|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20217K8511999-10-21021 October 1999
Summary of 990914 Meeting with Cp&L,National Marine Fisheries Service & North Carolina Wildlife Resources Commission at Brunswick Plant Re Biological Opinion Issued by NMFS & Need to Reinitiate Consultation with NMFS
ML20196D9751998-11-30030 November 1998
Summary of 981117 Meeting with Util in Rockville,Md Re Proposed Changes to TSs to Provide Longer Allowed Outage Times for Emergency & Balance of Plant Electrical Buses for Plant
ML20198L2631998-01-0505 January 1998
Summary of 971202 Meeting W/Util in Rockville,Md Re Changes Proposed by Licensee to TS for BSEP 1 & 2 Allowing Installation of Improvements to CREVS W/Both Plant Units Operating.List of Attendees & Slides Encl
ML20217C3021997-09-16016 September 1997
Summary of 970811 Meeting W/Util in Southport,Nc to Discuss Implementation of Endangered Species Act.List of Attendees Encl
ML20217H8221997-08-0808 August 1997
Summary of 970801 Meeting W/Util in Rockville,Md to Discuss Scheduling of NRC Reviews of Licensing Actions for Facility. List of Attendees & Activities Planned for Future Encl
ML20133E4371996-11-0505 November 1996
Trip Rept of 961016-17 Visit to Southport,Nc to Observe Testing Downcomer Strainer by Brunswick on 961017
ML20059A5881993-10-19019 October 1993
Summary of 930923 Meeting W/Util in Rockville,Md Re Status of Activities Associated W/Crack Indications Observed in Unit 1 Core Shroud.List of Attendees & Slides Presented Encl
ML20057E6271993-09-13013 September 1993
Summary of Operating Reactors Events Meeting 93-34 on 930908
ML20057B6321993-09-0909 September 1993
Summary of 930826 Meeting W/Util in Rockville,Md Re Status of Activities Involving Unit 1 Outage Status,Cracks in Core Shrouds & Spray Sparger & Metal Turnings Found in Fuel Assemblies.List of Meeting Attendees & Slides Encl
ML20127C3361993-01-11011 January 1993
Summary of 921217 Meeting W/Util Re Possible Concerns W/ Control Bldg Emergency Air Filtration Sys Chlorine Detection Logic.List of Attendees & Viewgraphs Encl
ML20127K9071992-08-10010 August 1992
Agenda for 920810 Meeting W/Util to Discuss Status of Nuclear Engineering Dept short-term actions,pre-startup/ post-startup Work Item & Classification & post-startup Backlog Disposition
ML20059B7331990-08-23023 August 1990
Summary of Operating Reactors Events Meeting 90-21 on 900822.Reactor Scram Statistics Encl
ML20248A6891989-09-13013 September 1989
Summary of 890818 Meeting W/Cp&L in Rockville,Md Re Unit 890617 Loss of Offsite Power Event.List of Attendees,Agenda & Presentation Encl
ML20246M8581989-09-0101 September 1989
Trip Rept of 890823-890825 Visit to Plants Re Active Licensing Actions Currently Under Review,Feedback from 890822 Meeting,Pending Type a Ilrt,Potential Amend to Double Allowable Containment Leak Rate & Hydrogen Injection Sys
ML20246P1361989-08-31031 August 1989
Summary of 890822 Meeting W/Util in Rockville,Md Re Tech Spec Change Mgt Program for Plant.List of Attendees & Viewgraphs Encl
ML20247H5611989-07-12012 July 1989
Summary of 890613 Meeting W/Util & Ncempa in Rockville,Md Re Future Plans for Plant Recirculation Sys Piping Replacement &/Or Repair.List of Attendees & Meeting Agenda Encl
ML20246F8691989-06-22022 June 1989
Summary of Operating Reactors Events Meeting 89-24 on 890621.On 890615,potential Unmonitored Primary Coolant Release Path to Environ Discovered at WPPSS-2.On 890617,loss of Offsite Power Occurred at Brunswick,Unit 2
ML20246L5121989-03-15015 March 1989
Summary of 890222 Meeting W/Licensee in Bethesda,Md to Discuss Characterization of & Proposed Actions For,Cracks Found in Unit 1 Recirculation Sys Safe Ends.Potential Implications for Unit 2 Also Addressed
ML20195H0271988-11-25025 November 1988
Summary of Operating Reactor Events Meeting 88-46 on 881122
ML20155E2041988-10-0606 October 1988
Summary of 881004 Meeting W/Util & SAIC in Rockville,Md Re Util Planned Submittal of 10CFR72 License Application for Dry Spent Fuel Storage
ML20154D3411988-09-12012 September 1988
Summary of 880714 Meeting W/Licensee in Rockville,Md Re Specifics of Recently Submitted Justification for Continued Operation Concerning Hpci/Rcic Valve Operability & Safety Sys Reliability.List of Attendees,Agenda & Viewgraphs Encl
ML20151Q8131988-08-0303 August 1988
Summary of Operating Reactors Events Meeting 88-031 on 880802.Viewgraphs & List of Attendees Encl
ML20151K6901988-07-18018 July 1988
Summary of Operating Reactors Events Meeting 88-28 on 880712.Viewgraphs & List of Attendees Encl
ML20148H6621988-01-15015 January 1988
Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl
ML20149F4741988-01-0707 January 1988
Summary of Operating Reactors Events Meeting 88-01 on 870105 Re Events That Occurred Since 871222.List of Attendees & Viewgraphs Encl
ML20236A5211987-10-20020 October 1987
Summary of 870917 Meeting W/Util in Bethesda,Md Re Generic Ltr 87-09, Sections 3.0 & 4.0 of STS on Applicability of Limiting Conditions for Operation & Surveillance Requirements. W/O List of Attendees
ML20235L4151987-09-28028 September 1987
Summary of 870721 & 22 Site Meetings W/Licensee & Eg&G Idaho,Inc Re Inservice Testing Program Submittals.Attendance List & Questions & Comments Re Pump & Valve Inservice Testing Program Encl
ML20237L1341987-08-12012 August 1987
Summary of 870804 Meeting W/Util in Region II Ofc to Discuss Recent Studies Performed on Reliability of Both RCIC & HPCI Sys
ML20237G3791987-08-11011 August 1987
Summary of Operating Reactors Events Meeting 87-23 on 870721.List of Attendees,Viewgraphs & Summary of Reactor Scrams & Significant Events Encl
ML20236J7051987-07-29029 July 1987
Summary of 870707 Operating Reactors Events Meeting 87-21 W/ Nrr,Aeod,Res & Regional Ofcs Re Events Occurring Since 870630 Meeting.List of Attendees,Discussion of Events & Summary of Reactor Scrams Also Encl
ML20206A9531987-04-0303 April 1987
Summary of 870318 Meeting W/Util Re Hydrogen Recombiner Capability.Util Agreed to Submit Tech Specs for Nitrogen Sys Pressure & Nitrogen Switchover Function by 870327.Generic Ltr 84-09 & NRC 861030 Safety Evaluation Also Discussed
ML20210T4031987-01-28028 January 1987
Summary of Operating Reactors Events Meeting 87-02 on 870112 of Events Which Occurred Since 870105.List of Attendees,Events Discussed & Summary of Events Encl
ML20212J3871987-01-21021 January 1987
Summary of 861103 Meeting W/Util,Westinghouse & O'Donnell & Assoc,Inc Re Possible Use of Pipe Locks to Repair IGSCC at Facility.List of Attendees & Slide Presentation Encl
ML20210T3641987-01-16016 January 1987
Summary of Operating Reactors Events Meeting 87-02 on 870112 Re Events Which Occurred Since 870105.List of Attendees,Events Discussed & Summary of Events Encl
ML20214P8971986-11-25025 November 1986
Summary of Operating Reactors Events Meeting 86-40 on 861117.List of Attendees,Events Discussed,Significant Events Data Sheet & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20214D4001986-11-18018 November 1986
Summary of 861015 Meeting W/Util Re Acceptance Criteria for Fire Barrier Penetrations.Util Described Configuration of Proposed Seals & Seal Matls Used.Further Review by NRC Required.List of Attendees Encl
ML20215G0561986-10-0707 October 1986
Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed
ML20206Q0821986-09-0202 September 1986
Summary of 860716 Meeting W/Util & GE Re Need for mid-cycle IGSCC Insp of Facility.List of Attendees Encl
ML20212N6801986-08-27027 August 1986
Summary of Operating Reactor Events Meeting 86-30 on 860825 to Discuss Events Which Occurred Since Last Meeting on 860818
ML20203P6801986-04-22022 April 1986
Summary of 860410 Meeting W/Project Managers & Utils in Bethesda,Md Re Automated Tracking,Integrated Schedules & Tech Specs.Attendees List,Viewgraphs & Meeting Agenda Encl
ML20141F4091986-04-10010 April 1986
Summary of Operating Reactors Events Meeting 86-10 W/Ofc Director,Div Directors & Representatives Re Events Since 860324.Viewgraphs & Supporting Documentation Encl
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20153H2281986-02-21021 February 1986
Summary of 860116 & 17 Meetings W/Util in Raleigh,Nc & at Site,Respectively,Re Status of Licensing Actions,Including Emergency Response Facilities & Cable Penetrations in Control Room Floor.Attendee Lists Encl
ML20153H2501986-02-18018 February 1986
Summary of 860214 Meeting W/Util Re Five Licensing Issues, Including Hydrogen Recombiner Capability,Spds,Integrated Schedule,Excess Flow Check Valve Relief & App J Exemption Request.Attendee Lists Encl
ML20205H8791986-01-22022 January 1986
Summary of Operating Reactor Events Meeting 86-02 on 860116 in Bethesda,Md Re Events Since 860106 Meeting.List of Attendees,List of Significant Elements of Events,Assignments & Status of Previous Assignments Encl
ML20138M9821985-12-17017 December 1985
Summary of 851204 & 05 Meetings W/Util in Raleigh,Nc & at Plant Site Re Status of Licensing Actions.List of Attendees & Licensing Issues Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20137U5031985-11-22022 November 1985
Summary of 851108 Meeting W/Util Re Util Response to Generic Ltr 84-09 on Hydrogen Recombiner Capability.List of Attendees Encl
ML20141E9501985-11-18018 November 1985
Summary of ACRS Subcommittee on Reactor Operations 851104 Meeting in Washington,Dc to Discuss Recent Plant Operating Experience.Fr Notice,Schedule of Discussion & Agenda Encl
ML20138P0081985-10-21021 October 1985
Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007
1999-10-21
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20217K8511999-10-21021 October 1999
Summary of 990914 Meeting with Cp&L,National Marine Fisheries Service & North Carolina Wildlife Resources Commission at Brunswick Plant Re Biological Opinion Issued by NMFS & Need to Reinitiate Consultation with NMFS
ML20196D9751998-11-30030 November 1998
Summary of 981117 Meeting with Util in Rockville,Md Re Proposed Changes to TSs to Provide Longer Allowed Outage Times for Emergency & Balance of Plant Electrical Buses for Plant
ML20198L2631998-01-0505 January 1998
Summary of 971202 Meeting W/Util in Rockville,Md Re Changes Proposed by Licensee to TS for BSEP 1 & 2 Allowing Installation of Improvements to CREVS W/Both Plant Units Operating.List of Attendees & Slides Encl
ML20217C3021997-09-16016 September 1997
Summary of 970811 Meeting W/Util in Southport,Nc to Discuss Implementation of Endangered Species Act.List of Attendees Encl
ML20217H8221997-08-0808 August 1997
Summary of 970801 Meeting W/Util in Rockville,Md to Discuss Scheduling of NRC Reviews of Licensing Actions for Facility. List of Attendees & Activities Planned for Future Encl
ML20059A5881993-10-19019 October 1993
Summary of 930923 Meeting W/Util in Rockville,Md Re Status of Activities Associated W/Crack Indications Observed in Unit 1 Core Shroud.List of Attendees & Slides Presented Encl
ML20057E6271993-09-13013 September 1993
Summary of Operating Reactors Events Meeting 93-34 on 930908
ML20057B6321993-09-0909 September 1993
Summary of 930826 Meeting W/Util in Rockville,Md Re Status of Activities Involving Unit 1 Outage Status,Cracks in Core Shrouds & Spray Sparger & Metal Turnings Found in Fuel Assemblies.List of Meeting Attendees & Slides Encl
ML20127C3361993-01-11011 January 1993
Summary of 921217 Meeting W/Util Re Possible Concerns W/ Control Bldg Emergency Air Filtration Sys Chlorine Detection Logic.List of Attendees & Viewgraphs Encl
ML20059B7331990-08-23023 August 1990
Summary of Operating Reactors Events Meeting 90-21 on 900822.Reactor Scram Statistics Encl
ML20248A6891989-09-13013 September 1989
Summary of 890818 Meeting W/Cp&L in Rockville,Md Re Unit 890617 Loss of Offsite Power Event.List of Attendees,Agenda & Presentation Encl
ML20246P1361989-08-31031 August 1989
Summary of 890822 Meeting W/Util in Rockville,Md Re Tech Spec Change Mgt Program for Plant.List of Attendees & Viewgraphs Encl
ML20247H5611989-07-12012 July 1989
Summary of 890613 Meeting W/Util & Ncempa in Rockville,Md Re Future Plans for Plant Recirculation Sys Piping Replacement &/Or Repair.List of Attendees & Meeting Agenda Encl
ML20246F8691989-06-22022 June 1989
Summary of Operating Reactors Events Meeting 89-24 on 890621.On 890615,potential Unmonitored Primary Coolant Release Path to Environ Discovered at WPPSS-2.On 890617,loss of Offsite Power Occurred at Brunswick,Unit 2
ML20246L5121989-03-15015 March 1989
Summary of 890222 Meeting W/Licensee in Bethesda,Md to Discuss Characterization of & Proposed Actions For,Cracks Found in Unit 1 Recirculation Sys Safe Ends.Potential Implications for Unit 2 Also Addressed
ML20195H0271988-11-25025 November 1988
Summary of Operating Reactor Events Meeting 88-46 on 881122
ML20155E2041988-10-0606 October 1988
Summary of 881004 Meeting W/Util & SAIC in Rockville,Md Re Util Planned Submittal of 10CFR72 License Application for Dry Spent Fuel Storage
ML20154D3411988-09-12012 September 1988
Summary of 880714 Meeting W/Licensee in Rockville,Md Re Specifics of Recently Submitted Justification for Continued Operation Concerning Hpci/Rcic Valve Operability & Safety Sys Reliability.List of Attendees,Agenda & Viewgraphs Encl
ML20151Q8131988-08-0303 August 1988
Summary of Operating Reactors Events Meeting 88-031 on 880802.Viewgraphs & List of Attendees Encl
ML20151K6901988-07-18018 July 1988
Summary of Operating Reactors Events Meeting 88-28 on 880712.Viewgraphs & List of Attendees Encl
ML20148H6621988-01-15015 January 1988
Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl
ML20149F4741988-01-0707 January 1988
Summary of Operating Reactors Events Meeting 88-01 on 870105 Re Events That Occurred Since 871222.List of Attendees & Viewgraphs Encl
ML20236A5211987-10-20020 October 1987
Summary of 870917 Meeting W/Util in Bethesda,Md Re Generic Ltr 87-09, Sections 3.0 & 4.0 of STS on Applicability of Limiting Conditions for Operation & Surveillance Requirements. W/O List of Attendees
ML20235L4151987-09-28028 September 1987
Summary of 870721 & 22 Site Meetings W/Licensee & Eg&G Idaho,Inc Re Inservice Testing Program Submittals.Attendance List & Questions & Comments Re Pump & Valve Inservice Testing Program Encl
ML20237L1341987-08-12012 August 1987
Summary of 870804 Meeting W/Util in Region II Ofc to Discuss Recent Studies Performed on Reliability of Both RCIC & HPCI Sys
ML20237G3791987-08-11011 August 1987
Summary of Operating Reactors Events Meeting 87-23 on 870721.List of Attendees,Viewgraphs & Summary of Reactor Scrams & Significant Events Encl
ML20236J7051987-07-29029 July 1987
Summary of 870707 Operating Reactors Events Meeting 87-21 W/ Nrr,Aeod,Res & Regional Ofcs Re Events Occurring Since 870630 Meeting.List of Attendees,Discussion of Events & Summary of Reactor Scrams Also Encl
ML20206A9531987-04-0303 April 1987
Summary of 870318 Meeting W/Util Re Hydrogen Recombiner Capability.Util Agreed to Submit Tech Specs for Nitrogen Sys Pressure & Nitrogen Switchover Function by 870327.Generic Ltr 84-09 & NRC 861030 Safety Evaluation Also Discussed
ML20210T4031987-01-28028 January 1987
Summary of Operating Reactors Events Meeting 87-02 on 870112 of Events Which Occurred Since 870105.List of Attendees,Events Discussed & Summary of Events Encl
ML20212J3871987-01-21021 January 1987
Summary of 861103 Meeting W/Util,Westinghouse & O'Donnell & Assoc,Inc Re Possible Use of Pipe Locks to Repair IGSCC at Facility.List of Attendees & Slide Presentation Encl
ML20210T3641987-01-16016 January 1987
Summary of Operating Reactors Events Meeting 87-02 on 870112 Re Events Which Occurred Since 870105.List of Attendees,Events Discussed & Summary of Events Encl
ML20214P8971986-11-25025 November 1986
Summary of Operating Reactors Events Meeting 86-40 on 861117.List of Attendees,Events Discussed,Significant Events Data Sheet & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20214D4001986-11-18018 November 1986
Summary of 861015 Meeting W/Util Re Acceptance Criteria for Fire Barrier Penetrations.Util Described Configuration of Proposed Seals & Seal Matls Used.Further Review by NRC Required.List of Attendees Encl
ML20215G0561986-10-0707 October 1986
Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed
ML20206Q0821986-09-0202 September 1986
Summary of 860716 Meeting W/Util & GE Re Need for mid-cycle IGSCC Insp of Facility.List of Attendees Encl
ML20212N6801986-08-27027 August 1986
Summary of Operating Reactor Events Meeting 86-30 on 860825 to Discuss Events Which Occurred Since Last Meeting on 860818
ML20203P6801986-04-22022 April 1986
Summary of 860410 Meeting W/Project Managers & Utils in Bethesda,Md Re Automated Tracking,Integrated Schedules & Tech Specs.Attendees List,Viewgraphs & Meeting Agenda Encl
ML20141F4091986-04-10010 April 1986
Summary of Operating Reactors Events Meeting 86-10 W/Ofc Director,Div Directors & Representatives Re Events Since 860324.Viewgraphs & Supporting Documentation Encl
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20153H2281986-02-21021 February 1986
Summary of 860116 & 17 Meetings W/Util in Raleigh,Nc & at Site,Respectively,Re Status of Licensing Actions,Including Emergency Response Facilities & Cable Penetrations in Control Room Floor.Attendee Lists Encl
ML20153H2501986-02-18018 February 1986
Summary of 860214 Meeting W/Util Re Five Licensing Issues, Including Hydrogen Recombiner Capability,Spds,Integrated Schedule,Excess Flow Check Valve Relief & App J Exemption Request.Attendee Lists Encl
ML20205H8791986-01-22022 January 1986
Summary of Operating Reactor Events Meeting 86-02 on 860116 in Bethesda,Md Re Events Since 860106 Meeting.List of Attendees,List of Significant Elements of Events,Assignments & Status of Previous Assignments Encl
ML20138M9821985-12-17017 December 1985
Summary of 851204 & 05 Meetings W/Util in Raleigh,Nc & at Plant Site Re Status of Licensing Actions.List of Attendees & Licensing Issues Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20137U5031985-11-22022 November 1985
Summary of 851108 Meeting W/Util Re Util Response to Generic Ltr 84-09 on Hydrogen Recombiner Capability.List of Attendees Encl
ML20141E9501985-11-18018 November 1985
Summary of ACRS Subcommittee on Reactor Operations 851104 Meeting in Washington,Dc to Discuss Recent Plant Operating Experience.Fr Notice,Schedule of Discussion & Agenda Encl
ML20138P0081985-10-21021 October 1985
Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007
ML20205C4111985-09-16016 September 1985
Summary of 850910 Meeting W/Util Re Util 841210 Request to Amend Dc Sys.Attendance List Encl
ML20135B0591985-09-0505 September 1985
Summary of 850827 Meeting W/Cp&L,Besu & Terera at Site Re 10CFR50,App R Exemptions.Request for Addl Info & Attendees List Encl
ML20127H3411985-06-19019 June 1985
Summary of Meeting W/Util to Discuss Extension of Time to Complete Environ Qualification.Attendance List Encl
1999-10-21
[Table view] |
Text
)
49* *% NC~ y Qd a k UNITED STATES ""~i l, f j NUCLEAR REGULATORY COMMISSION o WASHINGTON, D.C. 2005H001
%.....p tbwrber 30, S9B LICENSEE: Carolina Power & Light Company i FACILITY: Brunswick Steam Electric Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF NOVEMBER 17,1998, MEETING REGARDING PROPOSED CHANGES TO THE TECHNICAL SPECIFICATIONS TO PROVIDE LONGER ALLOWED OUTAGE TIMES FOR EMERGENCY AND BALAlICE OF PLANT ELECTRICAL BUSES - BRUNSWICK STEAM ELEC' Rn GNT, UNITS 1 AND 2 (TAC NOS. MA3738 AND MA3739)
On November 17,1998, members of the NRC staff met with Carolina Power & Light Company (CP&L or licensee) personnel at the NRC's One White Flint North headquarters in Rockville, Md. The meeting was open to the public. The purpose of the meeting was to discuss changes proposed by the licensee to the Technical Specifications (TS) for the Brunswick Steam Electric Piant Units 1 and 2 (BSEP 1 & 2) which would provide a longer allowed outage time (AOT) of 7 days for planned maintenance on emergency and balance of plant (BOP) electrical buses. The current AOT for these buses is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
The changes were first submitted to the NRC on November 1,1996, as part of CP&L's application for conversion to improved Standard Technical Specifications (ITS). The NRC later determined that it required more information concerning the impact of the AOT extension on plant risk. Thus, at the NRC's request, on September 14,1998, CP&L provided supplemental /
information in support of the AOT extension. /
d The licensee's basis for its request is that the additional time is needed to perform vendor- ,
recommended maintenance on the buses and associated components. The AOT extension .
l would only apply when one unit is operating and one unit is shut down and the planned f ;
maintenance is to be conducted on the shutdown unit's electrical system. However, because #, y /!
there is some cross sharing of electricalloads between units, a limited number of components /
on the operating unit wou d be affected by such maintenance.
l During the meeting the 'icensee presented further information on the proposed changes and the plant electrical system design. This information will assist the NRC staff in reaching its conclusion on the impact of the proposal on plant risk. In follow-up to the meetira the staff will issue a request for additional information (RAI). The staff asked that the licensee, as part of its response to the forthcoming RAI, determine if the planned maintenance can be l
9812030003 981130
! PDR ADOCK 05000324 F PDR
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- A e
fbveter 30,1998 i
- v. 2
. accomplished safely in a shorter period of time. If so, the staff asked that the licensee consider reducing the length of the requested AOT. <
A list of meeting attendees as well as the handout provided by the licensee are enclosed. :
l i
Original signed by: 1 David C. Trimble, Project Manager Project Directorate ll-3 !
,- Division of Reactor Projects -I/ll Office of Nuclear Reactor Regulation
Enclosures:
(1) Attendance List i i
. (2) Licensee Handout Docket Nos. 50-325 and 50-324 ;
cc w/encis: See next page EBRD COPY ,
WAAllte@
DUBLIC PDil-1 RF D. Trimble OGC ACRS 4
E-MAIL S. Collins /F. Miraglia B. Boger !
J. Zwolinski ;
T. Martin (SLM3)
D. O'Neal '
A. El-Bassioni M. Wohl P. Kang ;
J. Lazevnick l F.Ashe I M. Tschiltz l
- J. Johnson, Ril FILENAMf G:\BRUNSWIC\ BRA 3738.MTS OFFICE PM:PDll-3 LA:PDil-2 D:PDil-3 NAME DT ble EDu ton FHebdo
. DATE 11/'I98 11 8 8 11/f?98 COPY ((&s/No (Te)No (ho
" OFFICIAL RECORD COPY
2 i
accomplished safely in a shorter period of time. If so, the staff asked that the licensee consider reducing the length of the requested AOT.
A list of meeting attendees as well as the handout provided by the licensee are enclosed.
i
&?$
( David C. Trimble, Project Manager Project Directorate ll-3 Division of Reactor Projects -1/11 Office of Nuclear Reactor Regulation l
Enclosures:
(1) Attendance List (2) Licensee Handout Docket Nos. 59 32G and 50-324 l
cc w/ enc!s: See next page l
l 1
l l
i
?
L .
~
3 . Noveter 30,1998 2
accomplished safely in a shorter period of time. If so, the staff asked that the licensee consider reducing the length of the requested AOT.
I A list of meeting attendees as well as the handout provided by the licensee are enclosed.
J Original signed by: -
l I David C. Trimble, Project Manager Project Directorate 11-3 Division of Reactor Projects - 1/il Office of Nuclear Reactor Regulation
Enclosures:
'(1) Attendance List -
l (2) Licensee Handout l Docket Nos. 50-325 and 50-324 1
l- cc w/encis: See next page HARD COPY l I
Docket File -
PUBLIC l PDll-1 RF l- .D. Tnmble
! OGC ACRS i
j_ ' E-MAIL
- S. Collins /F. Miraglia l B.Boger J. Zwolinski T. Martin (SLM3)
D. O'Neal A. El-Bassioni l M. Wohl P. Kang J. Lazevnick F.Ashe M. Tschiltz J, Johnson, Ril l FILENAME- G:\BRUNSWIC\ BRA 3738.MTS OFFICE PM:PDil-3 LA:PDll-2 D:PDll-3 NAME DT 1ble EDu gton FHebdo DATE 11/498 11 8 8 11/f798 COPY (fas/No MNo tho l
~ OFFICIAL RECORD COPY l
> 1 l
l
. - . . . _ _ l
Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2
.cc:
Mr. William D. Johnson Ms. Karen E. Long .
Vice President and Senior Counsel .
Assistant Attorney General Carolina Power & Light Company State of North Carolina Post Office Box 1551 Post Office Box 629 Raleigh, North Carolina 27602 Raleigh, North Carolina 27602 Mr. Jerry W. Jones, Chairman Mr. Robert P. Gruber Brunswick County Board of Commissioners Executive Director Post Office Box 249 Public Staff- NCUC Bolivia, North Carolina 28422 Post Office Box 29520 Raleigh, North Carolina 27626-0520 Resident inspector U.S. Nuclear Regulatory Commission Director 8470 River Road Site Operations Southport, North Carolina 28461 Brunswick Steam Electric Plant Post Office Box 10429 Regional Administrator, Region il Southport, North Carolina 28461 U.S. Nuclear Regulatory Commission Atlanta Federal Center Mr. William H. Crowe, Mayor 61 Forsyth Street, SW, Suite 23T85 City of Southport Atlanta, Georgia 30303 201 East Moore Street Southport, North Carolina 28461 Mr. Mel Fry, Director Division of Radiation Protection Mr. Dan E. Summers N.C. Department of Environment Emergency Management Coordinator and Natural Resources New Hanover County Department of 3825 Barrett Dr. Emergency Management Raleigh, North Carolina 27609-7721 Post Office Box 1525 Wilmington, North Carolina 28402 Mr. J. J. Lyash (
Plant Manager Ms. D. B. Alexander Carolina Power & Light Company Manager Brunswick Steam Electric Plant Performance Evaluation and Post Office Box 10429 Regulatory Affairs CPB 9 Southport, North Carolina 28461 Carolina Power & Light Company Post Office Box 1551 Public Service Commission Raleigh, North Carolina 27602-1551 State of South Carolina Post Office Drawer 11649 Mr. K. R. Jury Columbia, South Carolina 29211 Manager- Regulatory Affairs .
Carolina Power & Light Company Mr. J. S. Keenan, Vice President Post Office Box 10429 Brunswick Steam Electric Plant Southport, NC 28461-0.t29 Carolina Power & Light Company Post Office Box 10429 l
Southport, North Carolina 28461
l 1
\
MEETING ATTENDANCE LIST I
Licensee: Carolina Power & Light Company Plant (s): Brunswick 1 and 2
Subject:
Proposed Changes to the Technical Specifications to Provide Longer Allowed Outage Times for Emergency and Balance of Plant Electrical Buses l l Date: November 17,1998 I Location: Room O-12802, One White Flint North Building,11555 Rockville Pike, Rockville, l Md.
l Time: 10:00 a.m.
l NAME NRC STAFF F.Ashe l
A. El-Bassioni l
J. Larevnick '
D. O'Neal M. Wohl D. Trimble CP&L G. Atkinson G. Ellis (contractor - Excel Services)
R. Delong D. LaBelle W. Dorman G. Miller M. Turkal i
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Enclosure 1
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1 l-l Discussion Topics l
ePurpose Of Request i eElectrical Distribution System Overview
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eTechnical Specification Overview l
4 eRisk insights
!, oConclusion 4
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O Purpose Of Request l e Modify Technical Specifications (TS) 3.8.1 l
and 3.8.7 To:
+ Provide Sufficient Time For Bus Maintenance l + Avoid incurring A Dual Unit Outage l o7 Day AOT Established Based On:
! + Most Restrictive AOT On Operating Unit l + Acceptable Risk Evaluation l mBenefit Of Performing Maintenance l mAvoid Unnecessary Transient On Operating Unit
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Electrical Distribution System
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- "" BRUNSWICK NUCLEAR PLANT 1 -
ELECTRICAL DISTRIBUTION SYSTEM i LEGEND:
summusus ALTERNATE OFF-SITE POWER SOURCE (BOTH UNITS $40seLAR)
- PftEFERRED OFF-SITE POWER SOURCE (80 Tis UNITS Sles!LAR) 4 N asummmus CLASS IE SYSTEtt t
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Electrical Distribution System System Configuration - E-Bus Loads E1 E2 E3 E4 Unit 1 ECCS CS Div 1 CS1A CS Div 11 CS18 LPCI Div i RHR1C RHR 1 A & Valves LPCI Div 11 RHR1D RHR 1B & Valves Unit 2 ECCS CS Div I CS 2A CS Div 11 CS 2B LPCI Div i RHR 2C & Valves RHR 2A LPCI Div ll RHR 2D & Valves RHR28 Service Water Nuc SW 1A 18 2A 2B Unit 1 Con SW 1B 1C 1A Unit 2 Con SW 2C 2A 2B
. 5 '
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- Technical Specification Overview Comparison i
Operability Operability AOT AOT Requirements Requirements (Current) (Proposed)
(Current) (Proposed)
TS 3.8.1 4 Offsite Circuits (2 per 4 Offsite Circuits (2 per 2 Offisite Circuits and 2 Offinite Circuits and unit) unit) EDG Inop EDGloop Enter LCO 3.0.3 Enter LCO 3.0.3 4 EDGs 4 EDGs (Unpianned)
I . 2 Offisite Circuits and EDG Inop (3/D Unit) 7 Days to Restore -
12 Hrs to Mode 3 (Planned)
TS 3.8.7 2 AC & 2 DC Divisions 2 AC & 2 DC Divisions 1 AC Divisioninop 1 AC Division Inop of Electrical Power of Electrical Power 8 Hrs to Restore 8 Hrs to Restore 12 Hrs to Mode 3 12 Hrs to Mode 3 (Unplanned) 1 AC Division Inop (S/D
- Unit) 7 Days to Restore 12 Hrs to Mode 3
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1 (Planned) 4
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Technical Specification Overview Examples eProposed T5 And Bases Changes oApplication Of Required Action B.1 ePractical Examples sessa 7
SFDP .
1 TS 5.5.11.b.1 Example 7 Day AOT(Proposed) .
Emergency Bus E4 TS 3.8.7 Inoperable u 7 Day AOT 7 Day AOT 1 A Core Spray Pump TS 3.5.1 IB LPCI Loop Inoperable Loss Of Safety Function u
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Enter LCO 3.0.3 mua
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SFDP TS 5.5.11.b.2 Example 7 Day AOT 125 VDC Control Power To Div II ESS Logic TS 3.8.7 Cabinet Inoperable v
24 Hrs. To Trip 1B LPCI Loop Logic
- Channels
,7 Day AOT 7 Day AOT 1 A Core Spray Pump IB LPCI Loop Inoperable TS 3.5.1 Loss Of Safety Function EMJSE.
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Enter LCO 3.0.3
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3 SFDP l TS 5.5.11.b.2 Example 7 Day AOT l 125 VDC Control Power To Div II ESS Logic TS 3.8.7 Cabinet Inoperable 4
24 Hrs. To Trip u Channels 24 Hrs. To Trip 1 A Core Spray Loop TS 3.3.5.1 1B LPCI Loop Logic Channels Logic Inoperable
, , 7 Day AOT , ,7 Day AOT
- IB LPCI Loop 1 A Core Spray Pump i
1 Loss Of Safety Function C(w{&L t
Enter LCO 3.0.3
. 10 5 .
1 Risk-informed Overview l Risk Management Process eBrunswick Risk Management Process l Complies With a(3) Of Maintenance Rule l o Additional Controls in TS 5.5.11, SFDP l + Redundant Safety Functions l eBrunswick Procedure AP-25:
l o Prevents Removal Of Additional High Risk j Components I + Contains Guidance For Actions if Unforeseen l Configurations Occur
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__[.___i,_____.___.-_.__..___________.___ _ _ _ _ _ _ _ _
1 l Risk-Informed Overview j Risk Management Process l eintegrated Assessment Of Plant l Configuration l o Based On Level 1 Internal Events PSA l + PSA Model includes Buses, Breakers,
- Offsite And Onsite AC Sources That .
Represent The Proposed Configuration
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> PSA Model 1s Updated Periodically
+ Equipment Performance is Monitored By Maintenance. Rule Program
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. - - . _ _ . _ _ _ _ . _ . . _ , , _ _ _ . . . . _ _ _ . _ . . _ . . _ . _ _ . . _ . _ . . . _ . _ _ _ . _ _ _ . _ . _ _ _ _ _ . _ . _ . ~ . _ , _ , . _ _ _ _ . . .
Risk-informed Overview impact of TS Change elmpact On The Operating Unit:
+1 RHR Pump
+1 RHR Service Water Pump (Same Division)
+ AC Power To 1 Loop Of LPCI Valves
+ 1 Conventional Service Water Pump mE1 Or E4 Outages Only e Adequate -Redundancy Exists On Remaining Equipment seet.
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Risk-informed Overview o '"
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Impact of TS Change "
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oOperating Unit i o Base Case CDF 9.2E-6/ year
+ Analyzed Case CDF 9.7E-6/ year
- sincremental Change 4.6E-7/ year ed'L'Q.
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! + Actual CDF Change Would Be Less l
mActual Out Of Service Time Much Less i
mNo Credit Taken c or improved Reliability Of E-Bus l (f!OR!!_
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l Risk-informed Overview
! Impact of TS Change i
MOST IMPORTANT SYSTEMS IMPACTIF ALSO CONTROLS TO i
REMOVED FROM PRECLUDE
- (E-BUS OUT OF SERVICE) SERVICE UNAVAILABILITY Core Spray TS LCO 3.0.3 YES 1
1 Conventional Service Water 7 day AOT YES Diesel Generator TS LCO 3.0.3 YES
! High Pressure Coolant injection 72 hr. AOT YES Reactor Core Isolation Cooling 14 day AOT YES aaea wum 15
! Risk-informed Overview l Impact of TS Change l
eLarge Early Release Not Significant .
l + Affected Systems Have Minimal impact On i Containment Performance l <> Some Isolation Valves Will Be in isolated l Position
! OExternal Events impact Not Significant
- o Proposed Configuration Does Not Create
! Additional Challenges Or increased initiating l Event Potential sPM -
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9 Risk-informed Overview impact of TS Change o TSs Allow This Configuration Indefinitely
+ Risk is Managed By Defense-in-Depth Philosophy (NUMARC 91-04) mConcurrent Outage Activities Are Limited o E-Bus Work is Performed Late in The Outage mLower Decay Heat oAdequate Redundancy Exists To Maintain Required Defense-in-Depth ses4 17
! Risk-informed Overview Conclusion - - . _ - _- - ____ --
l eProposed Change Has An Acceptably l Low Impact On Plant Risk ;
l cAdequate Plant Controls Are in Place To l Reduce The Likelihood Of Risk-Significant Configurations .
l sExisting Programs And Procedures Meet j The Recommendation For A Risk-
- informed Plant Configuration Control l Program
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