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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] |
Text
g f' %g UNITED STATES NUCLEAR REGULATORY COMMISSION
, 5 p WASHINGTON, D. C. 20555
\*****/ July 16, 1986 Docket No. 50-219 LICENSEES: GPU Nuclear Corporation Jersey Central Power and Light Company FACILITY: Oyster Creek Nuclear Generating Station
SUBJECT:
JUNE 23, 1986, MEETING WITH GPU NUCLEfR CORPORATION (GPUN)
TO DISCUSS SEALING OF ITS ELECTRICAL CONDUIT TO MEET FIRE PROTECTION REQUIREMENTS AND POTENTIAL FIRE PROTECTION TECHNICAL EXEMPTIONS On Monday, June 23, 1986, a meeting was held at Oyster Creek Station site with GPUN, the licensee, on how it plans to seal its electrical conduits to meet fire protection requirements and on potential fire protection technical exemptions. In the meeting summaries dated February 28 and May 22, 1986, of meetings between the licensee and the staff, the licensee explained that it
~
was planning to submit technical exemptions to Appendix R to 10 CFR Part 50 before the restart from the current Cycle 11 Refueling (Cycle 11R) outage.
The licensee stated that these exemptions are similar to exemptions that the staff has granted to other licensees. This meetino served as an information exchange between the licensee and the staff before the licensee submits its reauest for exemptions to Appendix R.
Attachment 1 is the list of individuals who attended the meeting. Attachment 2 is the agenda for the meeting' handed out by the licensee. The following is a sumary of the significant items discussed and the actions, if any, taken or proposed. The sumary will be in terms of the issues listed in the agenda.
1.0 Conduit Internal Seals The licensee explained its criteria on sealing the electrical conduit was based on the internal conduit seal testing done at Perry Nuclear Plant. This is for sealing the conduit which is penetrating fire barriers at Oyster Creek. The Oyster Creek plant is currently in its outage for Appendix R modifications and must complete these modifications, includino conduit sealing, before the restart from this outage.
The staff and the licensee discussed the criteria for sealing conduit that came from testing performed at Perry and the differences being considered by the licensee in developing its criteria for Oyster Creek. The licensee stated that the criteria it expected to use for Oyster Creek is more restrictive than that used for Perry. The licensee discussed the specific differences between the Perry criteria and the criteria for Oyster Creek. This discussion was an information exchange and no decisions were made.
2.0 Potential Exemption Reauests The following discussions were of potential requests for technical exemptions to Appendix R. The licensee has not submitted a request for exemptions 8607230478 860716 PDR F
ADOCK 05000219 PDR
July 16, 1986 since its letter of April 3, 1985. The staff's approval of these exemptions is in its letter and safety evaluation dated March 24, 1986. The discussions in this meeting are on possible exemptions other than those previously approved by the staff.
The licensee explained that it will issue revision 4 of its Fire Protection Plan. This revision will contain the agreements it made with the staff in its October 9,1985, letter on its fire protection exemptions. Revision 5 will address the exemptions to be discussed in this meetino if these exemptions are submitted to the staff. These potential exemptions are the followina:
(1) Manual Action To Re Taken To Operate Valves These actions would be taken in a fire zone after the fire has been extinguished.
These manual actions would be required to operate valves for the safety of the plant and would be instead of providing remote operation of these valves. The staff acceptance of such manual operation is an exemption to the requirements of Appendix R.
The specific manual actions on opening valves which were discussed are the following:
(a) close the reactor vessel isolation valves to the reactor water cleanup system within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after shutdown to prevent loss of water from the vessel, (b) close the injection valves for the core spray system within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after shutdown to prevent loss of water from the reactor vessel, (c) open valves from the reactor vessel to the condensate storage tank within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 24 minutes after shutdown to add water to the vessel, and (d) open valves from the condensate storage tank to the core spray system within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after shutdown to add water to the reactor vessel.
(2) Fire wrappings, to prevent spurious signals, of three terminal boxes and terminals in the boxes for three electrical penetrations based on nearby fire suppression and detection systems.
(3) Manual action to repair loss of motor control center (MCC) for control room HVAC in a fire in the 480 switchgear room. The repair is outside the fire area and is required within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after the loss of the MCC.
(4) Manual action to repair loss of 1A2/182 crosstie breaker in the A 4160/480 volt switchgear room. The repair is to disconnect the breaker from the IR?
bus in the R switchgear room which is next to the A switchgear room.
(5) Manual action to open the inlet and exhaust dampers to the A,B battery room and close the recirculation dampers within 45 minutes. This is external to the fire area. The dampers are designed to fail close to prevent cooling of the room in winter.
July 16, 1986 The staff discussed the potential exemptions listed above with the licensee.
The staff stated that the licensee must address the number of station personnel needed for the worst fire and the actions that the personnel must take to respond to the fire. These actions must include the actions discussed at this meeting. The discussion was an information exchance and no decisions were proposed or made.
- 3. Summary The staff requested that the formal submittal of exemptions to Appendix R be sent to the staff no later than August 15, 1986 The licensee must also submit Technical Specifications (TS) changes to reflect the requirement on the alternate shutdown panel and to revise the existing fire protection tables in the TS. This must be before the restart of the current outage. Acceptable TS on the alternate shutdown panel from the RWR Standard Technical Specifications are in Attachment 3.
The staff stated that the fire inspection by NRC Region I is oresently scheduled for November 1986 afte'r the restart from the current outage. Personnel from the staff will attend this inspection.
[h, %
j Jack N. Donoheh,.1r., Project Manager y RWR Project Directorate #1 Division of BWR Licensing Attachments:
- 1. List of Attendees
- 2. Licensee's handout
- 3. BWP Standard Technical Specifications cc: R. Bernero G. Lainas G. Hulman M. Srinivasan
_ l 0FC :BWD1: DBL :RYD1 L :BWD1: DEL :BWD1: DBL : : :
_____:_________ :_. ____:____:._l______:.___________:____________:____________:___________
NAME :CJamerson .df ono ew:em :JS :JZwolinski : : :
_ _ _ _ _ : _ _ _ _ _ _ _ _ _ _ _ : N_ L..y_______:_.
_ : _ _ .ga gA ___________:___________
DATE :07/pl/86 :07/1g/86 :07/N /86 :07/D/86 : : :
m .,
Y OFFICIAL RECORD COPY
- Oyster Creek Nuclerr Generating Station cc:
Ernest L. Blake, Jr. Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 1800 M Street, N.W. Post Office Box 445 Washington, D.C. 20036 Forked River, New Jersey 08731 J.B. Liberman, Esquire Commissioner Rishop, Liberman, Cook, et al. New Jersey Department of Energy 1155 Avenue of the Americas 101 Commerce Street New York, New York 10036 Newark, New Jersey 07102 Eugene Fisher, Assistant Director Regional Administrator, Region I Division of Environmental Ouality U.S. Nuclear Regulatory Commission Department of Environmental 631 Park Avenue Protection King of Prussia, Pennsylvania 19406 380 Scotch Road Trenton, New Jersey 08628 BWR Licensing Manager P. B. Fiedler GPU Nuclear Vice President & Director 100 Interpace Parkway Oyster Creek Nuclear Generating Station Parsippany, New Jersey 07054 P. O. Box 388 Forked River, New Jersey 08731 Deputy Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor lacey Township 818 West Lacey Road Forked River, New Jersey 08731 D. G. Holland i Licensing Manager Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731 i
I i
ATTACHMENT 1 MEETING WITH GPU NUCLEAR CORPORATION (GolfN)
TO DISCUSS FIRE PPOTECTION June 23, 1986 NAME ORGANIZATION J. Donohew NRC/NRR/ DBL J. Stang NRC/NRR/ DBL G. Busch GPUN J. Yuen GPUN M. Sanford GPUN M. Coltmreary GPUN
- J. Siegel GPUN F. Collado GPUN :=
R. Podesfinski Burns and Roe, Inc.
R. Ashby GPUN A. Bais GPUN
--e - - ,,, - , , -
-a -
ATTACHMENT 2 POIPTS OF DISCUSSION
- 1. Conduit Internal Seals
- 2. Exemption Requests
- 3. Submittals e
- 4. Inspection i
l
4; . . . . _ ..m. .
i
, ATTACHMENT 3 :
. Y INSTRIJMENTATION I c- .
r'j REMOTE SHUTDOWN MONITORING INSTRUMENTATION i
LIMITING CONDITION FOR OPERATION 1
~
3.3.6.4 The remote shutdown monitoring instrumentation channels shown in Table 3.3.6.4-1 shall be OPERABLE with readouts displayed external to i i the control room. -
. t.- ,
-( APPLICABILITY: CONDITIONS 1, 2, and 3. ,
ACTION:
i
.. a. With the number of OPERABLE remote shutdown monitoring channels ,
s less than the requirements of Table 3.3.6.4-1, either restore the inoperable channel to OPERABLE status within 30 days, or be in at
. least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN
~
within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .
, [ b. The provisions of Specification 3.0.4 are not applicable.
1 6 s: ,
t-c SURVEILLANCE REQUIREMENTS N
! s4
- ,48 b'7.
- 4.3.6.4 Each of the above required remote shutdown monitoring instru-l c ?? mentation channels shall be demonstrated OPERABLE by performance of the i i, y;' CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies l ;;. shown in Table 4.3.6.4-1.
l- .r is st.
ST O
3.'
.' h
- . i GE-STS 3/4 3-52 April 1, 1978
! h .,
,- J
i,.. ,
- TABLE 3.3.6.4-1 REMOTE SHUTDOWN INSTRUMENTATION R
o, i
d MINIMUM READOUT CHANNELS FUNCTIONAL UNIT LOCATION OPERABLE
- 1. Reactor Vessel Pressure -
1
- 2. Reactor Vessel Water Level 1 1
- 3. Safety / Relief Valve Position ((2) valves) 1
- 4. Suppression Chamber Water Level 1 f 5. Suppression Chamber Water Temperature 1
- 6. Suppression Chamber Air Temperature 1 1 w l 'e 1 7. Drywell Pressure 1 i w j h 8. Drywell Temperature 1 i
9.
- 10. <
1 l 11.
- 12. s,
- .g
, 1 M
< so l
5 l ~
/ ,,4 .~ : > ,m:: , ;&y., ;.; ) '; k:,; . ',::M;i;..
.. < . .. . ., 2 c . - %. 2. : .. .:._ .,. . . .
>:. , .., y.
.:> . . 0;Ri?._%QD..f.Y:!l4%.?A*C~ME1:' '. ' ,
M '- ' ' ' ' * * - 1" :.wk * '
t i
TABLE 4.3.6.4-1 REMOTE SHUTDOWN INSTRUENTATION SURVEILLANCE REQUIREMENTS cn T
w d CHANNEL CHANNEL FUNCTIONAL UNIT CHECK CALIBRATION
- 1. Reactor Vessel Pressure M Q i
i 2. Reactor Vessel Water Level M Q
- 3. Safety / Relief Valve Position M NA 4
- 4. Suppression Chamber Water Level M R
- l '-
l
- 5. Suppression Chamber Water Temperature M R l w 6. Suppression Chamber Air Temperature M R
! 5 1 w 7. Primary Containment Pressure M Q
- 8. Drywell Temperature M R 9.
\ .
j 10.
- 11. ,
I j > 12.
N i
i a
m
\
l 4
5
.. V %
r- I
.* 7 )
Distribution for Meeting Sumary Dated: July 16, 1986 Facility: Oyster Creek Nuclear Generating Station
- q Docket J (50-21h ma. YUR Local PDR BWD1 Readina J. Zwolinski J. Donohew J. ,Stang
- y. Jamerson OGC(Forinfoonly)
E. Jordan B. Grimes ACRS (10)
R. Bernero G. Lainas G. Hulman '
M. Srinivasan OC File
- Copies sent to persons on facility service list i
l i
i
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- - . - - . . _ - - - . - _ . - . . - - . - - - - - - . _ - - - - - _ . _