|
|---|
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
o Docket Nos. 50-325/324 LICENSEE: Carolina Power and Light Company (CP&L)
FACILITY: Brunswick Steam Electric Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF MEETING HELD ON NOVEMBER 3,1986: PIPE REPAIR FOR INTERGRAhULAR STRESS CORROSION CRACKING (IGSCC)
Background
Discussions were held with CP&L and its contractors on November 3, 1986 regarding the possible use of pipe locks to repair welded joints at Brunswick 1 and 2. The list of attendees is provided in Enclosure 1.
Brunswick I will be shutdown for a maintenance and refueling outage on February 13, 1987. During that outage, inspections will be performed to determine the existence of intergranular stress corrosion cracking (IGSCC) in Inconel weld butter in reactor coolant system pipe welds. Brunswick 2 is currently operating in Fuel Cycle 7 with unrepaired cracks in two nozzel-to-safe-end welds. Approval for continued operation for the duration of Fuel Cycle 7 was granted by the NRC in a letter dated October 5, 1986. Brunswick 2 reactor coolant system pipe welds will be re-examined at the end of Fuel Cycle 7.
CP&L is considering the use of pipe locks as a possible method of pipe repair in the event that unacceptable crack indicaticns are identified in Inconel butter joints in the Unit I and 2 IGSCC inspections. Consequently, CP&L requested that a meeting be held with the NRC staff to identify NRC concerns with the use of pipe locks and the information that would be required in a submittal to obtain NRC approval for the use of pipe locks.
Meeting Summary Some background information on the design and use of pipe locks at other nuclear power facilities was presented by Mr. William O'Donnel of 0'Donnell &
Associates, Inc. (0DAI), a CP&L contractor. ODAI is the developer of pipe locks and patent-holder for the design. CP&L stated the position that pipe locks are superior to weld overlay repair and are thus an acceptable long-term repair method for reactor coolant piping susceptible to IGSCC. One benefit accruir.g from the use of pipe locks relative to weld overlays is that pipe lock installation does not preclude future inspection of the original weld.
Copies of the slides used in the CP&L presentation are provided as Enclosure 2.
g2g@[ [3 p P
~ - _ ..
The use of pipe locks at other nuclear power facilities has-been done on a trial basis in areas where NRC approval was not required. That is, pipe locks have been used in conjunction with weld overlay where the weld overlay was the primary method of pipe repair and satisfied NRC criteria. NRC approval has not been granted for the use of pipe locks as the sole method of pipe repair at any facility. The current position of the NRC staff is that pipe locks are not an ASME-prescribed repair method for pipes but could be approved as an acceptable alternate to weld overlay repair if adequate justification is provided.
CP&L committed to provide justification for a representative use of pipe locks at the Brunswick facility prior to the start of the Unit I refueling outage, i.e. , before February 13, 1987. Additional information on the specific installations used at Brunswick 1 (if any) will be provided along with a request for approval to restart prior to startup from the outage in June 1987.
a
%w 'c.'c,;:1,!.c Ernest D. Sylvester, Project Manager BWR Project Directorate #2 Division of BWR Licensing
Enclosures:
As stated cc: See next page DISTRIBUTION Docket file; 4 NRC PDR Local PDR PD#2 Memo DRMuller ESylvester 0GC-Bethesda EJordan BGrimes ACRS (10)
NRC Participants DBL:PD#2 D%: 2 ESylyester/cd DRM 1 r 1/ W /87 1/LJ /87 0FFICIAL RECORD COPY
I{ . . . . _
~ -
Mr. E. E. Utley Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2 cc:
Mr. P. W. Howe , Mr. C. R. Dietz Vice President Plant General Manager Brunswick Nuclear Project Brunswick Nuclear Project Box 10429 Box 10429 Southport, North Carolina 28461 Southport, North Carolina 28461 Thomas A. Baxter, Esquire Mr. H. A. Cole Shaw, Pittman, Potts & Trowbridge Special Deputy Attorney General 2300 N Street, N. W. State of North Carolina Washington, D. C. 20037 Post Office Box 629 Raleigh, North Carolina 27602 Mr. D. E. Hollar Associate General Counsel Mr. Robert P. Gruber Carolina Power & Light Company Executive Director Post Office Box 1551 Public Staff - NCUC Raleigh, North Carolina 27602 Post Office Box 29b20 Raleigh, North Carolina 27626-0b20 Mr. Christopher Chappell, Chairman Board of Commissioners Post Office Box 249
, Bolivia, North Carolina 28422 Mrs. Chrys Baggett State Clearinghouse Budget and Management 116 West Jones Street Raleigh, North Carolina 27603 Resident Inspector U. S. Nuclear Regulatory Comission Star Route 1 Post Office Box 208 Southport, North Carolina 28461 Regional Administrator, Region II U. S. Nuclear Regulatory Comission 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 Mr. Dayne H. Brown, Chief Radiation Protection Branch Division of Facility Services -
N. C. Department of Human Resources 701 Barbour Drive Raleigh, North Carolina 27603-2008
ENCLOSURE 1 MEETING ATTENDEES NRC CP&L R. Hermann S. Zimmerman W. Hazelton S. Floyd R. Bosnak ,. B. Mann W. Koo J. Titrington Y. Li C. Patterson R. Johnson E. Sylvester O'Donnell & Associates, Inc. Westinghouse W. O'Donnell' J.~ Dougherty J. Porowski E. Krch E. Hampton Westinghouse - Innovative Technologies Inc.
J. Davis i - -
ra - ,
_~ , . . .
ENCLOSURE 2 CAROLINA POWER AND LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT APPLICATION OF PIPELOCK ON FLAWED INCONEL BUTTER WELDS NOVEMBER 3, 1986 e
^
PRESENTATIONS OUTLIRE-I. INTRODUCTION- ,
CHRIS PATTERSON (CP&L)
II. LICENSING APPROACH CHRIS PATTERSON (CP&L)-
III..PIPELOCK. SOLUTION BILL O'DONNELL (0DAI)
ED HAMPTON (ODAI)-
t IV, INSPECTABILITY- BRIAN MANN (CP&L)
V.
SUMMARY
/ CONCLUSIONS CHRIS PATTERSON (CP&L)
! JOHN TITRINGTON (CP&L) ;
.i I
i
)
1 4
i i
i
.~
a ._
INTRODUCTION o BRUNSWICK UNITS ARE. SUSCEPTIBLE TO INCONEL BUTTER CRACKING TWO SMALL INDICATIONS ON UNIT 2 PLAN TO REINSPECT UNIT 1 o MUST DEVELOP REPAIR FOR UNIT 2 INDICATIONS AND CONTINGENCY
~~~
REPAIR PLAN FOR UNIT 1 o CP&L DECISION ANALYSIS IDENTIFIES PIPELOCK AS AN ACCEPTABLE SOLUTION FOR THE BRUNSWICK UNITS
_o CP&L NEEDS NRC INPUT:
- 1. CONCURRENCE WITH CONCEPT
- 2. CONTENT OF SUBMITTAL 3, SCHEDULE ACCEPTABILITY CP&L REQUESTS NRC CONCURRENCE WITH THE PIPELOCK CONCEPT AND !
LICENSING APPROACH FOR APPLICATION ON THE BRUNSUICK UNITS, i
I .
LICENSING APPROACH o PRESENT PIPELOCK SOLUTION NOVEMBER 3, 1986 r o IDENTIFY NRC CONCERNS WITH THIS SOLUTION NOVEMBER 3, 1986 h o OBTAIN NRC INPUT FOR SUBMITTAL NOVEMBER 3, 1986 o SUBMIT COMPLETE LICENSING PACKAGE FOR REPRESENTATIVE RPV N0ZZLE TO SAFE-END PIPELOCK FOR APPROVAL PRIOR TO THE START OF THE UNIT 1 RF5 0UTAGE JANUARY 1987 o SUBMITTAL WILL CONTAIN:
- 1. ASME CODE DESIGN ANALYSIS l
- 2. TEST VERIFICATION PROGRAM o SUBMIT COMPLETED LICENSING PACKAGES FOR SPECIFIC RPV N0ZZLE TO SAFE-END PIPELOCK INSTALLATIONS PRIOR TO UNIT 1 RF5 0UTAGE STARTUP o INSTALLATION TO START AS EARLY AS MARCH 1987
- ~ ~
a r.
.__ u_ _
INSPECTABILITY O
THE PIPELOCK ITSELF CAN BE EXAMINED PER ASME XI REQUIREMENTS.AS AN ADDED MEASURE OF CONSERVATISM THE PIPELOCK IS DESIGNED FOR OPTIMUM INSPECTABILITY OF THE ORIGINAL WELD, 0 THE PIPELOCK, WHEN REMOVED, WILL NOT INTERFERE WITH UT --
EXAMINATION TECHNIQUES RECOMMENDED BY EPRI/BWROG, IGSCC RESEARCH PROJECT T-301-2, DEVELOPMENT OF IMPROVED PROCEDURE FOR EXAMINATION OF DISSIMILAR METAL WELDS IN BWR N0ZZLE-TO-SAFE-END WELD.
O THE GROOVES THAT-ENABLE THE PIPELOCK TO ADEQUATELY GRIP THE PIPE ARE DESIGNED TO ALLOW EXAMINATION TO THE WELD ROOT WITH A 60 TRANSDUCER.
O THE SURFACE FINISH, WHICH IS EXTREMELY CRITICAL TO IGSCC DETECTION AND SIZING, WILL REMAIN MACHINED IN THE AREA 0F INTEREST.
O THE ABILITY TO EXAMINE WITH THE USE OF AUTOMATED UT IS UNAFFECTED.
l O THE ABILITY TO EXAMINE-THE SAFE-END, THERMAL SLEEVE CREVICE AREA, AND SURROUNDING WELDS WILL BE UNAFFECTED.
THE PIPELOCK WILL ALLOW ACCEPTABLE EXAMINATION BY UT FOR DETECTION, SIZING, AND MONITORING OF IGSCC INDICATIONS.
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esmemame PIPELOCK SOLUTION k
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m go CONCLUSION o PIPELOCK MEETS ASME SECTION III CLASS I CODE.AND REGULATORY REQUIREMENTS; NO REDUCTION IN MARGIN -
o PIPELOCK INDUCES COMPRESSIVE STRESS IN PIPE WALL TO STOP CRACK GROWTH o PIPELOCK INTEGRITY IS EASILY VERIFIED o INSPECTION OF WELD JOINTS IS DOSSIBLE, BUT NOT NECESSARY FOR SAFETY PIPELOCK IS AN ACCEPTABLE REPAIR FOR INCONEL BUTTER JOINTS
