|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210E0201999-07-16016 July 1999
Summary of 990629 Meeting with Util in Rockville,Md Re Ongoing Efforts in Planning Sf Storage Strategy,Including Licensing of Isfsi,At Plant.With Attendance List & TVA Handout
ML20210D7801999-07-16016 July 1999
Summary of 990715 Meeting with TVA Re TVA Evaluation of Fee Structure Compared with Recent Actual Fees & NRC Guidance in Estimating Review Effort for Licensing Actions.List of Attendees & Matl Used in Presentation Enclosed
ML20210D7601999-07-16016 July 1999
Summary of 990616 Meeting with TVA in Rockville MD to Brief Staff on Planned SG Replacement.List of Attendees & Handout Provided by TVA Encl
ML20237E9811998-08-25025 August 1998
Summary of 980708 Meeting W/Tva & Framatome Cogema Fuel in Rockville,Md Re Ongoing Efforts W/Doe to Fabricate & Install Four Lead Test Assemblies in Plant,Unit 2 Core During Cycle 10 Refueling Outage in Spring of 1999.Attendance List Encl
ML20216H5261997-08-26026 August 1997
Summary of 970822 Meeting W/Util in Rockville,Md Re Followup to Series of Conference Calls on 970418,discussing Results of Recent Steam Generator Insps at Sequoyah Unit 1.List of Attendees,Handouts & Staff Questions Encl
ML20140B4701997-06-0404 June 1997
Summary of 970530 Meeting W/Tva in Rockville,Md to Discuss Status of Thermo-Lag Fire Barrier Corrective Action Program at Plant & Schedule for Completion of Program.W/Attendance List & TVA Handout
ML20140G5621997-05-0808 May 1997
Summary of 970227 Meeting W/Tva in Rockville,Md to Discuss Sequoyah Conversion to Framatome Cogema Fuel.List of Attendees Encl
ML20134J7451996-11-0808 November 1996
Summary of 961104 Meeting W/Tva in Rockville,Md Re Status of Thermo-Lag Fire Barrier Upgrades at Plant.List of Attendees & Copies of Handouts Encl
ML20129H5211996-10-29029 October 1996
Summary of Operating Reactors Events Meeting 96-13 on 961023,informing Senior Managers from Ofcs of Commission,Oe, NRR & Regional Ofcs of Selected Events That Occurred Since Last Briefing
ML20217D1931994-03-0707 March 1994
Summary of Sequoyah Restart Panel 940303 Meeting in Region II Ofc Re Status of NRC & Licensee Activities for Restart of Unit 1.Meeting Minutes & Unit 1 Restart Action Plan Encl
ML20059K3131993-11-0505 November 1993
Summary of Operating Reactors Events Meeting 93-42 on 931103
ML20056H5721993-08-0505 August 1993
Summary of Operating Reactors Events Meeting 93-28 on 930728
ML20217D2111993-06-16016 June 1993
Summary of Sequoyah Restart Panel 930614 Meeting in Region II Ofc Re Plant Restart & Listed Items.List of Attendees & Checklists Encl.Next Meeting Will Be Held on 930622
ML20127D1321993-01-12012 January 1993
Summary of Operating Reactors Events Meeting 93-01 on 930106
ML20058J8621990-11-27027 November 1990
Summary of 901005 Meeting W/Util in Rockville,Md Re Cable Conduit Testing Program.Viewgraphs & Attendee List Encl
ML20058K0311990-11-23023 November 1990
Summary of Operating Reactors Events Meeting 90-28 on 901114 Re Reactor Scrams for Wk Ending 901111.Attendees Listed
ML20062C8111990-10-16016 October 1990
Summary of Operating Reactors Events Meeting 90-25 on 901010.List of Attendees,Reactor Scram Statistics & Tabulation of Events Encl
ML20059N2091990-09-21021 September 1990
Summary of 900919 Operating Reactors Events Meeting 90-023 to Discuss Significant Elements
ML20059D8121990-09-0505 September 1990
Summary of 900817 Meeting W/Util in Rockville,Md Re Schedules of Certain Mods Committed for Completion in Unit 2 Cycle 4 Refueling Outage.Engineeering for Unit 2 Will Be Completed Before Restart from Outage
ML20056B4101990-08-20020 August 1990
Summary of 900723 Meeting W/Util in Rockville,Md Re Plant Cable/Conduit Testing Program for safety-related Cable.List of Attendees,Tva & NRR Handouts & Transcript of Meeting Encl
ML20055E2081990-07-0505 July 1990
Summary of 900531 Meeting W/Tva in Rockville,Md Re Plant safety-related Cable Inside Containment.List of Attendees, & Handouts Presented at Meeting Encl
ML20246J8031989-07-12012 July 1989
Summary of 890609 Meeting W/Util in Rockville,Md Re Dissolution of Engineering Assurance Organization.List of Meeting Attendees,Util Handout,Agenda & Transcript Encl
ML20245F9761989-06-22022 June 1989
Summary of 890614 Meeting W/Util & Westinghouse in Rockville,Md Re Future Work for Facility Cycle 4 Refueling Outage
ML20247M1001989-05-26026 May 1989
Summary of 890511 Meeting W/Util in Rockville,Md Re Performance of Best Estimate Calculations for App K Analyses.Proposed Plan for LOCA Analyses,Meeting Handouts & List of Attendees Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20155A8081988-09-29029 September 1988
Summary of 880915 Meeting W/Util in Rockville,Md Re Microbiological Influenced Corrosion Program at Plant.List of Attendees & Viewgraphs Encl
ML20154M9231988-09-21021 September 1988
Summary of 880913 Meeting W/Util at Site Re Unit 2 Shutdown Margin & Unit 1 Restart Readiness,Per Insp Repts 50-327/88-35 & 50-328/88-35.List of Attendees & Related Info Encl
ML20154H4341988-09-16016 September 1988
Summary of 880908 Meeting W/Util in Rockville,Md Re Changes to Conditions Adverse to Quality Program.List of Attendees Encl
ML20206B1961988-07-29029 July 1988
Summary of ACRS Subcommittee for TVA Organizational Issues 880722 Meeting in Washington,Dc Re Generic Lessons Learned from NRC Review of Util Concerning Restart of Facility
ML20153A8371988-07-0101 July 1988
Summary of 880622 Meeting W/Util in Rockville,Md Re TVA Commitments on Facility.List of Attendees & Util Handout Encl
ML20150E2321988-06-21021 June 1988
Summary of 880613 Meeting W/Util to Discuss Restart of Facility in Light of Recent Scrams from Power.Transcript of Meeting Encl
ML20196A9201988-06-17017 June 1988
Summary of Operating Reactors Events Meeting 88-24 on 880614.Two Significant Events Identified for Input to NRC Performance Indicator Program.No Events Suggested for long-term Followup.List of Attendees Encl
ML20154A4061988-05-0404 May 1988
Summary of 880414 Meeting W/Util in Rockville,Md Re Differences Between Units 1 & 2 Nuclear Performance Plan. List of Attendees & Licensee Handout Encl
ML20151D2701988-03-12012 March 1988
Summary of ACRS Subcommittee on TVA Organizational Issues Meeting on 880202-03 in Chattanooga,Tn Re Review of TVA Mgt Reorganization & Issues Re Restart of Unit 2
ML20149M6071988-02-22022 February 1988
Summary of 880211 Meeting W/Util Re Load Sequencing of Plant Diesel Generators.Attendance List & Handout Matl Used During Meeting Encl
ML20195J5251988-01-21021 January 1988
Summary of 880120 Meeting Between Commissioner Bernthal & Admiral White of TVA Re Util Request to Retain Ofc of Special Projects as Overseer of Plants After Sequoyah 1 Restart & Invitation to Bernthal to Tour Sequoyah Plant
ML20148Q0801988-01-21021 January 1988
Summary of Operating Reactors Events Meeting 88-03 on 880119.List of Events & Summaries of Presented Events & 1988 Scrams Encl
ML20195J6011987-12-0303 December 1987
Summary of ACRS Subcommittee TVA Organizational Issues 871004 Meeting W/Nrc & Util in Washington,Dc Re Actions Being Taken on Plant Restart Issues
ML20236X4741987-12-0202 December 1987
Summary of 871124 Meeting W/Util in Bethesda,Md Re Results of Testing of Silicone Rubber Insulated Cables for Unit 2. Transcript of Meeting Encl
ML20236K8951987-11-30030 November 1987
Trip Rept of 871028-30 Site Visit to Gather Info from Files to Facilitate Updating Sims Database
ML20235B2261987-09-15015 September 1987
Summary of 870910 Meeting W/Util in Knoxville,Tn Re Status of Cable Test Program.List of Attendees & Transcript Encl
ML20235B1271987-09-15015 September 1987
Summary of 870911 Meeting W/Tva Re NRC Staff Presentation to TVA Findings from Integrated Design Insp.List of Attendees & Meeting Transcription Encl
ML20239A6691987-09-0404 September 1987
Summary of 870901 Meeting W/Util,Bechtel & S&W in Bethesda, MD Re Criteria for Pipe Supports.List of Attendees,Handouts & SQN-DC-V-24.2 Supports for Rigorously Analyzed Category I Piping Encl
ML20237G7631987-08-26026 August 1987
Summary of 870819 & 20 Meetings W/Util at Facility Re Status of Technical Issues Requiring Resolution Prior to Restart. List of Attendees,Agenda & Handouts Encl
ML20235X0921987-07-16016 July 1987
Summary of 870713 Meeting W/Util,Franklin Research Ctr, Sandia,S&W & NUS Corp in Bethesda,Md Re Cable Testing Program.Util Proposing Revised Cable Testing Program to Test 380 Cables.Attendees List & Transcript Encl
ML20234B9831987-06-26026 June 1987
Summary of 870619 Meeting W/Util in Bethesda,Md Re Util Proposed Program for Regeneration of Nonretrievable Pipe Support Calculations & Verification of Technical Adequacy of Existing Calculations.Attendees List & Util Handout Encl
ML20216D0121987-06-19019 June 1987
Summary of 870601 Meeting in Bethesda,Md to Discuss Special Employee Concern Program.Attendee List & Handouts Encl
ML20215A1881987-06-0909 June 1987
Trip Rept of 870520-22 Visit to Regional Ofc & Site to Discuss Ofc Procedures for Processing of Util Allegations & Status of Essential Elements of Restart Program
ML20214L5911987-05-18018 May 1987
Summary of 870420 Meeting W/Tva in Chattanooga,Tn Re Review of Rev 4 to Vol 1 of TVA Nuclear Performance Plan & Status of Vol II of Plan.Agenda,Transcript of Meeting,List of Attendees & Viewgraphs Encl
1999-07-16
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210D7801999-07-16016 July 1999
Summary of 990715 Meeting with TVA Re TVA Evaluation of Fee Structure Compared with Recent Actual Fees & NRC Guidance in Estimating Review Effort for Licensing Actions.List of Attendees & Matl Used in Presentation Enclosed
ML20210D7601999-07-16016 July 1999
Summary of 990616 Meeting with TVA in Rockville MD to Brief Staff on Planned SG Replacement.List of Attendees & Handout Provided by TVA Encl
ML20210E0201999-07-16016 July 1999
Summary of 990629 Meeting with Util in Rockville,Md Re Ongoing Efforts in Planning Sf Storage Strategy,Including Licensing of Isfsi,At Plant.With Attendance List & TVA Handout
ML20237E9811998-08-25025 August 1998
Summary of 980708 Meeting W/Tva & Framatome Cogema Fuel in Rockville,Md Re Ongoing Efforts W/Doe to Fabricate & Install Four Lead Test Assemblies in Plant,Unit 2 Core During Cycle 10 Refueling Outage in Spring of 1999.Attendance List Encl
ML20216H5261997-08-26026 August 1997
Summary of 970822 Meeting W/Util in Rockville,Md Re Followup to Series of Conference Calls on 970418,discussing Results of Recent Steam Generator Insps at Sequoyah Unit 1.List of Attendees,Handouts & Staff Questions Encl
ML20140B4701997-06-0404 June 1997
Summary of 970530 Meeting W/Tva in Rockville,Md to Discuss Status of Thermo-Lag Fire Barrier Corrective Action Program at Plant & Schedule for Completion of Program.W/Attendance List & TVA Handout
ML20140G5621997-05-0808 May 1997
Summary of 970227 Meeting W/Tva in Rockville,Md to Discuss Sequoyah Conversion to Framatome Cogema Fuel.List of Attendees Encl
ML20134J7451996-11-0808 November 1996
Summary of 961104 Meeting W/Tva in Rockville,Md Re Status of Thermo-Lag Fire Barrier Upgrades at Plant.List of Attendees & Copies of Handouts Encl
ML20129H5211996-10-29029 October 1996
Summary of Operating Reactors Events Meeting 96-13 on 961023,informing Senior Managers from Ofcs of Commission,Oe, NRR & Regional Ofcs of Selected Events That Occurred Since Last Briefing
ML20217D1931994-03-0707 March 1994
Summary of Sequoyah Restart Panel 940303 Meeting in Region II Ofc Re Status of NRC & Licensee Activities for Restart of Unit 1.Meeting Minutes & Unit 1 Restart Action Plan Encl
ML20059K3131993-11-0505 November 1993
Summary of Operating Reactors Events Meeting 93-42 on 931103
ML20056H5721993-08-0505 August 1993
Summary of Operating Reactors Events Meeting 93-28 on 930728
ML20217D2111993-06-16016 June 1993
Summary of Sequoyah Restart Panel 930614 Meeting in Region II Ofc Re Plant Restart & Listed Items.List of Attendees & Checklists Encl.Next Meeting Will Be Held on 930622
ML20127D1321993-01-12012 January 1993
Summary of Operating Reactors Events Meeting 93-01 on 930106
ML20058J8621990-11-27027 November 1990
Summary of 901005 Meeting W/Util in Rockville,Md Re Cable Conduit Testing Program.Viewgraphs & Attendee List Encl
ML20058K0311990-11-23023 November 1990
Summary of Operating Reactors Events Meeting 90-28 on 901114 Re Reactor Scrams for Wk Ending 901111.Attendees Listed
ML20062C8111990-10-16016 October 1990
Summary of Operating Reactors Events Meeting 90-25 on 901010.List of Attendees,Reactor Scram Statistics & Tabulation of Events Encl
ML20059N2091990-09-21021 September 1990
Summary of 900919 Operating Reactors Events Meeting 90-023 to Discuss Significant Elements
ML20059D8121990-09-0505 September 1990
Summary of 900817 Meeting W/Util in Rockville,Md Re Schedules of Certain Mods Committed for Completion in Unit 2 Cycle 4 Refueling Outage.Engineeering for Unit 2 Will Be Completed Before Restart from Outage
ML20056B4101990-08-20020 August 1990
Summary of 900723 Meeting W/Util in Rockville,Md Re Plant Cable/Conduit Testing Program for safety-related Cable.List of Attendees,Tva & NRR Handouts & Transcript of Meeting Encl
ML20055E2081990-07-0505 July 1990
Summary of 900531 Meeting W/Tva in Rockville,Md Re Plant safety-related Cable Inside Containment.List of Attendees, & Handouts Presented at Meeting Encl
ML20246J8031989-07-12012 July 1989
Summary of 890609 Meeting W/Util in Rockville,Md Re Dissolution of Engineering Assurance Organization.List of Meeting Attendees,Util Handout,Agenda & Transcript Encl
ML20245F9761989-06-22022 June 1989
Summary of 890614 Meeting W/Util & Westinghouse in Rockville,Md Re Future Work for Facility Cycle 4 Refueling Outage
ML20247M1001989-05-26026 May 1989
Summary of 890511 Meeting W/Util in Rockville,Md Re Performance of Best Estimate Calculations for App K Analyses.Proposed Plan for LOCA Analyses,Meeting Handouts & List of Attendees Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20155A8081988-09-29029 September 1988
Summary of 880915 Meeting W/Util in Rockville,Md Re Microbiological Influenced Corrosion Program at Plant.List of Attendees & Viewgraphs Encl
ML20154M9231988-09-21021 September 1988
Summary of 880913 Meeting W/Util at Site Re Unit 2 Shutdown Margin & Unit 1 Restart Readiness,Per Insp Repts 50-327/88-35 & 50-328/88-35.List of Attendees & Related Info Encl
ML20154H4341988-09-16016 September 1988
Summary of 880908 Meeting W/Util in Rockville,Md Re Changes to Conditions Adverse to Quality Program.List of Attendees Encl
ML20206B1961988-07-29029 July 1988
Summary of ACRS Subcommittee for TVA Organizational Issues 880722 Meeting in Washington,Dc Re Generic Lessons Learned from NRC Review of Util Concerning Restart of Facility
ML20153A8371988-07-0101 July 1988
Summary of 880622 Meeting W/Util in Rockville,Md Re TVA Commitments on Facility.List of Attendees & Util Handout Encl
ML20150E2321988-06-21021 June 1988
Summary of 880613 Meeting W/Util to Discuss Restart of Facility in Light of Recent Scrams from Power.Transcript of Meeting Encl
ML20196A9201988-06-17017 June 1988
Summary of Operating Reactors Events Meeting 88-24 on 880614.Two Significant Events Identified for Input to NRC Performance Indicator Program.No Events Suggested for long-term Followup.List of Attendees Encl
ML20154A4061988-05-0404 May 1988
Summary of 880414 Meeting W/Util in Rockville,Md Re Differences Between Units 1 & 2 Nuclear Performance Plan. List of Attendees & Licensee Handout Encl
ML20151D2701988-03-12012 March 1988
Summary of ACRS Subcommittee on TVA Organizational Issues Meeting on 880202-03 in Chattanooga,Tn Re Review of TVA Mgt Reorganization & Issues Re Restart of Unit 2
ML20149M6071988-02-22022 February 1988
Summary of 880211 Meeting W/Util Re Load Sequencing of Plant Diesel Generators.Attendance List & Handout Matl Used During Meeting Encl
ML20148Q0801988-01-21021 January 1988
Summary of Operating Reactors Events Meeting 88-03 on 880119.List of Events & Summaries of Presented Events & 1988 Scrams Encl
ML20195J5251988-01-21021 January 1988
Summary of 880120 Meeting Between Commissioner Bernthal & Admiral White of TVA Re Util Request to Retain Ofc of Special Projects as Overseer of Plants After Sequoyah 1 Restart & Invitation to Bernthal to Tour Sequoyah Plant
ML20195J6011987-12-0303 December 1987
Summary of ACRS Subcommittee TVA Organizational Issues 871004 Meeting W/Nrc & Util in Washington,Dc Re Actions Being Taken on Plant Restart Issues
ML20236X4741987-12-0202 December 1987
Summary of 871124 Meeting W/Util in Bethesda,Md Re Results of Testing of Silicone Rubber Insulated Cables for Unit 2. Transcript of Meeting Encl
ML20235B2261987-09-15015 September 1987
Summary of 870910 Meeting W/Util in Knoxville,Tn Re Status of Cable Test Program.List of Attendees & Transcript Encl
ML20235B1271987-09-15015 September 1987
Summary of 870911 Meeting W/Tva Re NRC Staff Presentation to TVA Findings from Integrated Design Insp.List of Attendees & Meeting Transcription Encl
ML20239A6691987-09-0404 September 1987
Summary of 870901 Meeting W/Util,Bechtel & S&W in Bethesda, MD Re Criteria for Pipe Supports.List of Attendees,Handouts & SQN-DC-V-24.2 Supports for Rigorously Analyzed Category I Piping Encl
ML20237G7631987-08-26026 August 1987
Summary of 870819 & 20 Meetings W/Util at Facility Re Status of Technical Issues Requiring Resolution Prior to Restart. List of Attendees,Agenda & Handouts Encl
ML20235X0921987-07-16016 July 1987
Summary of 870713 Meeting W/Util,Franklin Research Ctr, Sandia,S&W & NUS Corp in Bethesda,Md Re Cable Testing Program.Util Proposing Revised Cable Testing Program to Test 380 Cables.Attendees List & Transcript Encl
ML20234B9831987-06-26026 June 1987
Summary of 870619 Meeting W/Util in Bethesda,Md Re Util Proposed Program for Regeneration of Nonretrievable Pipe Support Calculations & Verification of Technical Adequacy of Existing Calculations.Attendees List & Util Handout Encl
ML20216D0121987-06-19019 June 1987
Summary of 870601 Meeting in Bethesda,Md to Discuss Special Employee Concern Program.Attendee List & Handouts Encl
ML20214H8681987-05-18018 May 1987
Summary of 870326 Meeting W/Util Re Diesel Generator Sequencing Calculations.Util Response to Questions in Form of Rev 5 to Calculations,Engineering Change Notification, List of Attendees & Other Related Documents Encl
ML20214L5911987-05-18018 May 1987
Summary of 870420 Meeting W/Tva in Chattanooga,Tn Re Review of Rev 4 to Vol 1 of TVA Nuclear Performance Plan & Status of Vol II of Plan.Agenda,Transcript of Meeting,List of Attendees & Viewgraphs Encl
ML20214F4431987-05-0808 May 1987
Summary of 870410 Meeting W/Tva in Bethesda,Md Re Status of Plant Restart Issues.Meeting Transcript & Related Documentation Encl
1999-07-16
[Table view] |
Text
-
May 7, 1987 Docket Nos. 50-327/328 LICENSEE: TENNESSEE VALLEY AUTHORITY (TVA)
FACILITY: Sequoyah Nuclear Plants, Units I and 2
SUBJECT:
APRIL 2, 1987 MINUTES OF MEETING WITH TVA TO DISCUSS THE CRITERIA USED FOR THE SE000YAH NUCLEAR PLANT RESTART On Thursday, April 2,1987, a meeting was held at NRC, Bethesda, Maryland with representatives from TVA to discuss the criteria used by TVA for determining whether an issue or problem would require resolution prior to the restart of either Sequoyah Nuclear Plant Unit.
Attachment 1 is the meeting summary which describes the significant items discussed and the actions taken or proposed. Attachment 2 is the list of participants that attended the meeting. Attachment 3 is the subject restart criteria discussed which was provided by TVA via memorandum from S. A. White to those listed, entitled, " Restart Requirement Criteria," dated March 13, 1987 and in Table 7 of Revision 1 to Volume II of the TVA Nuclear Performance Plan, dated April 1, 1987. Attachment 4 is a flow chart provided by NRC staff which was used for discussion during the meeting.
NRC staff requested that TVA submit to NRC a summary of the history regarding the original process of identifying issues which required resolution prior to restart. This submittal should include a description of how issues were brought to the Restart Task Force and how the Restart Task Force functioned to differentiate the issues requiring resolution prior to restart from those that did not. The NRC staff concluded that the subject restart criteria provided in Attachment 3 are acceptable; however, certain documentation with regard to the implementation of these criteria needs to be provided. NRC staff requested TVA submit a description of the development of the restart criteria, and an explanation of actions taken in the past which would prevent items from being excluded from the Sequoyah Activities List. During the meeting, TVA committed to provide the requested submittals discussed above.
Original signed by Thomas S. Rotella, Project Manager Division of TVA Projects Office of Special Projects
Attachment:
- 1. Summary
- 2. List of Atterdees
- 3. Restart Criteria ',
- 4. Flow Chart cc w/ attachments:
See next page TVA:0SP TVA:0SP TVA:0SP h TV : P A CJamersakl TR9 tel.la.cw JDonohev JwolinsEi C$/ob/87 06/ j /87 0 /87 r7 /87 0705190177 070507 PDR ADOCK 05000327 P PDR L________
c Sequoyah Nuclear Plant CC:
Tennessee Department of Regional Administrator, Region II Public Health U.S'. Nuclear Regulatory Commission, ATTN: Director, Bureau of 101 Marietta Street, N.W.
Environmental Health Services Atlanta, Georgia 30323 l
)
Cordell Hull Building Nashville, Tennessee 37219 Mr. R. W. Cantrell Fr. Michael H. Mohley, Director ATTN: D.L. Williams Tennessee Valley Authority Division of Radiological Health 400 West Summit Hill Drive, W12 A12 T.E.R.R.A. Building Knoxville, Tennessee 37902 150 9th Avenue North Nashville, Tennessee 37203 Mr. Bob Faas Westinghouse Electric Corp. County Judge P.O. Box 355 Hamilton County Courthouse Pittsburgh, Pennsylvania 15230 Chattanooga, Tennessee 37402 Mr. R. L. Gridley Mr. Richard King Tennessee Valley Authority c/o U.S. GAO i
Efl 157B Lookout Place 1111 North Shore Drive l Suite 225, Box 194 Chattanooga, Tennessee 37402-2801 Knoxville, Tennessee 37919 Mr. M. R. Harding Tennessee Valley Authority Mr. S. A. White Sequoyah Nuclear Plant Manager of Nuclear Power P.O. Box 2000 Tennessee Valley Authority Soddy Daisy, Tennessee 37379 6N 38A Lookout Place 1101 Market Place Resident Inspector /Sequoyah NP Chattanooga, Tennesseee 37402-2801 c/o U.S. Nuclear Regulatory Commission 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379
(
Mr. H.L. Abercromhie Tennessee Valley Authority Secuoyah Nuclear Plant P.O. Box 2000 Soddy Daisy, Tennessee 37379
Attachment 1 4
SUMMARY
OF APRIL 2, 1987 MEETING WITH TVA REGARDING RESTART CRITERIA The meeting began with NRC staff introductory remarks regarding the_ purpose of the meeting. A discussion of the restart criteria subsequently commenced.
TVA presented an overall history of the direction taken to identify problems which might affect the restart of the Sequoyah Units. A description of this history was deemed important by the NRC staff and a request for submittal describing such was made.
The TVA explained how the list of restart items for Sequoyah was developed. TVA formed the Sequoyah Restart Task Force at the site with TVA upper managcment individuals. The Task Force requested that all individuals at the site present to it all lists of items that should be fixed at Sequoyah. From these lists, the Task Force identified 702 items at Sequoyah requiring resolution prior to restart. At this stage of the problem identification, no delineated or formal i
restart criteria existed; however, the Task Force members were stated as being experienced in the various disciplines to understand the specific issues and their impact on startup. Certain problems identified only required analysis for resolution while others required facility modifications.
' Sequoyah procedure, SOA-190, is the controlling procedure used for determination of whether a newly identified item requires resolution prior to restart.
TVA stated that on February 23, 1987, the Condition Adverse to Quality (CAQ)
, reporting process was implemented. This process provides a mechanism for anyone in TVA to raise a , safety issue or a particular problem to his/her supervisor to ascertain whether the issues needs to be fixed. All CAO reports get a restart determination. This determination is conducted using the restart x criteria in Attachment 3. TVA presented details of the actual process an individual would go through to resolve an issue thought to warrant restart consideration.
TVA stated that the Design Baseline Verification Program issues, which were found to require resolution prior to restart, are put or the Sequoyah Activities List t
(SAL). The decision that it is a restart item is based on the restart criteria.
The SAL is the controlling activities list used to track restart activities.
.The staff requested that TVA provide documentation regarding the development of the restart criteria, the SAL and the Sequoyah Restart Task Force. The staff requested that TVA explain any differences between how the SAL was developed for Sequoyah and how a similar list would be developed for Browns Ferry, t
i After consideration of the information presented by TVA and previous NRC staff
! review, NRC staff determined that the subject restart criteria were acceptable.
NRC staff expressed concern, bokever, regarding the effective implementation of these criteria. As a result, NRC staff requested that TVA submit to NRC an explanation of how the restart criteria have been developed and implemented and J
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.n . : :.. .
' - 2 who is currently making decisions regarding restart issues since the Restart Task Force had been officially dissolved on March 5,1987. NRC staff also suggested.TVA take a sample of the issues currently listed on the SAL and redetermine their requirement for completion prior to restart using the subject restart criteria.
NRC staff expressed some concern, due to a lack of docketed information, with regard to the consistency of application / interpretation of the restart criteria. The flow chart, see Attachment 4, was developed by NRC staff in an attempt to achieve consistency in applying the restart criteria. TVA stated that the CAQ reporting process provides the consistency the NRC stOff desired.
TVA stated that a planned revision to the CAQ program will include 6 procedural change to require an evaluation of individual CAQ's against the restart criteria.
The CAO definition stated by TVA was: Adverse conditions including nonconforming materials, parts, or components; failures; malfunctions; deficiencies; deviations; hardware problems involving system which do not comply with licensing, codes, specifications, or drawing requirements; and nonhardware problems such as failure to comply with the operating licensing, Technical Specifications, procedures, instructions, or regulations.
TVA committed to send to NRC a letter describing the CAQ program process of assuring quality as it relates to restart.
i
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- Attachment 2 s
Attendees.
April 2, 1987 Affiliation Name TVA Projects /NRC Thomas S. Rotella Office of Investigation, NRC Ben B. Hayes R. Gridley TVA - Licensing Mike Harding TVA - Site Licensing Mgr.
T. A. Ippolito TVA - Consultant TVA Projects /NRC John A. Zwolinski TVA Projects /NRC Jack N. Donohew TVA Projects /NRC B. D. Liaw ,
TVA Projects /NRC s.
John F. Stang Robert Hermann OSP/TVA/EB Jane A. Axelrad OSP/NRC G. Gears OSP/NRC i
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, ATTACHMEi1T 3
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UNJTCD $7ATEb COVERNMENT
", Memorand um Qi TENNESSEE VALLEY AUTHORIT[!
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I, 20 : Those listed i FROM : 5. A. White. Manager of Nuclear Power. LP 6N 38A-C DATI : March 13. 1987
SUBJECT:
RESTART REQUIREMENT CRITERIA
References:
(1) C. C. Mason's memorandum to Those listed dated November 26, 1986 (102 861126 013)
(2) R. W. Cantroll's memorandum to Those listed dated December 23. 1986 (L44 861224 108)
This memorandum supersedes references 1 and 2 and any other previous instructions relative to restart requirement criteria. The criteria in the attached table have evolved from the original Yolume 2 criteria. .
Though the requirements are in essence the same se the earlier.' criteria.
these include the lessons learned through implementation at Sequoyah and Browns Ferry. Use of these refined criteria on Sequoyah and Browns Ferry activities has shown that these criteria do meet the test of being easily understood and easily applied.
These critoria are in effect for all plants until we revise Volumes 2 and 3. After the units have been restored for normal operations the respective site directors will make a recommendation to me regarding a transition to sole reliance on plant technical specification requirements. ,
,h. ,
70: See list on page 2 l ,
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Those listed ,
March 13, 1987 t RESIAWT. REQUIREMENT CRITERIA 70: H. L. Ahv crombie, ONP, Sequoyah
- W. R. Bro... Jr.. EC70. ONP, Watts Bar ,
C. H. Crowell, LP 6N 38A-C J. P. Darling ONP, Bellefonte S. B. Fisher. LP SN 38A-C C. H. Fox, Jr., LP 6N 38A-C R. L. Gridley, LP $N 1575-C ,
W. H. Hannum, BR IN 768-C L. L. Jackson. LP 4N 38A-C T. 3. Jenkins, LP 6N 38A-C R. J. Johnson. POTC-C .
J. A. Kirkebo, W12 A12 C-R C. C. Mason. LP 6N 38A-C D. E. Nichols, 210 A14 C-K R. C. Parker, LP 4N 45A-C '
R. A. Pedde,11-127 SB-K R. A. Pedde. 101 PRO Bidt., Watts Bar .
H. P. Pomrehn. Browns Ferry C. G. Robertson, LF 55 83E-C R. K. Seiberling, 716C EB-C R. K. Sliger, LP 2N 978-C M. E. Taylor. LP 6N 38A-C G. Toto. ONP, Watts Sar
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Attachment cc: EIES._Mt 4N 721-C J ,tt,achme1 Int) %
c be: Mr. S. D. Ebnater Director TVA Projects Division U.S. Nuclear Regulatory Commission l
l Washington, D.C. 20555 l
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RESTART REQUIREME.17 CRITERIA 1
The following criteria shall be used in evaluating whether a particulac * .
item must be resolved prior to startup. -
1.
The 1~ tem identifies a specific deficiency which has significant
- probability of leading to the inoperability of a system required for startup or operation by the appropria'te Technical Specifications.
The item identifies a progrannatic deficier.cy which has a high 2.
probability of causing or has caused a specific deficiency which ,
meets No. I above. .
NOTE: To assist in the determination of required for restart reistive to Technical Specificaticas as in criteria No.1 and No. 2 above. an affirmative answer to any of the following questions requires consideration of the item for restart based on Technical '
' specification requirements. ,
- a. Does the item directly and ad'versely affect safety-related .
i equipment function. performance, reliability, or resp,onse timet
- b. Does the item indirectly and adversely affect safety-related
- equipment power supply, air supply, cooling. lubrication, or ventilation?
- c. Dces the item adversely affect primary cor.tainment intcarityf
- d. Dces the item adversely affect secondary containment integrity!
- e. Does the ltts adversely affect c'ontrol room habitability! . .
- f. Does the item adversely affect systems used to process ,
. radioactive wastaf ,
- a. . g. Does the stesi adversely affect fire protection or fire leadst ,
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- h. Does the item adversely affect the ability of a system or ,
component to meet its safety function during a design basis event by impacting the seismic analysis, single failure criteria, separation criteria, hign energy line break assumptions, or equipment qualificatient
- 1. Are the programs such as Radiological Health. Security. '
I Radiological Emergency preparedness, or quality Assurance which are necessary for safe conduct of operation of the plant adversely affectedt
- j. If not corrected prior to rotart, could it lead to an uncontrolled release or spread of radioactive contamination .
beyond the regulated area.
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The item identifies a specific deficiency that results in a failure 3.
to semply'With NRC regulations and ho variance has been approved by * ' .,
NAC; . . . . . .
- 4. TTA has conreitted to NRC to comp'lete the item prior to restatt. .
S. The item identifies a specific deficioney which has a significant .
probability of. leading to a persoral injury during plant operaties.
- 4. The item identifies a specific condition which has a forced estate **
risk (probability X outage length) during the next cycle in excess of ,
the critical path time to correct the condition prior to restart.
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?RESTARI? II B ANALYZER INPUIIIEM
--YES--dAFE OPERATIpH MAYlPACI
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'# tkREQUIREMENT M 0-(D s s 9./ ,- ._
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NOT RESIARI RESIARI -
ISSUE ISSUE (A) Safe Shutdown Systems / Equipment as define' in the FSAR (B) Accident Mitigation Svstems/ Equipment as described in the FSAR (C) NRC Approved Extension (i.e., Schedular Exemptions OSP Approved Completion Date)
(0) Regulations, Orders, License Conditiois, Technica Specifica ions l
l, _n Distribution for Meeting Summary Dated: May 7, 1987 Facility: Sequoyah Nuclear Plant, Units 1 and 2 WW???kYN!WD NRC PDR Local PDR J. Axelrad S. Ebneter S. Richardson J. Zwolinski B. D. Liaw G. Zech, RII S. R. Connelly, 01A B. Hayes 01 J. Donohew T. Rotella J. Holonich J. Kelly C. Jamerson F. Miraglia ACRS(10)
OGC-BETH TVA-Bethesda Projects Rdg SE0 File J. Stang J. Partlow R. Hermann G. Gears E. Jordan
- Copy sent to persons on facility service list I
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