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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20196K2781999-01-0404 January 1999 Summary of 981217 Meeting with Util to Discuss Plans & Activities Re Spent Fuel Storage at Plant.List of Attendees & Handouts Encl ML20236F7861998-06-30030 June 1998 Summary of 980623 Meeting W/Vynp Re Plans & Activities Related to long-term Spent Fuel Storage Plans.List of Attendees & Copies of Handouts Distributed at Meeting Encl ML20216H5751998-04-16016 April 1998 Summary of 980407 Meeting W/Vynp Re Plans & Activities Re Assurance of Adequate Net Positive Head for Certain safety- Related Pumps.List of Meeting Attendees & Copies of Meeting Handouts Encl ML20217J9111998-03-31031 March 1998 Summary of 980324 Meeting W/Representative of Vynpc Re Torus Strainer Installation,Post Installation Torus Testing & Containment Analysis Methodology.List of Attendees & Handouts Distributed at Meeting ML20198Q5211997-11-0505 November 1997 Summary of 971103 Meeting W/Vynpc in Rockville,Md on Plans & Activities Re Submittal & Implementation of Improved TS at Plant.List of Attendees,Handout of Plant Presentation & W Beckners Comments Encl ML20211P4991997-10-0909 October 1997 Summary of 970917 Meeting W/Vynp in Rockville,Maryland Re ASME Code Case N560.List of Meeting Attendees,Meeting Agenda & Meeting Handouts Encl ML20137X1131997-04-0303 April 1997 Summary of 970326 Meeting W/Vynp in Rockville,Md to Discuss Licensee Engineering,Improved Ts,Correction Actions & Plant Goals for 1997.List of Attendees & Presentation Matls Encl ML20133M4341997-01-16016 January 1997 Summary of 961223 Meeting W/Vynp Re Licensee Request to Be Briefed on Vynp Plan for Analysis in Preparation for Vermont Yankee Fuel Cycle 20 Reload.List of Attendees & Handouts Encl ML20059L8351993-11-0909 November 1993 Summary of 931025 Meeting W/Util in Bolton,Ma Re Status of Open Licensing Issues Involving Plant.Attendees Listed in Encl 1 ML20058M1861993-09-22022 September 1993 Summary of Operating Reactors Events Meeting 93-35 on 930915 ML20056D9841993-05-18018 May 1993 Summary of Operating Reactors Events Meeting 93-17 on 930512 ML20128E7681993-02-0404 February 1993 Summary of 921216 Meeting W/Vynp in Rockville,Md Re Licensing Issues Related to Plant.List of Attendees Encl ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 ML20247A8971989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl ML20206E3591988-11-10010 November 1988 Summary of Operating Reactors Events Meeting 88-44 on 881108.List of Meeting Attendees,Significant Events & Summary of Reactor Scrams Encl.One Significant Event Identified for Input to Performance Indicator Program ML20207M0771988-10-0505 October 1988 Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl ML20154L1661988-05-10010 May 1988 Trip Rept of 880412-15 Mgt Team Visit to Plant Sites,Two Matls Licensees & Region I Ofcs.List of Team Members & Summary of Observations & Perceptions from Visit Encl.Info Deleted ML20154B0861988-05-0909 May 1988 Summary of 871014-15 Meeting W/Util in King of Prussia,Pa Re Remaining Needs Associated W/Nrc Review of Util Inservice Testing Program for Pumps & Valves.Related Documents Encl ML20151T2121988-04-19019 April 1988 Summary of 880413 Meeting W/Util in Rockville,Md Re Low Level Waste Disposal Facility.List of Attendees & Viewgraphs Encl ML20148D5261988-03-17017 March 1988 Summary of 880315 Meeting W/Util Re Remaining Info Needs Associated W/Util Proposed Tech Spec to Change Logic Sys Functional Testing at Facility.Attendance Roster & Slides Presented Encl ML20196F7391988-02-16016 February 1988 Summary of 880209 Meeting W/Util in Rockville,Md Re Remaining Informational Need Associated W/Util Proposed Spent Fuel Expansion.List of Attendees,Transcript & Slides Encl ML20149F5821988-02-0909 February 1988 Summary of 880126 Meeting W/Util Re Environ Qualification Issues Contained in Util .List of Meeting Attendees & Agenda Encl ML20235Z4081987-10-16016 October 1987 Summary of Operating Reactors Events Meeting 87-35 on 871013.List of Attendees,Events Discussed,Significant Elements of Events & Summary of Reactor Scrams & Comparison of Wk Statistics W/Industry Averages Encl ML20210A0141987-02-0404 February 1987 Summary of 870115 Meeting W/Util in Richland,Wa Re thermal-hydraulic Analysis Supporting Util Proposed Expansion of Spent Fuel Pool.List of Attendees & Summary of Description of Util thermal-hydraulic Analysis Encl ML20207G1591987-01-0505 January 1987 Summary of 861223 Meeting W/Util,Ucs & Harman & Weiss in Bethesda,Md Re Heavy Loads Considerations for Spent Fuel Pool Expansion,Per Util 860423 Proposal.List of Attendees & Util Layout of Areas & Safe Load Paths Encl ML20212C4291986-12-23023 December 1986 Summary of 861117 Meeting W/Util,Delian Corp,State of VT Public Svc Dept & Nuclear Info Resource Svc in Bethesda,Md Re Util Response to NRC Questions on Containment Safety Study.List of Attendees & Util Draft Response Encl ML20213F0641986-11-10010 November 1986 Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl ML20215G0561986-10-0707 October 1986 Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed ML20210V1871986-10-0303 October 1986 Summary of 860911 Meeting W/Util,Ge,State of Ny,Pirg,Nutech & Bechtel in Bethesda,Md Re Mark I Containment Safety Study. List of Attendees & Viewgraphs Encl ML20210E7771986-09-10010 September 1986 Summary of 860729 Meeting W/Util & Eg&G in Bethesda,Md Re Review of Relap 5YA Computer Code for LOCA Analysis at Plant.Summary of Significant Items Discussed at Meeting Provided.List of Attendees,Agenda & Handouts Encl ML20209F0041986-09-0909 September 1986 Summary of 860806 Meeting W/Util,State of Vt,Harmon & Weiss & Vermont Pirg in Bethesda,Md Re Status of Facility Mark I Containment Safety Study.Attendee List & Viewgraphs Encl ML20212N6801986-08-27027 August 1986 Summary of Operating Reactor Events Meeting 86-30 on 860825 to Discuss Events Which Occurred Since Last Meeting on 860818 ML20212N6771986-08-25025 August 1986 Summary of Operating Reactor Events Meeting 86-29 on 860818 to Discuss Events Which Occurred Since Last Meeting on 860811,including Improper Ring Settings on PWR Main Steam Safety Valves NUREG-0518, Summary of ACRS 316th Meeting on 860807-09 in Washington,Dc Re Proposed Standardization Policy Statement & Review of Issues Related to Reorganization of TVA Mgt Structure & Shutdown of TVA Nuclear Power Plants1986-08-18018 August 1986 Summary of ACRS 316th Meeting on 860807-09 in Washington,Dc Re Proposed Standardization Policy Statement & Review of Issues Related to Reorganization of TVA Mgt Structure & Shutdown of TVA Nuclear Power Plants IA-86-778, Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl1986-07-31031 July 1986 Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl ML20213F8661986-07-31031 July 1986 Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl ML20211P1361986-07-16016 July 1986 Summary of 860707 Operating Reactor Events Meeting 86-23 W/ Div Directors & Representatives Re Events Since Last Meeting on 860630.Notification of Inability to Meet Assigned Target Completion Dates for Actions Requested.Viewgraphs Encl ML20202G1711986-07-0808 July 1986 Summary of Operating Reactor Events Meeting 86-22 on 860630 W/Ofc Director,Div Directors & Representatives to Discuss Events Occurring Since 860623.List of Attendees & Viewgraphs Encl ML20210S2611986-07-0101 July 1986 Summary of 860630 Meeting W/Util & Governor of State of VT in Montpelier,Vt Re 90% Conditional Failure Probability of Mark I Containments,Given Full Core Melt Accident ML20199L6471986-06-26026 June 1986 Summary of Operating Reactors Events Meeting 86-21 on 860623.Attendance List & Viewgraphs Encl ML20202G4981986-05-22022 May 1986 Summary of ACRS Reactor Operations Subcommittee 860409 Meeting in Washington,Dc.Schedule of Items Covered, Attendance List & Meeting Handouts Encl ML20203P6801986-04-22022 April 1986 Summary of 860410 Meeting W/Project Managers & Utils in Bethesda,Md Re Automated Tracking,Integrated Schedules & Tech Specs.Attendees List,Viewgraphs & Meeting Agenda Encl ML20205J9221986-04-18018 April 1986 Summary of ACRS 312th Meeting on 860410-12 in Washington,Dc Re Proposed NRC Safety Goal Policy Statement & Need for Guidance in Environ & PRA for Quantification of Public Health Risks to Nearby Populations ML20141N6831986-03-0707 March 1986 Summary of Operating Reactors Events Meeting 86-05 on 860224.Lists of Attendees,Events & Significant Elements Discussed & Assignment of Followup Review Responsibility Encl ML20154C9931986-02-24024 February 1986 Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl ML20137D4761986-01-10010 January 1986 Trip Rept of Observation of INPO Accreditation Team Visit During Wk of 850930-1004 of Util Power Plant Training Programs.List of INPO Evaluation Team Members Encl ML20134N5981985-08-29029 August 1985 Summary of 850716 Meeting W/Util & Bechtel in Bethesda,Md Re App R Compliance & Circuit Separation Evaluations.List of Meeting Attendees & Viewgraphs Encl ML19309H9241980-05-15015 May 1980 Summary of 800310 Meeting W/Nrc in Bethesda,Md Re Reload Licensing for Cycle IX ML20148F9891978-09-14014 September 1978 Minutes of the 216th ACRS Meeting on 780406-07 Re Ak Nuc 1, Unit 2 Pwr Plant,Liquid Pathway Generic Study,Mcguire Nuc Station Units 1 & 2 & Davis-Besse-1 Implementation of ACRS Recommendations from 770114 rept.pp1-35 ML20125C5621978-05-0101 May 1978 Summary of 780309-10 Meeting W/Mark I Owners Group in Bethesda,Md Re Changes in Long Term Program as Reflected in Rev 3 to Mark I Owners Group Program Action Plan 1999-01-04
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20196K2781999-01-0404 January 1999 Summary of 981217 Meeting with Util to Discuss Plans & Activities Re Spent Fuel Storage at Plant.List of Attendees & Handouts Encl ML20236F7861998-06-30030 June 1998 Summary of 980623 Meeting W/Vynp Re Plans & Activities Related to long-term Spent Fuel Storage Plans.List of Attendees & Copies of Handouts Distributed at Meeting Encl ML20216H5751998-04-16016 April 1998 Summary of 980407 Meeting W/Vynp Re Plans & Activities Re Assurance of Adequate Net Positive Head for Certain safety- Related Pumps.List of Meeting Attendees & Copies of Meeting Handouts Encl ML20217J9111998-03-31031 March 1998 Summary of 980324 Meeting W/Representative of Vynpc Re Torus Strainer Installation,Post Installation Torus Testing & Containment Analysis Methodology.List of Attendees & Handouts Distributed at Meeting ML20198Q5211997-11-0505 November 1997 Summary of 971103 Meeting W/Vynpc in Rockville,Md on Plans & Activities Re Submittal & Implementation of Improved TS at Plant.List of Attendees,Handout of Plant Presentation & W Beckners Comments Encl ML20211P4991997-10-0909 October 1997 Summary of 970917 Meeting W/Vynp in Rockville,Maryland Re ASME Code Case N560.List of Meeting Attendees,Meeting Agenda & Meeting Handouts Encl ML20137X1131997-04-0303 April 1997 Summary of 970326 Meeting W/Vynp in Rockville,Md to Discuss Licensee Engineering,Improved Ts,Correction Actions & Plant Goals for 1997.List of Attendees & Presentation Matls Encl ML20133M4341997-01-16016 January 1997 Summary of 961223 Meeting W/Vynp Re Licensee Request to Be Briefed on Vynp Plan for Analysis in Preparation for Vermont Yankee Fuel Cycle 20 Reload.List of Attendees & Handouts Encl ML20059L8351993-11-0909 November 1993 Summary of 931025 Meeting W/Util in Bolton,Ma Re Status of Open Licensing Issues Involving Plant.Attendees Listed in Encl 1 ML20058M1861993-09-22022 September 1993 Summary of Operating Reactors Events Meeting 93-35 on 930915 ML20056D9841993-05-18018 May 1993 Summary of Operating Reactors Events Meeting 93-17 on 930512 ML20128E7681993-02-0404 February 1993 Summary of 921216 Meeting W/Vynp in Rockville,Md Re Licensing Issues Related to Plant.List of Attendees Encl ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 ML20247A8971989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl ML20206E3591988-11-10010 November 1988 Summary of Operating Reactors Events Meeting 88-44 on 881108.List of Meeting Attendees,Significant Events & Summary of Reactor Scrams Encl.One Significant Event Identified for Input to Performance Indicator Program ML20207M0771988-10-0505 October 1988 Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl ML20154B0861988-05-0909 May 1988 Summary of 871014-15 Meeting W/Util in King of Prussia,Pa Re Remaining Needs Associated W/Nrc Review of Util Inservice Testing Program for Pumps & Valves.Related Documents Encl ML20151T2121988-04-19019 April 1988 Summary of 880413 Meeting W/Util in Rockville,Md Re Low Level Waste Disposal Facility.List of Attendees & Viewgraphs Encl ML20148D5261988-03-17017 March 1988 Summary of 880315 Meeting W/Util Re Remaining Info Needs Associated W/Util Proposed Tech Spec to Change Logic Sys Functional Testing at Facility.Attendance Roster & Slides Presented Encl ML20196F7391988-02-16016 February 1988 Summary of 880209 Meeting W/Util in Rockville,Md Re Remaining Informational Need Associated W/Util Proposed Spent Fuel Expansion.List of Attendees,Transcript & Slides Encl ML20149F5821988-02-0909 February 1988 Summary of 880126 Meeting W/Util Re Environ Qualification Issues Contained in Util .List of Meeting Attendees & Agenda Encl ML20235Z4081987-10-16016 October 1987 Summary of Operating Reactors Events Meeting 87-35 on 871013.List of Attendees,Events Discussed,Significant Elements of Events & Summary of Reactor Scrams & Comparison of Wk Statistics W/Industry Averages Encl ML20210A0141987-02-0404 February 1987 Summary of 870115 Meeting W/Util in Richland,Wa Re thermal-hydraulic Analysis Supporting Util Proposed Expansion of Spent Fuel Pool.List of Attendees & Summary of Description of Util thermal-hydraulic Analysis Encl ML20207G1591987-01-0505 January 1987 Summary of 861223 Meeting W/Util,Ucs & Harman & Weiss in Bethesda,Md Re Heavy Loads Considerations for Spent Fuel Pool Expansion,Per Util 860423 Proposal.List of Attendees & Util Layout of Areas & Safe Load Paths Encl ML20212C4291986-12-23023 December 1986 Summary of 861117 Meeting W/Util,Delian Corp,State of VT Public Svc Dept & Nuclear Info Resource Svc in Bethesda,Md Re Util Response to NRC Questions on Containment Safety Study.List of Attendees & Util Draft Response Encl ML20213F0641986-11-10010 November 1986 Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl ML20215G0561986-10-0707 October 1986 Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed ML20210V1871986-10-0303 October 1986 Summary of 860911 Meeting W/Util,Ge,State of Ny,Pirg,Nutech & Bechtel in Bethesda,Md Re Mark I Containment Safety Study. List of Attendees & Viewgraphs Encl ML20210E7771986-09-10010 September 1986 Summary of 860729 Meeting W/Util & Eg&G in Bethesda,Md Re Review of Relap 5YA Computer Code for LOCA Analysis at Plant.Summary of Significant Items Discussed at Meeting Provided.List of Attendees,Agenda & Handouts Encl ML20209F0041986-09-0909 September 1986 Summary of 860806 Meeting W/Util,State of Vt,Harmon & Weiss & Vermont Pirg in Bethesda,Md Re Status of Facility Mark I Containment Safety Study.Attendee List & Viewgraphs Encl ML20212N6801986-08-27027 August 1986 Summary of Operating Reactor Events Meeting 86-30 on 860825 to Discuss Events Which Occurred Since Last Meeting on 860818 ML20212N6771986-08-25025 August 1986 Summary of Operating Reactor Events Meeting 86-29 on 860818 to Discuss Events Which Occurred Since Last Meeting on 860811,including Improper Ring Settings on PWR Main Steam Safety Valves NUREG-0518, Summary of ACRS 316th Meeting on 860807-09 in Washington,Dc Re Proposed Standardization Policy Statement & Review of Issues Related to Reorganization of TVA Mgt Structure & Shutdown of TVA Nuclear Power Plants1986-08-18018 August 1986 Summary of ACRS 316th Meeting on 860807-09 in Washington,Dc Re Proposed Standardization Policy Statement & Review of Issues Related to Reorganization of TVA Mgt Structure & Shutdown of TVA Nuclear Power Plants ML20211P1361986-07-16016 July 1986 Summary of 860707 Operating Reactor Events Meeting 86-23 W/ Div Directors & Representatives Re Events Since Last Meeting on 860630.Notification of Inability to Meet Assigned Target Completion Dates for Actions Requested.Viewgraphs Encl ML20202G1711986-07-0808 July 1986 Summary of Operating Reactor Events Meeting 86-22 on 860630 W/Ofc Director,Div Directors & Representatives to Discuss Events Occurring Since 860623.List of Attendees & Viewgraphs Encl ML20210S2611986-07-0101 July 1986 Summary of 860630 Meeting W/Util & Governor of State of VT in Montpelier,Vt Re 90% Conditional Failure Probability of Mark I Containments,Given Full Core Melt Accident ML20199L6471986-06-26026 June 1986 Summary of Operating Reactors Events Meeting 86-21 on 860623.Attendance List & Viewgraphs Encl ML20202G4981986-05-22022 May 1986 Summary of ACRS Reactor Operations Subcommittee 860409 Meeting in Washington,Dc.Schedule of Items Covered, Attendance List & Meeting Handouts Encl ML20203P6801986-04-22022 April 1986 Summary of 860410 Meeting W/Project Managers & Utils in Bethesda,Md Re Automated Tracking,Integrated Schedules & Tech Specs.Attendees List,Viewgraphs & Meeting Agenda Encl ML20205J9221986-04-18018 April 1986 Summary of ACRS 312th Meeting on 860410-12 in Washington,Dc Re Proposed NRC Safety Goal Policy Statement & Need for Guidance in Environ & PRA for Quantification of Public Health Risks to Nearby Populations ML20141N6831986-03-0707 March 1986 Summary of Operating Reactors Events Meeting 86-05 on 860224.Lists of Attendees,Events & Significant Elements Discussed & Assignment of Followup Review Responsibility Encl ML20154C9931986-02-24024 February 1986 Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl ML20134N5981985-08-29029 August 1985 Summary of 850716 Meeting W/Util & Bechtel in Bethesda,Md Re App R Compliance & Circuit Separation Evaluations.List of Meeting Attendees & Viewgraphs Encl ML19309H9241980-05-15015 May 1980 Summary of 800310 Meeting W/Nrc in Bethesda,Md Re Reload Licensing for Cycle IX ML20148F9891978-09-14014 September 1978 Minutes of the 216th ACRS Meeting on 780406-07 Re Ak Nuc 1, Unit 2 Pwr Plant,Liquid Pathway Generic Study,Mcguire Nuc Station Units 1 & 2 & Davis-Besse-1 Implementation of ACRS Recommendations from 770114 rept.pp1-35 ML20125C5621978-05-0101 May 1978 Summary of 780309-10 Meeting W/Mark I Owners Group in Bethesda,Md Re Changes in Long Term Program as Reflected in Rev 3 to Mark I Owners Group Program Action Plan ML20127A4681978-03-0101 March 1978 Summary of 771129 Meeting W/Mark I Owners Group & GE in San Franciso,Ca Re Listed Topics,Including Results & Bases for long-term Program Decision Point 3.List of Attendees & Viewgraphs Encl ML20141N3471977-05-20020 May 1977 Summary of 770411 Meeting W/Mark I Owners Group & GE to Discuss Structural Acceptance Criteria for Mark I Containment long-term Program.List of Attendees Encl ML20125C5711976-09-0909 September 1976 Summary of 760812 Meeting W/Mark I Owners Group,Ge,Epri & Techncial Consultants Re Listed Long Term Program Tasks ML20125C5721976-09-0909 September 1976 Summary of 760819 Meeting W/Mark I Owners Group,(Ge) in Bethesda,Md Re Discussions on Mark I Containment Ltp.List of Attendees Encl 1999-01-04
[Table view] |
Text
October 3, 1986 e- .
Docket No. 50-271 LICENSEES: Vermont Yankee Nuclear Power Corporation FACILIlY: Vermont-Yankee Nuclear Power Station SUBJECI: SEPTEMBER'11, 1986 MEETING WITH THE VERMONI YANKEE NUCLEAR POWER CORP 0HAIION (VYNPC)
RE: Containment Safety Study On September'11, 1986,' a meeting was held at the NRC headquarters in Bethesda, Maryland to discuss the completed Vermont Yankee Mark I Containment Safety Study. Enclosure 1 is a list of individuals that attended the meeting.
Enclosure 2 is a handout of the slides presented by VPNPC at the meeting.
The study had been submitted on the Vermont Yankee docket by letter dated September 2, 1986, prior to the meeting. VYNPC described the contents of the study and answered various specific technical questions.
lhe staff acknowledged the receipt of the rcport and comented that plant specific information was provided which was expected to be useful in the generic BWR Containment Requirements effort. Furthermore, the staff noted that, considering the timing of the study, Vermont Yankee dovetails neatly as a sample case for generic containment requirements activities. Consistent with this purpose, the staff intends to review and comment on the study by late October to the extent of identifying significant areas of agreement and disagreement and providing questions. VYNPC comented that in order to provide timely response to questions, the continuation of this level of effort might conflict with certain other schedule commitments to NRR. The staff advised VYNPC to identity such cases to Project Management for discussion.
o Wi .!sd by Vernon L. Rooney, Project Manager BWR Project Directorate #2 Division of BWR Licensing
Enclosures:
DISTRIBUTION As stated R icYetvFile, 1 RBernero NRC PDR'~ " ~ DMuller cc w/ enclosures: Local PDR OGC - Bethesda See next page PD#2 Reading EJordan VRooney BGrimes ACRS (10) 0FFICIAL RECORD COPY DBL:PD#2 VRooney:cb h0100574861003 p DOCK 05000271 PDR
f D Kr. R. W. Capstick Vermont Yankee Nuclear Power Vermont Yankee Nuclear Power Corporation Station CC*
Mr. J. G. Weigand Mr. W. P. Murphy, Vice President &
President & Chief Executive Officer Manager of Operations Vermont Yankee Nuclear Power Corp. Vermont Yankee Nuclear Power Corp.
R. D. 5, Box 169 R. D. 5, Box 169 Ferry Road Ferry Road Brattleboro, Vermont 05301 Brattleboro, Vermont 05301 Mr. Donald Hunter, Vice President Mr. Gerald Tarrant, Commissioner Vermont Yankee Nuclear Power Corp. Vermont Department of Public Service 1071 Korcester Road 120 State Street Framingham, Massachusetts 01701 Montpelier, Vermont 0500E New England Coalition on Public Service Board Nuclear Pollution State of Vermont Hill and Dale Farm 120 State Street R. D. 2, Box 223 Montpelier, Vermont 05602 Putney, Vermont 05346 Vermont Yankee Decommissioning Mr. Walter Zaluzny Alliance Chairman, Board of Selectman Box 53 Post Office Box 116 Montpelier, Vermont 05602-0053 Vernon, Vermont 05345 Resident Inspector Mr. J. P. Pelletier, Plant Manager U. S. Nuclear Regulatory Commission Vermont Yankee Nuclear Power Corp. Post Office Box 176 Post Office Box 157 Vernon, Vermont 05354 Vernon, Vermont 05354 Vermont Public Interest Mr. Raymond N. McCandless Research Group, Inc.
Vermont Division of Occupational 43 State Street
& Radiological Health Montpelier, Vermont 05602 Administration Building .
10 Baldwin Street Regional Administrator, Region I Montpelier, Vermont 05602 U. S. Nuclear Regulatory Commission 631 Park Avenue
- Honorable John J. Easton King of Prussia, Pennsylvania 19406 Attorney General State of Vermont i 109 State Street l Montpelier, Vermont 05602 John A. Ritscher, Esquire Ropes & Gray i 225 Franklin Street i Boston, Massachusetts 02110 l
i l
i O Enclosure 1 LIST OF MEETING ATTENDEES VERMONT YANKEE CONTAINMENT SAFETY STUDY September 11, 1986 Name Organization D. Muller NRR/ DBL /PD#2 V. Rooney NRR/ DBL /PD#2 E. Wenzinger, Sr. NRC Region I J. Hulman NRR/ DBL /PSB D. Vassallo NRR/ DBL / FOB R. Houston NRR/ DBL M. Thadani NRR/ DBL /PD#2 D. Shum NRR/ DBL /F0B G. Lainas NRR/ DBL F. Eltawila NRR/DSR0/ RIB W. Hodges NRR/ DBL /RSB F. Lodwick VYNPC J. Thayer Yankee Atomic Electric Co.
S. Schultz Yankee Atomic Electric Co.
W. Murphy VYNPC J. Goetz Wa:hington L. Marinos Reporting Service T. Landers New York Power Authority J. Gray, Jr. New York Power Authority L. Clifford GE S. Floyd Carolina Power & Light Co.
K. Holtzclau GE N. Edwards NUTECH T. Pickens Northern States Power M. Jmay TVA-BFN R. Bachmann NRC/0GC S. Markiewicz State of Massachusetts K. Campe NRR/ DBL /PSB J. Coats Vermont Public Interest Research Group E. Weiss Harman & Weiss Union of Concerned Scientists S. Murphy Nud. Information & Resource Service E. Fotoponlos Bechtel S. Bokim NRR/ DBL /PSB F. Coffman NRR/ SORI 4
A. Notafrancesco NRR/ DBL /PSB C. Reid Bechtel
- 0. Scott Southern Co. Services J. Kudrick NRR/ DBL /PSB i
i I
, __ , ~...,_,.__._s _ _ . _ _ . _ _ _ _ . _ . _ . _ . , . _ _ _ . . . . _. . . _ _ __
4 4' g e Enclosura 2 e
VERMONT YANKEE CONTAINMENT SAFETY STUDY O
\
VERMONT YANKEE CONTAINMENT SAFETY STUDY 1 INTRODUCTION PERSPECTIVE SCOPE RESULTS
SUMMARY
11 MARK I CONTAINMENT DESIGN REVIEW 111 SEVERE ACCIDENT ANALYSIS AND QUANTIFICATION BWR DOMINANT SEQUENCES CONTAINMENT CONDITIONAL FAILURE PROBABILITY o METHODOLOGY o ACCIDENT SEQUENCE QUANTIFICATION o INITIATING EVENT FREQUENCIES o CORE MELT FREQUENCIES o CONTAINMENT EVENT TREES o CONTAINMENT PERFORMANCE RESULTS IV MARK I CONTAINMENT POLICY ISSUES o HYDR 0 GEN CONTROL o DRYWELL SPRAY CAPABILITY o CONTAINMENT VENTING o CORE DEBRIS CONTROL o SEVERE ACCIDENT TRAINING PROCEDURE V DECISION ANALYSIS FOR RECOMMENDATIONS o RECOMMENDATIONS AND INSIGHTS
PERSPECTIVE e INITIATED - TO RESPOND TO QUOTED STATEMENT
-THAT MARK I CONTAINMENTS HAVE A 90%
CORTAINMENT CONDITIONAL FAILURE PROBABILITY e AGREED UPON BY VERMONT YANKEE, THE NRC AND THE GOVERN 0R OF THE STATE OF VERMONT ON JUNE 30,1986 e PROGRESS.
INITIATED JULY 1, 1986 i
INTERIM STATUS MEETING IN BETHESDA ON AUGUST 6, 1986
^
i FINAL REPORT COMPLETE AND TRANSMITTED TO NRC AND STATE OF VERMONT ON SEPTEMBER 2, 1986 t
4
- = - . - - -,r-. -
- . , , . . . . _ .- ~,.-r- -
,_y p,
STUDY SCOPE e MARK I CONTAINMENT DESIGN REVIEW e QUANTIFY A VERMONT YANKEE SPECIFIC CONTAINMENT CONDITIONAL FAILURE PROBABILITY GIVEN A SCENARIO LEADING TO CORE MELT e ADDRESS MARK I CONTAINMENT POLICY ISSUES HYDR 0 GEN CONTROL DRYWELL SPRAY CAPABILITY CONTAINMENT VENTING
~~~
CORE DEBRIS CONTROL SEVERE ACCIDENT TRAINING AND PROCEDURES i
l 0 , . I STUDY RESULTS e VERMONT YANKEE CONDITIONAL CONTAINMENT FAILURE PROBABILITY OF 7%
e CONTAINMENT CAPABILITY IMPROVEMENTS IDENTIFIED PROCEDURE CHANGES / ENHANCEMENTS ISSUES FOR FURTHER EVALUATION INSIGHTS BASED ON SEVERE ACCIDENT SEQUENCES t
i G
i
. . . - _ . - _ . . ~ . . . . , , . - - _ _ _ . - . . . . . . _ . - _ . - . _ _ _ _ . - , . _ _ _ - _ - . . - . _ _ _ _ _ , - - ~ _ , . - - , _ - _ - _ . _ _ . _
o , ..
MARK I CONTAINMENT DESIGN REVIEW e SCOPE: COMPARE VERMONT YANKEE WITH THE MARK I REFERENCE PLANT T0 IDENTIFY DESIGN AND OPERATIONAL FEATURE DIFFERENCES SIGNIFICANT TO CONTAINMENT PERFORMANCE DURING SEVERE ACCIDENT SEQUENCES e
RESULTS: 4 SIGNIFICANT DESIGN FEATURES WERE IDENTIFIED RATIO 0F CONTAINMENT SIZE TO REACTOR POWER
- ELECTRICAL PLANT DIVERSITY DIESEL GENERATORS TIE LINE TO ADJACENT HYDROELECTRIC STATIONS
- CONNECTION FROM DIESEL FIRE PUMP TO LPCl/
CONTAINMENT SPRAY 8
l
CONTAINMENT FAILURE PROBABILITY EVALUATION e BACKGROUND
- WASH - 1400 (90%)
- DEFINITION OF CCFP e VERMONT YANKEE ANALYSES
- APPROACH
- ACCIDENT SEQUENCE IDENTIFICATION
- ACCIDENT SEQUENCE QUANTIFICATION
- CONTAINMENT EVENT TREE DEVELOPMENT
- CET QUANTIFICATION e
SUMMARY
OF RESULTS i
i Graphic Display of Containment' Performance
.-0 10 -
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1E-1 L i
i NORMAL OPERATIONS l
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w I: R:s e Ii DESGN BAS!S ACCIDENTS i:i:i. ~
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- LOCA
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g i DURING 1HE UFE OF THE POTENTIAL CORE DAMAGE SCENARIOS D Ps. ANT 3 (SEVERE ACCIDENTS) ,
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V 1E-6 .
.1 .2 .3 .4 .5 .6 .7 .8 .9 1.0
' CONTAINMENT fan.URE PROBASIUTY l
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- I 1
DEFINITION OF "90%"
WASH-1400 ASSUMPTIONS e ALL SEQUENCES (MEll/NON-MELT) ARE ASSOCIATED WITH CONTAINMENT FAI e CORE MELT RELEASE CATEGORIES
- 1. STEAM EXPLOSION
- 2. OVERPRESSURE FAILURE DIRECT TO ATMOSPHERE
- 3. OVERPRESSURE FAILURE THROUGH REACTOR BUILDING
- 4. ISOLATION FAILURE e RELEASE CATEGORIES 2 & 3 DOMINATE RISK l
e SEQUENCES WHICH CONTRIBUTE COMPRISE 90%
ATWS LOSS OF RESIDUAL CORE HEAT REMOVAL CURREN1' STUDY e DIFFERENT DOMINANT SEQUENCES IDENTIFIED e KNOWLEDGE OF CONTAINMEN1 FAILURE PHENOMENA AND CRITERIA HAS EVULVED
1 CONTAINMENT CONDITIONAL FAILURE PROBABILITY e CALCULATE THE CONTRIBUTION OF EACH ACCIDENT CLASS TO TOTAL LIKELlH00D OF CORE MELT e DETERMINE THE CONDITIONAL FAILURE PROBABILITY OF CONTAINMENT FOR EACH ACCIDENT CLASS e CALCULATE THE WEIGHTED AVERAGE OF PRIMARY CONTAINMENT FAILURE PROBABILITY T
4 0
i
- - - . . - -.=- - . , _ _ _ . - _ , , . - _ _ - - _ _ . - , _ _ . , - - - , - - - . - . - - - . - - . - _ . - _ - _ - . . - , _ _ , - _ - - - _ , . , , _ _. . - , , .. - _ . - .
COND1110NAL CONI AINMENT FAILURE PROPABill1Y 00AN11FICAll0N DOMINANT FRACTIONAL CONTAINMEliT CONTRIBUTION AcclDENT CONTRIBUTION FAILURE IO WElGHTED SE0VENCE _( CORE MELT) PRosasitiTy AvEnacE LOSS OF COOLANT MKEUP A A AxA LOSS OF i CONTAINtENT HEAT REM] VAL s B sxB 1
LOCA c C cxC ATWS o D oxD 1.0 E( ) = CFFP WHERE CCFP = CONDIT10NAL CONTAINMENT FAILURE PROBABillIY
. e CALCULATION PROCESS FLOW CHART i
/ .
i IDENhrY lDENTirY THE DEVELOP THE
! DOWINANT ACCIDENT SEQUENCE CONTAINWENT SEQUENCE TWES FREQUENQES EVENT TREE LEADING TO U ? FOR THE OCAR PLANT SEWRE ACCIDENT CONTAINWENT CONDITIONS RESPONSE W UNTOUE FEATURES) 1 1
1 I CALCULATE THE COND110NAL QUANEFY FAILURE THE O PR08A51UTY
. CET OF CONTA!NWENT l
i l
l SYSTEM ^"
PHENOMENOLOGICAL STRENGTH AND utilCAMON CALCULAh0NS WLNERABluTY gyggy EVALUAMON
BWR DOMINANT ACCIDENT SEQUENCES CLASS I LOSS OF COOLANT MAKEUP IA HIGH PRESSURE IB STATION BLACK 0UT IC ATWS ID LOW PRESSURE lE LOSS OF DC CLASS 11 LOSS OF CONTAINMENT HEAT REMOVAL CLASS l'Il LOCA CLASS IV ATWS 1
DOMINANT ACCIDENT SEQUENCE QUANTIFICATION ALTERNATIVES e PLANT - SPECIFIC PRA e VY INDIVIDUAL PLANT EVALUATION e MODIFICATION OF REFERENCE BWR MARK I PRA TO ACCOUNT FOR KEY DIFFERENCES v
PEACHBOTTOM BWR IPE ANALYSIS UTILIZED AS THE REFERENCE POINT
/
INITIATING EVENT FREQUENCIES Number of Vermont Yankee Events in Best Estimate Category Types of Events Frequency Data Base (yr-1) 1 Transients Resulting in 20 Reactor Scram with Bypass 1.62 Potentially Available 2
Events Bounded by Loss of 2 Feedwater 0.16 3
MSIV Closure 4 0.32 4
Events with Bypass Not 8 Available 0.65 5
Inadvertent Opening of One 0 or More SRVs 0.062 6
Loss of Off-site Power 1 0.071 l
1 l
1 l
4 DERIVATION OF VERMONT YANKEE SEVERE ACCIDENT SEQUENCE FREQUENCIES
, VERMONT YANKEE SURROCATE PLANT VERMONT YANKEE DOMINANT DOMINANT SEQUENCES UNIQUE FEATURES ACCIDENT SEQUENCES AND FREQUENCIES DESIGNATOR FREQUENCY FEATURE DELTA DESIGNATOR FREQUENCY (per Rx yr) *
(per RK yr)
Class IB Class IB TgQUV PHASE I 1E-6 -Initiator (x.044/.05) K.35 TgQUV PHASE I 3.5E-7 2 D/G (x2)
-Hydro Plant (45 Phase I, 6.6 Phase II, 10 Phase III, IV)
-No. of Switchyards
-Underground transmission t
TEQUV PHASE II 2E-6
-No Event Specific K.52 TgQUV PHASE II 1.0E-6 Station Blackout Procedures (Approx. same Phase II) Phase III, IV (K3)
TEQUV PHASE III 4E-6
-Battery Life K1.1 TgQUV PHASE III 4.4E-6 (Approx. same)
Phase II, III, IV TEQUV PHASE IV I.6E-6 HPCI Potential Larger K.26 T EQUV PHASE IV 4.2E-7 DC Power Reqm't (K2)
Phase II, III TOTAL Class IB = 6.2E-6 i
i
. . l
SUMMARY
OF CORE MELT FREQUENCY TYPES AT VERMONT YANKEE Class Description Frequency Fraction
~
(yr )
IA Loss of Makeup; RPV 1.33E-5 .43 at high pressure IB Loss of Makeup: 6.2E-6 .20 Station Blackout IC Loss of Makeup: 2.6E-6 .08 ATWS ID Loss of Makeup: 3.9E-6 .12 RPV at low pressure IE Loss of Makeup: 2.4E-7 .01 Loss of DC buses II Loss of Containment 2.~1E-6 .07 Heat Removal III LOCAs 7.3E-7 .02 IV ATWS 2.2E-6 .07 i
V -Interfacing LOCA Netlitible Negligible !
TOTAL 3.1E-5 100%
CONTAINMENT EVENT TREE DEVELOPMENT e CORE MELT ACCIDENT CLASS (ENTRY STATE) e CONTAINMENT MITIGATING SYSTEM RESPONSE e CONTAINMENT RESPONSE-FAILURE PATH & SIZE e REACTOR / AUXILIARY BUILDING RESPONSE
1 CONTAINMENT EVENT TREE END STATES TIMING T (BEYOND CORE MELT)
EARLY (E) T< 10 HOURS INTERMEDIATE (1) 10 < T< 24 HOURS LATE (L) T> 24 HOURS NO CONTAINMENT FAILURE (NCF) INTACT RELEASE QUANTITIES I (EQUIVALENT IODINE) PLils NOBLE GASES _
HIGH (H) I> 10%
MEDIUM (M) 0.1 < I < 10%
LOW (L) I< 0.1%
RNCTIONAL EVENTS: CONTAINTNT EVENT T E e CONTAltNENT ISOLATION AND INITIAL INTEGRITY
. eACTIVEMmGATIM: DRYWEU.T/PCONTROL e PASSIVE MITIGATION: CONTAlfEENTOFDEBRIS e CONTAlfNENT HEAT RBOVAL
-VIR
- VENTING e CONTAlfEENT BREACH SIZE f.AKAGE
- INERPRESSURE FAILURES e CONTAlfEENT BREACH 1.0 CATION YWEU.
LL AIRSPACE e REACTOR BUILDING EFFECTIVENESS
e CONTAINMENT EVENT TREES TOP EVENTS ACTIVE plTICATION CONTA!NWiNT N1[CRITY ACODCNT CON TAINgty1 WITICATION PASSVE CONTANWENTCONTAINW[N1 NO NO DRTMLL MTwEtt REACTOR CLASS ISOLATION ttWPotATUR[ WITICAfl0N NEAT PRESS *;RE IIANACE OVER- FNLURE A!R5 PACE BU:LDNC ENTRY & HlflAL CONTROL REMOVAL CONTROL PRESSURE STATE NTECRITY (WKCTFnd) (VENTINC) FAILURE cu et Y P W V D c W J R CLASSI + II l
ACQDENT CONhNUED ORWELL ActVE c0HTANWD81 NO NO OVDt- ORWELL M TWELL COOLANT EN MMCAMON PASSW PEACfDR CLASS E
ENTRY P[g LEAKACE PRES 5URE FAILURE AR5 PACE MAKEUP
{
MITICA110N BUILDNC sTA1E (WNTINC) FMLURE TO RPV WTECRITY
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(NKCTION)
Cu v (o) (C) (H) (J) c a 1 P R r
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CONTAINMENT EVENT TREE QUANTIFICATION BASES e PAST PRA EXPERIENCE e DETERMINISTIC EVALUATIONS (VY)
- MARCH /RMA
- MAAP
- HAND CALCULATIONS e IDCOR TECHNICAL REPORT INFORMATION e_ ENGINEERING JUDGMENT
s
SUMMARY
OF RELEASE FREQUENCY OF EACH RELEASE TYPE FOR EACH ACCIDENT CLASS: BASE CASE i "BEST ESTIMATE" CASE Accident Class Release Frequency (yr" ) of Release Type Designator Core Melt Frequency (yr _g) EH EN EL LM LL NCF IA 1.33E-05 7.38E-09 2.5BE-08 1.25E-07 6.89E-08 1.81E-07 1.29E-05 IB 6.20E-06 7.07E-09 1.11E-07 5.07E-07 3.56E-07 9.03E-07 4.31E-06 IC 2.60E-06 5.27E-07 2.83E-07 1.61E-08 9.31E-09 2.44E-08 1.74E-06 1
ID 3.90E-06 3.32E-09 4.60E-08 2.86E-08 5.44E-07 1.54E-06 1.74E-06 II 2.10E-06 4.73E-10 5.39E-07 1.56E-06 - - -
1 1
- III 7.30E-07 .
5.53E-10 9.06E-10 6.56E-09 4.55E-08 1.28E-07 5.49E-07 IV 2.20E-06 5.44E-09 6.55E-07 1.54E-06 - - -
Sum 3.10E-05 5.51E-07 1.66E-06 3.78E-06 1.02E-06 2.78E-06 2.12E-05 i
% of Total Core Melt Frequency 100% '7.1% 12% 3.3% 9.0% 6EL
. CONTAINMENT CONDITIONAL FAILURE PROBABILITY (D BASE AND SENSITIVITY CASE RESULTS CATAGORIZATION EH/M . EL_ LM LL 3CE BASE 7 12 4 9 68 S1 10 12 3 9 66 S2 3 9 4 10 74 S3 1 3 6 16 74 WHERE:
S1 -
.EARLY CONTAINMENT FAILURE INCREASE FOR BOTH HIGH AND LOW PRESSURE MELT DOWNS S2 -
INCREASED OPERATOR ACTION CREDIT FOR ATWS EVENTS S3 -
S2 PLUS CLASSIFICATION OF TW CLASS AS LATE VERSUS EARLY RELEASE
w -u..
4-MARK 1 CONTAINMENT POLICY ISSUES e HYDROGEN CONTROL e
DRYWELL SPRAY CAPABILITY e CONTAINMENT VENTING e CORE DEBRIS CONTROL e
SEVERE ACCIDENT TRAlHING AND PROCEDURES 5
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. , , , , , , - - - , , --- , ,-, - -- a
HYDR 0 GEN CONTROL e OBJECTIVE: PREVENT HYDR 0 GEN COMBUSTION FOLLOWING SEVERE ACCIDENTS e VY STATUS CONTAINMENT INERTED DE-INERT TIME CONTROLLED BY TECHNICAL SPECIFICATIONS OPERATING HISTORY INDICATES DE-INERT TIME IS 1.1% OF TIME PLANT IS IN RUN MODE VY RECENTLY CONVERTED TO N 2 CAD e EVALUATION: CURRENT VY PERFORMANCE AND DESIGN MEETS OBJECTIVE e RECOMMENDATIONS: NONE h
i
DRYWELL SPRAY CAPABILITY e
OBJECTIVE: PROVIDE AC INDEPENDENT CAPABILITY TO SPRAY DRYWELL TO LOWER PRESSURE AND TEMPERATURE e VY STATUS:
- NORMAL CAPABILITY FROM RHR, BACKED UP BY SERVICE WATER (DEPENDENT ON AC POWER)
DIESEL DRIVEN FIRE PUMP CAPABLE OF BEING ALIGNED TO LPC1/
CONTAINMENT SPRAY (AC INDEPENDENT)
- WATER SUPPLY FROM COOLING TOWER DEEP BASIN (AC DEPENDENT) e EVALUATION: CURRENT CAPABILITY ACCEPTABLE, ENHANCEMENTS POSSIBLE 10 INCREASE RELIABILITY OF SUPPLY FROM DIESEL FIRE PUMP e REC 0MMENDATIONS:
- ENHANCE THE OPERATION OF THE DIESEL FIRE PUMP TO DRYWELL SPRAY FLOW PATH
- IMPROVE ABILITY TO RESTORE AC POWER
CONTAINMENT VENTING e OBJECTIVE: PREVENT UNCONTROLLED LOSS OF CONTAINMENT INTEGRITY e VY STATUS:
ONLY VERY SMALL VENTING PATHWAY PROCEDURALIZED STUDY IDENTIFIES 6 VENTING PATHWAYS
- RISKS OF VENTING DISCUSSED e EVALVATION: CAPABILITY FOR WETWELL VENTING, 10 ACHIEVE FISSION PRODUCT SCRUBBING, SHOULD BE ENHANCED e RECOMMENDATIONS:
ENGINEERING EVALUATION OF UPGRADING WETWELL VENTING TO BE INITIATED
, VENTING GUIDELINE DOCUMENT PREPARED OUTLINING 32 POTENTIAL VENT PATHS, REQUIREMENTS FOR USE, ACCESS, ETC.
o s 8-CORE DEBRIS CONTROL e OBJECTIVE:
PRECLUDE CONTAINMENT FAILURL DUE TO SHELL CONTACT e VY STATUS:
SMALL CORE VOLUME IN LARGE DRYWELL PRO WILL NOT MIGRATE TO DRYWELL SHELL
- DRYWELL SPRAYS WILL " REFREEZE" CORIUM e EVALUATION:
CURRENT VY CONFIGURATION MEETS OBJECTIVE e
RECOMMENDATIONS: NONE
~
. i SEVEERE ACC' DENT TRAINING AND PROCEDURES e OBJECTIVE:
ENSURE OPERATORS READY TO USE PLANT FE BEST ADVANTAGE IN SEVERE ACCIDENTS e VY STATUS:
- VY HAS IMPLEMENTED E0P's BASED ON REV. 3 0F THE e
EVALUATION: VY MEETS CURRENT GUIDANCE e RECOMMENDATION:
IMPLEMENT REV. 4 0F EPG's WHEN AVAILABLE
- CONSIDER REVISION TO EXISTING E0P's FOR:
o STATION BLACK 0UT o CONTAINMENT VENTING o DRYWELL SPRAY USING DIESEL FIRE PUMP o GUIDANCE TO SUPPLY CST VIA FIRE SYSTEM o SAMPLE SUPPRESSION POOL BEFORE TRANSFER TO CST o PROCEDURALIZE 22H /0 CONTROL o COMPLETE DEVELOPMENT OF VY SPECIFIC LEVEL /
DECISION ANALYSIS FOR RECOMMENDATIONS e TWO PART TEST
- WHICH SEVERE ACCIDENTS WARRANT CONSIDERATION?
- WHAT IS ACCEPTABLE CONTAINMENT PERFORMANCE?
e SEVERE ACCIDENT SEQUENCES
- MOST CRITICAL TO CONTAINMENT PERFORMANCE ARE:
STATION BLACK 0UT ATWS WITH MSIV CLOSURE e ACCEPTABLE CONTAINMENT PERFORMANCE
- CONTAINMENT SHOULD REMAIN INTACT, WITHOUT EXCESSIVE LEAKAGE FOR 24 HOURS FOLLOWING EVENT INITIATION e RECOMMENDATIONS REPRESENT THE CONCENSUS OF THE STUDY TEAM REGARDING PROCEDURAL AND DESIGN ENHANCEMENTS T0 IMPROVE CONTAINKENT PERFORMANCE.
- MAXIMlZE USE OF EXISTING PLANT FEATURES
- AUGMENT EXISTING DESIGN WHERE CLEAR BENEFIT IS APPARENT
RECOMMENDATIONS e PROCEDURE ADDITIONS / ENHANCEMENTS e- ISSUES FOR FURTHER EVALUATION e INSIGHTS BASED ON SEVERE ACCIDENT SEQUENCES J
O
PROCEDURE ADDITIONS / ENHANCEMENTS e
PROVIDE PROCEDURAL GUIDANCE FOR RESTORATION OF AC POWER FOL A STATION BLACK 0UT e
PROVIDE A REPAIR PROCEDURE OUTLINING THE RESTORATION OF TH TIE LINE IF DAMAGE SHOULD OCCUR e
PROVIDE PROCEDURAL GUIDANCE FOR OPTIMlZATION OF DC POWER SOUR FOLLOWING A STATION BLACK 0UT f
e PROVIDE PROCEDURAL GUIDANCE FOR USE OF THE SRV's FOR MANUAL DEPRESSURIZATION FOLLOWING A STATION BLACK 0UT e
PRGVIDE PROCEDURAL GUIDANCE 10 ALIGN THE DIESEL FIRE PUMP FOLLOWING STATION BLACK 0UT e PROVIDE LEVEL / POWER GUIDANCE FOR ATWS
- - - , - , - _ _ , - - _ . - - - - - _ _ _ . - - . - - -- s--- . +
ISSUES FOR FURTHER EVALUATION e UPGRADE E0P's TO REV. I4 0F EPG's e UPGRADE SELECTED VALVE OPERATORS IN FLOW PATH FROM DIESEL FIRE PUMP TO LPC1/ CONTAINMENT SPRAY e ENHANCE RELIABILITY AND CAPABILITY OF CONTAINMENT WETWELL VENT O
4
'I
.1 INSIGHTS BASED ON SEVERE ACCIDENT SE0VENCES e
PROVIDE ADDITIONAL EVALUATION, GUIDANCE AND OPERATOR TRAINING ON RESPONSE OF THE RHR PUMPS TO HIGH SUPPRESSION P TEMPERATURES e
IMPROVE RELIABILITY OF THE NITROGEN SUPPLY TO THE A e
EVALUATE DESIGN AND POST-ACCIDENT RELIABILITY OF TH WATER SYSTEM e
EVALUATE STANDBY LIQUID CONTROL SYSTEM DESIGN AN
.