Letter Sequence Meeting |
|---|
|
|
MONTHYEARML20151X2711998-09-14014 September 1998
Informs That Info Contained in Re Holtec Rept, HI-981932,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended
Project stage: Other
ML20196K2781999-01-0404 January 1999
Summary of 981217 Meeting with Util to Discuss Plans & Activities Re Spent Fuel Storage at Plant.List of Attendees & Handouts Encl
Project stage: Meeting
ML20202E4021999-01-28028 January 1999
Forwards Draft RAI Re Proposed Amend on SFP Assemblies Storage Expansion.Memo & Encl Do Not Convey Formal Request for Info or Represent NRC Position
Project stage: Draft RAI
ML20205K7461999-04-0808 April 1999
Advises That Info Contained in Holtec Intl Affidavit, Will Be Withheld from Public Disclosure,Per 10CFR2.790
Project stage: Other
ML20206G6391999-05-0404 May 1999
Informs That Version of Holtec Intl Rept HI-981932 Marked as Proprietary Submitted by Util Will Be Withheld from Pubic Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended
Project stage: Other
ML20209G6931999-07-14014 July 1999
Forwards Request for Addl Info Re Spent Fuel Storage Capacity Expansion
Project stage: RAI
ML20217N3901999-10-25025 October 1999
Advises That Info Provided in & Affidavit Re Holtec Position Paper WS-115,rev 1,repts HI-87113, Rev 0,HI-87114,rev 0,HI-87102 Rev 0 & HI-87112,rev 0,marked Proprietary,Will Be Withheld from Public Disclosure
Project stage: Other
1999-10-25
[Table View] |
|
|---|
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
.~ .
l l ?
Jarmary 4,1999 fr:87/
l LICENSEE: Vermont Yankee Nuclear Power Corporation (VYNPC)
FACILITY: Vermont Yankee Nuclear Power Station
SUBJECT:
SUMMARY
OF MEETING ON DECEMBER 17,1998, REGARDING ACTIVITIES AT VERMONT YANKEE NUCLEAR POWER STATION (TAC NO. MA3490)
On December 17,1998, representativeo of VYNPC, licensee for the Vermont Yankee Nuclear Power Station met with members of the staff to discuss plans and activities related to spent fuel storage at Vermont Yankee Nuclear Power Station. Enclosure 1 is a list of attendees.
Enclosure 2 contains copies of handouts distributed at the meeting and enclosure 3 is a copy of the licensee's procedure titled " Radiological Controls for Underwater Diving Operations."
The staff requested that the licensee provide a letter documenting the correct enrichment tolerance used in it's analysis associated with the September 4,1998, submittal requesting an increase in the spent fuel storage capacity of the Vermont Yankee spent fuel pool from 2870 to 3355 fuel assemblies. The licensee agreed to provide the information in a letter.
Origimi signed by:
Richard P. Croteau, Project Menager Project Directorate 1-3
Enclosures:
- 1. List of Attendees Division of Reactor Projects - 1/11
- 2. Handouts Office of Nuclear Reactor Regulation
- 3. Radiological Controls for Underwater Diving Operations cc w/encls: See next page DISTRIBUTION wrencl.1 E-Mail Hard Coov w/encls.1&2 S. Collins /R. Zimmerman @ Docket File #
B. Boger Ve:mont Yankee r/f J. Zwolinski PUBLIC T. Martin (e-mail SLM3) ACRS T. Clark OGC NRC Meeting Attendees (see Enclosure 1)
C. Cowgill B.McCabe DOCUMENT NAME: G:\CROTEAU/MEETSM.128 To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy ,,
OFFICE PDI-3/PM PDi-3/LA m lE .PDi-3/PDa, , l l NAME RCroteauk TClarkMO CThomal l DATE 12/ //98 12/M/98 12/IT/98 7~
OFFICIAL RECORD COPY l
\\
't iOO i 9901110262 900104 PDR ADOCK 05000271 _ y~.
PDR
(.,o% (O .1 " " ' ' ^ fY e 7~ ~ _ '
P
Q Cit!
4? o t UNITED STATES
[e j f
NUCLEAR REGULATORY COMMISS!ON WASHINGTON, D.C. 20606-0001 o%, d January 4, 1999
. . . . . ,o JCENSEE: Vermont Yankee Nuclear Power Corporation (VYNPC)
ExCILITY: Vermont Yankee Nuclear Power Station
SUBJECT:
SUMMARY
OF MEETING ON DECEMBER 17,1998, REGA.RDING ACTIVITIES AT VERMONT YANKEE NUCLEAR POWER STATION (TAC NO. MA3490)
On December 17,1998, representatives of VYNPC, licensee for the Vermont Yankee Nuclear Power Station met with members of the staff to discuss plans and activities related to spent fuel storage at Vermont Yankee Nuclear Power Station. Enclosure 1 is a list of attendees.
Enclosure 2 contains copies of handouts distributed at the meeting and enclosure 3 is a copy of the licensce's procedure titled " Radiological Controls for Underwater Diving Operations."
The staff requested that the licensee provide a letter documenting the correct enrichment tolerance used in it's analysis associated with the September 4,1998, submittal requesting an increase in the spent fuel storage capacity of the Vermont Yankee spent fuel pool from 2870 to 3355 fuel assemblies. The licensee agreed to provide the information in a letter.
( a%
R.ichard P, Croteau, Project Manager Project Directorate I 3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Enclosures:
- 1. List of Attendees
- 2. Handouts
- 3. Radiological Controls for Underwater Diving Operations cc w/encls: See next page 1
l l
l l
l NRC/VYNPC Meetina i
December 17.1998 List of Attendees l LLAME ORGANIZATION Richard Croteau NRR Larry Kopp NRR Diane Jackson NRR Charles Hinson NRR Yong Kim NRR/DE/ECGB Bob Rothman NRR/DE/ECGB Ron Fish Vermont Yankee Thomas B. Silko Vermont Yankee Stan Miller Vermont Yankee John Hoffman Vermont Yankee l Kalyan K. Niyogi Holtec
! Everett Redmond ll Holtec Michael P. McNamara Holtec i James Doman DOE I l.
I i
l Enclosure 1 t
e l
. . . - - , .. .. .- . - - . - - . - - . - . - - - . - . - . - - . ~ . - . _ -
l i
l Vermont Yankee Nuclear Power Station cc: i i
L l Regional Administrator,' Region 1
_ Jonathan M. Block, Esq.
U. S. Nuclear Regulatory Commission Main Street 475 Allendale Road P. O. Box S66 King of Prussia, PA 19406 Putney, VT 05346-0566 L
! Mr. David R. Lewis Mr. Raymond N. McCandless t Shaw, Pittman, Potts & Trowbridge Vermont Division of Occupational
. 2300 N Street, N.W. and Radiological Health l
Washington, DC 20037-1128 Administration Building l l Montpelier, VT 05602 l- Mr. Richard P. Sedano, Commissioner Vermont Department of Public Service Mr. Gautam Sen <
120 State Street,3rd Floor Licensing Manager l 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 l P.O. Box 116 Vernon,VT 05354 i Vernon, VT 05354-0116 Mr. Peter LaPorte, Director Mr. Richard E. McCullough ATTN: James Muckerheide Operating Experler ce Coordinator Massachusetts Emergency Management Vermont Yankee Nuclear Power Station Agency P.O. Box 157 400 Worcester Rd.
Governor Hunt Road P.O. Box 1496 Vernon, VT 05354 Framingham, MA 01701-0317 l G. Dana Bisbee, Esq. Mr. Gregory A. Maret Deputy Attorney General Director of Operations 33 Capitol Street Vermont Yankee Nuclear Power Corp.
Concord, NH 03301-6937 185 Old Ferry Road Brattleboro,VT 05301
- , .. Chief, Safety Unit l Office of the Attorney General Mr. Michael J. Daley One Ashburton Place,19th Floor Trustee and Legislative Representative Boston, MA 02108 New England Coalition on Nuclear Pollution, Inc.
Ms. Deborah B. Katz Box 545 Box 83 Brattleboro, VT 05301 l Shelbume Falls, MA 01370 1
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'l Vermont Yankee Nuclear Power Corporation Spent Fuel Storage Rack License Amendment USNRC Meeting g
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! December 17,1998
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Team Members John Hoffman, Vermont Yankee, Special Projects Mgr
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- Tom Silko, Vermont Yankee, Senior Licensing Engmeer
- Stan Miller, Vermont Yankee, Spent Fuel Project Manager
- Ron Fish, Vermont Yankee, Spent Fuel Project Engmeer
- Mike McNamara, Holtec ,
- Everett Redmond, Holtec,
- K.K. Niyogi, Holtec December 17,1998 2
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Overview of Project
- Total 17 percent increase in storage capacity, from 2870 to 3355 licensed storage locations.
- Two racks (net increase of 219 storage locations - 8 percent) scheduled for installation in 2000-2001 operating cycle.
- Third rack (266 storage locations) will be available if needed for an unplanned full core discharge after 2004 refueling.
- Project philosophy is to simplify licensing by utilizing previously licensed technology (VY and other sites).
- hysical. parameters compatible with existing racks to simplify December 17,1998 4
SPENT FUEL P0OL' LAYOUT -
NORTH 4" ""
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EXISTING RACK EXISTING RACK -
20 X 13 20 X'13 SP 4A 5 6 I 4.2 ur l
l EXISTING RACK EXISTING RACK EXISTING RACK o Es&ES' tie'""
12.m- 20 X 15 20 X 15 20 X 15 4B 4D: 4C l t
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l EXISTING RACK EXISTING RACK '
EXISTING RACK _
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- 3.08" REF. I BUAL M RPOSE CELLS. ,
l RACE BEICITtIb.h 501 1.D. = 6.0 NI BALL TRE. = 0.075 uoOULE CA 25.8808- l 22 =
MM PM" " = ' "5 FIGURE 2.1: POOL LAYOUT FOR VERMONT YANKEE ""ot' s' 50MLE NE 16,8108 N N RACES : 640 CELLS NAL M RPOSE CELLS: 8 TOTAL CELL COUNT:672. _
i December 17, 1998 5 1
, l Comparison With Existing Racks ,
Same materials of construction (304L stainless steel). .
- Same fuel cell pitch (6.218 inche s).
- Same poison material (Boral).
- Same B io areal density (0.027 gm/cm2),
- Same top-of-rack elevation above spent fuel pool floor.
- Same construction codes and acceptance standards (ASME Section III, Subsection NF).
December 17,1998 6
- m Design / Analysis Overview
- Both the existing racks and the new racks were included in the dynamic analyses.
- Both the existing racks and the new racks were included in the criticality and thermal / hydraulic analyses.
i
- Reactor building structural loads (global and local) are bounded by the analyses performed to support Amendment No.104. .
- Heat load on Standby Fuel Pool Cooling System within system capability evaluated in Amendment No.130.
December 17,1998 7
StaffQuestions :
- Emergency Preparedness and Radiation Protection Branch
- In-plant Dose Rates
-- Installation
- DBA AccidentImpact
- Reactor Systems Branch .
~
- CASMO-4 Code
- Neutron Cross Sections
- Treatment of Gadolinia
- K, and Enrichment Limits .
- Axial Burnup
- Enrichment Tolerance December 17,1998 .
8 ,
i
In-Plant Dose Rate Effects
- Dose assessment basis used for Amendment No.104 (largest rack fully loaded with freshly discharged fuel located in most adverse position) bounds the effect of the three new racks proposed in this submittal.
- Other changes in fuel design and operating history since the Amendment No.104 re-racking have been evaluated and result in less than a 1 mrem /hr increase in in-plant dose at the exterior fuel pool wall.
- There will be no change in any plant area radiation classifications as a result of the addition of the three new spent fuel racks.
December 17,1998 9
Installation 4
- Minimal amount of highly irradiated material anticipated in pool when installation of racks begins in year 2000. ,
- Any diving activities will be controlled by plant procedure AP-0515, which is a Continuous Use procedure.
- AP-0515 requires a physical barrier to maintain separation between divers and radiation source.
December 17,1998 10
9 Design Basis Accident Design Basis Fuel Handling Accident is the drop of a fuel assembly onto the reactor core, involving damage to two fuel assemblies.
Accident consequences are unaffected by the proposed' change in storage capacity
- maximum possible drop height over the spent fuel racks is less than over the reactor vessel. Thus a " head on" drop into a fuel storage cell will be no more severe than a drop in the reactor vessel
- spent fuel racks have been analyzed for a fuel assembly drop to ensure that a drop onto a rack will not damage any stored fuel assemblies or result in a geometry change in the racks that would affect the criticality calculations.
December 17,1998 11
CASMO-4 Code 1
- CASMO-4 cannot be directly compared to critical experiments '
since it is a two dimensional code.
- The code developer has performed limited comparisons to critical experiments.
- CASMO-4 has been compared to MCNP-4A, which has been benchmarked against~ critical experiments.
- Comparison demonstrates that CASMO-4 is conservative and can be used without the need for a calculational bias.
December 17,1998 12
Neutron Cross Sections :
- CASMO-4 uses the 40 Group Library, Update L.
- MCNP-4A uses the cross sections in Appendix G of the User manual, which is based on the ENDF-B/V data. The benchmarking used the same cross sections. ;
i i
December 17,1998 13
m Gadolinia
- The statement that no credit is taken for gadolinia was :
confusing in the context it was used.
- The Technical Specification requirement limiting K-infinity to 1.31 or less in the Standard Cold Core Geometry inherently considers the effect of gadolinia and therefore no additional consideration is required in the analysis. .
- The analyses performed in support of this amendment request were conservatively performed using a K-infinity limit of 1.33.
- There are no burnup requirements or restrictions on storage of fuel in any of the racks.
December 17,1998 14
O K ny and Enrichment Requirements
- Technical Specification 5.5.E "The maximum core geometry infinite lattice multiplication factor of any '
segment of the fuel assembly stored in the spent fuel storage pool or the new storage facility shall be less than or .
equal to 1.31 at 20o C." ,
- This K-infinity based Technical Specification aligns Vermont Yankee with the fuel vendor's design criteria, as specified in Section 3.5 of GESTAR-II (NEDE-24011-P-A) ;
December 17,1998 15 i
e e
e K ay and Enrichment Requirements - Cont'd
- Maximum Cold K-infinity " figure of merit" provides the most meaningful test of fuel reactivity as it relates to its insertion into the spent fuel pool.
- K-infinity of the fuel is a function of enrichment, gadolinium content, burnup, void history, and enrichment distribution in the lattice.
- All the above effects can be accounted for by means of the maximum cold K-infinity check that is required by Technical Specification 5.5.E, and administered via OP 1401.
December 17,1998 16
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Axial Burnup Effects ,
- Reference to PWR fuel was confusing.
. BWR fuel has axial blankets which suppresses burnup effects.
- Analysis is performed at peak reactivity which is at a low burnup (<12 GWD/MTU). Potential axial burnup effects don't occur until higher burnups when assembly reactivity is lower than the peak. Therefore, it is not of concern.
December 17,1998 17
e k Enrichment Tolerance 1
- Vermont Yankee procures uranium from Cogema with a 0.013 w/o tolerance on enrichment and supplies the uranium. to General Electric Company. i
- Both the 1986 submittal and this application reported the Cogema enrichment tolerance in the submittal documentation. ;
- Immediate action was to .#erify that the 0.01 delta-K reduction term used for j the existing rack criticality analysis would bound an enrichment tolerance of 0.05 w/o (DOE value). It does.
- Criticality calculations supporting this application were re-performed using a 0.05 w/o enrichment tolerance. Results still satisfy USNRC acceptance criteria.
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- Structural Analysis Overview a
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Computer Code Used 3
DYNARACK i
- - used for whole pool multi-rack and single rack analysis i
t December 17,1998 19
_ y t
t Seismic Simulations I
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- A series of single rack and whole pool multi-rack simulations performed
- Dynamic Simulations performed for both SSE and OBE events i
December 17.1998 20
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1 Dynarack Model A set of three DYNARACK models used in the analysis :
Whole Pool Multi-Rack Model (WPMR) - I
- all racks included
- 3 new racks
- 9 existing racks
- Whole Pool Multi-Rack Model-II
- used for Intermediate Configuration of the pool :
all racks except rack CA included in the model December 17,1998 21
L Continued...
- Single Rack Model
- only one rack included
- rack with highest aspect ratio and weight (rack CA) selected for this model
- is simulated with different fuel array configurations
- is simulated to check the kinematic stability of an isolated rack in the pool a
December 17,1998 22
e # 6 a
Modeling Details
- The geometrical and material properties of new and existing racks are calculated for use in the multi-rack analysis.
- Rack beam stiffnesses (shear, bending, extension and torsion) calculated for both new and existing racks.
- Coefficients of friction used 0.2, 0.8 and random.
- Seismic Input - Taft Earthquake,1% Structural damping.
December 17,1998 23
~
Analysis Results I
- Racks kinematic stability is ensured.
- No rack-to-rack and rack-to-wall impacts predicted by the analysis during the occurrence of SSE and OBE seismic i events.
- Stresses in the racks are within the ASME Code, Subsection i
NT, allowable limit. -
i December 17,1998 24
l a Thermal-hydraulic Analysis Overview
- Decay Heat Loads - Branch Technical Position, ASB 9-2
- Bulk Pool Temperature - Remains within Tech. Spec. Limit
- Pool heat-up/ loss of cooling - Normal refueling TTB 11-12 hrs.
- Full core discharge TTB 6-21 hrs.
- Maximum local temperature - 50 F below saturation temperature December 17,1998 25
Summary Minor (17 percent), conservatively designed expansion in storage capacity.
Consistent with the conclusions documented in SERs i for Amendments No.104 and 130.
Uses previously licensed technology (either at .
Vermont Yankee or other reactor sites).
We are prepared to support XRC fully in your review of the application.
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December 17,1998 26 i
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