|
---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210H6271999-07-29029 July 1999 Summary of 990622 Meeting with EOI Re NRC Briefing by RBS on Issues Associated with Root Cause Investigation Into Fuel Cladding Failures That Occurred During Recent Cycle 8 Operation.List of Attendees Provided ML20205D4831999-03-25025 March 1999 Summary of 990222 Public Hearing with Util Re Gathering Addl Info Related to Two Petitions Filed Pursuant to 10CFR2.206 by Ucs Re Operation of River Bend Station & Perry Nuclear Power Plant.List of Attendees & Transcript of Hearing Encl ML20198G5501998-12-18018 December 1998 Summary of 981201-02 Workshop with Entergy Operations,Inc in Taft,La Re Licensing Processes,Licensing Submittals & Other Topics That May Affect Licensing Processes & Submittals. Copy of Slides Presented During Workshop Encl ML20155H3931998-11-0202 November 1998 Summary of 981007 Meeting with Util Re Review Status of Standard Quality Assurance Manual for All Util Sites.List of Meeting Attendees Encl ML20154C4771998-10-0202 October 1998 Summary of 980908 Meeting with Cleveland Electric Illuminating Co,Entergy Operations,Inc & Illinois Power Co Re Joint Effort to Propose TSs to Reduce Requirements on Secondary Containment Integrity During Refueling ML20151X0011998-09-10010 September 1998 Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees Encl ML20236M0501998-07-0808 July 1998 Summary of 980702 Meeting W/Entergy Operations,Inc to Discuss Review Status of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20217K3461998-04-24024 April 1998 Summary of 980401 Meeting W/Entergy Operations,Inc Re Licensing Issues & Regulatory Performance Efficiencies.List of Attendees & Agenda for Meeting Encl ML20217K5141998-04-24024 April 1998 Summary of 980416 Meeting W/Entergy Corp Re Standardization of site-specific Security Plans.List of Meeting Attendees & Agenda for Meeting Encl ML20217F4811998-03-26026 March 1998 Summary of 980319 Meeting W/Licensee to Discuss Status of Development of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20203B5741998-02-11011 February 1998 Summary of 980122 Meeting W/Entergy in Rockville,Maryland Re Licensing Issues & Standardization of Licensing Documents. List of Meeting Attendees & Meeting Agenda Encl ML20212G8521997-10-29029 October 1997 Summary of 971022 Meeting W/Entergy Svcs,Inc Re Development & Implementation of Common or Std QAP for All Sites.List of Meeting Attendees & Viewgraphs Encl ML20148F0391997-05-30030 May 1997 Summary of 970521 Meeting W/Entergy Operations,Inc Re Proposed Removal of MSL Lcs,Removal of Pvlc Sys & Increase of MSIV Leakage Requirements in TS ML20140C1681997-03-28028 March 1997 Summary of 970313 Meeting W/Entergy Operations,Inc to Discuss Proposed ECCS Suction Strainer Mod.List of Attendees & ECCS Suction Strainer Mod Encl ML20149M3611996-12-11011 December 1996 Summary of 96111 Meeting W/Licensee in Rockville,Md to Discuss Comments Developed in Response to NRC Advance Notice of Proposed Rulemaking on Financial Assurance Requirements for Decommissioning Nuclear Reactors.List of Attendees Encl ML20134M6611996-11-21021 November 1996 Summary of 961114 Meeting W/Listed Licensees in Rockville,Md to Discuss Results of Self Assessment of Accuracy of Info in FSARs for Four Nuclear Reactor Sites.List of Attendees & Licensee Handout Encl ML20056C5251993-06-18018 June 1993 Summary of 930513 Meeting W/Util Re Changes to Security & Response Plans.Meeting Agenda & List of Attendees Encl ML20059C7421993-03-0202 March 1993 Summary of 392nd ACRS Meeting on 921209-11 in Bethesda,Md Re SBO Rule,Ts Improvement Program,Advanced BWR Design,River Bend Nuclear Plant Reliability Monitoring Program & Generic Issue 120,online Testability of Protection Sys ML20055G8611990-07-18018 July 1990 Summary of 900712 Meeting W/Util Re Reload Design Methods. List of Attendees Encl ML20055F0941990-07-10010 July 1990 Summary of 900620 Meeting W/Util Re Proposed License Amends, Including Removal of Snubber Requirements from Tech Specs for Relocation Into Inservice Insp Program & Util Responses to Generic Ltrs 88-01 & 87-09 ML20246B6901989-08-0101 August 1989 Summary of 890727 Meeting W/Util in Arlington,Tx Re Plant Security Enhancement Program & Personnel Changes ML20205A7431988-10-12012 October 1988 Summary of 880928 Meeting W/Util Re 880825 Reactor Trip & Followup Actions by Licensee.Viewgraphs Encl ML20153G6331988-08-30030 August 1988 Summary of Operating Reactor Events Meeting 88-35 on 880830, Including Summary of Reactor Scrams for Wk Ending 880828. Significant Event Identified for Input to NRC Performenance Indicator Program ML20151Z7921988-08-25025 August 1988 Summary of 880817 Meeting W/Util in Rockville,Md Re Util 5-yr Business Plan to Improve Safety & to Reduce Operating Costs at Plant.List of Attendees & Handouts Encl ML20151Z4211988-08-25025 August 1988 Summary of 880818 Meeting W/Util in Rockville,Md Re License Amend Application to Permit Performance of Leak Rate Tests of Containment Isolation Valves in Parallel W/Refueling Operations ML20151R5391988-08-0808 August 1988 Summary of 880623 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines. Resolution of Issues Listed ML20151R8701988-08-0505 August 1988 Summary of 880726 Meeting W/Util in Arlington,Tx Re 5-yr Business Plan.Handouts Encl ML20154J4061988-05-17017 May 1988 Summary of 880414 Meeting W/Representatives & Contractors of Licensee in Rockville,Md Re 870605 Amend Application for Util.Highlights of Discussion Listed.Nrc Indicated That Request for Addl Info Would Be Prepared If Needed ML20148H6621988-01-15015 January 1988 Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl ML20147C8041988-01-0606 January 1988 Summary of 871215 & 16 Meetings W/Util in St Francisville,La Re Questions & Comments Resulting from Review of Inservice Testing Program.Inel Trip Rept,List of Attendees & Questions & Comments Encl ML20147C8201987-12-28028 December 1987 Trip Rept of 871215-16 Site Visit to Discuss Pump & Valve Inservice Testing Program ML20236J2291987-10-30030 October 1987 Summary of 871007 Meeting W/Hydrogen Control Owners Group (Hcog) Re Hcog Submittals on Methods for Calculating Equipment Temp Based on Quarter Scale Test Data & Impact of Station Blackout Considerations on Hcog Programs.W/Encl ML20235M9151987-07-19019 July 1987 Summary of 870615 Meeting W/Util in Bethesda,Md Re Revs to Util Emergency Operating Procedures & to Satisfy Sser Requirement.Attendee List Encl ML20214A2151987-05-13013 May 1987 Summary of 870508 Meeting W/Util & GE Re Licensee Plans for Fuel Reload.List of Attendees & Meeting Viewgraphs Encl ML20215L3281987-05-0505 May 1987 Summary of Operating Reactors Events Meeting 87-11 on 870420.List of Attendees,Viewgraphs & Input to NRC Performance Indicator Program Encl ML20212Q9681987-04-21021 April 1987 Summary of 870217 Meeting W/Util to Discuss Issues Re Containment Vending,Reg Guide 1.97,TDI Diesels,Util Plans for First Refueling Outage,Engineering Expertise on Shift, UHS Monitor & OL Amends ML20211M9761987-02-24024 February 1987 Summary of 870203 Meeting W/Mark III Containment Hydrogen Control Owners Group Re CLASIX-3 Computer Code Validation & Emergency Procedure Guidelines.List of Attendees Encl ML20207B0141986-10-31031 October 1986 Summary of 861022 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines for Hydrogen Generation Event & Validation of Methods for Calculating Heat Transfer.Viewgraphs Encl ML20203G6921986-07-25025 July 1986 Summary of 860619 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Mods of Clasix-3 Computer Code & Secondary Burning in Quarter Scale Test.List of Meeting Attendees & Handouts Encl ML20207E2811986-07-16016 July 1986 Summary of Operating Reactors Events Meeting 86-24 on 860714 Re Events Occurring Since 860707 Meeting ML20211G7781986-06-13013 June 1986 Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl ML20206G6571986-06-10010 June 1986 Summary of 860529 Meeting W/Util Re Licensing Priorities & Matters Associated W/Forthcoming Transition of Util from Startup Test to Commercial Operation.Attendees List & Viewgraphs Encl ML20211G9361986-06-0606 June 1986 Summary of Operating Reactor Events Meeting 86-18 on 860602 Re Events Occurring Since 860519 Meeting.Attendee List, Events,Significant Elements of Events & Completion Dates for Assignments Encl ML20210R8471986-05-13013 May 1986 Summary of Operating Reactors Events Meeting 86-16 on 860512 Re Events Occurring Since Last Meeting.List of Attendees & Related Info Encl ML20197F1691986-05-0808 May 1986 Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors ML20197F7721986-05-0808 May 1986 Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl ML20203M9431986-04-25025 April 1986 Summary of Operating Reactors Events Meeting 86-13 on 860421 Re Events Occurring Since 860414 Meeting.Attendance List, Viewgraphs & Supporting Documentation Encl ML20141G2901986-04-0707 April 1986 Summary of 860313 Meeting W/Mark III Containment Hydrogen Control Owners Group in Bethesda,Md Re Heat Loss Analysis. List of Attendees,Handout & Viewgraphs Encl ML20210J0261986-03-24024 March 1986 Summary of Operating Reactor Events Meeting 86-08 on 860317 to Discuss Events Occurring Since Last Meeting on 860310 ML20154P0071986-03-12012 March 1986 Summary of Operating Reactor Events 860303 Meeting 86-06 W/Ornl Re Events Occurring Since 860224 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl 1999-07-29
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210H6271999-07-29029 July 1999 Summary of 990622 Meeting with EOI Re NRC Briefing by RBS on Issues Associated with Root Cause Investigation Into Fuel Cladding Failures That Occurred During Recent Cycle 8 Operation.List of Attendees Provided ML20205D4831999-03-25025 March 1999 Summary of 990222 Public Hearing with Util Re Gathering Addl Info Related to Two Petitions Filed Pursuant to 10CFR2.206 by Ucs Re Operation of River Bend Station & Perry Nuclear Power Plant.List of Attendees & Transcript of Hearing Encl ML20198G5501998-12-18018 December 1998 Summary of 981201-02 Workshop with Entergy Operations,Inc in Taft,La Re Licensing Processes,Licensing Submittals & Other Topics That May Affect Licensing Processes & Submittals. Copy of Slides Presented During Workshop Encl ML20155H3931998-11-0202 November 1998 Summary of 981007 Meeting with Util Re Review Status of Standard Quality Assurance Manual for All Util Sites.List of Meeting Attendees Encl ML20154C4771998-10-0202 October 1998 Summary of 980908 Meeting with Cleveland Electric Illuminating Co,Entergy Operations,Inc & Illinois Power Co Re Joint Effort to Propose TSs to Reduce Requirements on Secondary Containment Integrity During Refueling ML20151X0011998-09-10010 September 1998 Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees Encl ML20236M0501998-07-0808 July 1998 Summary of 980702 Meeting W/Entergy Operations,Inc to Discuss Review Status of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20217K3461998-04-24024 April 1998 Summary of 980401 Meeting W/Entergy Operations,Inc Re Licensing Issues & Regulatory Performance Efficiencies.List of Attendees & Agenda for Meeting Encl ML20217K5141998-04-24024 April 1998 Summary of 980416 Meeting W/Entergy Corp Re Standardization of site-specific Security Plans.List of Meeting Attendees & Agenda for Meeting Encl ML20217F4811998-03-26026 March 1998 Summary of 980319 Meeting W/Licensee to Discuss Status of Development of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20203B5741998-02-11011 February 1998 Summary of 980122 Meeting W/Entergy in Rockville,Maryland Re Licensing Issues & Standardization of Licensing Documents. List of Meeting Attendees & Meeting Agenda Encl ML20212G8521997-10-29029 October 1997 Summary of 971022 Meeting W/Entergy Svcs,Inc Re Development & Implementation of Common or Std QAP for All Sites.List of Meeting Attendees & Viewgraphs Encl ML20148F0391997-05-30030 May 1997 Summary of 970521 Meeting W/Entergy Operations,Inc Re Proposed Removal of MSL Lcs,Removal of Pvlc Sys & Increase of MSIV Leakage Requirements in TS ML20140C1681997-03-28028 March 1997 Summary of 970313 Meeting W/Entergy Operations,Inc to Discuss Proposed ECCS Suction Strainer Mod.List of Attendees & ECCS Suction Strainer Mod Encl ML20149M3611996-12-11011 December 1996 Summary of 96111 Meeting W/Licensee in Rockville,Md to Discuss Comments Developed in Response to NRC Advance Notice of Proposed Rulemaking on Financial Assurance Requirements for Decommissioning Nuclear Reactors.List of Attendees Encl ML20134M6611996-11-21021 November 1996 Summary of 961114 Meeting W/Listed Licensees in Rockville,Md to Discuss Results of Self Assessment of Accuracy of Info in FSARs for Four Nuclear Reactor Sites.List of Attendees & Licensee Handout Encl ML20056C5251993-06-18018 June 1993 Summary of 930513 Meeting W/Util Re Changes to Security & Response Plans.Meeting Agenda & List of Attendees Encl ML20059C7421993-03-0202 March 1993 Summary of 392nd ACRS Meeting on 921209-11 in Bethesda,Md Re SBO Rule,Ts Improvement Program,Advanced BWR Design,River Bend Nuclear Plant Reliability Monitoring Program & Generic Issue 120,online Testability of Protection Sys ML20055G8611990-07-18018 July 1990 Summary of 900712 Meeting W/Util Re Reload Design Methods. List of Attendees Encl ML20055F0941990-07-10010 July 1990 Summary of 900620 Meeting W/Util Re Proposed License Amends, Including Removal of Snubber Requirements from Tech Specs for Relocation Into Inservice Insp Program & Util Responses to Generic Ltrs 88-01 & 87-09 ML20246B6901989-08-0101 August 1989 Summary of 890727 Meeting W/Util in Arlington,Tx Re Plant Security Enhancement Program & Personnel Changes ML20205A7431988-10-12012 October 1988 Summary of 880928 Meeting W/Util Re 880825 Reactor Trip & Followup Actions by Licensee.Viewgraphs Encl ML20153G6331988-08-30030 August 1988 Summary of Operating Reactor Events Meeting 88-35 on 880830, Including Summary of Reactor Scrams for Wk Ending 880828. Significant Event Identified for Input to NRC Performenance Indicator Program ML20151Z7921988-08-25025 August 1988 Summary of 880817 Meeting W/Util in Rockville,Md Re Util 5-yr Business Plan to Improve Safety & to Reduce Operating Costs at Plant.List of Attendees & Handouts Encl ML20151Z4211988-08-25025 August 1988 Summary of 880818 Meeting W/Util in Rockville,Md Re License Amend Application to Permit Performance of Leak Rate Tests of Containment Isolation Valves in Parallel W/Refueling Operations ML20151R5391988-08-0808 August 1988 Summary of 880623 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines. Resolution of Issues Listed ML20151R8701988-08-0505 August 1988 Summary of 880726 Meeting W/Util in Arlington,Tx Re 5-yr Business Plan.Handouts Encl ML20154J4061988-05-17017 May 1988 Summary of 880414 Meeting W/Representatives & Contractors of Licensee in Rockville,Md Re 870605 Amend Application for Util.Highlights of Discussion Listed.Nrc Indicated That Request for Addl Info Would Be Prepared If Needed ML20148H6621988-01-15015 January 1988 Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl ML20147C8041988-01-0606 January 1988 Summary of 871215 & 16 Meetings W/Util in St Francisville,La Re Questions & Comments Resulting from Review of Inservice Testing Program.Inel Trip Rept,List of Attendees & Questions & Comments Encl ML20236J2291987-10-30030 October 1987 Summary of 871007 Meeting W/Hydrogen Control Owners Group (Hcog) Re Hcog Submittals on Methods for Calculating Equipment Temp Based on Quarter Scale Test Data & Impact of Station Blackout Considerations on Hcog Programs.W/Encl ML20235M9151987-07-19019 July 1987 Summary of 870615 Meeting W/Util in Bethesda,Md Re Revs to Util Emergency Operating Procedures & to Satisfy Sser Requirement.Attendee List Encl ML20214A2151987-05-13013 May 1987 Summary of 870508 Meeting W/Util & GE Re Licensee Plans for Fuel Reload.List of Attendees & Meeting Viewgraphs Encl ML20215L3281987-05-0505 May 1987 Summary of Operating Reactors Events Meeting 87-11 on 870420.List of Attendees,Viewgraphs & Input to NRC Performance Indicator Program Encl ML20212Q9681987-04-21021 April 1987 Summary of 870217 Meeting W/Util to Discuss Issues Re Containment Vending,Reg Guide 1.97,TDI Diesels,Util Plans for First Refueling Outage,Engineering Expertise on Shift, UHS Monitor & OL Amends ML20211M9761987-02-24024 February 1987 Summary of 870203 Meeting W/Mark III Containment Hydrogen Control Owners Group Re CLASIX-3 Computer Code Validation & Emergency Procedure Guidelines.List of Attendees Encl ML20207B0141986-10-31031 October 1986 Summary of 861022 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines for Hydrogen Generation Event & Validation of Methods for Calculating Heat Transfer.Viewgraphs Encl ML20203G6921986-07-25025 July 1986 Summary of 860619 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Mods of Clasix-3 Computer Code & Secondary Burning in Quarter Scale Test.List of Meeting Attendees & Handouts Encl ML20207E2811986-07-16016 July 1986 Summary of Operating Reactors Events Meeting 86-24 on 860714 Re Events Occurring Since 860707 Meeting ML20211G7781986-06-13013 June 1986 Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl ML20206G6571986-06-10010 June 1986 Summary of 860529 Meeting W/Util Re Licensing Priorities & Matters Associated W/Forthcoming Transition of Util from Startup Test to Commercial Operation.Attendees List & Viewgraphs Encl ML20211G9361986-06-0606 June 1986 Summary of Operating Reactor Events Meeting 86-18 on 860602 Re Events Occurring Since 860519 Meeting.Attendee List, Events,Significant Elements of Events & Completion Dates for Assignments Encl ML20210R8471986-05-13013 May 1986 Summary of Operating Reactors Events Meeting 86-16 on 860512 Re Events Occurring Since Last Meeting.List of Attendees & Related Info Encl ML20197F1691986-05-0808 May 1986 Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors ML20197F7721986-05-0808 May 1986 Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl ML20203M9431986-04-25025 April 1986 Summary of Operating Reactors Events Meeting 86-13 on 860421 Re Events Occurring Since 860414 Meeting.Attendance List, Viewgraphs & Supporting Documentation Encl ML20141G2901986-04-0707 April 1986 Summary of 860313 Meeting W/Mark III Containment Hydrogen Control Owners Group in Bethesda,Md Re Heat Loss Analysis. List of Attendees,Handout & Viewgraphs Encl ML20210J0261986-03-24024 March 1986 Summary of Operating Reactor Events Meeting 86-08 on 860317 to Discuss Events Occurring Since Last Meeting on 860310 ML20154P0071986-03-12012 March 1986 Summary of Operating Reactor Events 860303 Meeting 86-06 W/Ornl Re Events Occurring Since 860224 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl ML20154C9931986-02-24024 February 1986 Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl 1999-07-29
[Table view] |
Text
I
/ 'o, UNITED STATES 8" ' 'o NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20666 e
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May 13,1987
% ,g Docket No. 50-458 l
MEMORANDUM T0: File FROM: Stephen M. Stern, Project Manager ProjectDirectorate-IV Division of Reactor Proje~ cts - III, IV, V and Special Projects
SUBJECT:
MINUTES OF MEETING; NRC AND GULF STATES UTILITIES ON FUEL RELOAD OF MAY 8, 1987 i
The River Bend Station licensee, Gulf States Utilities, its contractor and the ,
staff met to review licensee plans for fuel reload. General Electric Corporation !
attended as the licensee's contractor.
The licensee is currently projecting the end of their first refueling outage for November 1987.
The licensee and contractor state that the application for fuel reload will be i based on the General Electric standard fuel load application, GESTAR II. All i core reload materials will either be submitted on the River Bend docket or.by reference to GESTAR II which has earlier been docketed and approved by the staff.
The licensee and contractor stated that this application will be " conventional" with no special facets requiring additional staff resources for review.
The staff stated 'that the licensee must clearly specify and justify the applica-bility of all limiting events.
The staff advisea the licensee of resource limitations that might preclude timely review of a complex licensing application.
Thelicensedwillfileforthisreloadapplicationbyendo July, early August l 1987.~
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ATTENDEES MAY 8, 1987 MEETING: NRR & GS TOPIC: PLAN FOR FUEL RELOAD Name Organization Title Phone Stephen M. Stern DRST/NRR Pro;ect Manager 492-7000 ~
Chuck Paone GE/FuelProj. Pro ectManager(401)925-4696 Bill Zarbis GE/ Fuel Lic. Sen;ior Engineer (408 925-5070 Eddie R. Grant GSU/ Licensing Director (504 381-4145 Wayne Hodges NRR/RSB Chief (301 492-7483 l
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GESTAR II GENERAL ELECTRIC STANDARD APPLICATION FOR REACTQR FUEL o- BASIS FOR ALL FUEL LICENSING o CONTAINS RESULTS OF GENERIC NRC REVIEWS o FULLY APPROVED BY NRC ,
o MAINTAINED UP TO DATE o CONSISTS OF:
BASE DOCUMENT COUNTRY-SPECIFIC DOCUMENT STANDARDIZED PLANT-SPECIFIC SUBMITTAL l
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GESTAR-il LICENSING Pre-Approved A
.i f h Base Country Cycle Report Supplement Specific 1
- Fuel Design e Reactor Limits e Core Loading e Nuclear Models Methods Pattern e Thermal-
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- Plant-Unique i information scoss.oo i
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GESTAR II CONTENTS VOLUME 1: BASE DOCUMENT .
SECTION 1 INTRODUCTION SECTION 2 FUEL MECHANICAL DESIGN SECTION 3 NUCLEAR EVALUATION SECTION 4 STEADY-STATE HYDRAULIC ANALYSES APPENDIX A SAFETY ANALYSIS REPORT ROADMAP APPENDIX B SAFETY ANALYSIS REPORT VOLUME 2: COUNTRY-SPECIFIC DOCUMENT SECTION 1 INTRODUCTION SECTION 2 REACTOR LIMITS DETERMINATION APPENDIX A SUPPLEMENTAL RELOAD LICENSING SUBMITTAL APPENDIX B RESPONSES TO NRC QUESTIONS APPENDIX C NRC SAFETY EVALUATION REPORTS i
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GESTAR II VOLUME 1 SECTION 1 ; INTRODUCTION o REPORT PURPOSE AND SCOPE o CORE LATTICE TYPE o FUEL DESIGNATIONS AND LENGTHS I l l
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GESTAR II VOLUME 1 .
SECTION 2 - FUEL MECHANICAL DESIGN o FUEL ASSEMBLY DESCRIPTION o FUEL R0D LIMITS AND ANALYSES THERMAL MECHANICAL o FUEL ASSEMBLY MECHANICAL EVALUATIONS HANDLING AND SHIPPING NORMAL AND TRANSIENT SEISMIC AND LOCA I
o FUEL QUALITY ASSURANCE
GESTAR II VOLUME 1 -
SECTION 3 - NUCLEAR EVALUATION METHODS ,
o LATTICE NUCLEAR CHARACTERISTICS REACTIVITY LOCAL PEAKING FACTORS D0PPLER COEFFICIENT VOID REACTIVITY o REFERENCE LOADING PATTERN CALCULATIONS CORE REACTIVITY CONTROL SYSTEM WORTH SHUTDOWN MARGIN l STANDBY LIQUID CONTROL SYSTEM TRANSIENT AND ACCIDENT INPUT PARAMETERS
_ _._ _ __ _ . _ . . _ .-- ~ _ _ . . . .
GESTAR II VOLUME-1 _
SECTION 4 - STEADY-STATE HYDRAULIC ANALYSES MODELS I
o PRESSURE DROP CALCULATIONS o BYPASS FLOW DETERMINATION 4
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VOLUME 2 - COUNTRY-SPECIFIC DOCUMENT _.
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o PROVIDES SAFETY ANALYSIS METHODOLOGY UNIQUE TO EACH COUNTRY o PROVIDES FORMAT FOR RELOAD CYCLE-SPECIFIC INFORMATION o PROVIDES RESPONSES TO REGULATORY QUESTIONS AND REGULATORY- l SERs i
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GESTAR II VOLUME 2 - COUNTRY-SPECIFIC DOCUMENT (US).
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SECTION.1 - INTRODUCTION o PROVIDES PLANT APPLICABILITY OF DOCUMENT l
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GESTAR II VOLUME 2 - COUNTRY-SPECIFIC DOCUMENT (US). '
SECTION 2 - REACTOR LIMITS DETERMINATION i
o FUEL CLADDING INTEGRITY SAFETY LIMIT q i
STATISTICAL MODEL ,
B0UNDING ANALYSIS o OPERATING MCPR LIMIT DETERMINATION :
MODEL DESCRIPTION - TRANSIENT ANALYSIS ,
LIMITING EVENT DETERMINATION j TURBINE TRIP WITHOUT BYPASS
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LOAD REJECTION WITHOUT BYPASS LOSS OF FEEDWATER HEATING- ,.
n INADVERTENT HPCI STARTUP ,
FEEDWATER CONTROLLER FAILURE PRESSURE REGULATOR DOWNSCALE FAILURE (BWR/6 ONLY)
CONTROL R0D WITHDRAWAL ERROR (BOUNDING ANALYSIS) i -
C0ASTDOWN OPERATION LOW FLOW EFFECTS PLANT-SPECIFIC INPUTS MCPR MARGIN IMPROVEMENT OPTIONS OPERATING MAP EXPANSION OPTIONS- .
1 o OVERPRESSURE PROTECTION SAFETY VALVE SIZING BASIS
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MSIV CLOSURE - FLUX SCRAM o B0UNDING STABILITY APPROACH ,
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GESTAR II l
VOLUME 2 - COUNTRY-SPECIFIC DOCUMENT (US).
SECTION 2 - REACTOR LIMITS DETERMINATION o ACCIDENT EVALUATIONS CONTROL R0D DROP ACCIDENT ANALYSIS METHODOLOGY B0UNDING ANALYSIS LOSS-0F-COOLANT ACCIDENT ANALYSIS MODEL DESCRIPTIONS MAIN STEAM LINE BREAK ANALYSIS B0UNDING ANALYSIS 1
DOSE EVALUATION FUEL HANDLING ACCIDENT l BOUNDING ANALYSIS DOSE EVALUATION RECIRCULATION PUMP TRIP B0UNDING ANALYSIS DOSE EVALUATION LOADING ERROR ACCIDENT ROTATED EVALUATION METHOD MISLOCATED EVALUATION METHOD AND B0UNDING RESULTS 1
i GESTAR II VOLUME 2 - COUNTRY-SPECIFIC DOCUMENT (US) .
. APPENDICES o- APPENDIX A - SUPPLEMENTAL RELOAD LICENSING SUBMITTAL PLANT-SPECIFIC SUBMITTAL FORMAT REFERENCES ANALYSES DESCRIPTION 1
o APPENDIX B - RESPONSES TO NRC QUESTIONS i -
APPROVED RESPONSES ONLY UPDATED CONSISTENT WITH NRC SER' l 1
o APPENDIX C - NRC SAFETY EVALUATION REPORT l
-l
PLANT-SPECIFIC-SUBMITTAL (RELOADS);
=-
o RESULTS OF' RELOAD ANALYSES f
o RELOAD SPECIFIC INFORMATION o ONLY TABLES AND FIGURES I
o NO TEXT l
i l o NEW INFORMATION HIGHLIGHTED - SEPARATE APPENDICES l
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SUPPLDENTAL RELOAD LICENSING SUBMITTAL .
FOR' 4 O Prepared: @
Verified:
Approved:
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- 1. PLANT-UNIQUE ITEMS (1.0)*
List items different from or Appendix or Reference of Item @
not included in NEDE-24011: h '
- 2. RELOAD FUEL BUNDLES (1.0, 2.0, 3.3.1 and 4.0) t Number Fuel Type
- Qcle Loaded Irradiated h h New h Q Total
- 3. REFERENCE CORE LOADING PATTERN (3.3.1)
Nominal previous cycle core average exposure at end of cycle: h mwd /MT Minimum previous cycle core average exposure at end of cycle from cold shutdown considerations: Q mwd /MT Assumed reload cycle core average exposure at end of cycle: Q mwd /MT J Core loading pattern: Figure 1 h
- 4. CALCULATED CORE EFFECTIVE MULTIPLICATION AND CONTROL SYSTEM WORTH - NO VOIDS, 20*C (3.3.2.1.1 and_3.3.2.1.2)
Beginning of Cycle, K,ff Uncontrolled 1.1 @
Fully Controlled 0.9 @
Strongest Control Rod out 0.9 @
R. Maximum Increase in Cold Core Reactivity with Exposure into Cycle, AK 0.0 @
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- ( ) Refers to area of discussion in " General Electric Standard Application for Reactor Fuel". NEDE-24011-P-A (latest approved revision); a letter "S" preceding the number refers to the appropriate country-specific l supplement.
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- 5. STANDBY LIQUID CONTROL SYSTEM SHUTDOWN CAPABILITY (3.3.2.1.3) 1 Shutdown Margin (Ak) .
.m (20 den. C. Xenon Free)
@ 0.0 @ -
- 6. RELOAD-UNIQUE TRANSIENT ANALYSIS INPUT (3.3.2.1.5 and 5.2.2)
(COLD WATER INJECTION EVENTS ONLY)
EOC h EOC - h mwd /MT Void Fraction (%) h h Average Fuel Temperature (,F) h h Void Coefficient N/A* (C/% Rg) h/-h h /- Q j
l Doppler Coefficient -0. Q /-0. @ -0. @ /-0. Q N/A* (C/*F)
Scram Worth N/A*(S)
- 7. RELOAD-UNIQUE GETAB TRANSIENT ANALYSIS INITIAL CONDITION PARAMETERS (S.2.2) f Fuel Peaking Factors R- Bundle Bundle Flow Initia)
Design Local Radial Axial Factor Power (MWT) (1000 lb/hr)- MCPR i
Exposure: EOC Appro- hhhh h h 1.@ '
i priate Fuel .
]
Design (s) l Exposure: EOC h mwd /MT ,
Appro- hhhh h h 1.@
priate Fuel
. Design (s)
- N = Nuclear Input Data; A = Used in Transient Inalysis
- Generic exposure-independent values are used as given in " General Electric Standard Application for Reactor Fuel," NEDE-24011 (latest revision).
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_8.- SELECTED MARGIN IMPROVEMENT OPTIONS (S.2.2.2) f Transient Recategorization: h Recirculation Pump Trip: h (
Rod Withdrawal Limiter: h -
. Thermal Power Monitor: h Improved Scram Time: h Exposure Dependent Limits: Q Exposure Points Analyzed: @
- 9. OPERATING FLEXIBILITY OPTIONS (S.2.2.3)
Single-Loop Operation: h Load-Line Limit: h Extended Load Line Limit: h Increased Core Flow h Flow Point Analyzed: @%
Feedwater Temperature Reduction: h ARTS Program; h Maximum Extended Operating Domain: h
- 10. CORE-WIDE TRANSIENT ANALYSIS RESULTS (S.2.2.1)
- t. CPR Flux, Q/A Appropriate Transient (% NBR) (% NBR) Fuel Design (s) Figure Exposure: BOC to EOC - h mwd /MT Limiting Pressure and @ @ 0. @ @
Power Increase Transient Limiting Coolant Temperature @ @ 0. @ @
Decrease Transient Feedwater Controller Failure @ @ 0.@ @
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Flux, Q/A Transient (% NBR) (% NBR) Appropriate Fuel Design (s) Figure
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Exposure: EOC - h mwd /MT to EOC _
@ 0.@
Limiting Pressure @ @
and Power Increase ,
Transient Limiting Coolant @ Q 0.@ @
Temperature Decrease Transient Feedvater Controller @ g 0. @ @
Failure
- 11. LOCAL ROD WI'nIDRAWAL ERROR (WITH LIMITING INSTRUMENT FAILURE)
TRANSIENT
SUMMARY
(S.2.2.1) *
- Limiting Rod Pattern
- Figureh**
Rod Position *** 8x8R/P8x8R/ 8x8R/P8x8R/
Rod Block (Feet BP8x8R/CE8x8E/ BP8x8R/GE8x8E/
Reading Withdrawn) GE8x8EB 8x8 8x8 GE8x8EB b b l
@ b 4
l Set Point Selected: @
- If plant has ARTS, this section is replaced with a reference to the ARTS document.
- 1f the generic rod withdrawal error analysis is used, this figure is not reported.
- If the generic rod withdrawal error analysis is used, rod position and MLRCR are not reported since it will always be significantly below the plastic strain limit.
- 12. CYCLE MCPR VALUES (S.2.2) 4 Non-Pressurization Events _
Exposure Range: BOC h to EOC h Appropriate Fuel Design (s) ,
Limiting Coolant 1. @
Temperature Decrease Transient Fuel Loading Error 1.@
Rod Withdrawal Error 1.@
Pressurization Events Option A Option B i Appropriate Fuel Design (s) Appropriate Fuel Design (s)
Exposure Kange:
BOC to EOC - h mwd /MT Limiting Pressure 1.@ 1.@
and Power I
Increase Transient Feedwater Controller 1.@ 1.@
Failure Exposure Range:
EOC - @ mwd /MT to EOC i'
Limiting Pressure 1@ 1.@
- and Power l Increase Transient l
Feedwater Controller 1.@ 1@
Failure
- 13. OVERPRESSURIZATION ANALYSIS
SUMMARY
(S.2.3)
P P,3 v (psig) (psig) Plant Response Transient Figure 6
'l MSIV Closure (Flux Scram) h h
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- 14. LOADING ERROR RESULTS (S.2.5.4)
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Variable Water Cap Misoriented Bundle Analysis: h .
Event Initial CPR Resulting CPR j
- 15. CONTROL ROD DROP ANALYSIS RESULTS (S.2.5.1) l Bounding Analysis Results
Doppler Reactivity Coefficient: Figureh Accident Reactivity Shape Functions: Figureshandh Scram' Reactivity Functions: Figureshandh t
Plant Specific Analysis Results:
Parameter (s) not Bounded, Cold: @
Resultant Peak Enthalpy, Cold: h Parameter (s) not Bounded, HSB:
l l Resultant Peak Enthalpy, HSB: Q ,
- 16. STABILITY ANALYSIS RESULTS (S.2.4)*
Rod Line Analyzed: h Figur'eh Decay Ratio:
j Reactor Core Stability Decay Ratio, xy/x0 0.@
Channel Hydrodynamic Performance Decay Ratio, x2 /*0 l Channel Type P8x8R 0@
8x8R 0.@
. 8x8 0. @
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- This section is included only for BWR 4/5/6 plants which have not implemented i NRC approved stability monitoring documentation. All other BWR 4/5/6 plants are exempt from reporting these values providing they utilise acceptable fuel j
- types as outlined in Section S.2.4 of CESTAR and insert a note in this section l stating: "SIL-380 recosamendations have been included in the (plant name) l operating procedures and, therefore, no stability analysis is required". l l
For BWR 2/3 plants, the following note should be used: "BWR 2/3 plants are '
. exempt from performing cycle specific stability analyses".
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- 17. LOSS-OF-COOLANT ACCIDENT RESULT (S.2.5.2)
(For Those Plants With An ECCS Report Which is Separate From the FSAR)-
IDCA Method Used:
SAFE /REFLOOD/ CHASTE: h SAFER /GESTR-LOCA: h
Reference:
Individual Plant LOCA Document (as amended) o MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE (INCLUDE FOLI4 WING TABLE FOR i EACH NEW BUNDLE DESIGN)
' Plant: h Fuel Type: h i
Average Planar Exposure MAPLHGR PCT ' Oxidation (mwd /t) (kW/ft) (*F) Fraction j 200 Q Q Q l 4
1,000 . . .
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5,000 . . .
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10,000 . . .
15,000 . . .
20,000 . . .
25,000 . . .
30,000 . . .
35,000 . . .
d 40,000 Q Q Q ; /
j j *To account for the 2% uncertainty in bundle power required by Appendix K, ' i
! the SCAT calculation is performed with an MCPR of 1.18 (i.e., 1.2 divided l 4
by 1.02) for a bundle with an initial MCPR of 1.20.
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ll RELOAD LICENSING VERSUS INITIAL CORE LICENSING I o INITIAL CORE LICENSING ALL EVENTS CONSIDERED APPROVED METHODS USED DETAILED. TEXT AND RESULTS PROVIDED I -
REFLECTS INITIAL CORE CONDITIONS-o RELOAD-LICENSING ONLY LIMITING EVENTS CONSIDERED (JUSTIFICATION IN j GESTAR) r
-- APPROVED METHODS USED RESULTS PROVIDED ONLY (TEXT IN GESTAR)
REFLECTS RELOAD CYCLE CONDITIONS i
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GESTAR II o PROVIDES~ SIMPLIFIED DOCUMENTATION ORGANIZED THE WAY FUEL AND CORE ANALYSES ARE PERFORMED APPLICABLE TO ALL 8X8 FUEL TYPES CONCISE PLANT-SPECIFIC SUBMITTAL o ELIMINAT;ES REPETITIVE NRC REVIEW e
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LICENSING EVALUATION METHODS 1
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LICENSING VEHICLES o- GESTAR'II o LICENSING TOPICAL REPORTS 4
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EVALUATION MODEL LICENSING STATUS METHOD MQDEL APPLICATION GETAB APPROVED APPROVED ODYN APPROVED APPROVED GESTR-MECHANICAL APPROVED APPROVED NUCLEAR PHYSICS APPROVED APPROVED SAFE /REFLOOD APPROVED APPROVED i
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ELIMINATING OR B0UNDING ANALYSES
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ELIMINATING OR B0UNDING ANALYSES
- o. EVENTS ANALYZED 7 TRANSIENTS 3 ACCIDENTS OVER-PRESSURIZATION o ONLY LIMITING EVENTS REPORTED o WHEN POSSIBLE, LIMITING EVENTS ELIMINATED B0UNDED ,
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4 ELIMINATING OR BOUNDING ANALYSES o ANALYSES ELIMINATED CONTROL R0D DROP ACCIDENT MISL0CATED BUNDLE LOADING ERROR j
STABILITY
, o ANALYSES B0UNDED R0D WITHDRAWAL ERROR I
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FUEL DESIGN LICENSING
EVOLUTION OF-GE FUEL' DESIGN 1
GE8X8NB
'1 GE8X8EB
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i P8X8R 1
I 8X8R .
8X8 7
7X7R l
ry ,
7X7 BARRIERC 4
FUEL DESIGNS o ALL 8X8 DESIGNS IN'GESTAR II o REVIEW 0F NEW DESIGNS SIMPLIFIED
-- REVIEWED ON GESTAR II. DOCKET PRE-APPROVED METHODS AND CRITERIA 0
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t BARRIER FUEL DESIGN o USED WITH P8X8R FUEL O DESIGNED USING APPROVED--ANALYSES MODELS o UNCONDITIONALLY APPROVED BY NRC, APRIL 1983 i
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OPERATING FLEXIBILITY OPTIONS
OPERATING FLEXIBILITY OPTIONS fD o SINGLE LOOP OPERATION (SLO) o LOAD LINE LIMIT (EXTENDED LOAD LINE LIMIT IELLLA1) o INCREASED CORE FLOW (ICF) i o FEEDWATER TEMPERATURE REDUCTION (FWTR)
E0C FEEDWATER HEATER OUT OF SERVICE o MAXIMUM EXTENDED OPERATING DOMAIN (MEOD) d :
ELLLA ,
l ICF I
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OPERATING FLEXIBILITY OPTIONS PROGRAM WHAT IT IS ANALYSIS
- ELLLA OPERATION AB0VE 100% LOAD LINE TRANSIENTS ACCIDENTS SLO ONE RECIRC LOOP OUT OF SERVICE TRANSIENTS ACCIDENTS 4
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ICF OPERATION AT HIGHER THAN RATED TRANSIENTS FLOW ACCIDENTS FWTR 1. REDUCED FEEDWATER TEMPERATURE TRANSIENTS AT EOC ACCIDENTS
- 2. OPERATION WITH FEEDWATER HEATER OUT OF SERVICE ME0D ELLLA AND ICF TRANSIENTS ACCIDENTS I
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STANDARD LICENSED OPERATING MAP I
} Power l
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! Flow ,
l i Operating Map Constrained i by 100% Flow Control Line i
and 100% Pump Speed i scess.os
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STANDARD LICENSED FUEL CYCLE i-Power .
i Full Thermal Power Region with Coastdown
$ Exposure i
i Coastdown to 40% Power Consistent with Fuel Mechanical Design Limits Approved in Gestar-Il sesse.oo
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l EXPANDED OPERATING MAP Power l
j Load Line Limit Analysis t
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! Operating Map l
j Single increased l' Loop Core Operation Flow Flow
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Operational Flexibility improvement f to Expand Operating Map SC888.08 l
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FUEL CYCLE EXTENSION Power
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I 'Feedwater i Temperature i g l l 1
Load Line I
Full Thermal Power l Limit increased Region with Coastdown l Core Flow l i
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,i bFuel Mechanical :!
l Design Limited \ g Exposure Improved Uranium Utilization i SC688.07 l
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