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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
F AUS 11556 ENCLOSURE 2 MEETING
SUMMARY
- CABLE SEPARATION Licensee: Carolina Power and Light Company Facility: Harris Nuclear Plant Docket No.: 50-400 License No.: CPPR-158
SUBJECT:
PROBLEMS ASSOCIATED WITH ELECTRICAL CABLE SEPARATION A meeting was held in the NRC Region II office on July 30, 1986 to discuss CP&L's review of and subsequent actions on an NRC - identified cable separation problem.
The problem involved electrical cable installed and inspected to the separation requirements of Regulatory Guide (RG) 1.75, Physical Independence of Electric Systems. NRC inspectors had identified numerous cables that had already been installed, inspected and accepted by CP&L that had interaction points which violated RG 1.75 requirements.
CP&L discussed their program for inspection and identification of nonconformances and their subsequent engineering evaluation for acceptance or repair, using a Wyle Laboratory Analysis. A discussion commenced concerning the instructions provided to the QC inspector as to whether a " worst case" system was used for cable inspection or whether all separation violations were being identified.
CP&L stated that " worst case" was used and that if engineer evaluation revealed the need for rework, then the entire cable would be reinspected. CP&L provided a significance review of those violations that were not identified by QC. CP&L stated th'at, based on their review, the inspection proficiency was acceptable for cable separation in both the Fuel Handling and Reactor Auxiliary Building. This acceptability was based on comparing the number of missed cable separation violations to an estimated total potential inspection points. Region II questioned this process with respect to determining whether or not a safety issue existed in the cable separation area. Regardless of inspection proficiency, Region II was concerned about the total number of new separation violations that required rework. Specifically, in the Reactor Auxiliary Building, CP&L had reviewed two rooms and had identified several new violations which required rework. To improve the program, CP&L stated that they planned to increase QA surveillance manpower, intensify room turnover QA surveillance, reorganize the inspection force to achieve more consistent results and continue training of supervisory and inspection personnel. Based on Region II's concerns, CP&L stated that cable separation QA surveillances would be conducted on all rooms, including those already turned over. Region II additionally stated that the root cause appeared to be inadequate craf t work, compounded by the QC inspection problem.
An additional contribution to the problem appeared to be CP&L's using the " worst case" method of violation identification. CP&L stated that the inspection F608190204 PDR 860011 V
ADOCK 03000400 PDR
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'7 3 I TJS5 I Enclosure 2 2 instruction would be modified to ensure that all separation violations are identified by QC. The Regional Administrator expressed concern that CP&L was changing their program based on NRC concern, when problems in the program should have been recognized and changed independently by CP&L. Discussion continued on the " worst case" method, with CP&L stating that this inspection method was only used in cable separation inspections. The meeting was concluded with the NRC requesting CP&L to provide a schedule for conduct of the surveillances.
Subsequent to the meeting, by telephone call on July 31, 1986 (A. Herdt and D. Verrelli, NRC; M. McDuffy and A. Watson, CP&L), CP&L provided clarifica-tion of their commitment to perform 100% surveillance of all rooms. To begin with, CP&L plans 100% surveillance inspection of all electrical cable and equipment within an area. Depending on findings, this may be reduced to 80% tnan 60% as appropriate. However, as a minimum, CP&L will do 100% reinspection of all engineered safety feature (ESF) systems for compliance with RG 1.75 as modified by the Wyle Laboratory Analysis, which has received NRC approval for deviations from RG 1.75. ESF systems are those identified in Section 7.3 of the FSAR. At some future time, prior to licensing, CP&L will determine the root cause of identified deficiencies to the extent necessary to assure Region II that this craft /QC problem is an isolated condition and not applicable to other areas of construction. CP&L suggested that another meeting be held, in approximately two weeks to discuss their findings.
V P.' E.~ Fredrickson, Sed. ion Chief T N Bate Division of Reactor Projects
li'G 1 *. 'd36 ENCLOSURE 3 ATTENDANCE LIST Attendance at the CP&L - NRC meeting on July 30, 1986 at the NRC Region II office.
CP&L E. E. Utley R. A. Watson L. W. Eury H. R. Banks M. A. McDuffie J. L. Willis B. J. Furr NRC J. N. Grace #G. A. Belisle
- R. D. Walker G. F. Maxwell L. A. Reyes #R. W. Wright A. F. Gibson L. S. Mellen D. M. Verrelli *K. E. Brockman
- C, A. Julian #T. D. Gibbons
- A. R. Herdt #S. Stein P. E. Fredrickeson #D. Ford
- T. E. Conlon
- Attended Operator Licensing Portion Only
- Attended Cable Separation Portion Only l
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