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| ML20134G103 |
| Person / Time |
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| Site: |
Harris  |
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| Issue date: |
06/10/1983 |
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| From: |
NRC |
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| To: |
NRC |
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| Shared Package |
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| ML20132C567 |
List: |
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| References |
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| FOIA-85-173 NUDOCS 8508230037 |
| Download: ML20134G103 (4) |
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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] |
Inspection Report - Harris - 1983020 |
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N NRC EXIT MEETING June io, 1983
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400/401/83-20 g Attendees: wD# i Mr. G. M. Simpson, Principal CI Specialist Mr. F. R. Haney, Senior Construction Specialist Mr. D. C. Whitehead, QA Supervisor - Surveillance Mr. A. Fuller, Principal Engineer - Mechanical Mr. E. E. Willett, Resident Engineer - Mechanical ;
Mr. G. L. Forehand, Director - QA/QC j Mr. M. F. Thompson, Jr., Senior Resident Engineer '
Mr. R. M. Parsons, Project General Manager M N. J. Chiang1, Mana g e r - C A /0 C - Ha r r u P'.1r. :
Mr. D. A. McCaw, Superintendent - QA Mr. M. D. Vernon, Superintendent - QC
Mr. E. B. Isom, Construction Manager - Daniel i Mr. J. Pardi, Daniel General Manager .
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Mr. P. F. Foscolo, Assistent General Project Manager :
i NRC .
h Mr. R. Prevatte, SRIC i
Mr. P. Benis, USNRC Section'Chisf *
Mr. G. F. Maxwell. USNRC Sr. Ops. n Mr. J. W. York. USNRC, Sr. Mech / Weld Engineer i
The meeting was conducted by Mr. J. W. York, NRC, sb.s ad"is ad bc Icoked into three areas:
Previously identified items Post-weld heat treatment on structural steel Banger Inspection Program l
Previously Unresolved Items CLOSED Unresolved 1800/83-05-01 Ground Areas on Pipe Support Areas / Restraint No. 1-SW-H-376. Wt sure at that time you had minimum wall requirement l Sine- -he- vcu have cone ultrasenic tests and ver:flec it is not un d e r r.:. n =u- '
-C 1 re:4 ~- ents 8508230037 850814 f(;3 PDR FOIA GUILD 85-173 PDR-continued-hQ
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- 9% NhC Exit Meeting June 10, 1983 -
Prie Tuo Post .'el: Heat.- Tarc.ne Steel Checked for tnree welds on tower restraint for locp 1 - in varicus stages (one complete. one in process of being post-weld heat treated and one getting ready for setting insulation) - no proble Hanger Inspection Preeram Reinspected 10 hangers in Phase 1 (various stages); which means hanger may not have been totally inspected. Looked at these 10 and another one with weld inspect _cn pec:le (visual; fillet size; length, etc.). Had probler.s on three nangers which will be icentified as violation 400/63-20-01 fFac.cre to foll procedure for Hanger Inspection).
CS 2457,-
In this particular case there was a plate welded to the embedmen ll Tubular steel was welded to the plat Looking back throu6h the j, paperwork there was a change (2-3 times). This plate and the i,
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material was not a vendor package type but had been field issue The installed plate was 4' x 4" x .5/8*. It had been initially ;
requisitioned as 4" x 4" x 1/2". When the drawing was issued it was drawn as 5" x 5" x 5/8=. The CI inspector inspected to the drawing and did not viatch'tO~ varianc RB 165 In this case there is a tubular steel welded to the embedment on the end of which is a clip to which you intend to attach a snubber.
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This clip, according to Bergen-Paterson catalog, is not to be used l on the end where the snubber attachment is made. This is the wrong catalog number for the intended use. There is a slight dimensional dit.ference between this clip and the one that is supposed *.o be used. Dimensions. where snubber fits - 1/16" difference (staller).
All other dimensions are the sam had -continued-
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jJ NRC Exit Meeting )
gg June 10, 1983 Page Three n
Hanger 9 29 Safety Injection System - tubular steel (box type hanger, safety injection piping - from the tubular steel you have a brace that runs over from embed. Brace had been called to be 6" x 4" x 1/2" (in
thickness). It was 6" x 4" x 3/8". This particular piece was requisitioned t ros another hanger. CHR proves component from other hanger did nave 1/2" thickness on tubular steel. According to that package you should have put that particular part i However, marked on the hanger is another hanger number; that is marked through; another hanger number is marked on the hange- and that j nanger number is marked through and SI-H29 nas been 21-ked or i Mr. York expressed concsen that CI inspector did not pick this up as it was signed off. He wondered about material control on taese hanger Will probably, in the fu ture , take a look and see if you have material control problem Mr. Parsons asked Mr. Fuller regarding the 1/16" difference, could tne snubber Q have gone in and Mr. Fuller noted be did not think so. He Tu-ther stated at that poit.t the inspection program did not provide enough informatior that g
i catalog pieces matched. It is now t obeckpoint. This barger eas inspected .l
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two years ago. Mr . Willett advised 'that this is what promoted us to make ,
procedure chang !
. il Pr. Parsons noted we have found 50 different items that need te de checked on Phase II as we want through the last 3 4 year Mr. York advised there was another , clip hanging down and the clip had been f visibly bent. Will probably leave this out. This was signed off by a field :)
enginee In early Phase I this was allowed. Mr. Parsons cons:ented we do not 'l allow it if they see it. Mr. York noted the probles is, did be see it at the time it occurred or did it happen after he was there' There is a ci- ,haough this and a long member is hanging down from i Mr. Parsons reitereated it is a fine point bere. We need to support the inspectors and you could almost reverse intimidatior if you held them responsible fc- deficiencies noted after the insper'i.on is coet;eted It is our aesDoce!' 'ity to make sure the system in the r< Oatcher :arap .
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.c NRC Exit Meeting June 10, 1983 Page Four Mr. York advised he walked through the receipt area and area wnere :.acerials are issued in the plant itself. The area was closed but he could see che case where the material is issued. Mr. Parsons noted these materials are surplus hangers and instead of scrapping them we use some pieces to modify other hanger i i
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