Letter Sequence Meeting |
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MONTHYEARML20217J9111998-03-31031 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
Project stage: Meeting
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
Project stage: Meeting
1998-03-31
[Table View] |
|
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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
' April 16,1998
, LICENSEE: V rmont Ytnkee Nucbtr Pow r Corporttion (VYNPC)
FACILITY: Vermont Ycnk;o Nucirr Power St: tion
SUBJECT:
SUMMARY
OF MEETING ON APRIL 7,1998, REGARDING ACTIVITIES AT VERMONT YANKEE NUCLEAR POWER STATION (TAC NO. MA0987)
On April 7,1998, representatives of VYNPC, licensee for the Vermont Yankee Nuclear Pcwer Station met with members of the staff to discuss plans and activities related to the assurance of adequate net positive suction head (NPSH) for certain safety-related pumps. Enclosure 1 is a list of attendees. Enclosure 2 contains copies of handouts distributed at the meeting.
The licensee stated that no credit for containrnent pressure is necessary in the analysis for adequate NPSH. The pump vendor has confirmed the pump curve NPSH data being used by the licensee, and a vendor report documenting this position is expected shortly. The NPSH margins are being improved by installation of new suction strainers during the current outage.
Regarding containment temperature analysis, the licensee indicated that the adequacy of a 90 degree Fahrenheit (F) initial torus temperature would be confirmed and a technical specification (TS) amendment will be submitted before restart from the current outage. The current TS limit is 100 degrees F, however, the licensee is currently controlling torus temperature to a more restrictive temperature based on its analysis. The licensee has conservatively calculated peak i torus temperature following events to be less than 185 degrees F based on the results of the large break loss-of-coolant accident (LOCA) analysis (which results in a 182 degree F peak) and results of previous analyses indicating peak temperatures that were within 1 degree F of the large break LOCA peak or less. Confirmatory analyses of the additional events will be completed by the end of 1998. The licensee appears to be taking appropriate actions in this area.
The justification for pump curve extrapolation for the core spray pump at 4600 g.p.m. was discussed. The licensee agreed to pursue this with the pump vendor and provide the information to the NRC with a supplemental response to Generic Letter 97-04, Assurance of i Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps, i Original signed by l Richard P, Croteau, Project Manager I Project Directorate 1-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-271 3
Enclosures:
- 1. List of Attendees cc w/encis: See next page
- 2. Handouts D!STRIBUTION (wtencl.11 E-Mail Hard Cy wiencts.182
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J Zwohnski(JAZ) J. Kudock (JAK1) PUBLIC C. Hehl, RI R Croteau Y R Lobel(RML) R Wessman(RHW) )
T. Clark (TLC 1) T. Martin (SLM3) l C. Berhnger (CHB) J Kudnck(JAK1) l
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C. Cowgill(CJC1)
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DOCUMENT NAME: G:\CROTEAU\MEETSUM.498 To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with cttachment/ enclosure "N" = No copy , /)///
OFFICE PDI-3/PM ,, l PDI-3/LA , p() l(' EMEB, ,
TClark U fjN RWbsVm"$n CBerlinger hChiM SRXB -fgi Pfl-3/E llkJ NAME RCroteau l//n TCollins (G4fionias DATE 04/3/98 04/9/98 04/9/98 ,
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9804210196 980416 PDR ADOCK 05000271 P PDR
'o Vermont Yankee Nuclear Power Station ec:
Regional Administrator, Region i Jonathan M. Block, Esq.
U. S. Nuclear Regulatory Commission Main Street 475 Allendale Road P. O. Box 566 King of Prussia, PA 19406 Putney, VT 05346-0566 Mr. David R. Lewis Mr. Raymond N. McCandless Shaw, Pittman, Potts & Trowbridge Vermont Division of Occupational 2300 N Street, N.W. and Radiological Health Washington, DC 20037-1128 Administration Building Montpelier,VT 05602 Mr. Richard P. Sedano, Commissioner Vermont Department of Public Service Mr. Gautam Sen 120 State Street,3rd Floor Ucensing Manager Montpelier, VT 05602 Vermont Yankee Nuclear Power Corporation Public Service Board 185 Old Ferry Road State of Vermont Brattleboro, VT 05301 120 State Street Montpelier, VT 05602 Resident inspector Vermont Yankee Nuclear Power Station Chairman, Board of Selectmen U. S. Nuclear Regulatory Commission Town of Vemon P.O. Box 176 P.O. Box 116 Vemon, VT 05354 Vemon, VT 05354-0116 Mr. Peter LaPorte Director Mr. Richard E. McCullough ATTN: James Muckerheide Operating Experience Coordinator Massachusetts Emergency Management Vermont Yankee Nuclear Power Station Agency i P.O. Box 157 400 Worcester Rd.
Govemor Hunt Road P.O. Box 1496 Vemon, VT 05354 Framingham, MA 01701-0317 G. Dana Bisbee, Esq. Mr. Donald A. Reid Deputy Attomey General Senior Vice President, Operations 33 Capitol Street Vermont Yankee Nuclear Power Corp.
Concord, NH 03301-6937 185 Old Ferry Road Brattleboro,VT 05301 Chief, Safety Unit Office of the Attomey General One Ashburton Place,19th Floor Boston, MA 02108 ;
Ms. Deborah B. Katz Box 83 shellbume Falla, MA 01370 j
n LIST OF ATTENDEES NRCNYNPC Meeting April 7,1998 j NAME ORGANIZATION Cecil Thomas NRR Dick Wessman NRR/EMEB Richard Croteau NRR Bill Sherman Statt. JVermont Jack Kudrick NRR/SCSB Rich Lobel NRR/SCSB Kerri Kavanagh NRR/SRXB Joe Colaccino NRR/EMEB Don Leach Vermont Yankee '
George Morris NRC, Region I Greg Cranston NRC, Region i John Hoffman Vermont Yankee Bill Maher Sequoia Consulting Group Goutam Sen Vermont Yankee Thomas B. Silko Vermont Yankee Bruce Slifer Vermont Yankee Enclosure 1
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O VERMONT YANKEE NRC Meeting Agenda for 4/7/98 Introduction . . . . . . . . .. . . . . . . . . . . . . . . Don Leach Net Positive Suction Head (NPSH) . . Bruce C. Slifer Licensing Basis 1
Base Case and Sensitivity Study Vendor Issues / Pump Performance Bulletin Status . . . . . . . . . . . . . . . . John R. Hoffman a Status of Analyses Supporting Proposed TS Change . . . . . . . . . . John R. Hoffman
- BMO Status Update . . . . . . . . . . . . . . . . . Don Leach
- Open issues . . . . . . . . . . . . . . . . . . . . . . . . . . . . . All Enclosure 2 ,
1 4/7/98 i
@ VERMONT YANKEE NET POSITIVE SUCTION I-LEAD EFFECT OF NEW ECCS SUCTION STRAINERS Basis per response to GL 97-04 (dated 1/19/98)
No containment overpressure Debris effects per Regulatory Guide 1.82, Revision 1
. Evaluated effects of:
New strainers LOCA without LNP
- Vendor confirmed pump curve NPSH data
l 2 4/7/98 ,
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O VERMONT YANKEE NET POSITIVE SUCTION HEAD EFFECT OF NEW ECCS SUCTION STRAINERS The available NPSH is given as follows, I
NPSHA (ft)= h, + h,, - hyp, - h,,
I where: i l
- h=
a Absolute pressure (in feet) on the surface of I the liquid supply level h,,= Static height (in feet) that the liquid supply level is above or below the pump datum h,=
yp Head (in feet) corresponding to the vapor l pressure of the liquid at the temperature being pumped I h,, = All suction line losses (in feet) including entrance losses, friction losses, and strainer loss.
3 4/7/98
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VERMONT YANKEE NET POSITIVE SUCTION HEAD EFFECT OF NEW ECCS SUCTION STRAINERS h, Pressure at surface of suppression pool Vermont Yankee does not currently credit containment pressure above atmospheric in the NPSH evaluation.
A nominal value of 14.7 psia for the containment pressure is used.
Hence, i
h, = (14.7.) (144) / p, I where p,is the liquid density at the temperature of the liquid being pumped.
4 4/7/98
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VERMONT YANKEE NET POSITIVE SUCTION HEAD EFFECT OF NEW ECCS SUCTION STRAINERS h , Pool level relative to pump datum' Both the Vermont Yankee CS and RHR pumps are vertical, single stage pumps with in-line suction and discharge nozzles.
Thus, the datum of the CS and RHR pumps is taken as the elevation of the suction nozzle centerline.
The RHR and CS pump suction elevations are obtained from plant "as-built" drawings and are 215'-11" and 215'-9", respectively.
GL97-04 used the elevation of the suppression pool surface at minimum initial pool level of 227'-1 23/64" (FSAR Fig. 5.2-1).
This evaluation uses actualpool volume following a LOCA without an LNP.
5 4/7/98
O VERMONT YANKEE NET POSITIVE SUCTION HEAD EFFECT OF NEW ECCS SUCTION STRAINERS h,yp Vapor pressure of the pumped fluid The vapor pressure is a function of the bulk pool temperature. h,p is given by hyp, =P yo, (144) / p, where Pyo,is the vapor pressure.
Vermont Yankee uses the peak pool temperature for the limiting scenario to bound the NPSH calculation.
The peak pool temperatures used in the current NPSH calculations are 176 F for the long-term and 155 F for the short term.
This evaluation considers higher temperatures following a LOCA without an LNP.
6 4/7/98
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VERMONT YANKEE NET POSITIVE SUCTION HEAD EFFECT OF NEW ECCS SUCTION STRAINERS h,, Pump suction line losses. I The key elements in this term are the debris, strainer, and suction piping losses.
In the GL 97-04 calculation, i i
the debris loss is based on Regulatory Guide 1.82, Revision 1, the strainer loss is conservatively assumed to be 1 ft, l
)
the strainer entrance tee is included in the i suction piping loss calculation. l In the new strainer calculation, the debris loss based on Regulatory Guide 1.82, Revision 1 is nil, the strainerloss is based on the vendor guaranteed value and includes the transition fittings.
7 4/7/98
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VERMONT YANKEE NET POSITIVE SUCTION HEAD EFFECT OF NEW ECCS SUCTION STRAINERS
Operator action, as described in FSAR, at 10 minutes ,
o RHR secured from LPCI mode and put in containment cooling / spray mode,7000 gpm.
o Core spray throttled to 3000 gpm.
o NPSH evaluated at peak pool temperature, which occurs at ~ 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
l 8 4/7/98
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VERMONT YANKEE NET POSITIVE SUCTION HEAD EFFECT OF NEW ECCS SUCTION STRAINERS
- Pump Performance Based on original pump witness test data.
Vendor reviewed bounding pump operating conditions and confirmed acceptable pump performance.
Vendor recommended 28 ft NPSH @ 4600 gpm for Core Spray pump.
Vendor recognizes that pump cavitation is expected for design basis post-LOCA conditions, but will not prevent pumps from performing their intended function.
c Original pump curves remain acceptable for determining pump performance. !
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9 4/7/98
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l kNET POSITIVE VERMONT YANKEE SUCTION HEAD l
EFFECT OF NEW ECCS SUCTION STRAINERS RHR, Short-Term (<10 minutes),
2 Pumps / Loop,7100 gpm per Pump i
NEW TERM GL 97-04 STRAINER .
1 h, 34.65 34.75
-h, yp - 9.91 -12.32 h,, 11.2 12.32
-ho3,i, -1.83 nil '
-h,1,,ine, -3.86 -1.22
-h nigin, -3.95 -3.95 NPSHA 26.3 29.6 NPSHR 22.7 22.7
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MARGIN 3.6 6.9 NPSH Margin improved by New Strainer I
10 4/7/98
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@ VERMONT YANKEE NET POSITIVE SUCTION HEAD l EFFECT OF NEW ECCS SUCTION STRAINERS CS, Short-Term (<10 minutes),4600 gpm NEW TERM GL 97-04 STRAINER h, 34.65 34.75
-h, yp l - 9.91 -12.32 I h et 11.36 12.49
-hoes,i, - 0.68 nil 1
-h st,,ine, -2.16 - 0.55
-h oinin, - 5.31 - 5.31 NPSHA 28.0 29.1 NPSHR 27.7 28.0 MARGIN 0.3 /. / 0.0 4 NPSH Margin improved by New Strainer 11 4/7/98
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@ VERMONT YANKEE NET POSITIVE SUCTION HEAD EFFECT OF NEW ECCS SUCTION STRAINERS RHR, Long-Term,7000 gpm NEW TERM GL 97-04 STRAINER h, ! 34.90 34.97
-h ypo - 16.31 : -18.68 h,s 11.2 12.42
-ha3,is -1.72 nil
-h st,,ine, -1.74 - 0.31
-h pipino - 2.33 -2.33 NPSHA 24.0 26.1 NPSHR 22.6 22.6 MARGIN 1.4 3.5 NPSH Margin improved by New Strainer 12 4/7/98
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M VERMONT YANKEE NET POSITIVE SUCTION HEAD EFFECT OF NEW ECCS SUCTION STRAINERS l Core Spray, Long-Term,3000 gpm NEW TERM GL 97-04 STRAINER 1
h, 34.90 34.97
-h, yn - 16.31 -18.68 h,s 11.36 12.59
-hees,is -1.18 nil
-h st,,ine, -1.49 -0.24
-h pipin, -2.26 -2.26 NPSHA 25.0 26.4 NPSHR 24.1 24.1 MARGIN 0.9 2.3 NPSH Margin improved by New Strainer 13 4/7/98
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M VERMO:ST YANKEE Bulletin /GL Response Status
- Bulletin 96-03 Response submitted March 18,1998 Final response and design basis change when debris methodology is finalized
- GL 97-04 Response submitted January 19,1998 Information presented today updates that response 14 4/7/98 1
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k VERMONT YANKEE Status of Containment Temnerature Analvses
Complete licensing base case using new analysis methodology Establish margin adjustment for results to compensate for more limiting cases and confirm 90 F initial torus temperature Complete plant evaluations for increased torus temperature Implement any required procedure revisions and training Update BMO 96-05 (SE 96-008, BVY 97-60 concluded 166 F to 176 F not a USQ; new evaluation will be prepared to address increase above 176 F)
Submit Technical Specification Amendment to reduce the initial torus temperature to 90 F (this value is the input to the containment analysis !
calculations) l i
15 4/7/98 l
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'@ VERMONT YANKEE Status of Containment Temperature Analyses (cont.)
Complete confirmatory analyses for IBLOCA, SBLOCA, Appendix R, SRV transients (EOY 1998)
Update FSAR (EOY 1998)
Closecut BMO 96-05
Large break LOCA in review / approval cycle Conservatively calculated peak torus temperature less than 185 F Analyses incorporate instrument accuracy effects i
Analyses incorporate conservative treatment of feedwater addition !
Analyses incorporate operating mode effects i
16 4/7/98 l
i M VERMONT YANKEE I Basis for Maintaining Operation (BMOs) Related to Startup (update since 3/5/98 meeting)
Originally,13 scheduled for final resolution following the outage Two (2) closed BMO 97-03, off-site power TS (PC 194)
BMO 97-12, battery charger TS (PC 195)
Currently 12 scheduled for final resolution following the outage NRC inspection team for BMOs. Two (2) weeks ending April 24.
- Vermont Yankee letter to the NRC, April 24.
Includes integrated assessment 17 4/7/98
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