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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
,(.
,i.. Stptember 9, 1986 Docket No. 50-271 LICENSEE: Vermont Yankee Nuclear Power Corporation FACILITY: Vermont Yankee Nuclear Power Station
SUBJECT:
AUGUST 6, 1986 MEETING WITH THE VERMONT YANKEE NUCLEAR POWER CORPORATION (VYNPC)
Re: Containment safety study status On August 6, 1986, a meeting was held at the NRC headquarters in Bethesda, Maryland to discuss the status of the 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.
VYNPC reported that the Vermont Yankee plant had been compared to !! ark I containment design assumed for generic studies with respect to: hydrogen control, drywell sprays, containment pressure control, core debris control, and training and procedures.
These comparisons were almost complete, and at the time of the meeting, inputs by consultants were being condensed and integrated into a single report. The report should be complete at the beginning of September, as scheduled.
Vernon L. Rooney, Project Manager BWR Project Directorate #2 Division of BWR Licensing
Enclosures:
As stated cc w/ enclosures:
See next page i
BWR#2[
VRooney
'j/f/86 060912001D 060709 -
PDit ADOCK 05000271 P PDit
, , N..,
Mr. R. W. Capstick Vermont Yankee Nuclear Power Corporation Vermont Yankee Nuclear Power Station CC*
Mr. J. G. Weigand W. P. Murphy, Vice President &
President & Chief Executive Officer Manager of Operations Vemont Yankee Niclear Power Corp. Vemont Yankee Nuclear Power Corp.
R. D. 5, Pox 169 R. D. 5. Box 169 Ferry Road Ferry Road Brattleboro, Vermont 05301 Brattleboro, Vermont 05301 Mr. Donald Hunter, Vice President Mr. Gerald Tarrant . Comissioner Vermont Yankee Nuclear Power Corp.. Vermont Department of Public, Service
- 1671 Worcester Road 120 State Street Framingham, Massachusetts 01701 Montpelier, Vermont 05602 New England Coalition en Nuclear Pollution Hill and Dale Fam Public Service Board R. D. 2, Box 223 State of Vermont Putney, Vemont 05346 120 State Street Montpelier Vemont 05602 Mr. Walter Zaluzny Chaiman, Board of Selectman Vemont Yankee Decommissionirg Post Office Box 116 Alliance Vernon, Vermont 05345 Box 53 Montpelier, Vemont 05602-0053 J. P. Pelletier, Plant Maneger Vemont Yankee fluclear Power Corp.
Post Office Box 157 Resident Inspector Vernon, Vemont 05354 U. 5. Nuclear Regulatory Corrission Post Office Box 176 Raymond N. McCandless Vernon, Verront 05354 Vermont Division of Occupationti A Radiological Health Vermont Public Interest Administration Building Research Group, Inc.
10 Baldwin Street 43 State Street Montpelier Vemont 05602 Montpelier, Yemont 05602 Honorable liohn J. Easton Thomas A. Murley Attorney General Regional Adninistrator State of Vermont Region I office 109 State Street U. 5. tuclear Regulatory Corrission Montpelier, Vemont 05602 631 Park Avenue King of Prussia, Pennsylvania 19406 John A. P.itscher, Esquire Ropes & Gray 225 Franklin Street .
Boston, Massachusetts 02110
.E . i ..
Enclosure 1 LIST OF MEETING ATTENDEES August 6, 1986 Name Organization H. Abelson NRC/ DBL /PD#P D. Muller NRC/ DBL /PD#2 J. Thayer Yankee Atomic Electric Co.
R. Lodwick VYNPC W. Murphy VYhPC S. Shultz Yankee Atomic Electric Co.
R. Auluck NRC/ DBL /PD#1 P. Paull State of Vermont G. Tarrant State of Vermont S. Kurphy NIRS D. Shum NRC/ DBL /F0B T. Elasser NRC/RI P. Leech NRC/ DBL /PD#1 M. Thadani NRC/ DBL /PDf2 R. Bachmann NRC/0GC J. Gray, Jr. New York Power Authority J. Kopeck NRC/PA J. Coates Vermont Public Interest Research Group D. Hew Harmon & Weiss R. Houston NRC/ DBL M. Hodges NRC/ DBL /RSB G. Lainas NRC/ DBL /BWAD R. Bernero NRC/ DBL
,d , k,,
Enclosure 2 VERMONT YANKEE CONTAINMENT SAFETY STUDY
- 1. PURPOSE AND OBJECTIVE OF EACH TASK INCLUDING PRELIMINARY RESULTS MARK 1 DESIGN REVIEW o WASH 1400 DESIGN COMPARIS0N o KEY DESIGN DIFFERENCES o VERMONT YANKEE DESIGN
SUMMARY
VERMONT YANKEE CONTAINMENT CAPABILITY o VERMONT YANKEE APPROACH o STUDIES AND RESOURCES USED
! o ACCIDENTS AND TRANSIENTS STUDIED l 0 RESULTS UTILIZING KEY DIFFERENCES AT VERMONT YANKEE o DEFINITION OF "90%"
o VY CONTAINMENT CONDITIONAL FAILURE PROBABILITY i CURRENT MARK I ISSUES o DEFINITION AND TECHNICAL STATUS OF 5 ISSUES o APPLICABILITY AND NEED FOR FURTHER STUDY o ACTIVE INDUSTRY AND NRC EFFORTS
- 1. STATUS
- RESULTS TO DATE
- SCHEDULE FOR COMPLETION
? -
I' . ...
CONTAINMENT SAFETY STUDY DESIGN AND OPERATIONAL FEATURES COMPARISON
't Design / Operational Date Vermont Yankee (WASH-1400)
General Plant Data Plant Type CE BWR GE BWR C ntainment Type Mark 1 Pressure Suppression Mark I Pressure Suppression Rated Therwal Power, NWt 1,593 3,293 Rated Core Flow, Ib/hr 48.0 x 10E6 102.5 x 10E6 Rated Steam Flow, ib/hr 6.43 x 10E6 13.381 x 10E6 Reactor Data inside Height, ft-in 63 - 1.5 72 - 11 inside Diameter, in. 205 251
- Containment Data Internal Design Pressure, psig 56 56 Derwell Data cylinder Diameter, ft. 33 38.5 ft. 62 67 Spherical Free Air Volume, ft Diameter,3 134,000 159,000 Torus Data Major Diameter, ft. 98 111.5
- Minor Diameter, ft. 27.66 31 W;ter Volume, min / max., ft 3 68,000/70,000 123,000 Free Air Volume, ft3 114,200/112,200 119,000 Vent Pipes Data Number 8 8 I
Internal Diameter, ft. 6.75 6.75 Downcomer Pipe Data Number 96 96 Internal Diameter, ft. 2 2 Submergence, ft. (nominal) 4 4 Number of WW-DW Vacuum 10 12 Breakers 1
a
~1-
i Design / Operational Data Vermont Yankee (WASH-1400)
Secondary Containment Data Fece Air Volume 2,120,000 2,400,000 Mitigation Systems DeslKn Data HPCI System Eu;ber of Trains or Subsystems 1 1 Number of Pumps / Train 1 1 Design Flow / Train 4,250 spm at 1,120 to 150 psid 5,000 gpm at 1,100 to 150 pcis Electrical Power DC only (turbine-driven) DC only (turbine-driven)
RCIC System
~
Number of Trains or subsystems 1 1 Number of Pumps / Train 1 1 Design Flow / Train 400 600 spm Electrical Power DC only (turbine-driven) DC only (turbine-driven)
RHR System s Number of Trains or Subsystems 2 2' Number of Pumps / Train 2 2 Nu;ber of HXs/ Train 1 2 Design Flow / Train 14,400 gpm 20,000 spm Eltetrical Power Emergency ac and de Emergency ac and de Source of Water Torus Torus Service water (river) Service water Ultimate backup (Diesel fire pump.
cross-tie capability)
Emergency Diesel Generator Systess Nu;ber of Emergency Buses 2 4 per unit Number of Emergency Diesels 2* 4* - Shared between two units
- Single-Unit Site - Requires *Two-Unit Site - Requires two l one out of two emergency out of four emergency diesels diesels for safe shutdown. for safe shutdown.
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VERMONT YANKEE - WASH 1400 KEY DESIGN DIFFERENCES
. RATIO DESIGN PARAMETER VERMONT YANKEE / WASH 1400
- RATED THERMAL POWER .48 DRYWELL VOLUME / POWER 1.75 TORUS WATER VOLUME / POWER 1.19 TORUS AIR VOLUME / POWER 1.96
. HPCI PUMPING CAPACITY / POWER 1.77 RCIC PUMPING CAPACITY / POWER 1.40 t
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VERMONT YANKEE DESIGN
SUMMARY
o SMALL REACTOR PLANT (NSSS) IN LARGE MARK 1 CONTAINMENT o ENGINEERED SAFETY FEATURES CAPACITY o RESIDUAL HEAT REMOVAL CAPABILITY o ELECTRIC DRIVEN MAIN FEED PUMPS
- o DC SYSTEM CAPACITY & DIVERSITY
- 8 HOUR BATTERY RATING
- APPENDIX R BATTERIES
- SPECIAL PURPOSE BATTERIES
- UNINTERRUPTIBLE POWER SUPPLIES o AC SYSTEM RELIABILITY & DIVERSITY
- VERNON HYDRO IIE LINE NORTHEAST GRID RELIABILITY
- SEPARATE HIGH LINE RIGHT OF WAYS o DIESEL FIRE PUMP CROSSTIE TO RHR SYSTEM O
--r - - - --r - - , - - - -- -.--w w -- --- -w,n -
STUDY APPROACH o IDENTIFY THE DOMINANT ACCIDENT SEQUENCES WHICH CAN LEAD TO SEVERE ACCIDENTS AT VERMONT YANKEE.
o QUANTIFY THE DOMINANT SEQUENCES USING A REFERENCE MARK I MODIFIED FOR THE UNIQUE VERMONT YANKEE FEATURES.
! o DEVELOP THE CONTAINMENT EVENT TREE TO DISPLAY THE PATHWAYS TO SAFE MITIGATION AND POTENTIAL RADIONUCLIDE RELEASE TO THE ENVIRONMENT.
o QUANTIFY THE CONTAINMENT EVENT TREE USING AVAILABLE ESTIMATES OF MITIGATION RELIABILITY AND STANDARD MODELS.
o CALCULATE THE CONDITIONAL FAILURE PROBAB:LITY OF CONTAINMENT.
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STUDIES 8 RESOURCES STUDIES o WASH 1400 o IDCOR
- IPE METHODOLOGY
- TECHNICAL
SUMMARY
REPORT
- TASK REPORT DOCUMENTS o DRAFT BWR MARK I PSA's o SEVERE ACCICENT SEQUENCE ANALYSIS PROGRAM RESOURCES o YANKEE ATOMIC ELECTRIC COMPANY o DELIAN CORPORATION o FAUSKE AND ASSOCIATES o RISK MANAGEMENT ASSOCIATES o GENERAL ELECTRIC COMPANY o PICKARD LOWE & GARRICK, INC.
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."? . ii.. I BWR DOMINANT ACCIDENT SEQUENCES CLASS I LOSS OF COOLANT MAKEUP IA HIGH PRESSURE IB STATION BLACK 0UT I IC ATWS ID LOW PRESSURE IE LOSS OF DC CLASS 11 LOSS OF CONTAINMENT HEAT REMOVAL CLASS III LOCA i
CLASS IV ATWS l .
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