ML071140101
| ML071140101 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/11/2007 |
| From: | Susquehanna |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| 028401, 2007-14744 | |
| Download: ML071140101 (29) | |
Text
Apr. 11, 2007 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2007-14744 USER INFORMAT G XACH*R M EMPL#:028401 CA#: 0363 Addres CSA2 Pho : 2 194 SMITTAL INFORMATION:
TO: 04/11/2007 LOCATION: rUSNRC 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:
ADD MANUAL TABLE OF CONTENTS DATE:
CATEGORY: DOCUMENTS TYPE: TRM2
ýOc) I
Apr. 11, 2007 Page 2 of 2 ID: TEXT B3.1.3 REMOVE: REV:2 ADD: REV: 3 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT B3.10.2 REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT B3.3.9 REMOVE: REV:1 ADD: REV: 2 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: 0 4/10/2007 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 33 04/09/2007
Title:
LIST OF EF]FECTIVE SECT 'IONS TEXT TOC 9 *12/14/2006
Title:
TABLE OF CONTENTS TEXT 1.1 0 11/19/2002 K>
/
Title:
USE AND APPLICATION DEFINITIONS K
/N.
TEXT 2.1 02/04/2005
Title:
PLANT PROGRAMS AND SETPOINTS PLANT PROGRAMS.
TEXT 2.2 6 04/09/2,007,
Title:
PLANT PROGRAMS AND SETPOINTS INSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 2 01/29/2007
Title:
APPLICABILITY TECHNICAL\REQUIREMENT
... K\ .. FOR OPERATION (TRO) APPLICABILITY TEXT 3.1.1 0 11/19/2002
Title:
REACTIVITYCONTROLSYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION ý(ATWS"--ARI)" INSTRUMENTATION TEXT 3.1.2 7 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 6 04/0.3/2007
Title:
CORE OPERATING LIMITS CORE OPERATING LIMITS REPORT (COLR)
Report Date: 04/10/07.
Page 11 of of 15 15 Report Date: 04/10/07
SSES MANUAL
'Manual 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 O TEXT 3.3.6
Title:
INSTRUMENTATION 2 10/19/2005 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 ATitle: REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY Report Date: 04/10/07 Page 2 2 of of 15
.15 Report Date: 04/10/07
SSES MANUJAL 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 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 i1/19/2002
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN Report Date: 04/10/07 Page 33 Page of of 15 15 Report Date: 04/10/07
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: 04/10/07 Page 44 of of 15 15 Report Date: 04/10/07
SSES MANUAL 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: 04/10/07 PageS5 Page of of i~
15 Report Date: 04/10/07
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:
MISCELLANEOUSINDEPENDENT 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: 04/10/07 Page 66 of 15
.15 Report Date: 04/10/07
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: 04/10/07 Page 77 of of 15 15 Report Date: 04/10/07
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 Page 8 of 15 Report Date: 04/10/07
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.3.4 2 06/1.3/2006
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 Page9 of 15 Report Date: 04/10/07
SSES MANUAL 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 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 eotDt:0/00 Pae1 f1 Page 10 of 15 Report Date: 04/10/07
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.3.3 0 11/19/2002
Title:
PLANT SYSTEMS BASES 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 Report Date: 04/10/07 11 Page 11 of of 15 15 Report Date: 04/10/07
SSES MANTJAL 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: 04/10/07 12 Page 12 of of 15 15 Report Date: 04/10/07
SSES M4ANUAL O
Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.9.2 0 11/19/2002
Title:
ASES COMMUNICATIONS REFUELING OPEl RATIONS B.
TEXT B3.9.3 0 11/19/2002
Title:
REFUELING OPElRATIONS B.ASES 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: 04/10/07 Pagel3 Page 13 of
' of 15.
15 Report Date: 04/10/07
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.11.2.2 0 .11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES TEXT B3.11.2.3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATES FORM TEXT B3.11.2.4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.11.2.5 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: 04/10/07 Page 14 14 of of 15 15 Report Date: 04/10/07
SSES MANUAL Manual Name: TRM2 Manual
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 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM TEXT 4.7 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS TRAINING eotDt:0/00 Pae1 f1 Page 15 of 15 Report Date: 04/10/07
Control Rod Block Instrumentation PPL Rev. 3 B 3.1.3 B 3.1.3Control Rod Block Instrumentation BASES TRO The Control Rod Block Instrumentation is a portion of the Reactor Manual Control System (RMCS), which upon receipt of input signals from other systems and subsystems, inhibits movement or selection of control rods (Reference 1).
The purpose of the Control Rod Block function is to avoid conditions that would require Reactor Protection System (RPS) action if allowed to proceed.
The specific Functions associated with the TRM Control Rod Block Instrumentation are identified in Table 3.1.3-1 and are discussed below.
- 1. Average Power Range Monitors (APRM)
- 2. Source Range Monitors (SRM)
The same grouping of neutron monitoring equipment (SRM and IRM) that is used in the RPS is also used in the rod block circuitry. Half of the total monitors (SRM and IRM) provide inputs to one of the two RMCS rod block logic circuits and the remaining half provide inputs to the other RMCS rod block circuit.
Reference APRM Flux level input to the RMCS is through the rod block monitor.
A signal from one of the four redundant APRM channels supplies a reference signal for one of the RBM channels and a signal from another of the APRM channels supplies the reference signal to the second RBM channel. The RBM interfaces to the RMCS to determine rod selection conditions.
The APRM rod block settings are varied as a function of Reactor Coolant System (RCS) recirculation flow. The settings are selected so that all the neutron monitoring rod blocks are sufficient to avoid an RPS action. Mechanical switches in the SRM and IRM detector drive systems provide the position signals used to indicate that a detector is not fully inserted.
The SRM minimum count rate Allowable Value is discussed in the TS Bases for SR 3.3.1.2.4.
- 4. Scram Discharge Volume Water Level - High Scram Discharge Volume Water Level - High signals are provided as inputs into both rod block logic circuits. Both rod block logic circuits sense when the high water level scram trip for the Scram Discharge Volume is bypassed. The rod block from Scram Discharge Volume Water Level - High comes from one of two float type level switches installed in each of two scram discharge instrument volumes. The second float switch in each instrument volume provides a control room annunciation of increasing level below the level at which a rod block occurs.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.1-5 EFFECTIVE DATE 03/27/2007
Control Rod Block Instrumentation PPL Rev. 3 B 3.1.3 B 3.1.3 Control Rod Block Instrumentation BASES TRO 5. RCS Recirculation Flow (continued)
The recirculation flow system consists of four separate transmitters on each of two recirculation loops (eight total). The transmitter output signal from one flow channel is routed to one of four APRM channels. Each APRM processes and sums the transmitters signals. Each APRM then sends its total flow signal to both RBMs. Each RBM then compares the four flows and issues Alarms based on user entered values. Both RBM channels are identical, but are configured to support either RBM channel A or channel B.
With the NUMAC PRNMS system, the Upscale flow function is performed within the APRM and sent on to the reactor manual control system. Flow comparison is performed within the RBM but is processed as an alarm only since the RBM rod block functions are power and not flow dependent.
Recirculation flow inputs for system 'inop' functions are processed as part of the APRM 'Upscale/Inop' function.
ACTIONS The ACTIONS are defined to ensure proper corrective measures are taken in response to the inoperable components.
TRS The TRSs are performed at the specified Frequency to ensure that the Control Rod Block Function is maintained OPERABLE.
TRS 3.1.3.1, TRS 3.1.3.2, TRS 3.1.3.3, TRS 3.1.3.4, TRS 3.1.3.5, TRS 3.1.3.6, and TRS 3.1.3.7 Control Rod Block Instrumentation surveillances are performed consistent with the Bases for the comparable channels in LCO 3.3.1.1 and LCO 3.3.1.2.
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SUSQUEHANNA - UNIT 2 TRM / B 3.1-6 EFFECTIVE DATE 03/27/2007
Control Rod Block Instrumentation PPL Rev. 3 B 3.1.3 B 3.1.3 Control Rod Block Instrumentation BASES (continued)
REFERENCE 1. FSAR Section 7.7.1
- 2. NEDC-32410P-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option III Stability Trip Function" SUSQUEHANNA - UNIT 2 TRM / B 3.1-7 EFFECTIVE DATE 03/27/2007
OPRM Instrumentation PPL Rev. 2 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRO The OPRM system configuration governs its operation in accordance with the licensing analysis. Several configuration parameters are intrinsic to the trip function safety setpoint bases or provide settings for defense-in-depth algorithm features that are not assumed in the basis for the protection system safety analysis (Reference 2, Reference 3).
Each of the setting values may be used as the process setpoint or device setting without further adjustment for uncertainties.
Setpoints and Settinqs Bases TOL(r.) Period Tolerance The specified range of values for the period tolerance has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability. A range of values is provided to allow system tuning to avoid spurious alarms on period confirmations. Limiting the setpoint adjustment range provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability.
L Conditioning Filter Cutoff Frequency The specified value for the Conditioning Filter Cutoff Frequency has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability. Setting minimizes impact on signal amplitude and provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability.
Tmin Oscillation Period Lower Time Limit Tmax Oscillation Period Upper Time Limit The Oscillation Period Time Limit parameters establish the range of detectable oscillation periods of OPRM cell signals for signal oscillations associated with reactor core thermal-hydraulic instability.
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SUSQUEHANNA - UNIT 2 TRM / B 3.3-18 EFFECTIVE DATE 03/27/2007
OPRM Instrumentation PPL Rev. 2 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRO LPRMmi, (continued)
This value determines the availability and resulting sensitivity of cells in the reactor core in the event of LPRM channel failures. The minimum LPRM per cell parameter is an assumption of the OPRM trip setpoint (Sp) basis calculation.
Amplitude and Growth Rate Based Alqorithm Parameters S1 Peak Threshold Setpoint/ABA & GRBA S2 Valley Threshold Setpoint/ABA & GRBA Smax Amplitude Trip Setpoint/ABA DR3 Growth Rate Factor Setpoint/GRBA These parameters calibrate the Amplitude and Growth Rate Based Algorithm, described in References 2 and 3, which provides an OPRM trip output to the Reactor Protection System. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algorithm.
The algorithm is provided as a defense-in-depth feature in the event of unanticipated power oscillations. These Amplitude and Growth Rate Based Algorithm Parameters are considered sufficient to provide backup protection and to avoid spurious trips by maximizing margin to expected operating conditions and transients.
ACTIONS The required actions assure that the system settings that support the Period Based Algorithm setpoint analysis, and those parameters that define the Amplitude and Growth Rate Based Algorithm are returned in a timely manner to the values assumed in the analysis (Reference 2, Reference 3) or that the affected channel is declared inoperable and the applicable Required Action of LCO 3.3.1.1 is then entered, or an alternate method to detect and suppress thermal hydraulic instability oscillations is employed.
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SUSQUEHANNA - UNIT 2 TRM / B 3.3-19 EFFECTIVE DATE 03/27/2007
OPRM Instrumentation PPL Rev. 2 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS Note 1 has been provided to modify the ACTIONS related to affected OPRM (continued) channels. Technical Specification Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits will not result in separate entry into the Condition. Technical Specification Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for affected OPRM channels provide appropriate compensatory measures. As such, a Note has been provided that allows separate Condition entry for each affected OPRM channel.
B. 1 Several parameter settings are essential for the proper operation of the OPRM period-based trip algorithm. The permissible values of Period Confirmation Tolerance, Averaging Filter time constant, Conditioning Filter Cutoff Frequency, and minimum operable LPRM per cell parameters are limited by the setpoint basis calculations and system transient response analysis. The Minimum and Maximum Oscillation Period settings limit the algorithm window to the cell signal resonances that can be associated with unstable thermal-hydraulic conditions.
Because the ability of the OPRM channel to perform its safety function is affected by these parameter settings, the affected OPRM channel must be considered inoperable when these conditions are not met.
Operability is evaluated for each inoperable channel and Required Actions taken in accordance with LCO 3.3.1.1.
C.1 The design objective for the Amplitude and Growth Rate Based Algorithms is to provide automatic action to limit the size of these unanticipated oscillations, thereby preventing fuel cladding damage. Several parameter settings define the function of the Amplitude and Growth Rate Based Algorithm. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algqrithm, which is provided as a defense-in-depth feature in the event of unanticipated oscillations.
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SUSQUEHANNA - UNIT 2 TRM / B 3.3-19a EFFECTIVE DATE 03/27/2007
OPRM Instrumentation PPL Rev. 2 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS C.1 (continued)
Because the ability of the OPRM channel to perform its safety function is not affected by these parameter settings, the affected OPRM channel need not be immediately considered inoperable when these conditions are not met.
These parameters are to be maintained for conformance with the licensing requirement of a defense-in-depth feature in addition to the licensed OPRM trip function. This is corrected by returning the parameters to conformance within 120 days of identification.
Since the Amplitude and Growth Rate Based parameters affect only the defense-in-depth response within each channel, failure to maintain the proper parameters in the channel affects only the operability of that channel.
D.1 This Action is to be taken if the Period Based Detection Algorithm trip function is not available in accordance with LCO 3.3.1.1, and initiation of an alternate method to Detect and Suppress thermal hydraulic instability oscillations is required by the referenced LCO Required Actions. The applicable Conditions are entered as required.
E.1 As directed from Required Action D.1, this Action provides preemptive protection through Power/Flow Map operating restrictions.
When operating in Region I of the Power / Flow map specified in the COLR, or when operating in Region II of the Power / Flow map specified in the COLR with less than 50% of the required LPRM upscale alarms OPERABLE, the potential for thermal-hydraulic oscillations is greatly increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. Therefore, the reactor mode switch must be immediately placed in the shutdown position. Action is taken immediately to place the plant in a condition where any potential for thermal-hydraulic instabilities will be terminated.
Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/
alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors including PICSY.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.3-19b EFFECTIVE DATE 03/27/2007
OPRM Instrumentation PPL Rev. 2 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS F.1 (continued)
As directed from Required Action D.1, this Action provides guidance for Operator action in response to thermal-hydraulic instability oscillations.
When operating in Region II of the Power/Flow map specified in the COLR immediate response is necessary when there are indications that thermal hydraulic oscillations are occurring as defined in the CONDITION.
LPRM upscale alarms are required to detect reactor core thermal-hydraulic instability events. The criteria for determining which LPRM upscale alarms are required is based on assignment of these alarms to designated core zones. These core zones consist of the level A, B, and C alarms in 4 or 5 adjacent LPRM strings. The number and location of LPRM strings in each zone assure that with 50% or more of the associated LPRM upscale alarms OPERABLE sufficient monitoring capability is available to detect core wide and regional oscillations. Operating plant instability data is used to determine the specific LPRM strings assigned to each zone.
Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/
alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors including PICSY.
G.1 As directed from Required Action D.1, this Action provides guidance for Operator action in response to operation in conditions that may lead to thermal-hydraulic instability oscillations.
When operating in Region II of the Power/Flow map specified in the COLR, the potential for thermal-hydraulic oscillations is increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. Therefore, action must be initiated immediately to restore operation outside of Regions II of the Power/Flow map specified in the COLR. This can be accomplished by either decreasing THERMAL POWER with control rod insertion or increasing core flow by increasing recirculation pump speed. The starting of a recirculation pump will not be used as a means to exit the excluded Regions because the starting of a recirculation pump with the plant operating above the 80% rod line is prohibited due to potential instability problems.
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SUSQUEHANNA - UNIT 2 TRM / B 3.3-19c EFFECTIVE DATE 03/27/2007
OPRM Instrumentation PPL Rev. 2 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS H.1 (continued)
The LPRMs provide a capability to monitor power in selected locations of the reactor core. The LPRM Upscale Alarm Instrumentation provides information concerning local power oscillations. Condition F requires a reactor scram when operating in Region II of the Power/Flow map specified in the COLR with indications that thermal hydraulic oscillations are occurring. The number and location of LPRM strings in each zone assures that with 50% or more of the associated LPRM upscale alarms OPERABLE any power oscillations which could occur would be detected and proper actions can be taken.
Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/
alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors including PICSY.
A sign is posted in the Control Room to ensure that plant operators are aware of the system condition if a plant transient results in the plant entering into the instability region.
TRS TRS 3.3.9.1 Required only when the OPRM trip function is not available, this TRS ensures the combination of core flow and THERMAL POWER are within required limits to prevent uncontrolled thermal hydraulic oscillations by ensuring the recirculation loops are within the limits established by the Power / Flow map specified in the COLR. At low recirculation flows and high reactor power, the reactor exhibits increased susceptibility to thermal-hydraulic instability. The Power / Flow map specified in the COLR is based on guidance provided in References 7, 8, and 9 which also provided the guidance on how to respond to operation in these conditions. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is based on operating experience and the operator's inherent knowledge of the current reactor status, including significant changes in THERMAL POWER and core flow to ensure the requirements are constantly met.
TRS 3.3.9.2 This TRS is to be performed at the specified Frequency to ensure that the LPRM Upscale Alarm Instrumentation are maintained OPERABLE.
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SUSQUEHANNA - UNIT 2 TRM / B 3.3-19d EFFECTIVE DATE 03/27/2007
OPRM Instrumentation PPL Rev. 2 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRS TRS 3.3.9.3 (continued)
The parameter setpoint verification surveillance compares the desired settings and setpoints to the values contained in the processor memory.
This surveillance is required to assure that the settings are maintained in accordance with the setpoint analysis. The frequency is based on the OPRM CALIBRATION frequency per SR 3.3.1.1.18.
REFERENCES 1. NEDO-31960-A, BWROG Long Term Solution Licensing Methodology
- 2. NEDO-31960-A, Supp. 1, BWROG Long Term Solution Licensing Methodology
- 3. NEDO-32465-A, BWROG Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications
- 4. Deleted.
- 5. Generic Letter 94-02, Long-Term Solutions and Upgrade Of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in Boiling Water Reactors
- 6. LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation
- 7. GE Service Information Letter No. 380, "BWR Core Thermal Hydraulic Stability," Revision 1, February 10, 1984.
- 8. Letter, L. A. England to M. J. Virgilio, "BWR Owner's Group Guidelines for Stability Interim Corrective Action," June 6, 1994.
- 9. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis:
Assessment of STAIF with Input from MICROBURN-B2,"
November 1999.
- 10. NEDC-32410P-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option III Stability Trip Function" SUSQUEHANNA - UNIT 2 TRM / B 3.3-19e EFFECTIVE DATE 03/27/2007
Shutdown Margin Test RPS Instrumentation PPL Rev. 1 B 3.10.2 B 3.10.2 Shutdown Margin Test RPS Instrumentation BASES TRO Prior to demonstration of adequate shutdown margin, neutron monitoring system trips provide a level of defense-in-depth to assure that the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition. The intent of the requirement is to ensure that the protection system coincident trip logics are removed if a rod has been withdrawn and shutdown margin has not been demonstrated.
With the shorting links removed, the trip function is in the non-coincident mode, such that all trip channels go to both trip systems, effectively producing one trip system. For the NUMAC PRNMS, only the 2-Out-of-4 Voter logic provides trip inputs to RPS. Therefore, when the "shorting links" are removed, the Minimum OPERABLE Channels Per Trip system is four 2-Out-of-4 Voters, and 6 IRM Neutron Flux High or Inop. Two SRM channels are required, one in, and one near, the affected core quadrant undergoing shutdown margin testing.
ACTIONS The Actions are defined to ensure that defense-in-depth protection against inadvertent core criticality is provided during initial startup with a new full core; CORE ALTERATIONS (i.e. - control rod withdrawals) are prohibited, and withdrawn rods are inserted, to assure a subcritical core. The Conditions cover inoperable instrument channels and failure to remove the shorting links. These Actions are consistent with the non-coincident logic.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.10-2 EFFECTIVE DATE 03/27/2007
Shutdown Margin Test RPS Instrumentation PPL Rev. 1 B 3.10.2 B 3.10.2 Shutdown Margin Test RPS Instrumentation BASES (continued)
TRS The TRSs listed provide for the proper channel surveillances for the SRM trip that assure the trip function operates per design when needed. TRS 3.10.2.1 provides assurance that the SRM monitoring function that drives the RPS function remains OPERABLE. The IRM and APRM surveillances are properly defined for MODE 5 OPERABILITY in LCO 3.3.1.1.
TRS 3.10.2.2 assures that the shorting links are removed prior to and during MODE 5 Shutdown Margin demonstrations per LCO 3.1.1.
TRS 3.10.2.4 assures that the resulting RPS trip logic performs as designed with the shorting links removed.
REFERENCES 1. LCO 3.1.1
- 2. LCO 3.3.1.1 SUSQUEHANNA - UNIT 2 TRM / B 3.10-3 EFFECTIVE DATE 03/27/2007