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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210H6681999-07-29029 July 1999 Summary of 990329 Meeting with Gpu in Forked River,Nj Re Possibility of Decommisssioning of Oyster Creek Nuclear Generating Station.List of Attendees & Licensee Handouts Provided ML20195G1391998-11-16016 November 1998 Summary of 981103 Meeting with Gpu in Rockville,Md Re Possible Shutdown & Decommissioning of Oyster Creek Nuclear Generating Station in Year 2000.List of Attendees & Handout Encl ML20216E3421997-09-0303 September 1997 Summary of 970826 Meeting W/Gpu in Rockville,Md Re Possibility of Decommissioning of Plant.Agenda,Meeting Handouts & Primarily Centered Activities Associated W/Decommissioning Plant in Yr 2000 Encl ML20148D8531997-05-28028 May 1997 Summary of 970502 Meeting W/Util to Discuss Status of Implementation Schedule for Completion of Installation of Thermo-lag at Plants.List of Attendees Encl ML20149J5251994-12-29029 December 1994 Summary of 941219 Meeting W/Util Re Status of Licensing Actions.List of Attendees & Activities Encl ML20058K1831993-11-26026 November 1993 Summary of 931119 Meeting W/Licensee in Rockville,Md Re Licensing Issues Involved in Construction & Loading of Independent Spent Fuel Storage Installation to Be Constructed at Plant ML20059F3931993-10-27027 October 1993 Summary of 931020 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Status of Plant Licensing Actions.List of Attendees Encl ML20128K8261993-02-0909 February 1993 Summary of 921123-24 Meeting in King of Prussia,Pa Re Region I Positions on Operator Licensing Issues & Solicit Input from Util Training Staffs ML20127M5941993-01-26026 January 1993 Summary of 930112 Meeting W/Util in Rockville,Md Re Reactor Bldg Access Control Mod & Operational Safeguards Response Evaluation.List of Attendees & Handouts Encl ML20127F6681993-01-14014 January 1993 Summary of 930112 Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Individuals Participating in Discussion & Marked Up Copy of Staff Pmr Encl ML20127E1281993-01-13013 January 1993 Summary of 930106 Meeting W/Util in Rockville,Md Re Insp of Plant Core Spray Spargers.List of Discussion Participants & Licensee Agenda Encl ML20125C2461992-12-0707 December 1992 Summary of 921118 Meeting W/Util in Rockville,Md Re Status of Licensing Actions ML20058K1871990-12-11011 December 1990 Summary of 901114 Progress Review Meeting at Plant Site Re Status of Licensing Actions.List of Attendees Encl ML20062F1121990-11-15015 November 1990 Summary of 901107 Meeting W/Util in Rockville,Md,Re Fuel Channel Bowing & Reuse of Fuel Channels at Facility ML20059N5951990-10-0303 October 1990 Summary of 900919 Meeting W/Util in Rockville,Md to Discuss Matters Re Plant Drywell Corrosion.Viewgraphs Encl ML20246M5871989-08-29029 August 1989 Summary of 890802 Meeting W/Util in Rockville,Md Re full-term OL & Other Licensing Activities.List of Attendees & marked-up Regulatory Info Tracking Sys List of Unresolved SEP Topics & TAC Numbers Encl ML20246L4001989-07-10010 July 1989 Summary of 890627 Meeting W/Util in Rockville,Md Re Combustible Gas Control for Plant.List of Individuals Attending Meeting,Proposed Meeting Agenda,Matl Used by Util in Discussion & Condensed History of Gas Control Issue Encl ML20245J7191989-06-20020 June 1989 Summary of 890607 Meeting W/Util in Forked River,Nj to Discuss Status of Plant Licensing Actions.List of Attendees & marked-up Copy of Regulatory Info Tracking Sys Encl ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20245J0141989-04-26026 April 1989 Summary of 890413 Meeting W/Util in Rockville,Md Re Status of Licensing actions.Marked-up Regulatory Info Tracking Sys List Encl ML20235N0661989-02-21021 February 1989 Summary of 890213 Meeting W/Util & State of Nj Re Air Sys Relating to MSIVs & Reactor Bldg to Torus Vacuum Breakers. Util Should Document Overall Methodology Used for MSIV Leakage Problems Prior to Startup.Viewgraphs Encl ML20235H0521989-02-10010 February 1989 Summary of 890130 Meeting W/Util in Rockville,Md to Discuss SSOMI (SSOMI-design Phase) Issue 2 Re Setpoints for Process Variables & Actions to Be Taken Before Startup.List of Attendees & Agenda Encl ML20195H9671988-11-23023 November 1988 Summary of 881110 Meeting W/Util in Rockville,Md Re Status of Facility Licensing Actions ML20155F4801988-10-0606 October 1988 Summary of 880928 Progress Review Meeting W/Util in Forked River,Nj Re Status of Plant Licensing Actions ML20207M0771988-10-0505 October 1988 Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl ML20154F7971988-09-15015 September 1988 Summary of 880901 QA Meeting W/Util in Rockville,Md to Discuss Rev 2 of Util Operational QA Plan for Plants.Agenda & List of Participants Encl ML20207F4451988-08-0909 August 1988 Summary of 880721 Meeting W/Util in Rockville,Md Re Retran Analytical Model & Cycle 12 Fuel Reload Analyses.Attendance List & Matl Used by Licensee in Meeting Encl ML20151L8991988-07-28028 July 1988 Summary of 880713 Progress Review Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Participants & marked-up Copy of Staff Regulatory Info Tracking Sys Encl ML20150B3271988-07-0606 July 1988 Summary of 880628 Meeting W/Util in Rockville,Md Re Facility Outage IGSCC Insp/Stress Improvement Plans ML20150C0101988-06-22022 June 1988 Summary of 880525 Meeting W/Gpu in Rockville,Md Re Matters Related to site-specific Response Spectra.Viewgraphs Encl ML20195K0451988-06-16016 June 1988 Summary of 880526 Meeting W/Util in Rockville,Md Re Matters on Oyster Creek-12R Outage 1GSCC Insp/Stress Improvement Plan as Described in Licensee Ltr .Inps/stress Improvement Plans Rept Encl ML20154C6511988-05-0909 May 1988 Summary of 880414 Progress Review Meeting W/Util & State of Nj Re Status of Facility Licensing Actions.List of Attendees Encl ML20196J9901988-03-0707 March 1988 Summary of 880224 Meeting W/Util in Rockville,Md Re Status of Plant Licensing Actions.List of attendees,marked-up Licensing Action Rept & Updated SEP Issues Encl ML20149L5861988-02-16016 February 1988 Summary of 871221 Meeting W/Util in Bethesda,Md Re Licensee Proposed Methodology to Develop New Seismic Floor Response Spectra.Attendance List Encl ML20149H8331988-02-10010 February 1988 Summary of 880106 Meeting W/Util & State of Nj in Bethesda,Md Re Status of Plant Licensing actions.Marked-up Licensing Action Rept,List of Attendees,Util Topical Rept on Fuel Reload Review & Cycle 12 Reload Schedule Encl ML20236W3801987-11-30030 November 1987 Summary of 871113 Meeting W/Util in Bethesda,Md Re Drywell Corrosion Problem at Facility.List of Attendees,Proposed Meeting Agenda & Util Presentation Encl ML20236P2841987-11-0505 November 1987 Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams 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 ML20239A6721987-09-11011 September 1987 Summary of 870903 Meeting W/Util in Bethesda,Md Re Util Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Viewgraphs Encl ML20237K6461987-08-0606 August 1987 Summary of 870619 Meeting W/Util in King of Prussia,Pa Re Changes to Util Emergency Plan for Plants Based on Changing Plant Status & Reclassification to Post Defueling Monitored Storage ML20235U3351987-07-14014 July 1987 Summary of 870707 Meeting W/Util in Bethesda,Md Re Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Licensee Agenda Encl ML20215K0041987-06-18018 June 1987 Summary of 870611 Meeting W/Util in Bethesda,Md Re Drywell Corrosion at Plant & Status of Sep.Attendance List & Util Agenda for Proposed Actions Encl ML20214L1171987-05-22022 May 1987 Summary of 870515 Meeting W/Util in Bethesda,Md Re Status of Station Licensing Actions.Attendance List & marked-up Licensing Action Rept Encl ML20207A5221987-05-15015 May 1987 Summary of Operating Reactors Event Meeting 87-13 on 870507 Re Events Which Occurred Since 870428.List of Attendees, Events Discussed & Significant Elements of Events & Summary of Events Presented Encl ML20207S3431987-03-13013 March 1987 Summary of 870226 Meeting W/Util in Bethesda,Md Re Plans to Mitigate Corrosion of Drywell Shell.List of Attendees & Meeting Agenda Encl ML20207S1651987-03-13013 March 1987 Summary of 870120 Meeting W/Bwr Owners Group in Bethesda,Md Re Sys for Combustible Gas Control During Loca.Viewgraphs & Attendees List Encl ML20207R9701987-03-0909 March 1987 Summary of 870211 Meeting W/Util in Bethesda,Md Re Conceptual Design of Isolation Condensers Drywell Piping Penetrations.Attendee List Encl ML20207Q0871987-01-14014 January 1987 Summary of 861219 Third Meeting W/Util in Bethesda,Md Re Corrosion of Outer Drywell Shell at Elevation Just Below Downcomers.Supporting Documentation Encl ML20207N2271987-01-0505 January 1987 Summary of 861210 Meeting W/Util,Niagara Mohawk Power Corp, GE & Chicago Bridge & Iron in Bethesda,Md Re Corrosion of Outer Surface of Drywell Shell.List of Attendees,Drywell Figures,Meeting Notice & Licensee Handout Encl 1999-07-29
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210H6681999-07-29029 July 1999 Summary of 990329 Meeting with Gpu in Forked River,Nj Re Possibility of Decommisssioning of Oyster Creek Nuclear Generating Station.List of Attendees & Licensee Handouts Provided ML20195G1391998-11-16016 November 1998 Summary of 981103 Meeting with Gpu in Rockville,Md Re Possible Shutdown & Decommissioning of Oyster Creek Nuclear Generating Station in Year 2000.List of Attendees & Handout Encl ML20216E3421997-09-0303 September 1997 Summary of 970826 Meeting W/Gpu in Rockville,Md Re Possibility of Decommissioning of Plant.Agenda,Meeting Handouts & Primarily Centered Activities Associated W/Decommissioning Plant in Yr 2000 Encl ML20148D8531997-05-28028 May 1997 Summary of 970502 Meeting W/Util to Discuss Status of Implementation Schedule for Completion of Installation of Thermo-lag at Plants.List of Attendees Encl ML20149J5251994-12-29029 December 1994 Summary of 941219 Meeting W/Util Re Status of Licensing Actions.List of Attendees & Activities Encl ML20058K1831993-11-26026 November 1993 Summary of 931119 Meeting W/Licensee in Rockville,Md Re Licensing Issues Involved in Construction & Loading of Independent Spent Fuel Storage Installation to Be Constructed at Plant ML20059F3931993-10-27027 October 1993 Summary of 931020 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Status of Plant Licensing Actions.List of Attendees Encl ML20128K8261993-02-0909 February 1993 Summary of 921123-24 Meeting in King of Prussia,Pa Re Region I Positions on Operator Licensing Issues & Solicit Input from Util Training Staffs ML20127M5941993-01-26026 January 1993 Summary of 930112 Meeting W/Util in Rockville,Md Re Reactor Bldg Access Control Mod & Operational Safeguards Response Evaluation.List of Attendees & Handouts Encl ML20127F6681993-01-14014 January 1993 Summary of 930112 Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Individuals Participating in Discussion & Marked Up Copy of Staff Pmr Encl ML20127E1281993-01-13013 January 1993 Summary of 930106 Meeting W/Util in Rockville,Md Re Insp of Plant Core Spray Spargers.List of Discussion Participants & Licensee Agenda Encl ML20125C2461992-12-0707 December 1992 Summary of 921118 Meeting W/Util in Rockville,Md Re Status of Licensing Actions ML20058K1871990-12-11011 December 1990 Summary of 901114 Progress Review Meeting at Plant Site Re Status of Licensing Actions.List of Attendees Encl ML20062F1121990-11-15015 November 1990 Summary of 901107 Meeting W/Util in Rockville,Md,Re Fuel Channel Bowing & Reuse of Fuel Channels at Facility ML20059N5951990-10-0303 October 1990 Summary of 900919 Meeting W/Util in Rockville,Md to Discuss Matters Re Plant Drywell Corrosion.Viewgraphs Encl ML20246M5871989-08-29029 August 1989 Summary of 890802 Meeting W/Util in Rockville,Md Re full-term OL & Other Licensing Activities.List of Attendees & marked-up Regulatory Info Tracking Sys List of Unresolved SEP Topics & TAC Numbers Encl ML20246L4001989-07-10010 July 1989 Summary of 890627 Meeting W/Util in Rockville,Md Re Combustible Gas Control for Plant.List of Individuals Attending Meeting,Proposed Meeting Agenda,Matl Used by Util in Discussion & Condensed History of Gas Control Issue Encl ML20245J7191989-06-20020 June 1989 Summary of 890607 Meeting W/Util in Forked River,Nj to Discuss Status of Plant Licensing Actions.List of Attendees & marked-up Copy of Regulatory Info Tracking Sys Encl ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20245J0141989-04-26026 April 1989 Summary of 890413 Meeting W/Util in Rockville,Md Re Status of Licensing actions.Marked-up Regulatory Info Tracking Sys List Encl ML20235N0661989-02-21021 February 1989 Summary of 890213 Meeting W/Util & State of Nj Re Air Sys Relating to MSIVs & Reactor Bldg to Torus Vacuum Breakers. Util Should Document Overall Methodology Used for MSIV Leakage Problems Prior to Startup.Viewgraphs Encl ML20235H0521989-02-10010 February 1989 Summary of 890130 Meeting W/Util in Rockville,Md to Discuss SSOMI (SSOMI-design Phase) Issue 2 Re Setpoints for Process Variables & Actions to Be Taken Before Startup.List of Attendees & Agenda Encl ML20195H9671988-11-23023 November 1988 Summary of 881110 Meeting W/Util in Rockville,Md Re Status of Facility Licensing Actions ML20155F4801988-10-0606 October 1988 Summary of 880928 Progress Review Meeting W/Util in Forked River,Nj Re Status of Plant Licensing Actions ML20207M0771988-10-0505 October 1988 Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl ML20154F7971988-09-15015 September 1988 Summary of 880901 QA Meeting W/Util in Rockville,Md to Discuss Rev 2 of Util Operational QA Plan for Plants.Agenda & List of Participants Encl ML20207F4451988-08-0909 August 1988 Summary of 880721 Meeting W/Util in Rockville,Md Re Retran Analytical Model & Cycle 12 Fuel Reload Analyses.Attendance List & Matl Used by Licensee in Meeting Encl ML20151L8991988-07-28028 July 1988 Summary of 880713 Progress Review Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Participants & marked-up Copy of Staff Regulatory Info Tracking Sys Encl ML20150B3271988-07-0606 July 1988 Summary of 880628 Meeting W/Util in Rockville,Md Re Facility Outage IGSCC Insp/Stress Improvement Plans ML20150C0101988-06-22022 June 1988 Summary of 880525 Meeting W/Gpu in Rockville,Md Re Matters Related to site-specific Response Spectra.Viewgraphs Encl ML20195K0451988-06-16016 June 1988 Summary of 880526 Meeting W/Util in Rockville,Md Re Matters on Oyster Creek-12R Outage 1GSCC Insp/Stress Improvement Plan as Described in Licensee Ltr .Inps/stress Improvement Plans Rept Encl ML20154C6511988-05-0909 May 1988 Summary of 880414 Progress Review Meeting W/Util & State of Nj Re Status of Facility Licensing Actions.List of Attendees Encl ML20196J9901988-03-0707 March 1988 Summary of 880224 Meeting W/Util in Rockville,Md Re Status of Plant Licensing Actions.List of attendees,marked-up Licensing Action Rept & Updated SEP Issues Encl ML20149L5861988-02-16016 February 1988 Summary of 871221 Meeting W/Util in Bethesda,Md Re Licensee Proposed Methodology to Develop New Seismic Floor Response Spectra.Attendance List Encl ML20149H8331988-02-10010 February 1988 Summary of 880106 Meeting W/Util & State of Nj in Bethesda,Md Re Status of Plant Licensing actions.Marked-up Licensing Action Rept,List of Attendees,Util Topical Rept on Fuel Reload Review & Cycle 12 Reload Schedule Encl ML20236W3801987-11-30030 November 1987 Summary of 871113 Meeting W/Util in Bethesda,Md Re Drywell Corrosion Problem at Facility.List of Attendees,Proposed Meeting Agenda & Util Presentation Encl ML20236P2841987-11-0505 November 1987 Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams 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 ML20239A6721987-09-11011 September 1987 Summary of 870903 Meeting W/Util in Bethesda,Md Re Util Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Viewgraphs Encl ML20237K6461987-08-0606 August 1987 Summary of 870619 Meeting W/Util in King of Prussia,Pa Re Changes to Util Emergency Plan for Plants Based on Changing Plant Status & Reclassification to Post Defueling Monitored Storage ML20235U3351987-07-14014 July 1987 Summary of 870707 Meeting W/Util in Bethesda,Md Re Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Licensee Agenda Encl ML20215K0041987-06-18018 June 1987 Summary of 870611 Meeting W/Util in Bethesda,Md Re Drywell Corrosion at Plant & Status of Sep.Attendance List & Util Agenda for Proposed Actions Encl ML20214L1171987-05-22022 May 1987 Summary of 870515 Meeting W/Util in Bethesda,Md Re Status of Station Licensing Actions.Attendance List & marked-up Licensing Action Rept Encl ML20207A5221987-05-15015 May 1987 Summary of Operating Reactors Event Meeting 87-13 on 870507 Re Events Which Occurred Since 870428.List of Attendees, Events Discussed & Significant Elements of Events & Summary of Events Presented Encl ML20207S1651987-03-13013 March 1987 Summary of 870120 Meeting W/Bwr Owners Group in Bethesda,Md Re Sys for Combustible Gas Control During Loca.Viewgraphs & Attendees List Encl ML20207S3431987-03-13013 March 1987 Summary of 870226 Meeting W/Util in Bethesda,Md Re Plans to Mitigate Corrosion of Drywell Shell.List of Attendees & Meeting Agenda Encl ML20207R9701987-03-0909 March 1987 Summary of 870211 Meeting W/Util in Bethesda,Md Re Conceptual Design of Isolation Condensers Drywell Piping Penetrations.Attendee List Encl ML20207Q0871987-01-14014 January 1987 Summary of 861219 Third Meeting W/Util in Bethesda,Md Re Corrosion of Outer Drywell Shell at Elevation Just Below Downcomers.Supporting Documentation Encl ML20207N2271987-01-0505 January 1987 Summary of 861210 Meeting W/Util,Niagara Mohawk Power Corp, GE & Chicago Bridge & Iron in Bethesda,Md Re Corrosion of Outer Surface of Drywell Shell.List of Attendees,Drywell Figures,Meeting Notice & Licensee Handout Encl 1999-07-29
[Table view] |
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%'c, UNITED STATES
- *~ NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555 October 1,1986
% .*. . . . /
Occket No. 50-219 LICENSEES: GPil Nuclear Corporation Jersey Central Power and Light Company FACILITY: Oyster Creek Nuclear Generating Station AIIGUST 22, 1986, PEETING WITH GPU NUCLEAR CORPORATION (GPUN1 SUPJECT:
ON THE CONTAINMENT PROCESS PIPING PENETRATIONS FOR CONDENSEP On Friday, August 22, 1986, a meeting was held at NRP. headquarters, Bethesda, Maryland, with GPUN, the licenree, on the design marginsThese in thepenetrations pipinP 4
penetrations for the two emerg ncy isolation condensers.
are for the steam lines to the condensers and the condensate return lines from the condensers to the reactor vessel. The licensee had reauested th meeting to discuss the loading on the 15 process piping penetrations in the primary containment or drywell during a double-ended rupture of the pipe in the penetration. The licensee concluded under 10 CFR 50.59 that 11 of the 15 penet-ations were acceptable and 4 were not.
Attachment Attachment 1 is the l'st of individuals who attended the meeting. The markups 2 is the riaterial for the meetino handed out by the licensee.
The following is a summary of the were done by me durino the meetina. The significar.t items discussed and the actions, if any, taken The discussion on the drywell piping penetrations follows the material in Attachment 2. The licensee stated that its 10 CFP 50.50 reviews of the 11 penetrations will be included in the Updated Final Safety Analysis Report (FSAR1 for Oyster Creek. This material will be submitted in the earliest available update of the FSAR.
The only piping penetrations that do not have acceptable design maroins are the four penetrations for the two condensate return lines and the two ste
' lines for the Isolation Condensers.
' outside the drywell above the reactor vessel to allow natural circulation throuch the condensers and reactor core to cool the reactor core.
The licensee explained it is considering the the following pipes, (?) 3 potential restrict flow fixes for through the A piping penetrations: (1) anch-the break and (31 replace the penetrations. The last fix could not be done in the current Cycle 11 Refueling (Cycle 11R1 outage without significantly Anchoring the pipe would recuire a re-analysis of the extending the outape. stresses in the piping becau w the anchors might cause th 1 The licensee stated that the second l penetrations under other conditions.fix was possibly the best solution
- or not such a redesign of the 4 sing penetration could be implernted without significantly impacting the current outage in the use of resources or in extending the outage. gg g PDH ADOCK 05000219 P PDR l
i
_ _ . _ ~ _ - - ___ -
4 I. .
[ The licensee discussed the safety significance of the 4 penetrations. The
< licensee explained in its presentation its application of leak before break j in its evaluation of the condenser piping. A slide on this is in Attachment
- -2. The licensee stated that the pipe will leak before breaking and the leakage detection systems at Oyster Creek will assure the licensee will shut down Oyster Creek before a double ended rupture of the pipes. The penetrations
- can acceptably take the loads from smaller or less severe breaks.
The staff requested that the licensee complete its design of the fix for-j the 4 piping penetrations and evaluate its ability to implement the fix during the current outage. The results would be submitted before the restart for Operating Cycle 11. The fix would return the existing design margins in the piping penetrations to that in the FSAR when the plant was licensed. If the licensee concludes that the work cannot be done in this current outage, it must request the approval of the staff to implement the fix in the Cycle 12R outage. This outage should be in 1988. The staff requested, and the licensee agreed, that the licensee's submittal will be made at least one i month before its planned restart of Oyster Creek from the current Cycle 11R i _ outage and will explain the impact of the work on the outage. The staff stated that it will address this issue as part of the restart of Oyster Creek l from the Cycle 11R outage.
i 1
- I
/ k N. Donoh Jr., Project Manager i NBWRProjectDirectorate#1 Division of BWR Licensing i
- Attachments:
- 1. List of Attendees
, 2. Licensee's handout i cc: R. Bernero l R. Houston G. Lainas
,'- G. Hulman i M. Srinivasan l B. D. Liaw i
D Y DBL:BWD1 DBL:BWD1
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CJamerso [' DBL JD t)w$ijg JZwolinski q /pB6 /86 go / $ /86 l
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Oyster Creek Nuclear Mr. P. B. Fiedler Generating Station Oyster Creek Nuclear Generating Station cc: Resident Inspector Mr. Ernest L. Blake, Jr.
Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 2300 N Street, NW Post Office Box 445 Forked River, New Jersey 08731 Washington, D.C. 20037 J.B. Liberman, Esquire Comissioner New Jersey Department of Energy Bishop, Liberman, Cook, et al.
101 Comerce Street 1155 Avenue of the Americas Newark, New Jersey 072 New York, New York 10036 Mr. David M. Scott, Acting Chief Bureau of Nuclear Engineerir Regional Administrator, Region I Department of Environmental Protection U.S. Nuclear Regulatory Commission CN 411 631 Park Avenue Trenton, New Jersey 08625 r.ing of Prussia, Pennsylvania 19406 BWR Licensing Manager GPU Nuclear 100 Interpace Parkway Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN ll?
Trenton, New Jersey 08625 Mayor lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.
P. O. Box 388 Forked River, New Jersey 08731 Mr. P. B. Fiedler Vice President and Director Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
ATTACHMENT 1 MEETINr- VITH GPil NUCLEAR CORPOPt. TION (GPUn')
TO DISCUSS FIRE PROTECTION June 23, 1986 ORGAFIZATI0f:
Nf"I NRC/NRP/0P.L J. Donohew NPC/NRR/ DBL J. Iwolinski GPUN P. Crayr GPUN N. Shah GPUN M. Sanfero GPUN A. Pochino GPU?!
D. Croneberger
- -_ - -~-.-n , - . . -
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ATTACHMENT 2 PRESENTATION ON ANALYSIS FOR HELB IN THE DRYWELL PENETPATION PIPING
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9 I. BACKGROUND II. PENETRATIONS AffECTED III. ORIGINAL DESIGN CRITERIA VS. NEW DESIGN CRITERI IV. NEW ANALYSIS AND RESULTS V. HELB IN THE EMERGENCY CONDENSER STEAM SUPPLY AND PIPING VI. CONCLUSION l
l l
. 1 I. BACKGR M D A. NINE MILE POINT 1 ANALYSIS o Original analysis did not consider flow reversal effects oSeveralpenetrationsfoundtohaveexcessiveloads B. GPUK ]YSTER CREEK ANALYSIS o Original analysis similar to NMP 1 0 GPUN performed re-analysis i
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II. PENET MTIONS AFFECTED A. TYPICAL PENETMTION CONFIGUMTIONS - SKETCHES B. LIST OF PENET MTIONS AffECTED
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II B. LIST OF PENETRATIONS AffECTED PIPE PENETRATION N0. TYPE SIZE 10" Emerg.Cond. Steam 2 DoublefluedHead X-3A,B Emerg.Cond.Cond. 2 DoublefluedHead 10" X-SA,B Main Steam 2 Doublefluedvl 24" X-2A,B bellows Feedwater 2 Doublefluedvl 18" X-4A,B bellows CleanupLetdown i SinglefluedHead 6"
X-9 CleanupReturn i SinglefluedFead 6"
X-10 CoreSpray 2 SinglefluedHead 8"
X-128,X-70 ShutdownCooling 2 SinglefluedHead 14" X-7-8 i SinglefluedHead 3" CR0 Return X-61
~
III. ORIGINAL DESIGN CRITERIA VS. REVISEl
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REVISEDDESIGN CRITERIAi 0RIGINALDESIGN(PERfSAR) 1.PipeRuptureDesign PipeAssumedToRupture,At RupturelocationsSelected Random,OnEitherSideOfThe PerGiambussoletterCritera Condition Drywell Jetforceloadingfrom JetforcePlusMomentum 2.LoadOnPenetration Guillotine-TypePipeBreak EffectsDueToFow ReversalWithinGuardPipe f =1xP x A F = :(P+lV')A) e 9 9
+[(P+lV')A) a Where,P= Pressure A= Area V= Velocity Z= Density e=Processpipeconditionitthebreak a=Annularregionexitcondition ASMESect.III,1983
- 3. Allowible Stresses 0.9S fig.NE3221-3i.e.The Greaterof1.5Sor y
l.Sb mC Where, S = Yield Stress S = Allowable Stress Intensity
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6 IV. NEW ANALYSIS AND RESULTS A. CALCULATIONAL NETHOD B. SU R RY Of PENETRATIONS EVALUATED t
- - . - - --.- - -s-,-
IV A. CALCULATION Of THRUST LOAD DAYWELL STEEL SHELL IdiiDE OuTSIDE
" GUAR.D PIPE n PEoCEss ESPE
+
. a Ve
/' =
Paa
,V ,% 4-seAcreew rocce,F A C.
I
'mv:uduwk i
f=((p+2v')A: +[(p+zv')A) a e
fluidpressures, densities,andvelocitiescalculatedconsiderin
- Womogeneous, Steady flow and transient Analysis
- Multi-Node Computer Solution or fanno line Calculation
- Upstream Losses Accounted for -ihm hm, . ,,g
- Separation of Pipe Ends Exceeds Dl4
- flowfromBothDirections,ContainmentIncludej(whenAppro
. i IV 3. EVALUATION OF 0.0. PEETRATIONS Mhm gle m(re: p Mconc ,
for HIGH EERGY LIE BER (HELB)
FinalResults 4 ,
NORMAL CONDITIONS i
PRESS TEMP. ANALYSIS PIPE 'T EQUIRED REMARS -
TYPE PSIC.
PEETRATION N0.
SIZE Yes dingisacceptable 1020 Sat.
Emerg,Cond. Steam 2 Doublefluedhead 10" in stand-by node; Ili X-3A,B applies when initiatec Yet leakBeforeBreak 1020 Subcooled Emerg.Cond.Cond. 2 Doublefluedhead 10" Water applies in stand-by ani ,
X-5A,B operatingmodes Yes Icading is acceptable 1020 Sat.
1 Singlefluedhead 6" Cleanupletdown Water X-9 Sat. No Giambussoletter 1020 2 Doublefluedw/ criteriapredictsno 24" MainSteam Steam X-2A,B bellows HElBatthislocation
- - No CheckvalveintheDW 2 Doublefluedv/
18" Feedwater X-4A,B bellows
- - No CheckvalveintheEs 6" CleanupReturn i Singlefluedhead
-- - No CheckvalveintheDU 2 Singlefluedhead 8" CoreSpray .
X-12B,X-70
- - No CheckvalveintheB 1 Single flued head 3" CRDReturn X-61 linedepressurized
- No 2 Singlefluedhead 14" ShddownCooling X-7-8
-ML N L 6 8 = bk d&% gs g4,w s amahe t A y g e>t.
n a b n n>
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V. HELB IN THE EMERGENCY CONDENSER STEAN SU AND CONDENSATE RETURN PIPING-ANALYSIS RESU
- 1. STEAN SUPPLY LINE
. Leak Before Break Precludes Double Ended Rupture
. Double Ended Rupt;te is Tolerable in " Stand-Bf Node
. In Operating Mode, Double Ended Rupture vill Exc
- 2. CONDENSATE RETURN LINE
. Leak Before Break Precludes Doubles Ended Rupture
. Doub1e Ended Rupture Would Initiate Emergency Co and Exceed Allowables '
l t
4%M Mods h bra u;d v1 LaL1m ESF-oddu3Tx.
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Va. LEAK BEFORE BREAK (LBB)
- ConceptofLBBpreviouslyacceptedbyNRC
- Guidence by NCR for SEP topic for the Palisades Plant
. LBB accepted on,PWR'S to eliminate RCS pipe wh
- GDC 4 revision in April, 1986 i
LBBisconsideredvalid,inGDC4revisioncurrentlyindraft
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X Vb. APPLICATION 0FLBBTOEMERGENCYCONDE
" PALISADES"CRITERIAREQUIREMENT EMERGENCYCONDENSERPIPINGEVALU i TwoindependentQuantitativeLeakage DetectabilityRequirements monitoringsystemsinoperation i
Indirect indications available e i Specifiedconditionsusedfor IntegrityRequirements evaluation Level D Loads
. CrackStabilityexists .oubm3hh Extreme Conditions
- Material Properties
. Tendencyforthetracktodevelop SubcriticalCrackGrowth wasshown.
' Analysis made for time vs. crack growthandleakrate Augmented 151 s
. EmergencyCondenser #k QN
( cshwdl)
Piping (sublectedtoISIshowedrc IGSCC.
< J ' PenetrationWeld wasnotinspectedduetc inaccessibility.
VI. CONCLUSION
. 4penetrationsoutof15requiringNRCapprovalforunrevie question.
Remarks Penetration Loadingisacceptableinstandbymode; Emerg.Cond. Steam >
LBBApplieswheninitiated LBBappliesinstandbyandoperating Emerg.Cond. Condensate mode e 11 penetrations out of 15 found acceptable by 10 CF Remarks Penetration loadingisacceptable Clean-upLetdown PerGiambussolettercriterianoWEL MainSteam atthislocation Feedwater Check valve in DW,Loggg Check valve in DW, Clean-upReturn CheckvalveinDW,
- CoreSpray CheckvalveinDW, CRDReturn Lineisdepressurized, ShutdownCooling
.~
The The licensee discussed the safety significance of the 4 penetrations.
licensee explained in its presentation its application of leak before break in its evaluation of the condenser piping. A slide on this is in Attachment
- 2. The licensee stated that the pipe will leak before breaHng and the leakage detection systems at Oyster Creek will assure the licensee will shut The penetrations down Oyster Creek before a double ended rupture of the pipes.
can acceptably take the loads from smaller or less severe breaks.
The sta#f requested that the licensee complete its desion of the fix for the 4 piping penetrations and evaluate its ability to implement the fix The results would be submitted before the restart durine the current for Operatino Cycleoutage.The
- 11. fix would return the existing design margins in If the piping penetrations to that in the FSAR when the plant was licensed.
the licensee concludes that the work cannot be done in this current outage, it must request the approval of the staff to implement the fix ir. the Cycle 129 outage. This outage should be in 1988. The sta'f reauested, and the licensee agreed, that the licensee's submittal will be made at least one month before its planned restart of Oyster Creek from the currentThe Cycle staff11R outage and will explain the impact of the work on the outaae. stated t from the Cycle 11R outage.
C.%
\
Jack N. Donohew, Jr. I Pro.iect Manaaer BWR Project Directorate #1 Division of BWR Licensing Attachments:
- 1. List of Attendees
- 2. Licensee's handout cc: R. Bernero P. Houston G. Lainas G. Hulman j
- M. Srinivasan B. D. Liaw i
I l
October 1, 1986 Distribution for Meetinc Sumary Dated:
Facility: Oyster Creek Nuclear Generating Station
N RC ~ PDR '"" ~~'~""'~
Local PDF.
BWD1 Reading J. Iwolinski J. Donohew C. Jamerson OGC-BETH (For ir.fo only)
E. Jorcan B. Grimes ACRS (10)
R. Bernero R. Houstor G. Laines B. D. Liaw G. Hulman M. Srinivasan W. Hodges DC File
- Copies sent to persons on facility service list l'
I r
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