|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20207H3531999-06-14014 June 1999
Summary of 990317 Meeting with SCE Re Issues Staff Identified in Review of 980910 License Amend Application & Exemption Request to Remove Hydrogen Monitoring & Control Sys from SONGS Licensing Basis.Meeting Attendee List Encl
ML20216B8551998-05-0707 May 1998
Summary of 980429 Meeting W/Southern California Edison in Rockville,Maryland Re Proposed Amend to TS to Allow Operation of Plant at Reduced Tcold in Reactor Coolant Sys. W/Meeting Slides & List of Meeting Attendees
ML20203A3531998-01-29029 January 1998
Summary of 971223 Meeting W/Sce in Rockville,Md to Discuss Mechanical Nozzle Seal Assembly Relief Request.List of Attendees & Slides Encl
ML20199G7121997-11-0606 November 1997
Summary of 971023 Meeting W/Util in Rockville,Md Re Results of Steam Generator Tube Degradation & Run Time Analysis for SONGS Unit 2.List of Attendees & Slides Encl
ML20058N4851993-12-15015 December 1993
Summary of 931119 Meeting W/Sce in Rockville,Md Re Proposed Decommissioning Plan for SONGS 1.List of Attendees Encl
ML20057D1681993-09-27027 September 1993
Summary of 930805 Meeting W/Util Re Methods of Providing Control Room Operators W/Optimal Info on Instrument Accuracies Under Harsh Environ Conditions.List of Attendees & Util Slides Encl
ML20128F3481993-02-0202 February 1993
Summary of 920113 Meeting W/Util Re Commercial Grade Dedication at Plant
ML20126E7521992-12-14014 December 1992
Summary of 921119 Meeting W/Bg&E & SCE Re Document Retrieval Sys Development & Programs.List of Attendees Also Encl
ML20247E3641989-09-0606 September 1989
Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals
ML20247J6991989-05-19019 May 1989
Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl
ML20247J7051989-05-19019 May 1989
Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy
ML20055E3451989-05-0404 May 1989
Summary of 890501 Meeting Re Status of Util Effluents & Water Mgt Program & 1988 Annual Radiation Environ Operating Rept.Supporting Info Encl
ML20246N9201989-03-16016 March 1989
Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl
ML20247E4501989-03-16016 March 1989
Summary of 890213 Meeting w/C-E Owners Group in Rockville,Md Re Thermal Stratification in Pressurizer Surge Line,Per NRC Bulletin 88-011.List of Attendees & Viewgraphs Encl
ML20235M1671989-02-17017 February 1989
Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl
ML20151N0521988-07-26026 July 1988
Summary of Operating Reactors Events Meeting 88-30 on 880726.List of Attendees & Summary of Reactor Scrams Encl
ML20127A8631988-07-12012 July 1988
Trip Rept of 880210-11 Visit to Conax Buffalo Works to Obtain Info for Info Notice Re Problems W/Kapton Insulated Wire
ML20196F9951988-02-24024 February 1988
Partially Withheld Trip Rept of 880209-11 Mgt Team Visit to Region V & San Onofre & Trojan Sites Re Integrated Assessment of Mgt Effectiveness Associated W/Regionalized NRR & NMSS Programs
ML20149L4981988-02-12012 February 1988
Summary of 871207 Meeting W/Utils in Bethesda,Md Re Licensees Revised Proposal to Comply W/Nrc Requirement for Simulation Facilities Under 10CFR55.45(b).List of Attendees & Util Simulation Facility Group Guideline 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
ML20236A9731987-10-13013 October 1987
Summary of 870915-16 Meetings W/Four Facility Licensees in Bethesda,Md Re Proposal to Apply for NRC Approval for Simulation Facilities.Viewgraphs & Related Documents Encl
ML20239A0231987-09-10010 September 1987
Summary of Operating Reactor Events Meeting 87-30 on 870908, Re Briefing Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870825 Meeting.Attendees List,Summary of Reactor Scrams & Viewgraphs Encl
ML20214J4991987-05-15015 May 1987
Summary of Operating Reactors Events Meeting 87-09 on 870330 Re Events Which Occurred Since 870316 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20247H9551986-10-0303 October 1986
Summarizes Allegation Review Board 860822 Meeting Re Review of Allegation Presented by Allegation RV-86-A-0070.Board Agreed to Close Allegation Upon Notifying Licensee & Forwarding Info to Appropriate Law Enforcement Agency
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
ML20206S7361986-08-13013 August 1986
Summary of ACRS Subcommittee on Westinghouse Reactor Plants 860730 Meeting in Washington,Dc Re Review of Loss of All in- Plant Ac Power & 851121 Water Hammer Event.Presentation Schedule & Sequence of Events Encl
ML20206L9081986-08-11011 August 1986
Summary of Operating Reactor Events Meeting 86-27 on 860804 W/Ofc Director,Div Directors & Representatives Re Briefing on Events Which Occurred Since Last Meeting on 860728.List of Attendees & Viewgraphs Encl
ML20211L0581986-06-30030 June 1986
Summary of 860521 Meeting W/Nsss Owners Group,Numarc & INPO in Bethesda,Md Re Planned Industry Actions in Response to Check Valve & Water Hammer Event at Facility.List of Attendees,Agenda & Viewgraphs Encl
ML20211G7781986-06-13013 June 1986
Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20197F1691986-05-0808 May 1986
Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors
ML20203F1711986-04-22022 April 1986
Summary of 860407 Meeting W/Westinghouse,Ge,B&W & C-E NSSS Owners Groups in Bethesda,Md Re Actions in Response to 851121 Check Valve/Water Hammer Event
ML20141F4091986-04-10010 April 1986
Summary of Operating Reactors Events Meeting 86-10 W/Ofc Director,Div Directors & Representatives Re Events Since 860324.Viewgraphs & Supporting Documentation Encl
ML20205J7411986-02-28028 February 1986
Summary of ACRS 310th Meeting on 860213-15 in Washington,Dc Re Review Studies Done & Procedures Proposed by Gpu Nuclear to Protect Against Inadvertent Criticality During Defueling of TMI-2 Core
ML20138M9281985-12-12012 December 1985
Summary of Operating Reactor Events Meeting 85-25 on 851202 Re Listed Events.Attendee List,Summary of Events Discussed & Viewgraphs Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20133E4631985-10-0101 October 1985
Summary of Operating Reactors Events Meeting 85-17 on 850923.List of Attendees & Viewgraphs Encl
ML20133G9971985-07-10010 July 1985
Summary of ACRS SEP Subcommittee on San Onofre in Washington,Dc Re Integrated Plant Safety Analysis Rept
ML20127D6361985-04-15015 April 1985
Trip Rept of 850402-03 Meetings W/Util,Eg&G,Nct Engineering, Lll & Impell Re Proposed long-term Svc Criteria & Methodology.List of Attendees & Viewgraphs Encl
ML20136G6831985-02-28028 February 1985
Summary of 841106 Meeting in Washington,Dc Re Technical & Legal Reviews & Activities Concerning Investigation.W/O Stated Encls
ML20136G5951985-02-28028 February 1985
Summary of 841004 Meeting W/Util Re Restart
ML20126H0191984-10-22022 October 1984
Summary of 841019 Meeting W/Util Re Seismic Design Capability.Related Info Encl
ML20127C1831984-10-12012 October 1984
Summary of 841010 Meeting W/Util Re Legal Issues Associated W/Restart
ML20127C1791984-10-12012 October 1984
Summary of 841005 Meeting W/Util Re Restart Before Completion of Seismic Upgrade
ML20136H0481984-10-0202 October 1984
Summary of 840919 Meeting W/Util Re Util Organizational Changes
ML20215H5251984-08-24024 August 1984
Partially Deleted Summary of 870822 Meeting at Region V Ofc Re Allegation RV-84-0092 Concerning Alcohol & Drug Abuse at Plant.Members of Panel Listed.Action Plan Developed to Deal W/Allegations Encl.W/O Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20126D5631979-11-20020 November 1979
Summary of 791116 Meeting W/Applicant Re Seismology
ML20126D5261979-11-19019 November 1979
Summary of 791116 Meeting W/Applicant in Washington,Dc Re seismology.Woodward-Clyde Consultants Rept Encl
ML20148A2591978-10-16016 October 1978
Summary of 781006 Meeting W/Util to Discuss SSE Program. Summary of Util/Tera Presentation & Attendee List Encl
ML20126D5251978-10-0505 October 1978
Summary of 780928-29 Meeting in Bethesda,Md Re New Seismic Info Concerning Facility
1999-06-14
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20207H3531999-06-14014 June 1999
Summary of 990317 Meeting with SCE Re Issues Staff Identified in Review of 980910 License Amend Application & Exemption Request to Remove Hydrogen Monitoring & Control Sys from SONGS Licensing Basis.Meeting Attendee List Encl
ML20216B8551998-05-0707 May 1998
Summary of 980429 Meeting W/Southern California Edison in Rockville,Maryland Re Proposed Amend to TS to Allow Operation of Plant at Reduced Tcold in Reactor Coolant Sys. W/Meeting Slides & List of Meeting Attendees
ML20203A3531998-01-29029 January 1998
Summary of 971223 Meeting W/Sce in Rockville,Md to Discuss Mechanical Nozzle Seal Assembly Relief Request.List of Attendees & Slides Encl
ML20199G7121997-11-0606 November 1997
Summary of 971023 Meeting W/Util in Rockville,Md Re Results of Steam Generator Tube Degradation & Run Time Analysis for SONGS Unit 2.List of Attendees & Slides Encl
ML20058N4851993-12-15015 December 1993
Summary of 931119 Meeting W/Sce in Rockville,Md Re Proposed Decommissioning Plan for SONGS 1.List of Attendees Encl
ML20057D1681993-09-27027 September 1993
Summary of 930805 Meeting W/Util Re Methods of Providing Control Room Operators W/Optimal Info on Instrument Accuracies Under Harsh Environ Conditions.List of Attendees & Util Slides Encl
ML20128F3481993-02-0202 February 1993
Summary of 920113 Meeting W/Util Re Commercial Grade Dedication at Plant
ML20126E7521992-12-14014 December 1992
Summary of 921119 Meeting W/Bg&E & SCE Re Document Retrieval Sys Development & Programs.List of Attendees Also Encl
ML20247E3641989-09-0606 September 1989
Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals
ML20247J7051989-05-19019 May 1989
Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy
ML20247J6991989-05-19019 May 1989
Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl
ML20055E3451989-05-0404 May 1989
Summary of 890501 Meeting Re Status of Util Effluents & Water Mgt Program & 1988 Annual Radiation Environ Operating Rept.Supporting Info Encl
ML20247E4501989-03-16016 March 1989
Summary of 890213 Meeting w/C-E Owners Group in Rockville,Md Re Thermal Stratification in Pressurizer Surge Line,Per NRC Bulletin 88-011.List of Attendees & Viewgraphs Encl
ML20246N9201989-03-16016 March 1989
Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl
ML20235M1671989-02-17017 February 1989
Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl
ML20151N0521988-07-26026 July 1988
Summary of Operating Reactors Events Meeting 88-30 on 880726.List of Attendees & Summary of Reactor Scrams Encl
ML20149L4981988-02-12012 February 1988
Summary of 871207 Meeting W/Utils in Bethesda,Md Re Licensees Revised Proposal to Comply W/Nrc Requirement for Simulation Facilities Under 10CFR55.45(b).List of Attendees & Util Simulation Facility Group Guideline 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
ML20236A9731987-10-13013 October 1987
Summary of 870915-16 Meetings W/Four Facility Licensees in Bethesda,Md Re Proposal to Apply for NRC Approval for Simulation Facilities.Viewgraphs & Related Documents Encl
ML20239A0231987-09-10010 September 1987
Summary of Operating Reactor Events Meeting 87-30 on 870908, Re Briefing Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870825 Meeting.Attendees List,Summary of Reactor Scrams & Viewgraphs Encl
ML20214J4991987-05-15015 May 1987
Summary of Operating Reactors Events Meeting 87-09 on 870330 Re Events Which Occurred Since 870316 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20247H9551986-10-0303 October 1986
Summarizes Allegation Review Board 860822 Meeting Re Review of Allegation Presented by Allegation RV-86-A-0070.Board Agreed to Close Allegation Upon Notifying Licensee & Forwarding Info to Appropriate Law Enforcement Agency
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
ML20206S7361986-08-13013 August 1986
Summary of ACRS Subcommittee on Westinghouse Reactor Plants 860730 Meeting in Washington,Dc Re Review of Loss of All in- Plant Ac Power & 851121 Water Hammer Event.Presentation Schedule & Sequence of Events Encl
ML20206L9081986-08-11011 August 1986
Summary of Operating Reactor Events Meeting 86-27 on 860804 W/Ofc Director,Div Directors & Representatives Re Briefing on Events Which Occurred Since Last Meeting on 860728.List of Attendees & Viewgraphs Encl
ML20211L0581986-06-30030 June 1986
Summary of 860521 Meeting W/Nsss Owners Group,Numarc & INPO in Bethesda,Md Re Planned Industry Actions in Response to Check Valve & Water Hammer Event at Facility.List of Attendees,Agenda & Viewgraphs Encl
ML20211G7781986-06-13013 June 1986
Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20197F1691986-05-0808 May 1986
Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors
ML20203F1711986-04-22022 April 1986
Summary of 860407 Meeting W/Westinghouse,Ge,B&W & C-E NSSS Owners Groups in Bethesda,Md Re Actions in Response to 851121 Check Valve/Water Hammer Event
ML20141F4091986-04-10010 April 1986
Summary of Operating Reactors Events Meeting 86-10 W/Ofc Director,Div Directors & Representatives Re Events Since 860324.Viewgraphs & Supporting Documentation Encl
ML20205J7411986-02-28028 February 1986
Summary of ACRS 310th Meeting on 860213-15 in Washington,Dc Re Review Studies Done & Procedures Proposed by Gpu Nuclear to Protect Against Inadvertent Criticality During Defueling of TMI-2 Core
ML20138M9281985-12-12012 December 1985
Summary of Operating Reactor Events Meeting 85-25 on 851202 Re Listed Events.Attendee List,Summary of Events Discussed & Viewgraphs Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20133E4631985-10-0101 October 1985
Summary of Operating Reactors Events Meeting 85-17 on 850923.List of Attendees & Viewgraphs Encl
ML20133G9971985-07-10010 July 1985
Summary of ACRS SEP Subcommittee on San Onofre in Washington,Dc Re Integrated Plant Safety Analysis Rept
ML20136G6831985-02-28028 February 1985
Summary of 841106 Meeting in Washington,Dc Re Technical & Legal Reviews & Activities Concerning Investigation.W/O Stated Encls
ML20136G5951985-02-28028 February 1985
Summary of 841004 Meeting W/Util Re Restart
ML20126H0191984-10-22022 October 1984
Summary of 841019 Meeting W/Util Re Seismic Design Capability.Related Info Encl
ML20127C1831984-10-12012 October 1984
Summary of 841010 Meeting W/Util Re Legal Issues Associated W/Restart
ML20127C1791984-10-12012 October 1984
Summary of 841005 Meeting W/Util Re Restart Before Completion of Seismic Upgrade
ML20136H0481984-10-0202 October 1984
Summary of 840919 Meeting W/Util Re Util Organizational Changes
ML20215H5251984-08-24024 August 1984
Partially Deleted Summary of 870822 Meeting at Region V Ofc Re Allegation RV-84-0092 Concerning Alcohol & Drug Abuse at Plant.Members of Panel Listed.Action Plan Developed to Deal W/Allegations Encl.W/O Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20126D5631979-11-20020 November 1979
Summary of 791116 Meeting W/Applicant Re Seismology
ML20126D5261979-11-19019 November 1979
Summary of 791116 Meeting W/Applicant in Washington,Dc Re seismology.Woodward-Clyde Consultants Rept Encl
ML20148A2591978-10-16016 October 1978
Summary of 781006 Meeting W/Util to Discuss SSE Program. Summary of Util/Tera Presentation & Attendee List Encl
ML20126D5251978-10-0505 October 1978
Summary of 780928-29 Meeting in Bethesda,Md Re New Seismic Info Concerning Facility
ML20196H3981978-07-0505 July 1978
Summary of 780622 Meeting W/Westinghouse Owners Group to Discuss Results of Phase a of three-phase Plan & Current Schedule for Resolution of Asymmetric LOCA Loads Isssue.List of Attendees Encl
ML20148G7781978-01-18018 January 1978
Summary of 780105 Meeting W/Util Re SEP Review of Environ Qualification of Electrical Equipment
ML20245C3211977-07-11011 July 1977
Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls
1999-06-14
[Table view] |
Text
' # UNITED STATES l
- o g '
8 NUCLEAR REGULATORY COMMISSION
> $ CASHIN^; TON.C.C. 20666 f
- %,,,,,/ October 22, 1984 CFFICE OF THE COMMISSIONER MEMORANDUM FOR: Files FROFj: ohn Austin, Technical Assistant Patricia Davis, Legal Assistant Office of Comissioner Asselstine
SUBJECT:
MEETING ABOUT SAN ONOFRE 1 On October 19, 1984, Pat Davis and John Austin of Comissioner Asselstine's office met with Ken Baskin, Don Craven and Dave Piggott representing Southern California Edison Company (SCE) to discuss the seismic design capability of San Onofre 1. SCE indicated that in the May-June 1982 timeframe questions were raised by NRC staff about the capability of San Onofre 1 to withstand the original seismic design basis (0.5g) for the unit. The staff concerns arose from the preliminary results of a reanalysis of the plant using an assumed 0.67g acceleration. The staff evidently felt that the calculated stresses from the 0.67g value were so high that the ability of the plant to withstand a 0.59 acceleration was drawn into question.
SCE attempted a " generic" approach to resolving staff's concerns.
The approach consisted of looking at similar industrial facilities, designed in the same timeframe, which have experienced the effects of significant earthquakes. SCE and its consultants found that such facilities could withstand substantial accelerations even though earthquakes were not explicitly considered in the design.
SCE also performed an analysis on San Onofre 1 as-built, and as modified since 1982. SCE and its consultants analyzed, with a 0.5g input, about 1/3 of the large piping runs, all of the small piping runs, and most (about 90 percent) of the safety equipment. The large pipes analyzed were selected to be those 10 pipe runs which had been previously (i.e.1982) detemined to be the highest stressed pipes, and 3 other large pipe runs. The methods used were the same techniques that the NRC staff had approved in February 1984 for use in the 0.67g reanalysis, and are more sophisticated than those used in 1982. SCE found that all calculated stresses were within allowable limits.
The SCE position is that the ECCS and other necessary safety systems can withstand the effects of a 0.5g acceleration. The salt water in-take structure is qualified for at least that value also. SCE is not aware of any residual NRC staff concern about the capability of San Onofre 1 to withstand the effects of a 0.5g acceleration. SCE believes that the NRC staff will document its conclusions about the status of the seismic resistance of San Onofre 1 sometime during the week of October 22. ,
8506100215 B50326 PDR FOIA BELL 84-885 PDR i
V SAN ONOFRE UNIT 1 i[ '
STATUS 10/29/84 INFORMATION DUE REFERENCE
- 1. COMPLETION OF RETURN TO SERVICE PLAN LTR. CRUTCHFIELD A. CERTIFICATION PLAN COMPLETE TO BASKIN 10/19/84 B. DETERMINATION FAILURES IN NON-UPGRADED SYSTEMS WILL NOT PREVENT HOT STANDBY C. CONFIRMATION OF MASONRY WALL AS-BUILT CONFIGURATION (RECEIVED 10/29/84)
D. CONFIRMATION OF ANALYSIS QA/0C FOR 0.67G UPGRADES E. DETERMINISTIC BASIS FOR RESTART -
(IN J0/17/84 SCE LTR.)
- 2. REPORT DESCRIPTION OF 0.5G EVALUATION TELECONS GRIMES k TO BASKIN 10/24 AND 10/25/84
- 3. TDI - EVALUATION OF CRANKSHAFT CRACKING LTR. CRUTCHFIELD (REPORT RECEIVED 10/29/84 - COMPLETENESS TO BASKIN 9/18/84 NOT YET VERIFIED) AND MTG 10/22/84
- 4. REACTOR TRIP BREAKER TEST RESULTS GENERIC LTR 83-28 EVALUATION TO REGION V
- 5. ENVIRONMENTAL QUA'LIFICATION AUDIT REVIEW 10/02 JC0 ADDITIONAL INFORMATION THRU 10/04/84 AND MTG. 10/26/84 c/t
l l'
INFORMATION DUE REFERENCE 6.* MASONRY WALLS - SUPPORTING INFORMATION MTG. 09/05/84 7;* RESUBMIT "0VERPRESSURE MITIGATION SYSTEM" TELECON MCKENHA PROPOSED TECH SPECS TO PAINSBERRY 07/17/84
- 8,* REVISION TO LIMITING OVERTIME TECH SPEC LTR. PAULSON TO
~ ~
BASKIN'09/05/84 9.* SEP INTEGRATED ASSESSMENT - MTG. 07/10/84 ADDITIONAL INFORMATION AND UPDATE 10.* APPENDIX J TECH SPEC REVIEW TELECON MCKENNA TO SUPPORTING INFORMATION RAINSBERRY 06/29/84 11.* ENVIRONMENTAL QUALIFICATION REVIEW - LTR. CRUTCHFIELD TO SUPPORTING INFORMATION BASKIN 05/09/84
, 12.* ORGANIZATION TECH SPEC - LTR, PAULSON TO SUPPORTING INFORMATION BASKIN 09/07/84
- NOT REQUIRED FOR RESTART EVALUATION A FEW REQUESTS FOR ADDITIONAL INFORMATION ARE CURRENTLY BEING PREPARED IN CONJUNCTION WITH OTHER ONGOING REVIEWS WHICH SHOULD NOT AFFECT RESTART.
SAN ONOFRE UNIT 1 i STATUS 11/6/84 INFORMATION REQUESTED SUBMITTAL
- 1. COMPLETION OF RETURN TO SERVICE PLAN A. CERTIFICATION PLAN COMPLETE LETTER DATED 11/3/84 B. DETERMINATION FAILURES IN NON- LETTER DATED 11/3/84 UPGRADED SYSTEMS WILL NOT PREVENT HOT STANDBY C. CONFIRMATION OF MASONRY WALL LETTER DATED 10/27/84 AS-BUILT CONFIGURATION D. CONFIRMATION OF ANALYSIS QA/0C LETTER DATED 11/3/84 FOR 0.679 UPGRADES E. DETERMINISTIC BASIS FOR RESTART LETTER DATED 10/17/84
- 2. REPORT DESCRIPTION OF 0.59 EVALUATION LETTER DATED 11/3/84
- 3. TDI-$vALUATIONOFCRANKSHAFTCRACKING LETTER DATED 10/26/84
- 4. REACTOR IRIP BREAKER IEST fiESULTS RTB TESTS AND INSPEC-TO REGION V TIONS-ARE CC'MPLETE)
RESIDENT INSPECTOR REVIEW IS COMPLETE
- 5. ENVIRONMENTAL QUALIFICATION - JC0'S LETTER DATED 11/3/84 i
I
SAN ON0FRE UNIT 1
'( ITEMS REQUIRING COMPLETION OF LICENSEE ACTIONS PRIOR TO MODE 2 ENTRY REGION V ISSUES
- 1) ,
0PERATOR TRAINING ON DESIGN CHANGES
- 2) CALIBRATION OF STACK MONITORS
- 3) OPERATIONAL RADIATIONAL MONITORING SYSTEM (ORMS)
SATURATION /DOWNSCALE FAILURES - PROCEDURES
- 4) CALCULATIONAL TECHNIQUES FOR CORRECTING MAIN STEAM LINE MONITOR READING FOR SHIELDING
- 5) INCORPORATION OF PLANT VENT MONITOR CONVERSION FACTOR CHANGES WITH VENT FAN CHANGES
I AUDIT REVIEW 0F RETURN TO SERVICE PROGRAM
~
(
FOR HOT STANDBY SYSTEMS 7/26-8/1/84
- CRITERIA (NRC LETTER DATED 9/20/82 AND 2/8/84) . .[-
- EVALUATION OF RETURN TO SERVICE CRITERIA ? 4. -
- SEP GUIDELINES FOR SEISMIC EVALUATION CRITERIA .
- PEAK SHIFTING 0F INPUT FLOOR RESPONSE SPECTRA - AS ,
RECOP. MENDED BY PVRC .
- DAPPING RECOMMENDED BY PVRC
- STRESS LIMITS FOR PIPING FUNCTIONAL CAPABILITY
'E s.
2.0SY FOR CARBON STEEL [~
2,2SY FOR STAINLESS STEEL 4 7, ,,
L.? . . -
- SHORT TERM ANCHOR BOLT ALLOWABLES AS REQUIRED BY IEB 79-02 . :>. .
\ ~
WEDGE TYPE 0,5 ULTIMATE AS SPECIFIED BY MANLFACTURER - -
SHELL TYPE a;f
~
- g..
' ^
- FIVE PIPING SYSTEMS AUDITED AND INSPECTED (AF-02, CV-11, MS-01, ..
RC-102/CV-100/CV-101, AND RC-115)
- ASSOCIATED SUPPORTS AUDITED AND INSPECTED (136 TOTAL)
- THREE MECHANICAL EQUIPMENT ITEMS INSPECTED (AXU. FEEDWATER TURBINE DRIVEN PUMP G-]O, SEAL WATER Hx E-34, CHANGING PUMP G-8A8B)
- CRITERIA USED PET RE0VIREMENTS
- SUPPORTS OF PIPING AND EQUIPMENT PROPERLY INSTALLED
- SE!SMIC FUNCTIONAL CAPABILITY REASONABLY DEMONSTRATED m v
. SAN ONOFRE 1
\
SEISMIC DESIGN BASIS s
CP 3/64 (SER 11/1/63)
PROBABLE LARGEST GROUND ACCELERATION - 0.17G MAXIMUM GROUND ACCELERATION .0.40G 0.25G + WORKING STRESS
. CODE-0.5G + COMBINED STRESS - FUNCTION t
OL 3/67 (SER 10/12/66) i~
DISTINGUISH CATEGORY A AND B CATEGORY A - REFERS TO CP BASIS L
CATEGORY B - 0,2G STATIC i
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AUDIT REVIEW 0F ACCIDENT MITIGATION SYSTEMS
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PERFORMED ON 11/14-15/84
- SAME AS FOR HOT STANDBY SYSTEMS
- FSAR DESIGN BASIS GROUND' MOTION, I.E. , 0.5G HOUSNER SPECTRUF
- AWWA CRITERIA FOR CAST IRON PIPING
- FOUR PIPING SYSTEMS AUDITED (AC-05, MW-05, AC-23, AND SW-06)
- SUPPORTS AUDITED (69 TOTAL)'
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- COMP 0NE'NT COOLING WATER PUMP G-15A, B, C \
- RECIRCULATION HEAT EXCHANGER E-1 ( N .
- REFUELING WATER ST0' RAGE TANK l
- CRITERIA USED MET REQUIREMENTS
- SEISMIC FUNCTIONAL CAPABILITY REASONABLY DEMONSTRATED
- RWST AND CAST-IRON PIPE HAVE NO APPRECIABLE MARGIN AT 0.5G
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'( SAN ON0FRE UNIT 1 SEISMIC DESIGN 1967 DPR 0.25g CODE AND 0.5g FUNCTION 1976 MAJOR UPGRADES TO 0.679 1978 START SEP 11/79 TO 7/81 2.206 PETITIONS - 1560 CALIFORNIANS AND NADER 11/16/81 DIRECTOR'S DENI AL AND SER
( 2/27/82 SCHEDULED SHUTDOWN COMMENCES 5/20/82 SCE/NRC MTG, - DEMONSTRATE MEET 0.5g DESIGN BASIS 8/11/82 CONFIRMATORY ORDER - COMPLETE ALL 6/15/82
& 6/24/82 COMMITMENTS BEFORE RESTART 12/23/83 SCE PROPOSAL FOR HOT STANDBY SCOPE FOR RESTART 2/3/84 RESTART SER 8/30/84 SCE REQUEST FOR AUTHORIZATION To RESTART
-> SONGS SEISMIC DESIGN STATUS l
l UPGRADES TO 0.679 COMPLETE BY RESTART l e ALL SAFETY-RELATED STRUCTURES e REACTOR COOLANT SYSTEM TO ISOLATION VALVES, INCLUDING MAIN STEAM AND FEEDWATER LINES e CONTROL ROD DRIVES e AFWS AND CVCS e ELECTRICAL DISTRIBUTION & INSTRUMENT AIR NOT COMP.LETE e RHR AND PORTIONS OF SERVICE / COOLING WATER e SAFETY INJECTION SYSTEM AND RECIRCULATION e CONTAINMENT SPRAY e SPENT FUEL POOL COOLING l
l
E l STATUS AND SCHEDULE i
e HOT STANDBY CAPABILITY COMPLETE BEFORE RESTART e FINAL RESOLUTION OF SEISMIC IN SEP e HOT FUNCTIONAL TEST IN OCTOBER - FOLLOWING INTAKE STRUCTURE REPAIRS AND TDI INSPECTIONS e PLANT CRITICALITY SCHEDULED FOR NOVEMBER a
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CHRONOLOGY - SONGS 1 SEISMIC DESIGN
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3/27/67 DPR-13: FSAR 9.4, 0.25g Code and 0.5g Function 1973 SCE initiates 0.679 re-evaluation '
l 1976 Major upgrades to 0.679 - containment shield building, new i . diesels and various NSSS l 1978 Initiate SEP - scope includes shutdown systems, mitigation systems and B0P 12/20/79 44 FR 75535 Notice l'1/79 to 7/81 2.206 Petitions - 1560 Californians and Nader 4/28/80 SCE's JC0 - seismic capability i
, 8/4/80 & NRC 50.54f - seismic capability 4/24/81 9/80-1.0/81 SCE submittals - seismic scope and criteria 11/16/81 2.206 Director's denial and.SER: turbine building and FW heater mods complete by 1/1/83
( 12/81 ' Preliminary analysis results and SCE comitment to notify NRC when structural integrity cannot be demonstrated 2/27/82 Scheduled shutdown - ste'am generator inspection and seismic mods 5/6/82 Russell memo - analyses predict structurai (systems) failures 5/20/82 SCE/NRC meeting " licensees need(ed) to provide information that demonstrates that the facility meets its licensed design basis [0.5g] before . . . restart" 6/15/82 & SCE program to upgrade essentially all safety-related systems 6/24/82 and structures to 0.679 8/11/82 Confirmatory Order " maintain. . . shutdown condition until modifications . . . are completed and NRC approval is obtained for restart."
., 7/13/83 Clarification to 01 - the issue involves a " judgment rather than complete reanalysis" 11/21/83 SCE response to 12/29/82 Russell memo
-12/23/83 SCE proposal for restart scope and criteria
, 2/8/84 & SER 'for restart scope - hot standby scope and criteria 3/7/84 acceptable with exceptions 8/30/84' SCE request for authorization to restart
ENCLOSURE (1) TO APRfL 24,1981 50.54f LETTER i '-
SAFETY RELATED SYSTEMS, STRUCTURES AND COMP 0NENTS SAN ON0FRE 1 PLANT "The scope of review for the seismic re-evaluation program should include the systems, structures, and components (including emergency power supply and distribution, instrumentation, and actuation systems, with the following i
functions:
i
- 1. The reactor coolant pressure boundary as well as the core and vessel
- internals. This should also include those portions of the steam and feedwater system extending from and including the secondary side of the steam generator up to and including the outermost containment isolation
. valve and connected piping of 2-1/2 inch or larger nominal pipe size, up to and including the first valve that is either normally closed or is capable of automatic closure during all modes of normal reactor operation.
- 2. Systems or portions of systems that are required for safe shutdown as identified in the SEP safe shutdown review (SEP Topic VII-3). The system boundary includes those portions of the system required to perform the safety function and connected piping up to and including the first valve that is either normally closed or capable of automatic closure when the safety function is required.
- 3. Systems or portions of systems that are required to mitigate design basis events, i.e., accidents and trans *ents (SEP Topics XV-1 to XV-24). The i functions to be provided include emergency core cooling, post-accident N
containment heat removal, post-accident containment atmosphere cleanup, as well as support systems, such as cooling water, needed for proper
- functioning of these systems.
- 4. Systems and structures required for fuel storage (SEP Topic IX-1).
Integrity of the spent fuel pool structure including the racks is needed.
Failure of the liner plate due to the safe shutdown earthquake must not result in significant radiological releases, or in loss of ability to keep the fuel covered. Failure of cooling water systems or other systems connected to the pool should not permit draining of the fuel pool. Means to supply makeup to the pool as needed must be provided.
- 5. Structures that house the above equipment.
For the San Onofre 1 plant, the staff considers the following systems. and.
associated structures, and components should be addressed:"
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. Systems and Compon;nts System Status of Modifications Spectra a) Reactor Coolant System Complete =/
( b) Portions of Main Steam System a Complete 0.679 Housner 0.679 Housner (restart) c) Portions of Main Feedwater. < Complete 0.679 Housner (restart)
System d) Portions of Systems directly Complete 0.679 Housner (restart) connected to the RCS up to and including isolation valve
, e)_ Control Rod Drive Complete 0.67g Housner f) Auxiliary Feedwater System
h) Portions of Chemical and e Complete 0.679 Housner(restart)
Volume Control System
- 1) Portions of Component Cooling -------- --------
Water System j) Portions of Salt Water -------- --------
Cooling System k) Portions of Service /Miscel- -------- --------
laneous Water System
- 1) Portions of Instrunent Air Nitrogen bottles 0.67g Housner(restart)
System provided for required components m) Safety Injection System -------- --------
n)' Containment Spray System -------- - --------
o) ECCS Recirculation System ------- - --------
p) Spent fuel pool cooling -------- --------
f q) Electrical Distribution < Complete 0.67g Housner g System ,
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b itid intpcd :CO Structures Structure Status of Modifications Spectra Conta'inment Complete / 0.67g Housner t
Reactor Auxiliary Building Completei 0.67g Housner Control / Administration Complete / 0.67g Housner Building Fuel Storage Building Complete 3 0.679 Housner
.. (including pool)
Ventilation Equipment Complete 0.67g Housner Cuilding Turbine Building Complete / 0.679 Housner Intake Structure Modifications underway to resolve rebar corrosion 0.67g riousner Sphere Enclosure Building --------
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., 0.679 SONGS 2/3 L ,
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Diesel Generator Building --------
0.679 SONGS 2/3 CM v x._U p_c.i_. s y
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