS FIRE HOSE STATIONS 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: 04/03/07 Page 44 of of 15 15 Report Date: 04/03/07
SSES MANUAL
'Manual Manual Name: TRM2
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: 04/03/07 Page 55 of of 15
.15 Report Date: 04/03/07
SSES MANUAL Manual Name: TRM2 S 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 0 11/19/2002
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: 04/03/07 Pagek Page 6 of of 15 Report Date: 04/03/07
SSES MANU1TAL Manual Namee: TRM2 b 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 Pae7 o 5RprtDt:0/30 Page 7 of .15 Report Date: 04/03/07
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 2 11/22/2005
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 Page 8 of 15 Report Date: 04/03/07
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 1 11/22/2004
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 Report Date: 04/03/07 Page 9 of of 15 15 Report Date: 04/03/07
SSES MANUAL
'Manual Manual Name: TRM2
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 0 11/19/2002
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 i__0 of 15 Report Date: 04/03/07
SSES MANJAL
'Manual Manual Name: TRM2
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 1 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
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION Page 11 of 15 Report Date: 04/03/07
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 (DG) 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: 04/03/07 Page 12
- 12. of of 15
.15 Report Date: 04/03/07
SSES MANUAL 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 0 11/19/2002
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 B311.1.5 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: 04/03/07 Page 13.
13 of of 15
.15 Report Date: 04/03/07
SSES MANUAL
'Manual Manual Name: TRM2
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 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 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: 04/03/07 Page 14 Page of of 15 15 Report Date: 04/03/07
SSES MANUAL
'Manual Manual Name: TRM2
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 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 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT 4.5 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS TEXT 4.6 09/27/2003
Title:
ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM TEXT 4.7 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS TRAINING Report Date: 04/03/07 Page 2~
Page 15 of of 15 15 Report Date: 04/03/07
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 32 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 I 2.0-4 06/25/2002 Page TRM / 2.0-5 04/12/1999 Pages TRM / 2.0-6 and TRM / 2.0-7 11/15/2004 Page TRM / 2.0-8 12/03/2004 Pages TRM / 2.0-9 through TRM / 2.0-11 11/15/2004 Pages TRM / 2.0-12 through TRM / 2.0-15 11/15/2005 3.0 APPLICABILITY Pages TRM / 3.0-1 and TRM / 3.0-2 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 3.1-6 08/31/1998 Pages TRM / 3.1-7 and TRMI 3.'1-8 11/15/2005 Pages TRM / 3.1-9 and TRM I 3.1-9 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 TRMI 3.2-22 through TRM / 3.2-48 03/08/2007 I 3.3 INSTRUMENTATION PageslTRM I,3.3-1 through TRM / 3.3-3 07/16/1999
{Page TRM I 3.3-4 03/31/2006 Pages 3)3-5 and 3.3-6 08/3111998 Page TRM 3.3-7 03/31/2006 Page 3.3-8 08/31/1998 Pages TRM / 3.3-9 and TRM I 3.3-9a 12/17/1998 Page TRM / 3.3-10 05/30/2006 Page TRM / 3.3-11 06/02/2005 Page TRM / 3.3-1 la 05/30/2006 Page TRM / 3.3-12 03/30/2001 Page TRM / 3.3-13 09/13/2005 Page TRM 1 3.3-14 12/14/1998 Page TRM / 3.3-15 10/22/2003, TRMILOES-1 EFFECTIVE DATE 03/08/2007 SUSQUEHANNA - UNIT SUSQUEHANNA - UNIT 2 2 TRM / LOES-1 EFFECTIVE DATE 03/08/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 32 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / 3.3-16 06/27/2001 Pages TRM I 3.3-17 and TRM / 3.3-18 06/14/2002 Pages TRM I 3.3-19 and TRM / 3.3-20 10/22/2003 Page TRM / 3.3-21 11/15/2004 Pages TRM /3.3-21a through TRM / 3.3-21d 11/15/2004 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 TRM / 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 I 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 I 3.7-17 03/31/2006 Page TRM / 3.7-18 08/02/1999 Page TRM I 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 03/08/2007 SUSQUEHANNA-UNIT2 SUSQUEHANNA - UNIT 2 TRM / LOES-2 EFFECTIVE DATE 03/08/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 32 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM I 3.7-29 11/16/2001 Page TRM / 3.7-30 11/30/2005 Page TRM I 3.7-31 11/16/2001 Page TRM / 3.7-32 01/09/2004 Page TRM I 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 I 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 I 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 I 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 08131/1998 3.10 MISCELLANEOUS Page TRM / 3.10-1 03/31/2006 Pages 3.10-2 through 3.10-4 08/30/1998 Page TRM 3.10-5 03/08/2003 Page TRM / 3.10-6 06/05/2002 Page TRM / 3.10-7 03/31/2006 Page TRM / 3.10-8 08/16/2006 SUSQUEHANNA - UNIT 2 TRM / LOES-3 EFFECTIVE DATE 03/08/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 32 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 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 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 TRM / LOES-4 EFFECTIVE DATE 03/08/2007 SUSQUEHANNA SUSQUEHANNA - UNIT
- UNIT 22 TRM / LOES-4 EFFECTIVE DATE 03/08/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 32 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 I 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 11/15/2005 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 I B 3.3-3 and TRM / B 3.3-3A 01/3112005 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 3.3-12 09/13/2005 Page TRM / B 3.3-13 12/03/2004 Page TRM / B 3.3-14 06/25/2002 Page TRM / B 3.3-14a 06/14/2002 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 / B 3.3-17 10/22/2003 Pages TRM / B 3.3-18 and TRM / B 3.3-19 11/115/2004 Pages TRM / B 3.3-19a through TRM / B 3.3.19e 11/1512004 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 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 TRM / LOES-5 EFFECTIVE DATE 03/08/2007 SUSQUEHANNA - UNIT SUSQUEHANNA -
UNIT 22 TRM / LOES-5 EFFECTIVE DATE 03/08/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 32 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / B 3.6-4 09/23/1999 Page TRM / B 3.6-5 01/07/2002 Page TRM / B 3.6-6 12/03/2004 Pages TRM / B 3.6-7 through TRM I 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 0810211999 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 3.7-1Oa through TRM / B 3.7-1 Ia 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 / 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 03/08/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 32 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 Pages B 3.10-1 through B 3.10-2 08/31/1998 Page TRM / B 3.10-3 03/08/2003 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 3.11-1 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 08/31/1998 Page TRM I 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 / 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 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 TRM2 text LOES.doc 3/612007 SUSQUEHANNA - UNIT 2 TRM / LOES-7 EFFECTIVE DATE 03/08/2007
Core Operating Limits Report (COLR)
PPL Rev. 6 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 / 3.2-1 EFFECTIVE DATE 8/31/1998
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 1 of 47 Susquehanna SES Unit 2 Cycle 14 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering March 2007 Ij
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ppI S I ,
~
4 SUSQUEHANNA UNIT 2 TRM/3.2-2 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 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.
FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 2 TRM/3.2-3 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 3 of 47 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 14 CORE OPERATING LIMITS REPORT Table of Contents 1.0 INTR O D UCT IO N ..................................................................................................... 4 2.0 DEFINITIO N S ..................................................................................................... 5 3.0 SHUTDOW N MARG IN............................................................................................ 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 (RBM) SETPOINTS AND OPERABILITY REQ UIR EM ENTS .................................................................................................. 29 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION ..................................... 31 9.0 POW ER / FLO W MAP ............................................................................................ 43 10.0 O PRM SETPO INTS ................................................................................................ 45 11.0 R E FE R E N C E S ............................................................................................................ 46 SUSQUEHANNA UNIT 2 TRM/3.2-4 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 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 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 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 LHGRFACf is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFACf multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbm/hr.
2.5 LHGRFACP is a multiplier applied to the LHGR limit when operating at less than 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 Monitor (OPRM) will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR safety limit is not violated.
2.9 Np is the OPRM setpoint for the number of consecutive confirmations of oscillation half-cycles that will be considered evidence of a stability related power oscillation.
2.10 Sp is the OPRM trip setpoint for the peak to average OPRM signal.
2.11 Fp is the core flow, in Mlbm / hr, below which the OPRM RPS trip is activated.
SUSQUEHANNA UNIT 2 TRM/3.2-6 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 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 (BOC) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirrement fror either 3.2.a or 3.2.b plus an adder, "R". The adder, "R", is the difference: between the calculated value of maximum core reactivity (that is, minimum SDM) during the operating cycle and the calculated BOC core reactivity. If the value of "R" is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOC measured value is required.
The SHUTDOWN MARGIN limits provided in 3.2a and 3.2b are applicable in MODES 1, 2, 3, 4, and 5. This includes core shuffling.
SUSQUEHANNA UNIT 2 TRM/3.2-7 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 7 of 47 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 Technical Specification Reference Technical Specification 3.2.1 4.2 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 DATE 03/08/2007
eP
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0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWDIMTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION ATRIUMTM-10 FUEL FIGURE 4.2-1
PPL Rev. 6 PL-NF-07-002 Rev. 0 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 (ATRIUMTM-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 5.2-1: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOC b) Main Turbine Bypass Inoperable / 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 TRM/3.2-10 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 10 of 47 5.3 Average Scram Time Fraction If the average measured scram times are greater than the Realistic Scram times listed in Table 5.3-1 then the MCPR operating limits corresponding to the Maximum Allowable Average Scram Insertion Time must be implemented.
Determining MCPR operating limits based on interpolation between scram insertion times is not permitted. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.
SUSQUEHANNA UNIT 2 TRM/3.2- 11 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 11 of 47 EOC-RPT and Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-12 EFFECTIVE DATE 03/08/2007
e e SSES UNIT 2 CYCLE 14 Q~ 2.2 LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES AREOPERABLE PER SR 3.7.6.1 AND 3.7.6.2 "E 1.8 USED IN DETERMINING MFLCPR
.03 S1.7 N3
- 0. (50,1.62)
Q 1.6 1.5
- (80.5,1.41) (0 ,.1 (108,1.41
-n m 1.4 B
REFERENCE:
T.S. 3.2.21 (86.3,1.37) (108,1.37)
CD) 1.3 m'
mo 1.2 N) 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) CDI (0 <
(D Z MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 0 EOC-RPT AND MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC) C4)
FIGURE 5.2-1
e e e SSES UNIT 2 CYCLE 14 3.5 I I I 3.4 LEGEND C/'
3.3 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM (25,3.15) TIME (INSERTION 3.2 3.1 (30,2.94) CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME N) 3.0 - I I I I L
2.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.8 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.7 E USED IN DETERMINING MFLCPR/
2.6
.- J I-2.5 N) 0.
2.4 0 2.3 0.
W 2.2 2.1 2.0 1.9
-n V' (40,1.76) ¶ 1.8 + t 1~
1.7 " A -.. I T T (40,1.68) 1.6 & _________
B
IREFERENCE:
T.S. 3.2.21 - (80,1.47)
I (100,1.41) 1.5 I.
(65,1.56)-
CD) (100,1.37)
I I 1.4 I (85,1.44)
II n - ____________
1.3 !. 6 ___________
co) 50 60 70 80 90 100 20 30 40 NJ Core Power (% RATED) (0<
CD CD '
CA)
MCPR OPERATING LIMIT VERSUS CORE POWER 0
EOC-RPT AND MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC) -4 FIGURE 5.2-2
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 14 of 47 Main Turbine Bypass Inoperable I EOC-RPT Operable SUSQUEHANNA UNIT 2 TRM/3.2- 15 EFFECTIVE DATE 03/08/2,007
0 c/) SSES UNIT 2 CYCLE 14 2.3 V)
D A: MAXIMUM ALLOWABLE AVERAGE SCRAM 2.2 INSERTION TIME 2.1 4-I[: - 1 111-' B: REALISTIC AVERAGE SCRAM INSERTION TIME
-(30,1.98)
K 2.0 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
---q 1.9 (50,1.87)
,-J USED IN DETERMINING MFLCPR 0)
C S1.8 0.
CY)
. 1.7 1.6 A B m (81.8,1.58) (108,1.58) 1.5 m
C:) 1.4
REFERENCE:
T.S. 3.7.6 and 3.2.21___________
0H Nm 1.3 40 50 60 70 80 90 100 110 30 Total Core Flow (MLBIHR) (D (D 0
(0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-3
e e SSES UNIT 2 CYCLE 14 3.5
______ LEGEND:
3.4 3.3 (25,3.34) CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM NJ~
3.2 INSERTION TIME 3.1 (30,2.94) CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 2.9 2.8 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
- 2.7 E
D2.6
_USED IN DETERMINING MFLCPR 2.5 2.4 0.
0 2.3
.2.2 2.1 2.0 1.9 m-n 1.8
_n m (40,1.8 1) A 1.7 _ _ __ _ _ - B_ ---. __ _ _ _(100,1.58) 1.6 (72.9,1.58)
]
REFERENCE:
T.S. 3.7.6 and 3.2.2 m 1.5 S(72.9,1.58)
CD 1.4 1.3 CD 90 100 40 50 60 70 80 20 30 N) Core Power (% RATED) ~1CD Co<
CD '
MCPR OPERATING 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. 6 PL-NF-07-002 Rev. 0 Page 17 of 47 EOC-RPT Inoperable /
Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-18 EFFECTIVE DATE 03/08/2007
U SSES UNIT 2 CYCLE 14 2.2 T I D
_-H 2.1 4 4 A: MAXIMUM ALLOWABLE AVERAGE SCRAM Fn INSERTION TIME 2.0 ¶ B: REALISTIC AVERAGE SCRAM INSERTION TIME q
1.9 4 J.
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
"*1.8 4 -~ 1.
USED IN DETERMINING MFLCPR I c~)
(30,1.7)
N) 4 1.7 I.
0 1l.6 (50,1.62)
- 1.5 m
1.4 180.5,1.41) (108,1.41)
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 1.3 N~)
1.2 50 60 70 80 90 100 110 30 40 T ca I-C=) Total Core Flow (MLBIHR) T) <
(D Z MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 0 EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC) -4 rQ FIGURE 5.2-5
U U 6 V) SSES UNIT 2 CYCLE 14 cU) 3.5 -- I I I mT~ 3.4 LEGEND 3.3 (25,3.15)_ CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM D> 3.2 INSERTION TIME 3.1 (09
-(30,2.94)-- CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 2.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.8 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
.4t 2.7 E
2.6 CA) Z) USED IN DETERMINING MFLCPR 2.5 CL N.) 2.4 CD 0 W. 2.3 0L 2.2 2.1 2.0 1.9 mm
-T 1.8 m
1.7 (40,1.76) A
-H 1.6 B F
REFERENCE:
T.S. 3.3.4.1 and 3.2.21 _
m 1.5 (100,1.41) 1.4 7(80,1.47) 1.3 70 80 90 100 co 20 30 40 50 60 N) Core Power (% RATED) (~<
(1- Z MCPR OPERATING LIMIT VERSUS CORE POWER (0 0 EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE 4-1 4~
TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-6
PPL Rev. 6 PL-NF-07-002 Rev. 0 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 0.630 0.860 25 1.500 1.910 5 2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 2 TRM/3.2-21 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 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 ATRIUM TM-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 I 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 limit multipliers in Figures 6.2-1 through 6.2-5 are valid for both Two Loop and Single Loop operation.
SUSQUEHANNA UNIT 2 TRM/3.2-22 EFFECTIVE DATE 03/08/2007
V)16 1SSES UNIT 2 CYCLE 14 m
.o I o * *O* e
- h e
- . , , I ,, I I 14.0,130.4.4- -----------------
REFERENCE:
T.S. 3.2.3--
.) . USED IN DETERMINING FDLRX[
" ",." ;.. . . ... -; '. . . .* . . . ................ . ; 2"---.. .-------- ' , " ' ' CF")""
Z °','...
N) .2 10 1, ~ '....... ... . ..... * :
CD W
-º ' " " '. ' ' ... . . ' . ' ".N ' ; ." .- r * - . .. '. U.E D.E M N G D R CD':
........... ... . 4..0.-
C.4 CD
.9 0 10000 20000 30000 40000 50000 60000 70000 80000 N)Pellet Exposure (MWDIMTU) WC r LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE m 6 TM 0 ATRIU -0 FUEL 0.
FIGURE 6.2-1
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 23 of 47 Main Turbine Bypass Operable /
EOC-RPT Operable and Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-24 EFFECTIVE DATE 03/08/2007
U 4 V) SSES UNIT 2 CYCLE 14 (V)
.1.10 1.00 (90,1.00) (10.8,1.00) 0.90 (3,.0 (6,080
- ............ ........... .......... IIII ..... .
.......................... .. . .......... a..............
75 W 0.80 . a.
- ... *... . . ... a ... a.. .. .. ... a......a..... . ...... j.............
Ca 5- 0.70 a a a a a a a a a a a a a a a a a a a a* a a a a a a a a a a a a a a a a a a a a a a a a 0 a a a a a a a a a a a a ANALYSES ASSUME THAT FOUR BYPASS VALVES a a a
. . ... .SAFETY a aARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.60
REFERENCE:
T.S. 3.2.3 and 3.7.6 CD) a a a a a UED IN~ DETERMINING FDLRX a a
-4
~0.40- I I I I I I ,,i .
0 40 50 60 70 80 90 100 110 Total Core Flow (MLB/hr) CD (0<
CD " Z C) C FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS OPERABLE 0
-10 FUEL 4 o ATRIUM FIGURE 6.2-2
C/)
1SSES UNIT 2 CYCLE 14 1.00 - ................. L ..... ------- .......
CL I a
. ., USE IN ETEMINNGoDLR 0.8
.0.60 L .. .... I .... I. .....
- A.. ... o ..... .....
. J -- -- J..... ......
ih DETER
. .. . ININ a.....
r -- - - ---
4,07) y ---- -----... 1 . .1"l SAFETY 1 - - 1 ANALYSES
.. 11.... ..... .
ASSUME
° I. . ..... I.a THAT FOUR .....
BYPASS.. ......
VALVES
..... C M 0.5 - -----...
a a , a a a a a a C0 FERENCE: . 3 . . T.S. . . . . ", .and 3.2.3 . . . .3.7.6
. . . ; . . . i . . . . IR....
. . . . . . . . I ' ' , . . . . . , .,. . . . . . . .
0 0 .9 (25,0.42).. .. (30,0.46)........... ....
0.40 50 60 70 80 9.0 100 co 20 30 40 r9 ~~Core Power (% RATED)WCDr CDCD Z POWER DEPENDENT LHGR LIMIT MULTIPLIER 6.1 MAIN TURBINE BYPASS OPERABLE0 ATRI-U"Mi0 FUEL C FIGURE 6.2-3
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 26 of 47 Main Turbine Bypass Inoperable I EOC-RPT Operable and Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-27 EFFECTIVE DATE 03/08/2007
SSES UNIT 2 CYCLE 14
~I.Iu * ' I Si I i S
i i
I I
i I
S S
i
- SIi m
- I . i I i . . . .
I i i
S i S
- , S i i I I S S i S S I S i S I S I S
- I I 1.00
-.- ........ (90,1.0 0) (1 0 8,1.0 0) 0.90 . .*......*.....
L.
0.
4.,
2))
3: n,0.80
. . . SAFETY
. ANALYSES 1-ASSUME - - - - - -I - -
THAT TWO OR MORE BYPASS
- i S I i i i I VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 S S i I I S I 0.7 0.70 I S I I i S i I S S S i I S co
... .. ~~~~~~
. . . . .. . ; . ... . . . . .. ~~~
REFERENCE:
T.S....- 3.2.3 and;.... 3.7.6
.(007) .. (5,.0 I i
... I i i S i S i
- i 0
- II I S S S S S
- I I I I S -&-&
S I " I I I S
.8. ... s USEDI IN DETERMINING I FDLRX 0.60
- I-A S-I J..8
- * ~~ - S - - - - iA ISI I S m
-n
-'r m
0.50
.S . . . . .
. I . .i I .
- i I m
c0.40 30 40 50 60 70 80 90 100 110 co Total Core Flow (MLB/HR) E CD (o <
CD~ '
N) C 0 FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE 0 ATRIUMTM-10 FUEL 4 N)
FIGURE 6.2-4
(_ SSES UNIT 2 CYCLE 14
,* I.IU 1.00 l i.9 (i
--. 9 ... ..... ..... ..... ..... . I..... 1..... ...... ..... .....
. . I........
I...... ...
(250 ...... 2 --... ... - .....
...-.. ) .. .-..... .-......... .....
0.90-AR INPRAL PE SR 3... OR 3.7.6.2 VAVE
.... . -. - - -..- ..-... ----- a.
' ..-- ...--- SAEYAAYE
...--....--- ASSUME THAT- TWOi OR MOR BYAS -
S 0.80 ----------------------------
G) 0.70 (25,0.2).0,0(100------- .. ..
0 0.60 "r-i
-nI
-n 0.50 r--
m 0.40 40 50 60 70 80 90 100 021 0 30 N) Core Power (% RATED) W C r-(0 <
CD CD
- N c) -n POWER DEPENDENT LHGR LIMIT MULTIPLIER 0 -,
MAIN TURBINE BYPASS INOPERABLE ATRIUMTM-10 FUEL - C
-4 FIGURE 6.2-5
PPL Rev. 6 PL-NF-07-002 Rev. 0 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 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 30 of 47 Table 7.2-1 RBM Setpoints Allowable Nominal Trip Function Value(') 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 MCPR (2.3)
(% of Rated)
>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 TRM/3.2-31 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 31 of 47 8.0 RECIRCULATJON 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 ATRIUMTM-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1.
The APLHGR limits in Figure 8.2-1 are valid for Main Turbine Bypass Operable and Inoperable 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 (ATRIUMTM-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 BOC to EOC Figure 8.2-3: Power-Dependent MCPR value determined from BOC to EOC b) Main Turbine Bypass Inoperable I 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 SUSQUEHANNA UNIT 2 TRM/3.2-32 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 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 TRM/3.2-33 EFFECTIVE DATE 03/08/2007
e SSES UNIT 2 CYCLE 14 16 m
REFERENCE T.S. 3.4.1 and Il2'.
M-1 14 -~~~~~~~~ . .== , . . . . .n - o. . .i - . ..
]
., . .= . . . .p .
I, N) USED IN DETERMINING MAPRAT V
~12 E
0.4 w.2i0o w"
cc i = , t = = i :67000,5.6l l
8.
m 6
C=)
4 40000 50000 60000 70000 0 10000 20000 30000 NJ Average Planar Exposure (MWD/MTU) W~ CD~
(0 <
CD '
-n AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE wc)
SINGLE LOOP OPERATION -~0 14 N ATRIUMTM-10 FUEL FIGURE 8.2-1
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 34 of 47 EOC-RPT and Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-35 EFFECTIVE DATE 03/08/2007
U SSES UNIT 2 CYCLE 14 2.3 I LEGEND cri CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.2 -(30,2.18) 4 4 4-CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
_ _ I _/_ . ......
2.1 t -
- E L SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 (50,2.08)
'4- *1II ~ 1.
N.) 2 2.0 USED IN DETERMINING MFLCPR
- 0. 4 a-(3.
1.9 P1 (108,1.81) m B A-71 1.8 FRE: T 34. an-(80.5,1.81)-
IREFERENCE:
T.S. 3.4.1 and 3.2.2 C-D 1.7 cz) 110 co 30 40 50 60 70 80 90 100 CDI Total Core Flow (MLBIHR)
(D c--i c) _
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 0
EOC-RPT AND MAIN TURBINE BYPASS OPERABLE 0 0
SINGLE LOOP OPERATION (BOC to EOC) -4 N)
FIGURE 8.2-2
U SSES UNIT 2 CYCLE 14 U-)
4.1 -(25,4.01)
I .
m LEGEND 3.9 (30,3.74) CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM MH INSERTION TIME 3.7 CURVE B: REALISTIC AVERAGE SCRAM TIME N) 3.5 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 3.3 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 E I I
-J 3.1 I + 4 -.------ I USED IN DETERMINING MFLCPR P 1 1 N) 2.9 U) 0.
0
.2.7 2.
2.5 2.3 4 (40,2.26) 9 I~ .r I
-n 9 L .
2.1 _______________ .4 .4 (76,1.93)
(100,1.93) m CA-)
1.9
REFERENCE:
T.S. 3.4.1 and 3.2.2 1.7 N) 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
Nz) a)
(0 CD MCPR OPERATING LIMIT VERSUS CORE POWER hD C)n EOC-RPT AND MAIN TURBINE BYPASS OPERABLE 6O SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-3
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 37 of 47 Main Turbine Bypass Inoperable / EOC-RPT Operable SUSQUEHANNA UNIT 2 TRM/3.2-38 EFFECTIVE DATE 03/08/2007
9 V SSES UNIT 2 CYCLE 14 2.6 -I I I
(30,2.53) LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 2.5
,,, Ii INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME N.) 2.4 (50,2.39)
SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS E 2.3 -
m IN VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
-71 Jm
- 4. 1 N Kr USED IN DETERMINING MFLCPR 2.2 1.
N%
c:)
L 2.1 4 4- -4.
N B _____________ +
(108,2.03)
(120 A L-I (81.8,2.03)-
- 4. -4 co) 2.0
- 4 N.)
CD 1.9 --
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 I I-1.8 _________ I 70 80 90 100 110 30 40 50 60
-u CD r-Total Core Flow (MLBIHR)
CD 6
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW o 0
MAIN TURBINE BYPASS INOPERABLE / EOC-RPT OPERABLE 0--
N N.
SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-4
..... li I Im A A* I A m m
- C SSES UNIT 2 CYCLE 14
__ 4.3 (25,4.25 LEGEND 4.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.9 INSERTION TIME
-H (30,3.74) CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.7 3.5 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 3 3
-J I USED IN DETERMINING MFLCPR (D "
.- 3.0- C 0g2.9 O- 279 2.5 2.3 (40,2.'32)- ,m'Q" B '
mB 2.1 kA __(100,2.03)
_*>~ 1.9--
1 (72.9,2.03) m .
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 1.7 40 50 60 70 80 90 100 20 30 Core Power (% RATED) 0 "D rQ (<Z
-n MCPR OPERATING LIMIT VERSUS CORE POWER 6
/IEOC-RPT OPERABLE MAIN TURBINE BYPASS INOPERABLE 0 SINGLE LOOP OPERATION (BOC to EOC) 4 )
FIGURE 8.2-5
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 40 of 47 EOC-RPT Inoperable I Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-41 EFFECTIVE DATE 03/08/2007
e e e SSES UNIT 2 CYCLE 14 CZ) 2.3 I M LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM VI I INSERTION TIME 2.2 12 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
- 2.0 2.1 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 0 .2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 (50,2.08) I i I 1.9
- 0) USED IN DETERMINING MFLCPR L.
1.9 .1~-
(108,1.81)
B A m
1.8 3.41,3.3.41,and3(80.5,1.21).2
REFERENCE:
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 m
CD) 00 1.7 50 60 70 80 90 100 110 30 40 Total Core Flow (MLBIHR) (0<
(D - Z 0 -n MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW -6 EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE -h
1 U V,)
SSES UNIT 2 CYCLE 14 4.1 -(25,4.01)
I I I I LEGEND 3.9 Nm (30,3.74) CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.7 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.5 I
3.3 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES E ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
-- 3.1 2.9 F. USED INDETERMINING MFLCPR 0.
cl)
(L 2.7 L) 2.5 4- ,(40,2.26) 1 4. 4.
m 2.3 m
Cm 4 1 m 2.1 I J.
(100, 1.93) m 1.9 I I I
IREFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 (76,1.93)
-1 1.7 7 7. 4 90 1010 30 40 50 60 70 80 co 20 Core Power (% RATED)
--j MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-7
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 43 of 47 9.0 POWER I 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 inoperable per TS 3.3.1.1, Region I of the Power I Flow map is considered an immediate scram region.
Region II of the Power / Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation.
SUSQUEHANNA UNIT 2 TRM/3.2-44 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 44 of 47 120 120
- ====== ;--.,.*UNIT 2 Tri Stpont POWER I FLOW MAP
]Initial
Purpose:
ARM Rod Block 110- 110
/ Date: I Trip Setpoint RESTRICTED REGION STABILITY REGION I IF OPRM INOPERABLE IMMEDIATE
+ Iý.-- - - t I SCRAM lAW ON-278-002 100. MELILL 100 IF OPRM OPERABLE IMMEDIATE Boundar EXIT lAW ON-27-.002 BMTAILITY REGION 11 MMFDIATELY EXIT lAWON-278-002 *,
I ll 90 RESTRICTED REGION 4_L 90
[As defined In Attachment G to NDAP-*A0338) M
.i:F A80VE MELLLA BOUNDARY, MMEDIATELY EXITLAWON-27"02 80 80 a'
LU 70-j Lj j L
I.
IT- I I
+
T I
F T -I I I I ji F
II
~I.-
I 4-I I I I I 'U lU A
T -T 1- T I -I -I- T I -I -I- -WI- IL L I L -t -j 60 I 1 1 _
I j j
-~ ~j7 60 LI -I __ L _JL . -L -- L III I I II L I J-j j i ý-t-I 1 1-r 1 1-1 I - I
,-ti ,~ ~ One , mp ,--,---,-,--,
I
-- r, III I- 11z - -, '1"1-i 0140,10-A-pr-50 50 I I I One Pum --
i J -I- -Spe
-7 41 11 1 , :80-11 .,60 ij_70 ij_80_-ii_90 Li.IO0 i-i K2.,
40 Natural Circulation Line Ell 40 L Ij I I II 30 Approx 30 J One Pump - L 1 4 1-I I 1 30% Speed. III' T, r i -j- - r I - r 7 1 fl -
I L I I I 3Jl
_L. I :: - I J, I I I 20 I Approx 20 Two Pump 4 1-30% Speed. j
+
T I
L I j J TT4- - 1 - I 10 I T I 10 L1.* I I L I J _I-0 I I I . I I , ; . 6"4144*44419*4W1ý1i'* . I I i I I i I 1 0 0 10 20 30 40 50 60 70 80 90 100 110 Total Core Flow (Mlbmlhr)
(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 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 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
= 16 S 60 Mlbm / hr SUSQUEHANNA UNIT 2 TRM/3.2-46 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 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 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984.
- 2. EMF-2361 (P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model,"
Framatome ANP, May 2001.
- 3. EMF-2292(P)(A), Revision 0, "ATRIUM TM-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.
- 4. XN-NF-84-105(P)(A), Volume 1 and Volume 1 Supplements 1 and 2, "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," Exxon Nuclear Company, February 1987.
- 5. XN-NF-80-19(P)(A), Volume 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(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," Exxon Nuclear Company, September 1982.
- 7. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987.
- 8. XN-NF-80-19(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, June 1986.
- 9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc.,
September 1986.
- 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 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 47 of 47
- 12. ANF-89-98(P)(A) Revision 1 and Supplement 1,."Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995'
- 13. EMF-2209(P)(A), Revision 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 LEFMITM System," Engineering Report - 80P, March 1997.
- 15. Caldon, Inc., "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFMITM or LEFM CheckPlusTM System," Revision 0, Engineering Report ER-1 60P, 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 Applications," 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 03/08/2007