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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] |
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a m%
. m- * +t UNITED STATES
'. 'f E NUCLEAR REGULATORY COMMISSION 5 E W ASHIN GTON, D.C. 20555
/
OFFICE OF THE February 28, 1985 CHAIRMAN MEMORANDUM TO THE FILES FROM: C. W.
Reamer [(
SUBJ: SAN ONOFRE UNIT 1 RESTART --
MINUTES OF MEETING HELD NOVEMBER 6, 1984 A meeting was held in the Chairman's Conference Room at 10:00 am on Tuesday, November 6, 1984. The meeting was scheduled as a briefing and discussion concerning the staff's technical review, OGC's legal reviews, and OI's activities regarding the investigation at San Onofre Unit 1. The Chairman and Commissioner Zech, as well as others, attended. (See attached attendance list) .
The Chairman opened the meeting by suggesting that the NRC staff representativos adaress the technical issues first.
Mr. Grimes stated that the NRC staff was preparing a Safety Evaluation Report (SER) which would be an extension of the staff's February 1984 Return to Service scope SER. He said the SER would rely principally on audits of licensee analyses, field inspections and staff analysis of licensee supplied reports. He said that staff needed two weeks after receipt of needed information to complete the SER. He said that the staff had received information from SCE the previous day and that it appeared the staff now had all the material it needed from SCE to complete the restart evaluation. He also noted the recurrent question of "to what extent does non-upgraded equipment meet 0.5g?" He said the staff had received information and supporting documentation from SCE on the .5g question.
The Chairman asked what the staff's technical conclusion would be if the staff could conclude that non-upgraded portions'of Unit 1 met .5g. Mr. Grimes responded that the staff believed the capability of Unit 1 to achieve hot stand-by was sufficient to protect public health and safety. Ile said that if the non-upgraded portions of the plant meet .5g, then the basis for the staff's safety conclusion would be strengthened. lie noted that the non-upgraded aspects of the plant would be integrated into the Systematic Evaluation Program (SEP) for completion of action and that Unit 1 SEP action was scheduled for completion by the second refueling outage after rectart, lie said that 0500190603 050709 ,
PDR FOTA DELLO4 ' DOS PDR p ,
I
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= -- - - - - -
' t i
modifications of Unit 1 would likely be necessary to meet .67 even assuming Unit 1 meets .5g.
I Commissioner Zech asked what the staff's analysis covered and <
what the basis was for the NRC's confidence. Mr. Grimes responded that the basis of the staff's review of the plant's i
capability to withstand 0.5g is based on sample analyses, that SCE selected the sample, and that the staff satisfied itself i
that SCE picked the key systems in its sampling and that additional samples were not necessary.
Commissioner Zech asked what confidence the staff had in .5g for other equipment at Unit 1. Mr. Case responded that, on the basis of the way Unit 1 is built and configured today, the staff believes it meets .5g. He said it was impossible today
- to say whether or not Unit 1 met .5g at the time of licensing.
l He said the staff understands the licensees' methods and stress criteria but has not reviewed their application and analyses. -
I i The Chairman asked whether or not that was usual practice and .
) Mr. Case said it was consistent with staff practice to rely on !
licensee assertions that it has completed the necessary steps a
) and has come out okay.
! Commissioner Zech asked whether or not the staff has adequate information to decide that the licensees' analyses look sound and their conclusions right. Mr. Case responded that the staff '
j had satisfied itself that today's methods of the licensee wero okay.
Mr. Dircks noted that once the legal, technical and investigative inputs are received they will need to be assembled in a decision document and the commission will need to address the question of who's going to make the decision.
i The Chairman asked what the staff would ordinarily do on the question of who makes the decision, and Mr. Dircks responded
, that the significance of the case made it extraordinary. The Chairman asked what were the policy issues in the case. Mr.
Dircks responded that the magnitude of the case meant that the restart decision would have policy consequences. He said that the potential consequences included the impact of the Sholly procedure on the nuclear industry, and the effect of the Unit 1 decision on the Integrated Safety Assessment Program (ISAP) l program, or the staff's ability to obtain safety concessions from licensees, and on NRC practices regarding confirmatory orders, i
1 The Chairman then asked whether more discussion was needed on 3 the technical issues. Mr. Grimes responded that there were non-seismic issues involving reactor trip breaker testing, TDI diesels and environmental qualification of plant electrical
} l 2 ,
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~
E equipment. He said the staff believed that it should update the technical status of the plant on these non-seismic issues a before a restart decision.
Mr. Malsch asked whether the licensee had accounted for all 2 overstresses identified in the licensee's 1982 submittals and Mr. Grimes said he believed the licensee had but, if it had _
not, the basis for the sample would have to be justified.
Commissioner Zech asked how many exemptions from the '
Commission's general design criteria would be needed. Mr. Case responded that the SER would make clear that, for the Unit 1 -
return to service, some systems would be required to meet .5g and other systems required to meet .67g and that no exemptions would be needed. Mr. Grimes observed that Unit I was not unique in the SEP and that the staff was not applying present-day criteria for the safe shutdown earthquake to other SEP plants. Mr. Chandler noted that the question of exemptions depended on what design basis was being applied to Unit 1. He said that if .5g were the design basis and the staff was -
satisfied that the facility met .5g, then no exemptions would -
be needed but if .67g were used, then exemptions to GDC 2, 34 )
and possibly other GDC's may be needed.
The Chairman asked how it would be decided whether .5g or .679 3' is the design basis, and Mr. Case said he would use the latest information which would be .67g, the design basis for Units 2 and 3.
Mr. Malsch stated the issue was whether er not the GDC applied to Unit 1, and he said the staff's " working view" was that the GDC do apply to the SEP. ;
apply to the SEP plants "over time.,Mr. " Case said the GDC Commissioner would Zech asked =
whether or not one could use .5g, and Mr. Case responded that -
one could, for some period of time. Mr. Malsch stated that -
there was a question of what label should be applied to this process of applying the GDC over time to SEP plants. He said _
the most straight-forward label was " exemption" but that "SEP" d might be another acceptable label.
The Chairman asked what procedure would apply if exemptions were needed, and Mr. Malsch responded that the procedural issue -
was very complicated. He said that an exemption issue would remain, even if the 1982 order were not deemed to be an amendment. He said that hearing rights and the Sholly procedure might be argued to apply to exemptions.
The Chairman asked whether or not a significant hazards consideration was involved, and Mr. Case responded that if the 1982 order were viewed as an amendment, then the answer would be "yes." ,
Mr. Malsch then reviewed the conclusions of the OGC legal )
analysis of the " order or amendment" issue. He said OGC's
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[ .
analysis assumes the plant meets .5g. He said OGC concluded that the substance of the order rather than its label is important. He said that a restart order (i.e., a return-to-service authorization) would be an amendment if the 1982 order is deemed to be an amendment. He said that the Commission not has discretion to issue enforcement orders that are license amendments. He said that under NRC regulations an order would necessarily be an amendment either if it is in l conflict with technical specifications in the license or if it is issued in response to a licensee request for a physical change question.
in the plant that involves an unreviewed safety He said that the 1982 order would not be an amendment under either description and, thus, need not be regarded as an amendment under NRC regulations.. He said, however, that certain orders effecting major and permanent changes in.the plant may be viewed as amendments notwithstanding the regulations, and there was no clear judicial or statutory guidance on the question of whether or not the order was an amendment under the Atomic Energy Act. He said that two underlying policies of the Act -- public participation and enforcement flexibility--were in conflict and led to. opposing conclusions. He said that, in OGC's judgment, a Court would probably resolve the conflict in favor of an amendment in this particular case because the consequences of the 1982 order were substantial, far-reaching and fairly permanent.
The Chairman asked what the possible outcome's would be if the Commission were to conclude that the order was not an amendment.
Mr. Malsch said that the worst outcome would be a broad Court ruling that could severely restrict Commission enforcement discretion, but that a more likely outcome would be a Court ruling applicable only to the Unit I case. Mr.
Chandler said that an important fact was that the 1982 order could be read to have changed the basis underlying plant operation but Mr. Malsch responded that Mr. Chandler's analysis was too restrictive and that the issue depended upon how major, substantial and permanent the change was. The Chairman asked whether or not the interim nature of the order would change the outcome, and Mr. Malsch answered "no."
The Chairman asked what the relevance was of the licensees' assertions regarding staff representations and conduct, and Mr. Malsch answered "none."
Mr. Cunningham noted that while the equities would not likely influence the legal issue, they might affect the court's decision on whether or not to stay operation. Mr. Malsch noted that. consideration of the equities might include more than agency conduct, for example, how consumers would be affected.
The Chairman asked what the next steps should be, and Mr.
Dircks stated that the Commission could give guidance on the legal issue or it could involve itself in the technical issue as-well.
Mr. Sohinki stated that Commissioner Bernthal's I
position had been that the staff should provide its l recommendation on the technical and legal issues, and !
Commissioner Zech stated that he agreed. Mr. Dircks stated that he had sought policy guidance from the Commission and would prefer to avoid giving a recommendation which might i lessen the Commission's flexibility in exercising its policy prerogatives.
l Mr. Zech stated that his main concerns were the i technical matters and that the legal matters were also important in that the Commission could not do something that l was illegal. Mr. Grimes responded that the staff was convinced in February 1984 that the restart plan for Unit I would be safe enough. The Chairman said he was undecided on whether to request staff recommendations, and Mr. Cutchin indicated he would consult Commissioner Roberts. Commissioner Zech said the Commission needed a discussion of options, including the pro's and con's, and Mr. Malsch offered that OGC could prepare an options paper in a couple of days. Mr. Austin said that, in the past, Commissioner Asselstine wanted a staff recommendation on the order vs. amendment issue and also wanted the issue brought before the Commission in a public meeting.
The meeting then moved to OI information (See attachment).
Mr. Cunningham stated that the California PUC deadline was January 1, 1985, extendable to February 1, 1985 for cause.
The Chairman said that Commissioner offices should respond on whether they wanted an options paper which included pro's and con's on policy and legal considerations. He said the staff would continue its work on the technical review and that OI should give priority to the investigation. He noted that the Commissioners needed to decide whether or not to hold a public meeting.
The meeting closed at approximately 12:15 pm.
Attachments:
- 1. List of Attendees
- 2. Minutes of OI Presentation (Limited Distribution) i I
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-8 o NUCLEAR REGULATORY COMMISSION
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% , , , , . *' November 7 1984 CHAIRMAN COMFP 84-45 MEMORANDUM FOR: Commissioner Roberts Commissioner Asselstine Commissioner Bernthal Commissioner Zech FROM:
Nunzio J. Palladi i
SUBJECT:
DECISION REGARDING RESTART OF THE SAN ON0FRE NUCLEAR GENERATING PLANT, UNIT 1 Yesterday morning Commissioner Zech and I met with NRC staff, OGC, OI and others to discuss the above subject.
9 As a sbparate matter, my office received a call from a Southern California Edison (SCE) representative on Tuesday morning. My e office returned the call'that afternoon and was informed by the SCE representative that SCE believed the Commission needed to act by the end of next week if SCE is to satisfy the conditions set by the California PUC.
to verify the SCE st,atement with the NRC staff so as not toMy office has not sought
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delay this memo. By copy of thi5 mem . I request E00's view on t the SCE statement.
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