|
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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
F I
/s sM8% o UNITED STATES hcY-t
[ig g
'k NUCLEAR REGULATORY COMMISSION Ebl l
l
,. , ; WASWNQTON, D. C. 20555
% Q,, January 26, 1993 i
Docket No. 50-219 LICENSEE: GPU Nuclear Corporation FACILITY: Oyster Creek Nuclear Generating Station
SUBJECT:
SUMMARY
OF MEETING REGARDING REACTOR BUILDING ACCESS CONTROL MODIFICATIONS AND OPERATIONAL SAFEGUARDS RESPONSE EVALUATION On Tuesday, January 12, 1993, a meeting was held at One White Flint North, Rockville, Maryland with GPU Nuclear Corporation (GPUN/the licensee) to discuss the reactor building access control modification and operational safeguards response evaluation (OSRE). Enclosure 1 is the list of individuals participating in the discussion. Enclosure 2 is the licensee's agenda.
to discuss their The plans meeting to cancel awas requested reactor by GPU building access control Nuclear modificatCorporation (GPUN) ion to conduct an Operational Safeguards Response Evaluation at Oyster Creek. The modification had originally been planned to address issues raised by the NRC concerning the adequacy of security measures to protect certain systems and components located in the reactor building needed for safe plant shutdown.
Based on higher priority work, GPUN had extended the schedule for the modification several times. In a letter dated September 14, 1992, GPUN informed the NRC of their decision to cancel the modification and the bases for the decision. By letter dated November 18, 1992, the NRC informed GPUN that staff planned to conduct an OSRE at Oyster Creek which would provide information necessary for the staff to complete their evaluation of the proposal for cancelling the modification.
At the meeting the licensee described and expanded on their rationale for cancelling the modification. With respect to the insider threat, the licensee presented their position that measures other than reactor building access control modification provided sufficient protection. Staff did take issue with this rationale. With respect to the external threat, the licensee indicated that the barriers proposed in the modification would provide little protective benefit and that contingency procedures were in place to enhance '
protection of equipment in the reactor building. Staff stated _that the purpose of the OSRE would be to confirm the adequacy of the, contingency procedures and that the issue could be closed subject to findings of the OSRE.
Regarding an OSRE for Oyster Creek, the licensee agreed that the evaluation would be beneficial but proposed that it not be scheduled until after identified improvements, including measures taken to strengthen the (
9301280240 930126, DR ADOCK 0500 9 n
['
f
s GPU Nuclear Corporation 0)erations/ Security interface, were made. Based on-this, GPUN proposed that t1e OSRE be scheduled for the first quarter of 1994. Staff stated that-closure of the issue did not need to be delayed pending program refinements and proposed the OSRE be scheduled no later than the summer of 1993.
Original signed by Alexander W. Dromerick, Sr. Project Manager Project Directorate 1-4 Division of Reactor Projects - 1/11-Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ enclosures:
See next page Distribution:-
Docket file NRC & t.ocal PDRs PD I-4 Memo TMurley/FMiraglia JPartlow SVarga JCalvo ADromerick - --
- SNorris OGC EJordan RHernan BDube
- PHcKee BManili EButcher RKeimig ACRS (10)
VMcCree, EDO
- JFRogge, RI omcc LA:PDI-4 PM: PDI-4d Dht-4 WE SNOW !hhMerNk:cn JStb DAIE f-/5/93- / h d93 l - /d/93 / - /- / ' /-
Off101AL RECORD COPY Document Name: G:\DROMERIC\0CMTG l
O Mr. John J. Barton Oyster Creek Nuclear GPU Nuclear Corporation Generating Station cc:
Ernest L. Blake, Jr., Esquire Resident inspector Shaw, Pittman, Potts & Trowbridge c/o -U.S. Nuclear Regulatory Commission 2300 N Street, NW. Post Office Box 445 Washington, DC 20037 Forked River, New Jersey 08731 Regional Administrator, Region 1 Kent Tosch, Chief U.S. Nuclear Regulatory Commission New Jersey Department of 475 Allendale Road Environmental Protection King of Prussia Pennsylvania 19406 Bureau of Nuclear Engineering
- CN 415 BWR Licensing Manager Trenton, New Jersey 08625 GPU Nuclear Corporation 1 Upper Pond Road Parsippany, New Jersey 07054 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.
Post Office Box 388 Forked River, New Jersey 08731
e
Enclosure 1 OYSTER CREEK Nt) CLEAR GENERATING STATION-DOCKET NO. 50-219 MEETING - JANUARY 12. 1993 AIIINDANCE LIST HAE ORGANIZATION Ron Hernan NRC/NRR John Fornicola GPU Nuclear James Knubel - GPU Nuclear ;
Rich Enkeboll NUMARC Bob Whitesel NUMARC-Ken Pastor GPU Nuclear ,
Bob Dube -
NRC/NRR Alex Dromerick - - NRC/NRR Phil McKee NRC/NRR Barry Manili NRC/NRR-Ed Butcher NRC/DRSS Phil Scallon GPU Nuclear Larry J, Defibaugh GPU Nuclear Richard T. Ewart GPU Nuclear
- Mike Heller GPU Nuclear Mike Lair GPU Nuclear-Mike Laggart GPU Nuclear-John Stolz NRC/NRR RKeimig NRC/ Region I i.-
e i
I
- + y
d'WC/osudd" A GPU NUCLEAll PilESENTATION nn ItEACTOlt ilUILDING ACCESS CONTitOL MODIFICATION '
and OPEllATIONAL SAFEGUAllDS ItESPONSE EVALUATION JANUARY 12,1993 ItOCKVILLE, MAllYLAND
i 1
AGENDA- }
I. Introduction / Objectives M. Laggart II. Background M. Laggart 4
III. Reactor Building Access Control Mod K. Pastor A. Integrated Schedule M. Lair B. Industry Initiatives J. Knubel IV. Operational Safeguards Response Evaluation P. Scallon V. Conclusion M. Laggart ,
W 1
l
s OB.lFCTIVE 9 Reactor Building Access Control Modification 4 Operational Safeguards Response Evaluation (OSRE)
I 2
t 3
I I
BACKGROUND g T t
+
-7/88 Regulatory Effectiveness Review.
Decision to modify Rx Bldg access controls -
2/89 Modification added to Integrated Schedule- ;
6/89
-6/92 Integrated Schedule update letter .
3 7/92 Inspection 92-17, GPUN/NRC meeting
.i 9/92 GPUN letter re: cancellation of modification -
11/92 NRC letter re: OSRE 12/92 Integrated Schedule update letter P
t a
?
r 3-1
,4,- , - , - ,',4 --- ,-.. & , y , , . . , , - . . . -c, - , , 1,, , , ,,- ,
m e - -
. u-+' >
REACTOR 11UILDING ACCESS CONTROL MODIFICATION TIIE ESTIMATED COST FOR THE MODIFICATION IIAS INCREASED SINCE IT WAS INITIALLY .
PROPOSED.
i
. 1989 ESTIMATE (CONCEPTUAL):
$570,000
. 1992 ESTIMATE:
$859,000 4
- , , - .e a..+-, ,.m-, , , , - - , ., -e - ----- ~ . - .. -, . . -., ..
e LOCKED AND ALARMED DOORS IIAVE LITTLE VALUE.
. The RER Program gave little credit for the protective benefit of access control barriers.
"The NRC RER drills have shown that vital area doors are of minimal value as an obstacle".
Chain-Reaction, October 1992
. The current OSRE Program continues that practice.
Peach Bottom OSRE: Seventeen (17) seconds to penetrate the perimeter fence and breach the access control barrier.
Similar experience with other plant's evaluations:
. San Onofre 18 Seconds
. Duane Arnold 30 Seconds
. Maine Yankee - 45 Seconds 5
I IIIGH TRAFFIC LEVELS IN TIIE REACTOR BUILDING '
COULD DIVERT SECURITY RESOURCES FROM A'ITENTION TO TIIE BALANCE OF THE SECURITY SYSTEMS.
. It is estimated that in the order of 1100 individuals would have access to the Reactor Building during a normal operating cycle.
. The number doubles (to about 2200) during an outage.
6
C ADDITIONAL REACTOR BUILDING ACCESS CONTROL BARRIERS WOULD DECREASE OPERATIONAL EFFECTIVENESS.
E
. The Coinmissioners are looldng for linproved operational effectiveness. In their response to the Stati regarding recommendations of SECY-92 272, they state: .
"The changes proposed by the Staff provide very little in the way of an expected increase in operational safety or increase in operational clicctiveness".
. Additional Reactor 11ullding access controls would decrease operational clicctiveness.
7
,+. - -
, .- - - .,-%-- .ev-- e
TIIE ALTERNATE PROTECTION STRATEGY ELIMINATES TIIE NEED FOR INTERNAL ACCESS CONTROL 11ARRIERS.
. Insider threat reduced by new regulations:
> 10 CFR 73.57 Criminal llistory Checks
> 10 CFR 26 - Fitness for Duty Program
> 10 CFR 73.56 - Access Authorization Program o Psychological Evaluations o Ilackground Investigations a Continual llehavioral Observation
. Commissioner's response to the Staff regarding SECY-92 272:
"I'he stali. . .should work with NUMARC to fully understand the goals of their proposed Alternate Protection Strategy as a stepping off point for exploring alternatives'.
"The staff should consider the implementation of fitness for duty and supervisor observation for aberrant behavior in a comprehensive review of the insider threat. This includes a review of the usefulness of vital areas within the plant boundary".
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9 OYSTER CREEK CONTINGENCY PROCEDURES ENIIANCE PROTECTION OF EQUIPMENT IN TIIE .
REACTOR I3UILDING.
. Response force reacts immediately to pre determined locations, which include the Reactor Building.
. Response locations determined in conjunction with Plant Operations based on the importance of the equipment to safe shutdown. .
. Security force drills monthly provide training in rapid response to these critical locations.
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f AN ADDITIONAL DEGREE OF PROTECTION IS PROVIDED BY PERIODIC VERIFICATION OF SAFETY SYSTEM EQUIPMENT LINEUP.
. Station Procedure 680.4.007, ' Safety Related Equipment Verification" periodically confirms that safety systems are properly aligned to perform their safety function.
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APPROPRIATENESS OF AN OSRE TO EVALUATE ,
ACCESS CONTROL BARRIERS.
- An Operational Safeguards Response Evaluation (OSRE) evaluates the response capability of the Site Security Force to an external design basis threat i .
. Previous OSRE exercise scenarios breach vital area barriers within seconds from the start of protected area intruslon by the external adversary.
. An OSRE will provide no significant information with which the NRC can evaluate the value or effectiveness of access control barriers.
. The review of GPU Nuclear's proposal to cancel plans to modify Reactor Ilullding access control barriers is separate from evaluation of the response capability of the Oyster Creek security force to an external threat.
. The Oyster Creek OSRE should not be accelerated because of the Reactor Iluilding access control barrier issue.
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e PROJECI' PRIORITY i
GENERAL PRIORITIZATION HASIS
. License Amendment to negotiate the appropriate balance and -
prioritization of proposed projects
. Consider costs and benefits Nuclear safety Capacity Factor System Reliability ,
Personnel Safety i
Person Rem General Working Conditions
. Management review of projects and resource targets.
- Resources defined by Life Cycle Forecast and GPU Management - .
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GPUN FOCUS _
- Material Condition of plant equipment
. Reduce operator challenges >
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-. Dose reduction
- Improvements in availability -
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INITIAL ACCESS CONTROL PRIORITIZATION 1989 - Access Control Projects initiated Control Room Access planned for 1990 (Cycle 12).
Reactor Unilding Access planned for 1993 (Cycle 14) >
1990 - Projects combined and planned for 1993 (Cycle 14)
I 1992 - Estimate increased and project split into 2 parts
- Control Room Access Control planned for 1994 (Cycle 14)
- Reactor Building Access Control planned for 1997 (Cycle 16) 14 e y 9' -599 "+ e -v9 ry '--* --wwreww g ysmy-w- y rios vyMy- y ymyf yr't*ftw (v**N D'W WWf*+d-'4L-J'- f*-E-wwWWF3--ev h -M?t?M- nr 9
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MAlfHt PRO.1ECU DEFERRED 4CARCEIED
. Replace Upper Turbine Building Roof
. Drywell Exposure Reduction Modifications
. Reactor Building Roof Frame
. T.B.C.C.W. IIcat Exchanger Replacement
. Recirculation Flow Scram Electronics Replacement
. Low Pressure Turbine 'C' Blade Replacement
. Reactor Overfill Protection
. Generator Protection Upgrade
. Recirculation Pump Motor RTD Circuit Upgrade 15 4
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CURRENT PRIORITIZATION
- Control Room Access Control planned for 1994 in cycle 14
. Reactor Building Access Control proposed cancellation ,
REASON FOR CURRENT PRIORITIZATION t-
. Reactor Building Access'Controlis a high cost and perceived low benefit project
- NUMARC Initiative would limit extent of plant vitalization ,
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- 4 blUMARC INITIATIVE IIISTORY
. NUMARC Security Working Group was formed mid 1990, with its first meeting August 7,1990. 1
. On June 24,1992 - NUMARC submitted " Protective Measures Requirements Re evaluation" to the NRC Staff,
. August 4,1992 - NRC Staff proposal for Security changes was forwarded to the Commissioners (Secy-92-272) with the NUMARC
" Alternate Protection Strategy" (APS), as an enclosure.
- October 2,1992 NUMARC briefed Commissioner Remick and other representatives of the commissioners staff on the NUMARC "APS" and the industry's view on Secy-92 272.
. November 5,1992 - Staff Requirements Memorandum (SRM) issued, directs the staff to work with NUMARC to understand "APS".
. December 22,1992 - N'UMARC Working and NRC Staff Members met for information exchange.
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NUMARC POSITION
. The basis for the "APS" Is 10 CFR_73.5(a)
'The Commissioner may authorize'an applicant or licensee to provide measures for protection against radiological sabotage other than:-
those required by this section...'-
. The "APS" provides a level of assurance that obviates the need for the; vol area requirements'specified in-10 CFR 73.55 paragraphs (b).
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Q DERE READINESS _/1993 OYSTER CREEKACHEDULE
- Response Improvements Underway
. July 1988 - RER conducted at Oyster Creek identified weaknesses in armed response to security contingencies.
. Tactical Response Team Deployment Plan and Exercise Control Plan developed and implemented. Joint Training / Security monthly drills initiated.
. Use of plant referenced simulator for security drills will strengthen Operations / Security interface.
. 14R Outage - November 1992 through February 1993 Plant Referenced Simulator / Operator Availability
. Ready for Training - March 1993
. Emergency Operating Procedure Audit - May/ June / July 1993 l
. Operator Training - March 1993 through August 1993 l
. INPO Evaluation & Assessment - June 1993 l
. Operator Evaluations - August / September 1993
- Available for security drills ~ Ist quarter 1994 19
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CONCLUSION-O The Reactor Building Access Control Modification should be separate and-distinct from the OSRE. !
O The Reactor. Building Access Control Modification is not justified per a cost -
benefit perspective.
e 'It would be inappropriate to consider adding an additional vital area at-Oyster Creek given the' industry position on "APS" and ~the consideration-being given to the. industry positio'n by the NRC Commissioners and Staff.1 9 An OSRE would benefit Oyster Creek after identified improvements are; addressed.
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