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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217J3001999-10-20020 October 1999 Notification of 991104 Meeting with Gpu Nuclear,Inc & Amergen in Rockville,Maryland Re Sale & License Transfer of OCNGS from Gpun to Amergen ML20217D0201999-10-12012 October 1999 Requests Assistance in Determining If Info Submitted by Gpu,Inc on 990922 in Response to NRC Ltr ,meets Criteria Set Forth in 10CFR20,Subpart E for Release of Property to Be Sold by Gpu ML20217C9671999-10-12012 October 1999 Requests Assistance in Determining Whether Info Sent by Gpu,Inc on 990922 in Response to NRC Ltr ,meets Criteria Set Forth in 10CFR20,Subpart E for Release of Property to Be Sold by Gpu ML20217C6151999-10-0707 October 1999 Requests Assistance in Determining Whether Info Sent by Gpu, Inc Meets Criteria Set Forth in 10CFR20 Subpart E for Release of Property to Be Sold by Gpu ML20207H3721999-06-10010 June 1999 Informs That Attached Draft Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding, Was Transmitted by Facsimile to G Busch of Gpu Nuclear to Be Discussed in Conference Call Scheduled for 990614 ML20204B6181999-03-12012 March 1999 Notification of 990329 Meeting in Forked River,Nj to Discuss Licensee Efforts Re Possible Early Shutdown & Decommissioning of Facility ML20202H6011999-02-0303 February 1999 Notification of 990218 & 19 Meetings with Util in Forked River,Nj Re Overview & Discussion of Licensee Efforts Concerning Possible Early Shutdown & Decommissioning of Plant ML20154K9781998-10-15015 October 1998 Notification of 981103 Meeting with Gpu Nuclear,Inc in Rockville,Md to Discuss Planning for Possible Shutdown of Oyster Creek & Related Decommissioning Activities ML20154J0271998-10-13013 October 1998 Notification of 981028 Meeting with Gpu Nuclear Inc,In Rockville,Md to Discuss Licensee Calculations Re 980505 Licensing Basis Change Request ML20154B3731998-09-29029 September 1998 Forwards Correspondence from Licensee Re Questions Asked by NRC Staff & Answers from Licensee with Respect to Submittal for Approval of Alternate 17R Insp Re GL 88-01, Intergranular Stress Corrosion Cracking Commitments ML20236T0891998-07-21021 July 1998 Notification of Significant Licensee Meeting 98-64 W/Util on 980804 in Forked River,Nj to Discuss NRC SALP for Period of 961201-980613 ML20247N5021998-05-14014 May 1998 Notification of Significant Licensee Meeting 98-46 W/Util on 980529 in King of Prussia,Pa to Conduct pre-decisional Enforcement Conference Re Three Apparent Violations Re Automatic Depressurization Sys Issues ML20216G6261998-03-0606 March 1998 Notification of Significant Licensee Meeting 98-24 W/Util on 980323 Predecisional Enforcement Conference to Discuss Apparent Violation in NRC Integrated Insp Rept 50-219/97-11 (EA-98-049) ML20217C1041997-09-18018 September 1997 Notification of 970930 pre-decisional Enforcement Conference W/Gpu Nuclear,Inc in King of Prussia,Pa to Discuss Five Apparent Violations Re Three Control Issues & One Control of Matl in Emergency Swp Issue ML20210J6161997-08-14014 August 1997 Notification of 970826 Meeting W/Util in Rockville,Md to Discuss Possible Plant Operating Scenarios,Current Status & Planning Activities Associated W/Scenarios ML20148F7201997-05-30030 May 1997 Forwards Semiannual Status Rept on Fire Protection Task Action Plan & plant-specific Thermo-Lag Correction Action Programs ML20140D5251997-04-18018 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Relating to Thermo-Lag Fire Barriers ML20137R4531997-04-0101 April 1997 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision of LBP-97-01 Expired. Decision Became Final Agency Action on 970326.W/Certificate of Svc.Served on 970401 ML20132F7651996-12-16016 December 1996 Forwards Signed Copy of Affidavit of RB Eaton in Support of NRC Staff Response in Support of Licensee Motion for Summary Disposition. Document Replaces Unsigned Affidavit Which Was Filed on 961206 ML20132F7571996-12-13013 December 1996 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision LBP-96-23 Has Expired. Commission Declined Review & Decision Became Final Agency Action on 961204.W/Certificate of Svc.Served on 961213 ML20135F4841996-12-10010 December 1996 Informs That Signed Copy of Affidavit of RB Eaton in Support of NRC Staff Response to Licensee Motion for Summary Disposition Filed on 961206,will Be Provided as Soon as Possible ML20134M6331996-11-21021 November 1996 Discusses TIA Re 10 CFR 50.59 Evaluation Prepared by Licensee to Allow Movement of Spent Fuel from SFP to Dry Storage Facility While Plant Is in Cold Shutdown ML20134L4891996-11-12012 November 1996 Forwards Copy of 961107 Amend 187 to License DPR-16 & Safety Evaluation for Facility ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20129F6401996-10-25025 October 1996 Requests That Encl Handout for Nuclear Energy Inst/GPUN-OG/ NRC Conference Call on Nuclear Energy Inst/Epri Revised Source Term Task Force for Plant,Be Placed in Docket File 50-219 ML20134G1731996-10-24024 October 1996 Informs Commission That Final No Significant Hazards Consideration Determination & License Amend Will Be Issued on or About 961030 to Gpu Nuclear Corp,Per Util 960415 Request to Revise TS 5.3.1.B ML20128L7191996-10-0909 October 1996 Forwards from Jc Fornicola to K Cozen Re Consideration of Oyster Creek as Pilot Plant for Submittal of Revised Source Term ML20129G7861996-10-0101 October 1996 Discusses 960923 Telcon from P Gunter Re Listed Topics. Update of Status of SPF 2.206 & Memo to Commission from Taylor, Resolution of Sf Storage Pool Action Plan Issues, Also Discussed ML20132A9681996-06-12012 June 1996 Forwards Copy of Ltr Requesting NRC to Investigate & Correct Highly Inaccurate Public Statement That Appeared in Gpu June 1996 Neighborhood Update ML20059J8431994-01-11011 January 1994 Notification of Significant Licensee Meeting 94-02 W/Util on 940125 Re Enforcement Conference to Discuss NRC Operational Safety Team Insp Findings ML20059M7931993-11-17017 November 1993 Notification of 940119 Meeting W/Util in Rockville,Md to Discuss Matters Related to Water Backed Welding of Oyster Creek Safety Related Piping ML20059F9551993-11-17017 November 1993 Notification of 940119 Meeting W/Util in Rockville,Md to Discuss Matters Related to Water Backed Welding of Plant Safety Related Piping.Meeting Time Changed as Listed ML20059J5661993-11-0909 November 1993 Notification of 931119 Meeting W/Util in Rockville,Md to Discuss Proposed ISFSI & to Receive Status Rept on Staff Effort to Issue Certificate of Compliance for Standardized NUHOMS Sys & to Discuss License Requirements ML20058P9701993-10-18018 October 1993 Notification of Significant Licensee Meeting 93-133 W/Util on 931029 in Forked River,Nj to Discuss Operational Safety Team Insp Public Exit ML20057B4751993-09-16016 September 1993 Notification of 931020 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20057D7141993-08-0303 August 1993 Requests Assistance in Determining Adequacy of Plant Methodology for Determining Reportability of Plant Operation Above Licensed Core Thermal Limit ML20128K9051993-02-0303 February 1993 Notification of Significant Licensee Meeting 93-15 W/Util on 930208 to Discuss Results of NRC Review of Plant Operation W/Degraded Shutdown Cooling ML20127F3661993-01-0505 January 1993 Notification of Significant Licensee Meeting 93-002 W/Util on 930126 to Discuss Integration of Simulator Into Training Program ML20126J8041993-01-0404 January 1993 Notification of 930106 Meeting W/Util in Rockville,Md to Discuss Matters Re Core Spray Downcomer Leak (Weld L3a) ML20126J9941993-01-0404 January 1993 Notification of 930112 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20126F4571992-12-18018 December 1992 Notification of 930112 Meeting W/Util in Rockville,Md to Discuss Reactor Bldg Access Modification for Facility ML20217B0841991-03-0505 March 1991 Forwards AEOD Diagnostic Evaluation Team Rept for Plant for Info.Rept Documents Team Findings & Conclusions & Includes Discussions of Licensee Strengths & Weaknesses ML20058D5561990-10-31031 October 1990 Notification of 901114 Meeting W/Util in Forked River,Nj to Discuss Status of Licensing Activities for Plant ML20058D5721990-10-26026 October 1990 Notification of 901107 Meeting W/Util in Rockville,Md to Discuss Matters Re Fuel Channel Box Bowing ML20058A3411990-10-18018 October 1990 Notification of 901029 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20058N9351990-08-13013 August 1990 Notification of 900816 Meeting in Bethesda,Md W/Util to Discuss Emergency Response Data Sys ML20058M4071990-08-0808 August 1990 Notification of 900829 Meeting W/Util in Forked River,Nj to Discuss Status of Licensing Activities for Plant ML20058L5781990-07-31031 July 1990 Notification of 900919 Meeting W/Util in Rockville,Md to Discuss Matters Re Plant Drywell Corrosion Problem ML20055C3341990-02-0909 February 1990 Notification of 900216 Enforcement Conference Meeting 90-19 W/Util in King of Prussia,Pa Re Safety Concern Process & Degraded ADS Logic ML20247K8611989-09-15015 September 1989 Notification of 890927 Meeting W/Util in Rockville,Md to Discuss site-specific Response Spectra & Methodology to Develop New Seismic Floor Response Spectra 1999-06-10
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217J3001999-10-20020 October 1999 Notification of 991104 Meeting with Gpu Nuclear,Inc & Amergen in Rockville,Maryland Re Sale & License Transfer of OCNGS from Gpun to Amergen ML20217D0201999-10-12012 October 1999 Requests Assistance in Determining If Info Submitted by Gpu,Inc on 990922 in Response to NRC Ltr ,meets Criteria Set Forth in 10CFR20,Subpart E for Release of Property to Be Sold by Gpu ML20217C9671999-10-12012 October 1999 Requests Assistance in Determining Whether Info Sent by Gpu,Inc on 990922 in Response to NRC Ltr ,meets Criteria Set Forth in 10CFR20,Subpart E for Release of Property to Be Sold by Gpu ML20217C6151999-10-0707 October 1999 Requests Assistance in Determining Whether Info Sent by Gpu, Inc Meets Criteria Set Forth in 10CFR20 Subpart E for Release of Property to Be Sold by Gpu ML20207H3721999-06-10010 June 1999 Informs That Attached Draft Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding, Was Transmitted by Facsimile to G Busch of Gpu Nuclear to Be Discussed in Conference Call Scheduled for 990614 ML20204B6181999-03-12012 March 1999 Notification of 990329 Meeting in Forked River,Nj to Discuss Licensee Efforts Re Possible Early Shutdown & Decommissioning of Facility ML20202H6011999-02-0303 February 1999 Notification of 990218 & 19 Meetings with Util in Forked River,Nj Re Overview & Discussion of Licensee Efforts Concerning Possible Early Shutdown & Decommissioning of Plant ML20154K9781998-10-15015 October 1998 Notification of 981103 Meeting with Gpu Nuclear,Inc in Rockville,Md to Discuss Planning for Possible Shutdown of Oyster Creek & Related Decommissioning Activities ML20154J0271998-10-13013 October 1998 Notification of 981028 Meeting with Gpu Nuclear Inc,In Rockville,Md to Discuss Licensee Calculations Re 980505 Licensing Basis Change Request ML20154B3731998-09-29029 September 1998 Forwards Correspondence from Licensee Re Questions Asked by NRC Staff & Answers from Licensee with Respect to Submittal for Approval of Alternate 17R Insp Re GL 88-01, Intergranular Stress Corrosion Cracking Commitments ML20236T0891998-07-21021 July 1998 Notification of Significant Licensee Meeting 98-64 W/Util on 980804 in Forked River,Nj to Discuss NRC SALP for Period of 961201-980613 ML20247N5021998-05-14014 May 1998 Notification of Significant Licensee Meeting 98-46 W/Util on 980529 in King of Prussia,Pa to Conduct pre-decisional Enforcement Conference Re Three Apparent Violations Re Automatic Depressurization Sys Issues ML20216G6261998-03-0606 March 1998 Notification of Significant Licensee Meeting 98-24 W/Util on 980323 Predecisional Enforcement Conference to Discuss Apparent Violation in NRC Integrated Insp Rept 50-219/97-11 (EA-98-049) ML20217C1041997-09-18018 September 1997 Notification of 970930 pre-decisional Enforcement Conference W/Gpu Nuclear,Inc in King of Prussia,Pa to Discuss Five Apparent Violations Re Three Control Issues & One Control of Matl in Emergency Swp Issue ML20210J6161997-08-14014 August 1997 Notification of 970826 Meeting W/Util in Rockville,Md to Discuss Possible Plant Operating Scenarios,Current Status & Planning Activities Associated W/Scenarios ML20148F7201997-05-30030 May 1997 Forwards Semiannual Status Rept on Fire Protection Task Action Plan & plant-specific Thermo-Lag Correction Action Programs ML20140D5251997-04-18018 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Relating to Thermo-Lag Fire Barriers ML20137R4531997-04-0101 April 1997 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision of LBP-97-01 Expired. Decision Became Final Agency Action on 970326.W/Certificate of Svc.Served on 970401 ML20132F7651996-12-16016 December 1996 Forwards Signed Copy of Affidavit of RB Eaton in Support of NRC Staff Response in Support of Licensee Motion for Summary Disposition. Document Replaces Unsigned Affidavit Which Was Filed on 961206 ML20132F7571996-12-13013 December 1996 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision LBP-96-23 Has Expired. Commission Declined Review & Decision Became Final Agency Action on 961204.W/Certificate of Svc.Served on 961213 ML20135F4841996-12-10010 December 1996 Informs That Signed Copy of Affidavit of RB Eaton in Support of NRC Staff Response to Licensee Motion for Summary Disposition Filed on 961206,will Be Provided as Soon as Possible ML20134M6331996-11-21021 November 1996 Discusses TIA Re 10 CFR 50.59 Evaluation Prepared by Licensee to Allow Movement of Spent Fuel from SFP to Dry Storage Facility While Plant Is in Cold Shutdown ML20134L4891996-11-12012 November 1996 Forwards Copy of 961107 Amend 187 to License DPR-16 & Safety Evaluation for Facility ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20129F6401996-10-25025 October 1996 Requests That Encl Handout for Nuclear Energy Inst/GPUN-OG/ NRC Conference Call on Nuclear Energy Inst/Epri Revised Source Term Task Force for Plant,Be Placed in Docket File 50-219 ML20134G1731996-10-24024 October 1996 Informs Commission That Final No Significant Hazards Consideration Determination & License Amend Will Be Issued on or About 961030 to Gpu Nuclear Corp,Per Util 960415 Request to Revise TS 5.3.1.B ML20128L7191996-10-0909 October 1996 Forwards from Jc Fornicola to K Cozen Re Consideration of Oyster Creek as Pilot Plant for Submittal of Revised Source Term ML20129G7861996-10-0101 October 1996 Discusses 960923 Telcon from P Gunter Re Listed Topics. Update of Status of SPF 2.206 & Memo to Commission from Taylor, Resolution of Sf Storage Pool Action Plan Issues, Also Discussed ML20132A9681996-06-12012 June 1996 Forwards Copy of Ltr Requesting NRC to Investigate & Correct Highly Inaccurate Public Statement That Appeared in Gpu June 1996 Neighborhood Update ML20059J8431994-01-11011 January 1994 Notification of Significant Licensee Meeting 94-02 W/Util on 940125 Re Enforcement Conference to Discuss NRC Operational Safety Team Insp Findings ML20059M7931993-11-17017 November 1993 Notification of 940119 Meeting W/Util in Rockville,Md to Discuss Matters Related to Water Backed Welding of Oyster Creek Safety Related Piping ML20059F9551993-11-17017 November 1993 Notification of 940119 Meeting W/Util in Rockville,Md to Discuss Matters Related to Water Backed Welding of Plant Safety Related Piping.Meeting Time Changed as Listed ML20059J5661993-11-0909 November 1993 Notification of 931119 Meeting W/Util in Rockville,Md to Discuss Proposed ISFSI & to Receive Status Rept on Staff Effort to Issue Certificate of Compliance for Standardized NUHOMS Sys & to Discuss License Requirements ML20058P9701993-10-18018 October 1993 Notification of Significant Licensee Meeting 93-133 W/Util on 931029 in Forked River,Nj to Discuss Operational Safety Team Insp Public Exit ML20057B4751993-09-16016 September 1993 Notification of 931020 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20057D7141993-08-0303 August 1993 Requests Assistance in Determining Adequacy of Plant Methodology for Determining Reportability of Plant Operation Above Licensed Core Thermal Limit ML20128K9051993-02-0303 February 1993 Notification of Significant Licensee Meeting 93-15 W/Util on 930208 to Discuss Results of NRC Review of Plant Operation W/Degraded Shutdown Cooling ML20127F3661993-01-0505 January 1993 Notification of Significant Licensee Meeting 93-002 W/Util on 930126 to Discuss Integration of Simulator Into Training Program ML20126J8041993-01-0404 January 1993 Notification of 930106 Meeting W/Util in Rockville,Md to Discuss Matters Re Core Spray Downcomer Leak (Weld L3a) ML20126J9941993-01-0404 January 1993 Notification of 930112 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20126F4571992-12-18018 December 1992 Notification of 930112 Meeting W/Util in Rockville,Md to Discuss Reactor Bldg Access Modification for Facility ML20217B0841991-03-0505 March 1991 Forwards AEOD Diagnostic Evaluation Team Rept for Plant for Info.Rept Documents Team Findings & Conclusions & Includes Discussions of Licensee Strengths & Weaknesses ML20058D5561990-10-31031 October 1990 Notification of 901114 Meeting W/Util in Forked River,Nj to Discuss Status of Licensing Activities for Plant ML20058D5721990-10-26026 October 1990 Notification of 901107 Meeting W/Util in Rockville,Md to Discuss Matters Re Fuel Channel Box Bowing ML20058A3411990-10-18018 October 1990 Notification of 901029 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20058N9351990-08-13013 August 1990 Notification of 900816 Meeting in Bethesda,Md W/Util to Discuss Emergency Response Data Sys ML20058M4071990-08-0808 August 1990 Notification of 900829 Meeting W/Util in Forked River,Nj to Discuss Status of Licensing Activities for Plant ML20058L5781990-07-31031 July 1990 Notification of 900919 Meeting W/Util in Rockville,Md to Discuss Matters Re Plant Drywell Corrosion Problem ML20055C3341990-02-0909 February 1990 Notification of 900216 Enforcement Conference Meeting 90-19 W/Util in King of Prussia,Pa Re Safety Concern Process & Degraded ADS Logic ML20247K8611989-09-15015 September 1989 Notification of 890927 Meeting W/Util in Rockville,Md to Discuss site-specific Response Spectra & Methodology to Develop New Seismic Floor Response Spectra 1999-06-10
[Table view] |
Text
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[ g NUCLEAR REGULATORY COMMISSION
, & ij WASHWGTON,0. C. 20555
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! MEMORANDUM FOR: Comissioner Asselstine i FROM: William J. Dircks Executive Director for Operations
SUBJECT:
OYSTER CREEK i
f This is in response to your request of June 18, 1985 to elaborate on the dis-
{ crepancies in the Oyster Creek Plant drawings. >
1 l Region I has been performing the final closeout inspections for a number of IE i Bulletins for the last two years with Oyster Creek being the last plant to be j inspected. This announced inspection (50-289/85-14) was conducted Ma i 17, 1985, at both the GPUN Corporate Office (Parsippany, New Jersey) and aty the 14 to
! Oyster Creek site. The inspection revealed that adequate documentation was not 4
readily available to confirm that appropriate inspections and analyses had been i
performed during 1979 and 1980 in response to IE Bulletins 79-02, " Pipe Support i Baseplate Designs", and 79-14. " Seismic Analysis For As-Built Safety-Related Piping Systems". It should be noted that at that time Jersey Central Power and .
i Light Company (JCP&L) owned and operated the Oyster Creek Facility. GPUN did !
not assume responsibility as the licensee for Oyster Creek until January 1, 1982.
j Based upon the poor preliminary results, a management meeting was conducted
! with the licensee on May 20, 1985 to discuss discrepancies identified by Region I and contractor inspectors in the documentation and in the small portion of plant systems directly inspected by the NRC. GPUN committed to embark on a detailed review of the as-built condition of the plant piping systems important to safety and provide a status of this review within three weeks. It was acknow-ledged by GPUN that portions of the JCP&L files were being located and these l were responsive to the inspector's needs but not yet fully assembled.
At the second Management Meeting held at Region I on June 13, 1985, the results
. of the review regarding the as-built conditions were discussed and GPUN ac-knowledged that most of the JCP&L records of the subject inspections had not
- . been incorporated into their record system for the plant.
l The principal elements of their review and inspection program including screen-
- ' ing criteria, were discussed along with the engineering analysis and disposi-tion of the nonconformances resulting from the Quality Control inspections to l date. GPUN stated that, although a number of deficiencies exist in the records, i evaluations, and plant installations, their overall evaluation thus far con-
! firmed the correctness of the original design. Since the plant was shut down just previous to the meeting for an unrelated reason, the extent of r inspection activities that could be conducted in the drywell during this period
! . were also discussed. The licensee comitted to perfom inspections of the 8507220168 850708 PDR CDPMS NRCC
] CORRESPONDENCE PDR I
- . - _ - ..- .. .,--_. .- --- . -., .- _ . . ~ . . . . - - _ . - . ,
\
Comissioner Asselstine 2 accessible portions of several key systems during the duration of the shutdown.
The licensee was instructed to provide a Justification for Continued Operation (JCO) before comencing a restart. The GPUN response was provided June 14, 1985 and is attached. Based upon the outcome of the June 13 meeting, the JC0 '
and the resident inspector's onsite confirmation of results, the staff agreed to the Oyster Creek restart.
Subsequently, on June 25, 1985, Region I and NRR staff visited the GPUN corporate offices to verify the underlying bases for the GPUN program. Based upon the detailed examinations, GPUN was found to have recovered and assessed the JCP&L documentation that was not previously available in that the conclu-sions an( bases for the licensee's effort were confirmed.
A number of discrepancies were repaired as they were discovered in the course of their program. None resulted in the need for declaring any of the affected systems inoperable. The staff concluded that adequate GPUN inspection, engi-neering and management resources were involved to assure timely completion of the effort.
The Region I and NRR staffs have been actively involved in this issue since its discovery in mid-May, have concluded the licensee's JC0 has a valid technical basis and that the GPUN corrective actions are appropriate.
(Signes William J.Direkt William J. Dircks Executive Director for Operations
Attachment:
GPUN letter dated June 14, 1985 cc w/ attachment:
Chairman Palladino Comissioner Bernthal Comissioner Zech SECY OPE OGC J. M. Cutchin I
i o .
Commissioner Asselstine 3 Distribution:
J. Roe T. Rehm V. Stello G. Cunningham J. Taylor EDO 000736 T. Murley J. Allan R. Starostecki S. Ebneter H. Kister E. Conner W. Bateman Docket No. 50-219 Public Local Document Public Room Document Room (PDR) (LPDR)
Region I Docket Room ED0 r/f HDenton i
RI:DRP RI:DRP RI:DRP RI:RA ED0////
Conner /sm Kister Starostecki Murley ks 7/5/85 7/&/85 7/ %f85 Dirg/85 7/g 7/$/85 e i
07/01/85' 19:06 tRC REG 1 FC.008 004
- Attachment GPU Nuclear Corporation
- h. M M7 100 Interpace Parkway Pers opany. New Jersey 070541149 '
(201)263 6500 TELEX 136 482 Writer's Direct Dial Number:
201-299-6797 June 14,1985 Dr. Thomas E. Murley, Administrator Region 1 U.S. Nuclear Regulatory Comission 631 Park Avenue King of Prussia, PA 19406
Dear Dr. Murley:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Preliminary Response to IE Inspection 85-14 During IE Inspection 65-14, several discrepancies between drawings which were updated as a result of IE Bulletin 79-14, and the inspector's field
- 2::r :tS.: Mere Matified. At a meeting with members of your staff on May 20,1955, we committed to reinspect those systems accessible during operation to ascertain the extent that drawings reflect actual field conditions and determine if seismic analyses, which were based on these drawings, were still valid. On June 13, 1985, we presented our preliminary results of that reinspection. This letter complies with your request that we provide a written response outlining the bases for continued operation of the Oyster Creek Nuclear Generating station untti the reinspection is completed.
We have concluded that the major techriical requirements of IE Bulletin 79-14 have been addressed and satisfied through a review of documentation relating to the 1979/1900 inspection. This docunentation review has detertnined that seismic concerns were addressed and corrected during the 1979/1900 effort.
L k l C 1'd },'
GPU Nuclear Corporation is a sues.oiary of GeneralPuboc Utstities Corporation
07/01/95^ 10:07 mC REG 1 ND. 0M 005 Dr. Thomas E. Murley June 14,1985 Page Twc With regard to IE Bulletin 79-02, our review of the existing documentation has concluded that the technical requirements of the Bulletin such as base plate flexibility, factor of safety, cyclic loads and load testing have Men addressed and show evidence of being satisfied. The existing test results will be summarized and statistics developed to document confidence levels.
The 1979/1980 inspection contained all the attributes required by IE Bulletin 79-14. The 1985 inspection included all the required 75-14 attributes plus additional attributes which surpass the requirements of the bulletin. Based on our 1985 inspection results, as of June 13, 1985, we have seen numerous minor deviations from the engineering drawings, primarily with -
regard to hangers. Many of these nonconformances are being corrected as they are found and the remainder are being evaluated by engineering for impact on system seismic capability. An engineering assessment is being performed in two steps. Each Material Nonconformance Report (MNCR) is first individually evaluated for conditional release. A system reevaluation is then conducted in order to assess the aggregate effect of all the MNCR's issued against that ,
system. No variances have resulted in any safety related system being declared inoperable. The 1985 inspection effort, as of June 13, 1985, '
confirmsBulletin 79-14 conclusions reached in 1979/1980, and it does not change our conclusions about the overall seismic acceptability of the affectea piping systems.
Because of the plant trip on June 12th, we are now in the process of performing inspections in the drywell. As of today we would expect to complete the 79-14 inspections of the accessible portions of one Main Steam Line, one equivalent Recirculation Piping Loop, one Fain Feedwater line, and one Core Spray Line. We will continue to inspect until the plant is ready for restart. Very preliminary inspection results from within the drywell, current as of June 14th, show a much reduced number of deviations between inspection .
attributes and drawings. No significant or major defects have been found to da te. The reinspection effort will he completed during our next scheduled outage of October,1985. If system reanalysis is required, the results will be reported to you as they becone available.
i In 1978 and 1979, a probabilistic risk analysis of the Oyster Creek Nuclear Generating Station was performed. This analysis, entitled the "0yster Creek Probabilistic Safety Analysis" (OPSA) estimated earthq akes of 0.229 or greater to have a mean frequency of approximately 1.15 x 10 /yr. The OPSA
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- 07/01/85' 10:08 WC REG 1 NO.008 006 1
Dr.' Thomas E. Murley, Administrator June 14,1985 Page Three study calculated a core melt frequency of approximately 1.5 x 10-4/yr for all seismic related events and approximately 2.6 x 10-0/yr due to seismic-induced LOCAs (seismic pipe breaks which is the 79-14 issuc). This equates to approximately 2% of the seismic core melt frequency, and is about 1% of the total core melt frtquency. This results from the relatively high seismic capacities of the piping systems.
In summary, our bases for concluding there is reasonable justification for continuing Oyster Creek operation pending final completion of the inspections are as follows:
- 1. Inspection to date as previously noted does not change the prior 1979-1980 ef fort on Bulletin 79-14. Hence we conclude the seismic piping design capability is valid.
- 2. Very preliminary inspection results from within the drywell . -current as of June 14th, show a much reduced number of deviations between inspection attributes and drawings. No major defect has been found.
- 3. The probability of a design bases or more severe earthquake prior to the completion of 79-14 inspection activities, is extremely remotc.
- 4. The PRA studies show seismic induced LOCA's to be a very small contribution to core melt frequency and inspection results do not channe this assessment.
It is our conclusion from all of the above that there is no perceptible change in any seismic induced LOCA risk which would affect public health and safety due to the continued operation of Oyster Creek.
Very truly yours, s"B. M P. R. Clark President pRC:kh .
0534U cc: Mr. John A. Zwolinski, Chief Operating Reactors Branch No. 5 U. S. Nuclear Regulatory Coamission Washington, DC 20555 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, N. J. 08731 0534U
' + * ' ' ' pM ucy
- y UNITED STATES y, ,9,1 g
E NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 5.,*****/
EDO PRINCIPAL CORRESPONDENCE CONTROL FROM: DUE: 07/01/85 EDO CONTROL: 000736 DOC DT: 06/18/85 COMMISSIONER ASSELSTINE FINAL REPLY:
TO:
DIRCKS FOR SIGNATURE OF: ** PRIORITY ** SECY NO:
EXECUTIVE DIRECTOR DESC: ROUTINO:
OYSTER CREEK DIRCKS ROE DATE: 06/19/85 U N& !* } REHM ASSIGNED TO: M CONTACT: DEMTON
. ~ . _ -
STELLO MURLEY OCUNNINGHAM SPECIAL INSTRUCTIONS OR REMARKS: TAYLOR RECEIVED NRR: 06/19/85 gACTION:,r -- _7DLrTHOMPSONa-"?
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