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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20196H1471999-06-24024 June 1999 Summary of 990609 Meeting with Duke Energy Corp Re NRC Conclusions for TIA-98008 on Use of Compensatory Actions for Control Room Emergency Ventilation System & to Present Positions.List of Participants & Licensee Handouts Encl ML20203C2351999-02-0404 February 1999 Summary of 990127 Meeting with Duke Energy Corp Re Proposed License Amend to Take Credit for Soluble Boron & Partial Credit for Boraflex in Sf Pools at McGuire Nuclear Station. List of Attendees & Handouts Provided by Duke Encl ML20236P1761998-07-13013 July 1998 Summary of 980709-10 Meeting W/Util Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl ML20249C7711998-06-29029 June 1998 Summary of 980617 & 18 Meetings W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TSs for Catawba & McGuire Nuclear Stations.List of Meeting Attendees Encl ML20249B4361998-06-17017 June 1998 Summary of 980514 Meeting W/Duke Energy Corp Re Info Related to Ice Condenser Issues,Ice Weight Redistribution & Reduction & Block Ice Utilization.List of Participants & Handout Provided by Util,Encl ML20248E7911998-06-0101 June 1998 Summary of 980518 Meeting W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl ML20203L9501998-02-19019 February 1998 Summary of 980204 Meeting W/Util to Discuss Info Re Design, Operabiliy & Qualifications of Grinnell Snubbers at Plant. Meeting Scheduled to Resolve Issues Re Staff Rai.List of Participants & Handouts Provided by Util Encl ML20203B7081998-02-10010 February 1998 Summary of 980127 Meeting W/Duke Energy Corp Re Proposed Rev of Topical Repts.List of Attendees & DEC Slides Encl ML20198G2131997-12-23023 December 1997 Summary of 971118 Meeting W/Duke Energy Corp in Rockville, Md,Re non-vital Electrical Bus,Kxa,Dual Unit Reactor Trip on 970906.List of Meeting Attendees & Licensee Handout Encl ML20202E6761997-11-26026 November 1997 Summary of 971030 Meeting W/Duke Energy Corp Re Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Attendees,Meeting Agenda & Licensee Handout Matl Encl ML20217P0651997-08-22022 August 1997 Summary of 970709 Meeting W/Util Re Issues Related to 1996 Rev of McGuire Ufsar.List of Attendees & Verbal Response Encl ML20129K3791996-11-21021 November 1996 Summary of 961016 Meeting W/Dpc at Plant Re Ongoing Current Licensing Issues & Safety Initiatives at Three Nuclear Stations.Meeting Attendees,Agenda & Handouts Encl ML20059L0651994-01-26026 January 1994 Summary of 931201 Meeting W/Util in Rockville,Md Re Presentation by Licensee on SG Replacement Project. Attendees Listed in Encl 1 ML20059H9901993-10-29029 October 1993 Summary of 930929 Meeting W/Util in Rockville,Md to Discuss Results of Util Investigation Into Unit 1 SG Tube Leaks. Licensee Agreed to Investigate Leakage Monitoring Program ML20059A5941993-10-14014 October 1993 Summary of 930929 Meeting W/B&W Re Generic Implications for of Steam Generator Leak for Similar Sleeves Installed at Other Facilities.List of Attendees & Meeting Handouts Encl ML20057F1471993-10-0606 October 1993 Summary of Operating Reactors Events Meeting 93-37 on 930929 ML20058M5891993-09-27027 September 1993 Summary of Operating Reactors Events Meeting 93-36 on 930922 ML20056D6661993-06-0101 June 1993 Summary of Operating Reactors Events Briefing 93-19 on 930526 ML20126G7701992-12-21021 December 1992 Summary of 921215 Meeting W/Util Re Status of Plans to Replace Snubbers During Next Scheduled Unit 1 Outage in Mar 1993 ML20210E1761992-06-10010 June 1992 Summary of 920415 Meeting W/Representatives of Util to Discuss a Study by Kalsi Engineering on Capability of MOV Actuators.List of Attendees,Handouts,And Comments/Concerns Encl ML20217B4961991-02-0707 February 1991 Summary of 910204 Meeting W/Util in Atlanta Re self- Assessment of Facility Performance from 891101 - 910202.List of Attendees & Presentation Summary Encl ML20248E8521989-10-0202 October 1989 Trip Rept of 890907 Visit to Plant Re Steel Containment Corrosion.Attendee List & Slides Encl ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247C1091989-05-17017 May 1989 Summary of 890513 Meeting W/Util in Rockville,Md Re 890307 Steam Generator 1B Tube Rupture Event.Nrc Will Support 890504 Restart Only If Further Meetings & Reportings Result Into Effective Corrective Actions ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20246N9201989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl ML20247A8971989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl ML20235S7701989-02-21021 February 1989 Summary of 890118 Meeting W/Util at Site Re Certain Human Engineering Deficiencies Identified During Dcrdrs & Not Implemented.Attendees Listed in Encl 1 & Presentation Aids Listed in Encl 2 ML20148H2851988-01-22022 January 1988 Summary of ACRS Subcommittee on Generic Items 871216 Meeting W/Util in Washington,Dc Re Effectiveness of NRC Process That Deals W/Generic Issues & Usis.Viewgraphs & Presentation Schedule 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 ML20196B1461988-01-11011 January 1988 Summary of CRGR Meeting 127 on 871223 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys in LWR Nucl Nuclear Power Plants. Committee Recommended Forwarding Ofc Package to EDO Following Incorporation of CRGR Comments 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 ML20237L1111987-08-28028 August 1987 Summary of Operating Reactors Events Meeting 87-28 on 870825 Re Events Which Occurred Since 870818 Meeting.List of Attendees & Significant Elements Encl ML20237G3891987-08-27027 August 1987 Summary of Operating Reactors Events Meeting 87-25 on 870804 Re Events That Occurred Since 870728 Meeting.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl ML20236E4291987-07-23023 July 1987 Summary of 870709 Meeting W/Util Re Groundwater Monitoring & Control at Site.Location of Wells Shown on Encl Sketch ML20215M3341987-06-22022 June 1987 Summary of 870618 Meeting W/Util & B&W Re Schedule for Review of Topical Repts Concerning Use of B&W Fuel for Plant Reloads.List of Attendees,Agenda & Presentation Matl Encl ML20214E5711986-11-18018 November 1986 Summary of 861103 Operating Reactors Events Meeting 86-38 Re Briefing of Ofc & Div Directors on Events Occurring Since 861027 Meeting.List of Attendees,Viewgraphs & Addl Documentation Encl ML20212M8961986-08-21021 August 1986 Summary of 860801 Meeting W/Util & Westinghouse in Bethesda, MD Re Failed Fuel Due to Baffle Jetting Discovered During Unit 1,Cycle 4 Refueling Outage & Licensee Proposed Corrective Actions ML20214J6111986-08-0808 August 1986 Summary of 860725 Meeting W/Util & Westinghouse in Bethesda, MD Re Licensee Request to Change Tech Specs on Steam Generator Tube Plugging Criteria ML20204C5451986-07-24024 July 1986 Summary of 860715 Telcon W/Util & Westinghouse Re Alternative Steam Generator Tube Plugging Criterion for Defects Located in Tube Sheet Region.List of Participants Encl IA-87-465, Trip Rept of 860210-21 Site Visit W/Inpo Re INPO Process for Evaluating Util Activities in Operating Experience Review. Observations & Conclusions Summarized1986-07-22022 July 1986 Trip Rept of 860210-21 Site Visit W/Inpo Re INPO Process for Evaluating Util Activities in Operating Experience Review. Observations & Conclusions Summarized ML20244E1291986-07-22022 July 1986 Trip Rept of 860210-21 Site Visit W/Inpo Re INPO Process for Evaluating Util Activities in Operating Experience Review. Observations & Conclusions Summarized ML20202D2421986-07-0202 July 1986 Summary of 860610 Meeting W/Util in Bethesda,Md Re Licensee Analyses on Performance of Structural Steel Supports for Cable Trays (Electrays) in Unit 1 Mechanical Pipe Chase & Unit 2 Auxiliary Feedwater Pump Room After Fire ML20199D4651986-06-10010 June 1986 Summary of 860527 Meeting W/Util,B&W & Metal Improvement Co in Bethesda,Md Re Plans to Perform Shot Peening of Unit 1 Steam Generator Tubes.Results of Unit 2 Tests of Steam Generator Tubes Also Reviewed.Attendee List Encl ML20202G4981986-05-22022 May 1986 Summary of ACRS Reactor Operations Subcommittee 860409 Meeting in Washington,Dc.Schedule of Items Covered, Attendance List & Meeting Handouts Encl ML20197F1691986-05-0808 May 1986 Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors ML20197E0721986-05-0707 May 1986 Summary of 860408 Meting W/Util Re Hydrogen Control Measures,Standby Shutdown Facility & Nuclear Svc Water Sys Testing.Meeting Agenda,Attendance List & Viewgraphs Encl ML20205J9221986-04-18018 April 1986 Summary of ACRS 312th Meeting on 860410-12 in Washington,Dc Re Proposed NRC Safety Goal Policy Statement & Need for Guidance in Environ & PRA for Quantification of Public Health Risks to Nearby Populations ML20202G4891986-04-16016 April 1986 Summary of ACRS Combined DHR Sys/Eccs Subcommittee 860326 Meeting in Washington,Dc Re Review of Duke Power Co Request to Delete ECCS Upper Head Injection Sys & Proposed NRR Resolution Position for Generic Issue 124 ML20210J0261986-03-24024 March 1986 Summary of Operating Reactor Events Meeting 86-08 on 860317 to Discuss Events Occurring Since Last Meeting on 860310 1999-06-24
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20196H1471999-06-24024 June 1999 Summary of 990609 Meeting with Duke Energy Corp Re NRC Conclusions for TIA-98008 on Use of Compensatory Actions for Control Room Emergency Ventilation System & to Present Positions.List of Participants & Licensee Handouts Encl ML20203C2351999-02-0404 February 1999 Summary of 990127 Meeting with Duke Energy Corp Re Proposed License Amend to Take Credit for Soluble Boron & Partial Credit for Boraflex in Sf Pools at McGuire Nuclear Station. List of Attendees & Handouts Provided by Duke Encl ML20236P1761998-07-13013 July 1998 Summary of 980709-10 Meeting W/Util Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl ML20249C7711998-06-29029 June 1998 Summary of 980617 & 18 Meetings W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TSs for Catawba & McGuire Nuclear Stations.List of Meeting Attendees Encl ML20249B4361998-06-17017 June 1998 Summary of 980514 Meeting W/Duke Energy Corp Re Info Related to Ice Condenser Issues,Ice Weight Redistribution & Reduction & Block Ice Utilization.List of Participants & Handout Provided by Util,Encl ML20248E7911998-06-0101 June 1998 Summary of 980518 Meeting W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl ML20203L9501998-02-19019 February 1998 Summary of 980204 Meeting W/Util to Discuss Info Re Design, Operabiliy & Qualifications of Grinnell Snubbers at Plant. Meeting Scheduled to Resolve Issues Re Staff Rai.List of Participants & Handouts Provided by Util Encl ML20203B7081998-02-10010 February 1998 Summary of 980127 Meeting W/Duke Energy Corp Re Proposed Rev of Topical Repts.List of Attendees & DEC Slides Encl ML20198G2131997-12-23023 December 1997 Summary of 971118 Meeting W/Duke Energy Corp in Rockville, Md,Re non-vital Electrical Bus,Kxa,Dual Unit Reactor Trip on 970906.List of Meeting Attendees & Licensee Handout Encl ML20202E6761997-11-26026 November 1997 Summary of 971030 Meeting W/Duke Energy Corp Re Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Attendees,Meeting Agenda & Licensee Handout Matl Encl ML20217P0651997-08-22022 August 1997 Summary of 970709 Meeting W/Util Re Issues Related to 1996 Rev of McGuire Ufsar.List of Attendees & Verbal Response Encl ML20129K3791996-11-21021 November 1996 Summary of 961016 Meeting W/Dpc at Plant Re Ongoing Current Licensing Issues & Safety Initiatives at Three Nuclear Stations.Meeting Attendees,Agenda & Handouts Encl ML20059L0651994-01-26026 January 1994 Summary of 931201 Meeting W/Util in Rockville,Md Re Presentation by Licensee on SG Replacement Project. Attendees Listed in Encl 1 ML20059H9901993-10-29029 October 1993 Summary of 930929 Meeting W/Util in Rockville,Md to Discuss Results of Util Investigation Into Unit 1 SG Tube Leaks. Licensee Agreed to Investigate Leakage Monitoring Program ML20059A5941993-10-14014 October 1993 Summary of 930929 Meeting W/B&W Re Generic Implications for of Steam Generator Leak for Similar Sleeves Installed at Other Facilities.List of Attendees & Meeting Handouts Encl ML20057F1471993-10-0606 October 1993 Summary of Operating Reactors Events Meeting 93-37 on 930929 ML20058M5891993-09-27027 September 1993 Summary of Operating Reactors Events Meeting 93-36 on 930922 ML20056D6661993-06-0101 June 1993 Summary of Operating Reactors Events Briefing 93-19 on 930526 ML20126G7701992-12-21021 December 1992 Summary of 921215 Meeting W/Util Re Status of Plans to Replace Snubbers During Next Scheduled Unit 1 Outage in Mar 1993 ML20210E1761992-06-10010 June 1992 Summary of 920415 Meeting W/Representatives of Util to Discuss a Study by Kalsi Engineering on Capability of MOV Actuators.List of Attendees,Handouts,And Comments/Concerns Encl ML20217B4961991-02-0707 February 1991 Summary of 910204 Meeting W/Util in Atlanta Re self- Assessment of Facility Performance from 891101 - 910202.List of Attendees & Presentation Summary Encl ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247C1091989-05-17017 May 1989 Summary of 890513 Meeting W/Util in Rockville,Md Re 890307 Steam Generator 1B Tube Rupture Event.Nrc Will Support 890504 Restart Only If Further Meetings & Reportings Result Into Effective Corrective Actions ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20246N9201989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl ML20247A8971989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl ML20235S7701989-02-21021 February 1989 Summary of 890118 Meeting W/Util at Site Re Certain Human Engineering Deficiencies Identified During Dcrdrs & Not Implemented.Attendees Listed in Encl 1 & Presentation Aids Listed in Encl 2 ML20148H2851988-01-22022 January 1988 Summary of ACRS Subcommittee on Generic Items 871216 Meeting W/Util in Washington,Dc Re Effectiveness of NRC Process That Deals W/Generic Issues & Usis.Viewgraphs & Presentation Schedule 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 ML20196B1461988-01-11011 January 1988 Summary of CRGR Meeting 127 on 871223 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys in LWR Nucl Nuclear Power Plants. Committee Recommended Forwarding Ofc Package to EDO Following Incorporation of CRGR Comments 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 ML20237L1111987-08-28028 August 1987 Summary of Operating Reactors Events Meeting 87-28 on 870825 Re Events Which Occurred Since 870818 Meeting.List of Attendees & Significant Elements Encl ML20237G3891987-08-27027 August 1987 Summary of Operating Reactors Events Meeting 87-25 on 870804 Re Events That Occurred Since 870728 Meeting.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl ML20236E4291987-07-23023 July 1987 Summary of 870709 Meeting W/Util Re Groundwater Monitoring & Control at Site.Location of Wells Shown on Encl Sketch ML20215M3341987-06-22022 June 1987 Summary of 870618 Meeting W/Util & B&W Re Schedule for Review of Topical Repts Concerning Use of B&W Fuel for Plant Reloads.List of Attendees,Agenda & Presentation Matl Encl ML20214E5711986-11-18018 November 1986 Summary of 861103 Operating Reactors Events Meeting 86-38 Re Briefing of Ofc & Div Directors on Events Occurring Since 861027 Meeting.List of Attendees,Viewgraphs & Addl Documentation Encl ML20212M8961986-08-21021 August 1986 Summary of 860801 Meeting W/Util & Westinghouse in Bethesda, MD Re Failed Fuel Due to Baffle Jetting Discovered During Unit 1,Cycle 4 Refueling Outage & Licensee Proposed Corrective Actions ML20214J6111986-08-0808 August 1986 Summary of 860725 Meeting W/Util & Westinghouse in Bethesda, MD Re Licensee Request to Change Tech Specs on Steam Generator Tube Plugging Criteria ML20204C5451986-07-24024 July 1986 Summary of 860715 Telcon W/Util & Westinghouse Re Alternative Steam Generator Tube Plugging Criterion for Defects Located in Tube Sheet Region.List of Participants Encl ML20202D2421986-07-0202 July 1986 Summary of 860610 Meeting W/Util in Bethesda,Md Re Licensee Analyses on Performance of Structural Steel Supports for Cable Trays (Electrays) in Unit 1 Mechanical Pipe Chase & Unit 2 Auxiliary Feedwater Pump Room After Fire ML20199D4651986-06-10010 June 1986 Summary of 860527 Meeting W/Util,B&W & Metal Improvement Co in Bethesda,Md Re Plans to Perform Shot Peening of Unit 1 Steam Generator Tubes.Results of Unit 2 Tests of Steam Generator Tubes Also Reviewed.Attendee List Encl ML20202G4981986-05-22022 May 1986 Summary of ACRS Reactor Operations Subcommittee 860409 Meeting in Washington,Dc.Schedule of Items Covered, Attendance List & Meeting Handouts Encl ML20197F1691986-05-0808 May 1986 Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors ML20197E0721986-05-0707 May 1986 Summary of 860408 Meting W/Util Re Hydrogen Control Measures,Standby Shutdown Facility & Nuclear Svc Water Sys Testing.Meeting Agenda,Attendance List & Viewgraphs Encl ML20205J9221986-04-18018 April 1986 Summary of ACRS 312th Meeting on 860410-12 in Washington,Dc Re Proposed NRC Safety Goal Policy Statement & Need for Guidance in Environ & PRA for Quantification of Public Health Risks to Nearby Populations ML20202G4891986-04-16016 April 1986 Summary of ACRS Combined DHR Sys/Eccs Subcommittee 860326 Meeting in Washington,Dc Re Review of Duke Power Co Request to Delete ECCS Upper Head Injection Sys & Proposed NRR Resolution Position for Generic Issue 124 ML20210J0261986-03-24024 March 1986 Summary of Operating Reactor Events Meeting 86-08 on 860317 to Discuss Events Occurring Since Last Meeting on 860310 ML20154N8751986-03-12012 March 1986 Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl ML20154P0071986-03-12012 March 1986 Summary of Operating Reactor Events 860303 Meeting 86-06 W/Ornl Re Events Occurring Since 860224 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl ML20205J7411986-02-28028 February 1986 Summary of ACRS 310th Meeting on 860213-15 in Washington,Dc Re Review Studies Done & Procedures Proposed by Gpu Nuclear to Protect Against Inadvertent Criticality During Defueling of TMI-2 Core 1999-06-24
[Table view] |
Text
_-___ _ _ _ _ _ _ _
July 3,1991 Docket No. 50-370 LICENSEE: Duke Power Company FACILITY: McGuire Unit 2
SUBJECT:
SUMi :Y OF MAY 22, 1991 MEETING On May 22, 1991, the NRC str.ff met with representatives of Dule Power Company (DPC) to discuss a DPC proposal to extend on a one. time basis the ice weight surveillance intern i for McGuire Unit 2 associated with Technical Specification (TS',3/4.6.5.1. The proposal is to extend the surveillance interval which currently comes due on August 3, 1991, until the next McGuire Unit 2 refueling outage currently scheduled for January 1992. The licensee's technical appro3ch is to examine the historical sublimetion rates for McGuire Unit 2, then choosing the worst case rate, multiply this rate by 150% for conservatism to account for unknowns. Ice basket ice weight is then projected to the January 1992 outage and shown to be greater than the TS limit.
The NRC staff believes that the DPC approach is conservative and that such an approach can be approved on a one-time basis for McGuire Unit 2. DPC is expediting the TS amendment package in order to have the submittal to the staff by June 5. [The amendment was indeed received by June 5, 1991.] The meeting participants are listed on Enclosure 1. Enclosure 2 is the presentation given by DPC.
/s/
Timothy A. Reed, Project Manager Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Enclosures:
- 1. Meeting Participants
- 2. Presentation cc w/ enclosures:
See next page
- See Previous Concurrence OFC :LA:PDII-3* :PM:PDII-3* :D:PDII-3* : :
NAME :R!ngram : Treed :DMatthews : :
DATE :07/2/91 :07/2/91 :07/3/91 : :
OFFICIAL RECORD COPY Document Name: MTG SUM /MCGUIRE 9107170179 910'703 !T -
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Meeting Sunrnary - Dated July 3.1991 Facility: McGuire Unit 2 Docket file NRC & Local PDRs F. Miraglia J. Partlow S. Varga G. Lainar PDil-3 Reading
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, ' * ~....f July 3,1991 Docket No. 50-370 LICENSEE: Duke Power Company FACILITY: McGuire Unit 2
SUBJECT:
SUMMARY
OF MAY 22, 1991 MEETING On May 22, 1991, the NRC staff met with representatives of Duke Power Company (DPC) to discuss a DPC proposal to extend on a one-time basis the ice weight surveillance interval for McGuire Unit 2 associated with Technical Specification (TS) 3/4.6.5.1. The proposal is to extend the surveillance interval which currently comes due on August 3,1991, until the next McGuire Unit 2 refueling outage currently scheduled for January 1992. The licensee's technical approach is to examine the historical sublimation rates for McGuire Unit 2, then choosing the worst case rate, multiply this rate by 150% for conservatism to account for unknowns. Ice basket ice weight is then projected to the January 1992 outage and shown to be greater than the TS limit.
The NRC staff believes that the DPC approach is conservative and that such an approach can be approved on a one-time basis for McGuire Unit 2. DPC is expediting the TS amendment package in order to have the submittal to the staff by June 5. [The amendment was indeed received by June 5, 1991.] The meeting participants are listed on Enclosure 1. Enclosure 2 is the presentation given by DPC.
s }
Timothy A. Reed, Project Manager Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Enclosures:
- 1. Meeting Participants
- 2. Presentation cc w/ enclosures:
See next page
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McGuire Nuclear Station CC:
Mr. A.V. Carr, Esq. Dr. John M. Barry Pule Pcwer Cor:peny Departirent of Environmental Health 422 Scuth Church Street Mecklenburg Cour.ty Charlotte, Nc th Carolina 28242-0001 1200 Cbthe Coulevard Charlotte, North Carolina 28203 County Manager of Mecklenburg County 720 East Fourth Street Mr. Dayne H. Brown, Director Charlotte, North Carolina 28202 Department of Environmental, Health and Natural Resources Mr. Paul Guill Division of Radiation Protection Duke Power Company P.O. Box 27687 Nuclear Production Department Raleigh, North Carolina 27611-7687 P.O. Box 1007 Charlotte, North Carolina 28201-1007 Mr. Alan R. Herdt, Chief Project Branch #3 U.S. Nuclear Regulatory Commission J. Michael McGarry, III, Esq. 101 Marietta Street, NW, Suite 2900 Winston and Strawn Atlanta, Georgia 30323 1400 L Street, N.W.
Washington, DC 20005 Ms. Karen E. Long Assistant Attorney General N. C. Department of Justice Senior Resident inspector P.O. Box 629 c/o U.S. Nuclear Regulatory Commission Raleigh, North Carolina 27602 12700 Hagers Ferry R 9d Huntersville, North Carolina 28078 Mr. R.L. Gill, Jr.
Nuclear Production Department Regional Administrator, Region 11 Duke Power Company U.S. Nuclear Regulatory Commission P.O. Box 1007 101 Marietta Street, N.W., Suite 2900 Charlotte, North Carolina 28201-1007 Atlanta, Georgia 30323 Mr. M. S. Tuckman Mr. Frank Modrak Vice President - Nuclear Operations Project Manager, Mid-South Area Duke Power Company ESSD Projects P. O. Box 1007 Westinghouse Electric Corporation Charlotte, North Carolina 28201-1007 MNC West Toser - Bay 241 P. O. Box 355 Pittsburgh, Pennsylvania 15230
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DUKE POWER COMPANY MCGUIRE NUCLEAR STATION AGENDA MAY 22,1991 MEETING WITH ONRR ONE TIME TS Ah01NDMENT FOR UNIT 2 ICE BASKET WEIGHING SURVEILLANCE I. Introduction / Opening Remarks P. F. Guill II. Presentation N. A. Smith,III
- Background
- Current Technical Specification Requirements
- Proposed Ice Weight Reduction TS Amendment
- Ice Basket U-Bolt Issue
- One Time Technical Specification Amendment (Unit 2)
- Technical Justification III. Discussion / Closing Remarks P. F. Guill IV. Caucus NRC
l MCGUIRE NUCLEAR STATION UNIT 2 ICE CONDENSER SURVElLLANCE WINDOW EXTENSION TECHNICAL SPECIFICATION AMENDMENT ICE CONDENSER:
SYSTEM PURPOSE The lee Condenser's primary function is to mitigate the containment pressure consequences associated with a Loss Of Coolant Accident or Main Steam Line Break inside containment.
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MCCUlRE NUCLEAR STATION
- UNIT 2:lCE CONDENSER- -
- SURVEILLANCE WINDOW EXTENSIONi TECHNICAL SPECIFICATION AMENDMENT :
1
-TECllNICAL SPECIFICATION-
< LIMITING CONDITION OF OPERATION McGuire Technical Specification Limiting Condition of Operation 3.6.5.1,d defines a minimum acceptable total ice weight of 2.466,420 (2,099,790*) lbs at a 95% level of confidence.
SURVEILLANCE REQUIREMENTS Surveillance Requirement 4.6.5.1.b.2 further specifies:
- Of a-144 basket sample (0/ bay), all must contain a minimum 1269 (1081') lbs of ice. For a basket below the minimum, additional baskets from the same bay must contain a -
minimum mean ice weight of 1269 (1081') lbs of ice.at a 95%
- level of confidence.
--The mean basket ice weight at a 95% level of confidence from each row group must be greater than 1269 (1081'l lh.s
- Thew total ice weight at a 95% level of confidence must -
be greater than 2,466,420 (2,099,790') Ibs.
Denotes ice weight reduction amendment, submitted June,1990.
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MCGUIRE NUCLEAR STATION UNIT 2 ICE CONDENSER SURVElLIANCE WINDOW EXTENSION TECHNICAL SPECIFICATION AMENDMENT ICE WElGilT REDUCTION TECil SPEC AMENDMENT:
PURPOSE The amendment to Technical Specification 3/4.6.5.1 to reduce the minimum required ice weight was submitted to preclude mid-cycle ice basket replenishment outages during the forthcoming longer cole cycles.
BASES The Technical Specification amendment is justified by a LODIC analysis defining postulated containment pressure / temperature transients within design limits with reduced ice weight.
EFFECT ON PEAK CONTAINMENT PRESSURE PEAK CONTAINMENT TECH SPEC ICE WElGHT PRESSURE LIMll 2.220,000 lbs 12.36 psig 14.8 psig 1,890,000 lbs 14.07 psig 14.8 psig STATUS NRC approval expected shortly.
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'TECllNICAL SPECIPICATION AMENDMENT I
U-BOLT ISSUE:
I FAILURE MODE Duke determined the failure mode of the U-Bolts to be a result of
-a manufacturing flaw propagated by construction / maintenance induced loads.
OPERABILITY EVALUAT10" I A nroof load test was performed on a large population of U-Bolts-demonstrating their integrity and an extremely low failure rate. 1 The test established the U-Bolt's integrity for one load cycle of design basis magnitude. As the loads induced during ice weighing were considered significant, the Operability Evaluation for both Units excluded on-line ice weighing using current techniques.
.LONG TERM PLAN-During the upcoming retueling outages on both McGuire Units, a-phased replacement of U-Bolts will begin. The bolts, mounting bracket, and associated hardware will be replaced with a swivel base bracket. The bracket not only eliminates U-Bolt. concerns, it i
enhances the on-line weighing technique. Replacement is expected to take 4 refueling outages. '
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1 l EFFECT ON ICE WElGHING y On-line ice weighing cannot be performed under the current l- ' surveillance requirements. The initial population of upgraded ice i
baskets will include those for the mid-cycle ice weight l surveillance. These baskets may be weighed on-line, reestablishing j the ability to meet the Technical Specification requirements.
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P MCGUIRE NUCLEAR STATION UNIT 2 ICE CONDENSER SURVEILIANCE WINDOW EXTENSION TECHNICAL SPECIFICATION AMENDMENT REQUESTED TECllNICAL SPECIFICATION AMENDMENT:
REQUEST Amendment to Technical Specification 3/4.6.5.1 extending the ice weight surveillance interval for Unit 2 Cycle 7 to the next refueling outage.
PURPOSE Preclude a mid-cycle outage during Unit 2 Cycle 7 to perform a Tech Spec surveillance.
CONSEQUENCES IF NOT OBTAINED Implement less desirable options.
- Perform on-line weighing of non-ejectable baskets
+ Requires relief from current surveillance rec,uirements
- Perform off-line ice weight surveillance.
7 MCCU!RE NUCLEAR STATION UNIT 2 ICE CONDENSER SURt!P;LiANCE WINDOW EXTENSION TECllNICAL SPECIFICATION AMENDMENT TECllNICAL JUSTlFICATION:
OVERVIEW The approach to technically justify the amendment is based on a projection of current ice weight through the fuel cycle. Beginning of Cycle ice weight data, worst case historical sublimation rates, and a multiplier (150r)o for unknowns were used in a linear extrapolation of ice weight through the fuel cycle.
TECHNICAL JUSTIFICATION HISTORICAL BAY SUBLIMATION RATES
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.k MCGUIRE NUCLEAR STATION UNIT 2 ICE CONDENSER SURVEILIANCE WINDOW EXTENSION TECHNICAL SPECIFICATION AMENDMENT TECHNICAL JUSTIFICATION:
WORST CASE SUBLIMATION RATES UNIT 2 MAXIMUM HISTORICAL R0W GROUP SUBLIMATION RATES CYCLE 2 THROUGH CYCLE 6 BASED ON 95% LOC B0C TO ECO DATA SUBLIMATION RATE 801 GROUP ClCLE (lbs/ month) 9 3 4 18.9 9 2 5 18.8 9 1 6 16.0 9 1 4 15.6 9 3 5 14.7
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- MCGUIRE NUCLEAR STATION 7 UNIT 2 ICE CONDENSER SURVEILLANCE WINDOW EXTENSION:
TECHNICAL SPECIFICATION AMENDMENT TECllNICAL JUSTIFICATION:
METHODOLOGY -
Using the following formula to project ice weight throughout cycle _7.
Wt = W-bec - SR x M SR x ( Dt - Dboc )
- Where:
W.t -= Projected mean ice weight for row 'a' group.'b' at time
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Wb oc = Beginning of cycle surveillance mean ice weight at a 95% level of confidence for row 'a' group 'b'-
SR = - Sublimation rate, worst case historical (Ibs/ month)
MSR = Sublimation rate multiplier, accounts for uncertainly l
Dboc = Beginning of cycle date (month) l Dt -= Date at time 't' (month)
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MCGUIRE NUCLEAR STATION I UNIT 2 ICE CONDENSER SURVEILLANCE WINDOW EXTENSION TECllNICAL SPECIFICATION AMENDMENT CONCl,USIONS:
The conservative analytical approach towards projecting ice weight ,
demonstrates that with a high level of confidence, adequale ice mass will exist in the Unit 2 ice condenser at the end of cycle 7.
Projections indicate the end of cycle worst case mean ice weight will be 116 lbs above the Tech Spec limit, that required at the beginning of cycle. The request for the extended surveillance interval is e therefore technically justified.
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