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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20059C7311993-01-30030 January 1993
Summary of 391st ACRS Meeting on 921105-07 in Bethesda,Md Re NRC Regulatory Analysis Guidelines & Reactor Operating Events & Occurrences,Shearon Harris Plant Loss of High Head SI & LaSalle Overfill Due to Failure of MFW Pumps to Trip
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20245D8411988-09-28028 September 1988
Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920
ML20196B1461988-01-11011 January 1988
Summary of CRGR Meeting 127 on 871223 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys in LWR Nucl Nuclear Power Plants. Committee Recommended Forwarding Ofc Package to EDO Following Incorporation of CRGR Comments
ML20236A5211987-10-20020 October 1987
Summary of 870917 Meeting W/Util in Bethesda,Md Re Generic Ltr 87-09, Sections 3.0 & 4.0 of STS on Applicability of Limiting Conditions for Operation & Surveillance Requirements. W/O List of Attendees
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
ML20235W9431987-10-13013 October 1987
Summary of Operating Reactors Events Meeting 87-32 on 870922.Notes That Meeting 87-31 Did Not Occur.List of Attendees & Events Discussed & Significant Elements of Events Encl
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20215H2981986-10-10010 October 1986
Summary of 860925 Meeting W/Util at Region II Ofc Re Status of Operational Readiness & const-related Concerns.Attendee List Encl
ML20203N2851986-09-10010 September 1986
Summary of 860829 Meeting W/Util at Region II Re Problems Associated W/Electrical Cable Separation
ML20212K1601986-08-0808 August 1986
Summary of 860730 Meeting W/Util in Region II Ofc Re Review & Subsequent Actions on NRC-identified Cable Separation Problem
ML20212K1461986-08-0808 August 1986
Summary of 860730 Meeting W/Util in Region II Ofc Re Effect of High Failure Rate by Reactor Operator Candidates on NRC Simulator Exams
ML20212C0551986-08-0404 August 1986
Trip Rept of 860710-11 Site Visit Re Concerns Arising from Desk Top Review of Util Procedures Generation Package & Operator Use of Emergency Operating Procedures on Simulators.Rev 2 to Procedure OMM-006 & Related Info Encl
ML20133M4951985-08-0606 August 1985
Summary of 850723 Meeting W/Util in Atlanta,Ga Re Initial Operator Licensing Exams.Attendance List,Viewgraphs & Contingency Plans for Exam Dates Encl
IR 05000400/19830201983-06-10010 June 1983
Summary of 830610 Exit Meeting for Insp Repts 50-400/83-20 & 50-401/83-20.Major Areas Discussed:Previously Unresolved Item Re Ground Areas on Pipe Support Areas/Restraint & post-weld Heat for Turbine Steel
ML20214G6951977-04-18018 April 1977
Summary of 770216-17 Meeting W/Mark II Owners,Ge & BNL Re Mark II Containment Pool Dynamic Load Support Program.List of Meeting Attendees & Viewgraphs Encl
1993-01-30
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20059C7311993-01-30030 January 1993
Summary of 391st ACRS Meeting on 921105-07 in Bethesda,Md Re NRC Regulatory Analysis Guidelines & Reactor Operating Events & Occurrences,Shearon Harris Plant Loss of High Head SI & LaSalle Overfill Due to Failure of MFW Pumps to Trip
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20245D8411988-09-28028 September 1988
Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920
ML20196B1461988-01-11011 January 1988
Summary of CRGR Meeting 127 on 871223 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys in LWR Nucl Nuclear Power Plants. Committee Recommended Forwarding Ofc Package to EDO Following Incorporation of CRGR Comments
ML20236A5211987-10-20020 October 1987
Summary of 870917 Meeting W/Util in Bethesda,Md Re Generic Ltr 87-09, Sections 3.0 & 4.0 of STS on Applicability of Limiting Conditions for Operation & Surveillance Requirements. W/O List of Attendees
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
ML20235W9431987-10-13013 October 1987
Summary of Operating Reactors Events Meeting 87-32 on 870922.Notes That Meeting 87-31 Did Not Occur.List of Attendees & Events Discussed & Significant Elements of Events Encl
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20215H2981986-10-10010 October 1986
Summary of 860925 Meeting W/Util at Region II Ofc Re Status of Operational Readiness & const-related Concerns.Attendee List Encl
ML20203N2851986-09-10010 September 1986
Summary of 860829 Meeting W/Util at Region II Re Problems Associated W/Electrical Cable Separation
ML20212K1601986-08-0808 August 1986
Summary of 860730 Meeting W/Util in Region II Ofc Re Review & Subsequent Actions on NRC-identified Cable Separation Problem
ML20212K1461986-08-0808 August 1986
Summary of 860730 Meeting W/Util in Region II Ofc Re Effect of High Failure Rate by Reactor Operator Candidates on NRC Simulator Exams
ML20133M4951985-08-0606 August 1985
Summary of 850723 Meeting W/Util in Atlanta,Ga Re Initial Operator Licensing Exams.Attendance List,Viewgraphs & Contingency Plans for Exam Dates Encl
IR 05000400/19830201983-06-10010 June 1983
Summary of 830610 Exit Meeting for Insp Repts 50-400/83-20 & 50-401/83-20.Major Areas Discussed:Previously Unresolved Item Re Ground Areas on Pipe Support Areas/Restraint & post-weld Heat for Turbine Steel
ML20214G6951977-04-18018 April 1977
Summary of 770216-17 Meeting W/Mark II Owners,Ge & BNL Re Mark II Containment Pool Dynamic Load Support Program.List of Meeting Attendees & Viewgraphs Encl
1993-01-30
[Table view] |
Text
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ENCLOSURE 1 MEETING
SUMMARY
Licensee: Carolina Power and Light Company Facility: Shearon Harris Nuclear Plant Docket No.: 50-400 License No.: CPPR-158
SUBJECT:
Operational Readiness Status A meeting was held in the NRC Region II Office on September 25, 1986, to discuss general status of operational readiness of Shearon Harris and also specific construction related concerns.
The licensee provided a schedule of milestones, leading up to an anticipated license issue of October 11, 1986. The licensee also provided an update status of preoperational tests remaining. A discussion ensued clarifying the ten proposed tests to be deferred beyond fuel load. Recently identified problems with the Emergency Diesel Generators (EDG) were discussed, specifically problems relating to head welds, the turbocharger and the load sequencer. The licensee stated that they had merged their many status lists into one " punch list" that was operational mode oriented.
A construction fire protection status was provided, with anticipated fuel load fire penetration seals and fire wraps and corresponding fire watches. Completion of the remaining fire protection items was anticipated to be November 1, 1986.
In the structural steel area, the licensee had conducted a review for both undersized welds and potential inadequate weld stress analysis, by looking at 92 heavily loaded beams.
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l To complete the electrical separation review, the' licensee needed to complete manhole inspections and complete ESF fire wrap inspections. Based on the progress so far, approximately 1000 identified deviations require rework, after analysis. Half of these are in ESF systems. The licensee stated that all ESF cable separation inspections would be conducted and deficiencies corrected prior to license issue. Other cable separation deficiencies would be corrected prior to the effected system being operationally needed, but no later than five percent
- power. The licensee had identified several deviations in one wrapped ESF cable, l and therefore is expanding the wrapped ESF cable inspection percentage from 30 to i 60.
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V A O 10230080 861010 Da(e Srgned kR ADOCK 05000400 PDR Paul E. Fredrickson, Section Chief Division of Reactor Projects A
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ENCLOSURE 2 l ATTENDANCE LIST Attendance at the Carolina Power and Light - NRC meeting on September 25, 1986, at the Region II Office.
Carolina Power and Light Company R. A. Watson, Vice President, Harris Nuclear Plant J. L. Willis, Plant General Manager NRC Region II M. L. Ernst, Deputy Administrator, RII R. D. Walker, Director Division of Reactor Projects (DRP)
A. F. Gibson, Director, Division of Reactor Safety (DRS)
L..A. Reyes, Deputy Director, DRP D. M. Verre111, Chief, Branch No. 2, DRP P. E. Fredrickson, Chief, Section 2A, DRP F. Jape, Chief, Test Programs Section, DRS G. A. Belisle, Acting Chief, Quality Assurance Programs Section, DRS N. Merriweather, Plant Systems Section, DRS l
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