|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20196J2351999-06-29029 June 1999
Summary of 990617 Meeting with B&Wog & FTI Re B&Wog Emergency Operating Procedure Program.List of Meeting Attendees & Presentation Slides Encl
ML20206D6031999-04-30030 April 1999
Summary of 990318 Meeting with Firstenergy Nuclear Operating Co in Rockville,Maryland Re Review Schedule & Content of Proposed QA Topical Rept for Both Davis-Besse & Perry Facilities.List of Meeting Attendees Encl
ML20206D0951999-04-23023 April 1999
Summary of 990419 Meeting with Firstenergy Nuclear Operating Co in Rockville,Maryland Re Briefing New NRR Projects Personnel on History & Organization of Davis-Besse & Schedule & Priority of near-term Licensing Actions
ML20195D4551998-11-10010 November 1998
Summary of Operating Reactors Events Briefing 98-07 Held on 981021.List of Attendees,Significant Elements of Discussed Events & Significant Events That Were Identified for Input Into NRC Performance Indicator Program Encl
ML20236P6611998-07-10010 July 1998
Summary of 980708 Briefing 98-06 to Inform Senior Managers from Ocm,Edo,Aeod & NRR & Regional Ofcs of Selected Events That Occurred Since Last Brief on 980701.List of Attendees & Briefing Slides Encl
ML20198G1721997-12-18018 December 1997
Summary of 971215 Meeting W/Util in Rockville,Md to Discuss Quality Programs at Davis-Besse Nuclear Power Station.List of Meeting Participants & Meeting Handouts Encl
ML20216J9211997-09-12012 September 1997
Summary of 970821 Meeting W/Toledo Edison Co in Rockville,Md to Discuss Instrument Drift Study.List of Attendees & Handouts Encl
ML20137X9341997-04-16016 April 1997
Summary of 970403 Meeting W/Licensee to Discuss plant-specific Thermo-Lag Corrective Action Programs. List of Attendees & Handouts Encl
ML20134A9621997-01-22022 January 1997
Summary of 961204 Meeting W/Util in Rockville,Md to Discuss Proposed Merger Between Centerior Energy Corporation & Ohio Edison Company.List of Attendees & Info Handouts Encl
ML20059G7451993-11-0101 November 1993
Summary of 931101 Meeting W/Util in Rockville,Md Re Implementation of RG 1.97 for Steam Generator (SG) Pressure Instruments at Plant.List of Mtg Attendees & Handouts Encl
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
ML20056E2051993-08-0303 August 1993
Summary of 930729 Meeting W/Util in Rockville,Md Re Response to GL 90-06 Involving TS for Porv.List of Attendees & Handouts Encl
ML20128L5271993-02-12012 February 1993
Summary of 930115 Meeting W/Util in Rockville,Md Re Containment Penetration Bellows Tests in Response to NRC Info Notice 92-20
ML20126H9221992-12-30030 December 1992
Summary of 921230 Meeting W/Util in Rockville,Md to Discuss Upcoming Refueling Outage Plans & Recent Plant Performance
ML20126H9251992-12-30030 December 1992
Summary of 921215 Meeting W/Util in Rockville,Md to Discuss Proposed Amend That Would Allow Alternative to Safety Features Actuation Sys in Mode 6
ML20125A4161992-12-0202 December 1992
Summary of 921118 Meeting W/Util in Rockville,Md Re Status of Licensing Issues.Schedule for License Amend Requests Associated W/Upcoming Refueling Outage & Fire Protection Exemption Request Discussed
ML20125A7991992-12-0202 December 1992
Summary of 921119 Meeting W/Util in Rockville,Md Re Local Leak Rate Testing of Containment Penetration Bellows at Plant,Per NRC Info Notice 92-020
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20154N9081988-09-23023 September 1988
Summary of 880721 Meeting/Util in Rockville,Md Re Licensee App R Reappraisal Efforts.List of Meeting Attendees & Viewgraphs Encl
ML20207E2961988-07-28028 July 1988
Summary of 880714 Meeting W/B&W Owners Group Re Industry & NRC Actions to Resolve Issues Raised in Generic Ltr 87-12. List of Attendees,Viewgraphs & B&W Design Differences Encl
ML20196J7851988-03-10010 March 1988
Summary of Operating Reactors Events Meeting 88-10 on 880308.List of Attendees & Significant Elements of Events Discussed Encl
ML20148H6031987-12-15015 December 1987
Summary of ACRS DHR Sys Subcommittee 871117 Meeting in Washington,Dc Re Util Decision Not to Install Dedicated Blowdown Sys at Davis Besse & Implications of Diablo Canyon Loss of Shutdown Cooling Event.Viewgraphs Encl
ML20239A0231987-09-10010 September 1987
Summary of Operating Reactor Events Meeting 87-30 on 870908, Re Briefing Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870825 Meeting.Attendees List,Summary of Reactor Scrams & Viewgraphs Encl
ML20204E4951987-03-19019 March 1987
Summary of Operating Reactor Events Meeting 87-07 on 870316. List of Attendees,Events Discussed & Significant Elements of Events Presented & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20214L0051987-01-16016 January 1987
Summary of 870114 Allegation Review Board Meeting to Discuss Allegation RIII-87-A-0001.Meeting Participants Listed
ML20214P9371986-11-21021 November 1986
Summary of Operating Reactor Events Meeting 86-39 on 861110.List of Attendees,Events Discussed & Significant Elements of Events Encl
ML20214P6911986-08-0707 August 1986
Summary of ACRS Subcommittee on Davis-Besse 860627 Meeting in Washington,Dc Re Facility Restart
ML20205K2051986-07-21021 July 1986
Summary of ACRS 315th Meeting on 860710-12 in Washington,Dc Re Loss of Feedwater Event at Davis Besse Nuclear Power Station,Unit 1 & Review of Proposed Commission Policy Statement on Tech Specs
ML20214Q4781986-07-11011 July 1986
Summary of ACRS Regulatory Policies & Practices Subcommittee 860626 Meeting in Washington,Dc to Discuss Incident Investigation Team Review & Regulatory Process Re 850609 Event at Facility
ML20203H2181986-04-14014 April 1986
Summary of 860205 Meeting W/B&W Owners Group in Bethesda,Md Re B&W Owners Group Ongoing Programs & Activities & 850609 & 1226 Transients at Davis Besse & Rancho Seco,Respectively. Attendance List & Handout Incl
ML20195B4641986-03-15015 March 1986
Summary of ACRS Subcommittee on Davis Besse (Restart) 860206 Meeting in Washington,Dc Re Restart Activities Since 850609 Loss of Feedwater Event.Fr Notice,Agenda & List of Attendees 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
ML20138P8841985-12-17017 December 1985
Summary of 851209 Meeting W/Util in Bethesda,Md Re Status Rept on Course of Action.List of Meeting Attendees & Info Presented by Util Encl
ML20138Q5501985-12-17017 December 1985
Summary of 851126 Meeting W/Util,Beta & Consolidated Controls Corp in Bethesda,Md Re Proposed Changes to Safety Features Actuation Sys.Viewgraphs & List of Attendees Encl
ML20136E2921985-11-27027 November 1985
Summary of ACRS Subcommittee on Davis-Besse 851004 Meeting in Oak Harbor,Oh to Review Course of Action Prior to Facility Restart.List of Items Discussed at Meeting & List of Attendees & Handouts Encl
ML20137Q3981985-11-21021 November 1985
Summary of 851104 Meeting W/Util,B&W & Essex Corp Re Auxiliary Feedwater Sys Mods & Changes.Viewgraphs & List of Attendees Encl
ML20137P7871985-11-21021 November 1985
Summary of 851016-17 Meetings W/Util & Impell Corp Re Licensee Auxiliary Feedwater Reliability Analyses.Viewgraphs & Proposed Outline of Reliability Analysis Rept Encl
ML20137P6401985-11-20020 November 1985
Summary of 851105 Meeting W/B&W Owners Group in Bethesda,Md Re Action Plan Developed in Response to Davis-Besse 850609 Loss of Feedwater Event.List of Attendees & Handouts Encl
ML20137P7041985-11-20020 November 1985
Summary of 851009 Meeting W/Util,Science Applications Intl Corp & Essex Corp in Bethesda,Md Re Issues Identified in NRC Re Preimplementation Audit Findings in Late Apr 1985.Summary of Commitments Encl
ML20136E2491985-11-0707 November 1985
Proposed Summary of ACRS Subcommittee on Regulatory Policies & Practices 851101 Meeting in Washington,Dc to Discuss SECY-85-208, Incident Investigation Program & Process Used to Investigate 850609 Event at Facility
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
ML20138M4151985-10-17017 October 1985
Summary of 851004 Meeting W/B&W Owners Group Transient Assessment & Availability Committees in Bethesda,Md Re Operating Experience of Operating Reactors & Plans to Improve Experience.Viewgraphs Encl
ML20133F9941985-10-0707 October 1985
Summary of Operating Reactors Events Meeting 85-16 on 850916 Re Briefing of Director,Div Directors & Representatives on Events Occurring Since 850909 Meeting.List of Attendees & Viewgraphs Encl
ML20133E4631985-10-0101 October 1985
Summary of Operating Reactors Events Meeting 85-17 on 850923.List of Attendees & Viewgraphs Encl
ML20134K8521985-08-0808 August 1985
Summary of ACRS ECCS Subcommittee 850731 Meeting w/B&W,C-E & Westinghouse in Washington,Dc Re Review of 10CFR50.46 & App K,Implementation of GE App K Analysis Effort & 850609 Incident at Facility
ML20128K7491985-07-12012 July 1985
Summary of Operating Reactor Events Meeting 85-11 on 850701. List of Attendees,Events Discussed,Significant Elements of Events & Assignment of Followup Review Responsibility Encl
ML20127N9021985-06-24024 June 1985
Summary of Operating Reactors Events Meeting 85-10 on 850612.Only 3 of 17 Items Scheduled for Completion by 850531 Remain Incomplete.List of Attendees,Summary of Events Discussed & Status of Previous Assignments Encl
ML20207N6001984-09-10010 September 1984
Summary of 840905 Meeting at NRC Region III Ofc Re Inservice Insp of HPI Sys
ML20155C9641984-08-0606 August 1984
Summary of 840612 Meeting W/Util in Bethesda,Md Re Program to Correct Fire Protection Deficiencies in Facility Fire Protection Features & non-compliance W/Respect to Requirements of App R to 10CFR50.Related Info Encl
1999-06-29
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20196J2351999-06-29029 June 1999
Summary of 990617 Meeting with B&Wog & FTI Re B&Wog Emergency Operating Procedure Program.List of Meeting Attendees & Presentation Slides Encl
ML20206D6031999-04-30030 April 1999
Summary of 990318 Meeting with Firstenergy Nuclear Operating Co in Rockville,Maryland Re Review Schedule & Content of Proposed QA Topical Rept for Both Davis-Besse & Perry Facilities.List of Meeting Attendees Encl
ML20206D0951999-04-23023 April 1999
Summary of 990419 Meeting with Firstenergy Nuclear Operating Co in Rockville,Maryland Re Briefing New NRR Projects Personnel on History & Organization of Davis-Besse & Schedule & Priority of near-term Licensing Actions
ML20195D4551998-11-10010 November 1998
Summary of Operating Reactors Events Briefing 98-07 Held on 981021.List of Attendees,Significant Elements of Discussed Events & Significant Events That Were Identified for Input Into NRC Performance Indicator Program Encl
ML20236P6611998-07-10010 July 1998
Summary of 980708 Briefing 98-06 to Inform Senior Managers from Ocm,Edo,Aeod & NRR & Regional Ofcs of Selected Events That Occurred Since Last Brief on 980701.List of Attendees & Briefing Slides Encl
ML20198G1721997-12-18018 December 1997
Summary of 971215 Meeting W/Util in Rockville,Md to Discuss Quality Programs at Davis-Besse Nuclear Power Station.List of Meeting Participants & Meeting Handouts Encl
ML20216J9211997-09-12012 September 1997
Summary of 970821 Meeting W/Toledo Edison Co in Rockville,Md to Discuss Instrument Drift Study.List of Attendees & Handouts Encl
ML20137X9341997-04-16016 April 1997
Summary of 970403 Meeting W/Licensee to Discuss plant-specific Thermo-Lag Corrective Action Programs. List of Attendees & Handouts Encl
ML20134A9621997-01-22022 January 1997
Summary of 961204 Meeting W/Util in Rockville,Md to Discuss Proposed Merger Between Centerior Energy Corporation & Ohio Edison Company.List of Attendees & Info Handouts Encl
ML20059G7451993-11-0101 November 1993
Summary of 931101 Meeting W/Util in Rockville,Md Re Implementation of RG 1.97 for Steam Generator (SG) Pressure Instruments at Plant.List of Mtg Attendees & Handouts Encl
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
ML20056E2051993-08-0303 August 1993
Summary of 930729 Meeting W/Util in Rockville,Md Re Response to GL 90-06 Involving TS for Porv.List of Attendees & Handouts Encl
ML20128L5271993-02-12012 February 1993
Summary of 930115 Meeting W/Util in Rockville,Md Re Containment Penetration Bellows Tests in Response to NRC Info Notice 92-20
ML20126H9221992-12-30030 December 1992
Summary of 921230 Meeting W/Util in Rockville,Md to Discuss Upcoming Refueling Outage Plans & Recent Plant Performance
ML20126H9251992-12-30030 December 1992
Summary of 921215 Meeting W/Util in Rockville,Md to Discuss Proposed Amend That Would Allow Alternative to Safety Features Actuation Sys in Mode 6
ML20125A4161992-12-0202 December 1992
Summary of 921118 Meeting W/Util in Rockville,Md Re Status of Licensing Issues.Schedule for License Amend Requests Associated W/Upcoming Refueling Outage & Fire Protection Exemption Request Discussed
ML20125A7991992-12-0202 December 1992
Summary of 921119 Meeting W/Util in Rockville,Md Re Local Leak Rate Testing of Containment Penetration Bellows at Plant,Per NRC Info Notice 92-020
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20154N9081988-09-23023 September 1988
Summary of 880721 Meeting/Util in Rockville,Md Re Licensee App R Reappraisal Efforts.List of Meeting Attendees & Viewgraphs Encl
ML20207E2961988-07-28028 July 1988
Summary of 880714 Meeting W/B&W Owners Group Re Industry & NRC Actions to Resolve Issues Raised in Generic Ltr 87-12. List of Attendees,Viewgraphs & B&W Design Differences Encl
ML20196J7851988-03-10010 March 1988
Summary of Operating Reactors Events Meeting 88-10 on 880308.List of Attendees & Significant Elements of Events Discussed Encl
ML20148H6031987-12-15015 December 1987
Summary of ACRS DHR Sys Subcommittee 871117 Meeting in Washington,Dc Re Util Decision Not to Install Dedicated Blowdown Sys at Davis Besse & Implications of Diablo Canyon Loss of Shutdown Cooling Event.Viewgraphs Encl
ML20239A0231987-09-10010 September 1987
Summary of Operating Reactor Events Meeting 87-30 on 870908, Re Briefing Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870825 Meeting.Attendees List,Summary of Reactor Scrams & Viewgraphs Encl
ML20204E4951987-03-19019 March 1987
Summary of Operating Reactor Events Meeting 87-07 on 870316. List of Attendees,Events Discussed & Significant Elements of Events Presented & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20214L0051987-01-16016 January 1987
Summary of 870114 Allegation Review Board Meeting to Discuss Allegation RIII-87-A-0001.Meeting Participants Listed
ML20214P9371986-11-21021 November 1986
Summary of Operating Reactor Events Meeting 86-39 on 861110.List of Attendees,Events Discussed & Significant Elements of Events Encl
ML20214P6911986-08-0707 August 1986
Summary of ACRS Subcommittee on Davis-Besse 860627 Meeting in Washington,Dc Re Facility Restart
ML20205K2051986-07-21021 July 1986
Summary of ACRS 315th Meeting on 860710-12 in Washington,Dc Re Loss of Feedwater Event at Davis Besse Nuclear Power Station,Unit 1 & Review of Proposed Commission Policy Statement on Tech Specs
ML20214Q4781986-07-11011 July 1986
Summary of ACRS Regulatory Policies & Practices Subcommittee 860626 Meeting in Washington,Dc to Discuss Incident Investigation Team Review & Regulatory Process Re 850609 Event at Facility
ML20203H2181986-04-14014 April 1986
Summary of 860205 Meeting W/B&W Owners Group in Bethesda,Md Re B&W Owners Group Ongoing Programs & Activities & 850609 & 1226 Transients at Davis Besse & Rancho Seco,Respectively. Attendance List & Handout Incl
ML20195B4641986-03-15015 March 1986
Summary of ACRS Subcommittee on Davis Besse (Restart) 860206 Meeting in Washington,Dc Re Restart Activities Since 850609 Loss of Feedwater Event.Fr Notice,Agenda & List of Attendees 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
ML20138Q5501985-12-17017 December 1985
Summary of 851126 Meeting W/Util,Beta & Consolidated Controls Corp in Bethesda,Md Re Proposed Changes to Safety Features Actuation Sys.Viewgraphs & List of Attendees Encl
ML20138P8841985-12-17017 December 1985
Summary of 851209 Meeting W/Util in Bethesda,Md Re Status Rept on Course of Action.List of Meeting Attendees & Info Presented by Util Encl
ML20136E2921985-11-27027 November 1985
Summary of ACRS Subcommittee on Davis-Besse 851004 Meeting in Oak Harbor,Oh to Review Course of Action Prior to Facility Restart.List of Items Discussed at Meeting & List of Attendees & Handouts Encl
ML20137P7871985-11-21021 November 1985
Summary of 851016-17 Meetings W/Util & Impell Corp Re Licensee Auxiliary Feedwater Reliability Analyses.Viewgraphs & Proposed Outline of Reliability Analysis Rept Encl
ML20137Q3981985-11-21021 November 1985
Summary of 851104 Meeting W/Util,B&W & Essex Corp Re Auxiliary Feedwater Sys Mods & Changes.Viewgraphs & List of Attendees Encl
ML20137P7041985-11-20020 November 1985
Summary of 851009 Meeting W/Util,Science Applications Intl Corp & Essex Corp in Bethesda,Md Re Issues Identified in NRC Re Preimplementation Audit Findings in Late Apr 1985.Summary of Commitments Encl
ML20137P6401985-11-20020 November 1985
Summary of 851105 Meeting W/B&W Owners Group in Bethesda,Md Re Action Plan Developed in Response to Davis-Besse 850609 Loss of Feedwater Event.List of Attendees & Handouts Encl
ML20136E2491985-11-0707 November 1985
Proposed Summary of ACRS Subcommittee on Regulatory Policies & Practices 851101 Meeting in Washington,Dc to Discuss SECY-85-208, Incident Investigation Program & Process Used to Investigate 850609 Event at Facility
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
ML20138M4151985-10-17017 October 1985
Summary of 851004 Meeting W/B&W Owners Group Transient Assessment & Availability Committees in Bethesda,Md Re Operating Experience of Operating Reactors & Plans to Improve Experience.Viewgraphs Encl
ML20133F9941985-10-0707 October 1985
Summary of Operating Reactors Events Meeting 85-16 on 850916 Re Briefing of Director,Div Directors & Representatives on Events Occurring Since 850909 Meeting.List of Attendees & Viewgraphs Encl
ML20133E4631985-10-0101 October 1985
Summary of Operating Reactors Events Meeting 85-17 on 850923.List of Attendees & Viewgraphs Encl
ML20134K8521985-08-0808 August 1985
Summary of ACRS ECCS Subcommittee 850731 Meeting w/B&W,C-E & Westinghouse in Washington,Dc Re Review of 10CFR50.46 & App K,Implementation of GE App K Analysis Effort & 850609 Incident at Facility
ML20128K7491985-07-12012 July 1985
Summary of Operating Reactor Events Meeting 85-11 on 850701. List of Attendees,Events Discussed,Significant Elements of Events & Assignment of Followup Review Responsibility Encl
ML20127N9021985-06-24024 June 1985
Summary of Operating Reactors Events Meeting 85-10 on 850612.Only 3 of 17 Items Scheduled for Completion by 850531 Remain Incomplete.List of Attendees,Summary of Events Discussed & Status of Previous Assignments Encl
ML20155C9641984-08-0606 August 1984
Summary of 840612 Meeting W/Util in Bethesda,Md Re Program to Correct Fire Protection Deficiencies in Facility Fire Protection Features & non-compliance W/Respect to Requirements of App R to 10CFR50.Related Info Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
1999-06-29
[Table view] |
Text
December 2, i992 DISTRIBUTION Docket No. 50-346 Docket File OGC NRC & Local PDRs ACRS(10)
PD111-3 Reading JHannon LICENSEE: TOLEDO EDISON COMPANY TMurley/FMiraglia PKreutzer JPartlow JHopkins FAtiLITY: DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 JRoe EJordan TKing GGrant,EDO
SUBJECT:
SUMMARY
OF MEETING HELD ON NOVEMBER 19, 1992 RGN III.DPR TO DISCUSS CONTAINMENT PENETRATION BELLOWS LOCAL LEAR RATE TESTING (IN 92-20)
On November 19, 1992, NRC staff members met at Rockville, Maryland, with employees of Toledo Edison Company (TE) to discuss local leak rate testing of containment penetration bellows at the Davis-Besse Nuclear Power Station, Unit 1. A list of attendees is included as enclosure 1. The handout used at the meeting is included as enclosure 2.
Davis-Besse has four containment penetrations for the feedwater and steam lines that have bellows. The bellows sizes are 40 inches and 60 inches. TE plans to perform the next Type B local leak rate tests (LLRTS) of these penetrations in a manner to check that test pressure propagates through the entire length of the bellows. If the LLRT proves inadecuate, then TE might ask for an wsption based, in part, on their integratec leak rate test (ILRT) history. However, an ILRT is not planned to be performed during the upcoming refueling outage. The NRC staff asked what would be the radiation exposure if cne of the tests was performed at power instead of waiting for the refueling outage. The NRC staff also asked what would be the acceptance criteria for this method of testing and if helium would be used for the test. The staff encouraged the licensee to continue to work on this issue including contingency test approaches or penetration bellows replacement in case the LLRTs prove inadequate. TE stated that they will continue to work on the issue and that they would get back to the staff with the information requested.
original signed by Jon B. Hopkins, Sr. Project Manager Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ enclosure:
Seu next page ,
0FFICE PDill-3:LA:DRPW PDill-3:PM:DRPW PDill-3:Ph;$RPW NAME PKreutzer JBHopkins/jbh M JHannonh lDATE d / / /92'hI tb / \' /92 h / L /92 0FFICIAL RECORD g:\davisbes\dbil19.mts DOCUMENT NAME:
y, us -
4, ,4 ,, -
t 9212090060 921202 DR ADOCK0500g6 J
({l
~ . , _ _ . _ - - - _ -
a D111BJJWIJDif Docket No. 50-346 Docket filer 0GC NRC & Local PDRs ACRS(10)
PDill-3 Reading JHannon LICENSEE: TOLEDO EDIS0N COMPANY TMurley/FMiraglia PKreutzer JPartlow JHopkins FACILITY: DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 JRoe EJordan TKing GGrant,EDO .
SUBJECT:
SUMMARY
OF MEETING HELD ON NOVEMBER 19, 1992 RGN lil,DPR TO DISCUSS CONTAINMENT PENETRATION BELLOWS LOCAL LEAK RATE TESTING (IN 92-20)
On November 19, 1992, NRC staff members met at Rockville, Maryland, with employees of Toledo Edison Company (TE) to discuss local leak rate testing of containment penetration bellows at the Davis-Besse Nuclear Power Station, Unit 1. A list of attendees is included as enclosure 1. The handout used at the meeting is included as enclosure 2.
Davis-Besse has four containment penetrations for the feedwater and steam lines that have bellows. The bellows sizes are 40 inches and 60 inches. TE plans to perform the next Type B local leak rate tests (LLRTs) of these penetrations in a manner to check that test pressure propagates through the entire length of the bellows. If the LLRT proves inadequate, then TE might ask for an exemption based, in part, on their integrated leak rate test (ILRT) history. However, an ILRT is not planned to be performed during the upcoming refueling outage. The NRC staff asked what would be the radiation exposure if one of the tests was performed at power instead of waiting for the refueling outage. The NRC staff also asked what would be the acceptance criteria for this methr:i of testing and if helium would be used for the test. The staff encouraged the licensee to continue to work on this issue including contingency test approaches or penetration bellows replacement in case the LLRTs prove inadequate. TE stated that they will c.ontinue to work on the issue and that they would get back to the staff with the info'mation requested, original signed by Jon B. Hopkins, Sr. Project Manager Project Directorate 111-3 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ enclosure:
See next page OFFICE PDill-3:LA:DRPW PD!Il-3:PM:DRPW PDIII-3: Ph;/)RPW NAME PKreutzer JBHopkins/jbh 3M JHannon[
DATE -
/' /9; ^ #_ P-/\ /92 h//92 L OfflCIAL PFORD DOCUMENT NAME: g:\davisbes\dbil19.mts
pe ssog
+ It
,' ! ,, o UNITED STATES 3 NUCLEAR REGULATORY COMMISSION
. g ! WASHINoToN. D.C. 20E6
- % , , , , , M December 2. 1992 Docket No. 50-346 ,
LICENSEE: TOLEDO EDISON COMPANY FACILITY: DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1
SUBJECT:
SUMMARY
Of HEETING HELD ON NOVEMBER 19, 1992 TO DISCUSS CONTAINMENT PENETPATION BELLOWS LOCAL LEAK RATE TESTING (l;i 92-20)
On November 19, 1992, NRC staff members met at Rockville, Maryland, with employees of Toledo Edison Company (TE) to discuss local leak rate testing of containment penetration bellows at the Davis-Besse Nuclear Power Station, Unit 1. A list of attendees is included as enclosure 1. The handout used at the meeting is included as enclosure 2.
Davis-Besse has four containment penetrations for the feedwater and steam lines that have bellows. The bellows sizra are 40 inches and 60 inches. TE plans to perform the next Type B local leak rate tests (LLRTs) of these penetrations in a manner to check that test pressure propagates through the entire length of the bellows. If the LLRT proves inadequate, then TE might ask for an exemption based, in part, on their integrated leak rate test (ILRT) history. However, an ILRT is not planned to be performed during the upcoming refueling outage. The NRC staff asked what would be the radiation exposure if one of the tests was performed at power instead of waiting for the refueling outage. The NRC staff also asked what would be the acceptance criteria for this method of testing and if helium would be used for the test. Thu staff encouraged the licensee to continue to work on this issue including contingency test approaches or penetration bellows replacement in case the LLRTs prove inadequate. TE stated that they will continue to work on the issue and that they would get back to the staff with the information requested.
37 '
f Jon B. Hopkins, Sr, Project Manager Project Directorate 111-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ enclosure:
See next page l
A F
Hr. Donald C. Shelton Davis-Besse Nuclear Power Station Toledo Edison Company Unit No. I cc:
Mary E. O'Reilly Centerior Energy Corporation Radiological Health Program 300 Madison Avenue Ohio Department of Health Toledo, Ohio 43652 Post Office Box 118 Columbus, Ohio 43266-0149 Mr. Robert W. Schrauder Attorney General .
Manager, Nuclear Licensing Department of Attorney Toledo Edison Company General 300 Madison Avenue 30 East Broad Street Toledo, Ohio 43652 Columbus, Ohio 43215 Mr. James W. Harris, Director Gerald Charnoff, Esq. Division of Power Generation Shaw, Pittman, Potts Ohio Department of Industrial Regulations and Trowbridge P. O. Box 825 2300 N Street, N.W. Columbus, Ohio 43216 Washington, D.C. 20037 Regional Administrator, Region 111 Ohio Environmental Protection Agency U.S. Nuclear Regulatory Commission DERR--Compliance Unit 199 Roosevelt Road ATTN: Zack A. Clayton Glen Ellyn, Illinois 60137 P. O. Box 1049 Columbus, Ohio 43266-0149 Mr. Robert B. Borsum Babcock & Wilcox President, Board of Ottawa Nuclear Power Generation Division County Commissioners 1700 Rockville Pike, Suite 525 Port Clinton, Ohio 43452 Rockville, MD 20852 Resident inspector State of Ohio V. S. Nuclear Regulatory Commission Public Utilities Commission 5503 N. State Route 2 180 East Broad Street Oak Harbor, Ohio 43449 Columbus, Ohio 43266-0573 Mr. Hurray R. Edelman Mr.-James R. Williams Executive Vice President - State Liaison to the NRC Power Generation Adjutant General's Department Centerior Service Company Office of Emergency Management Agency 6200 Oak Tree Boulevard 2825 West Granville Road Independence, Ohio 44101 Columbus, Ohio 43235-2712 l
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., Enclosure 1 l ATTENDEES November 19, 1992 NAME Q8GANIZATION ,
J. Hopkins NRC P. Smith TE E. Caba . TE -
J. Hannon NRC J. Kudrick NRC J. Pulsipher NRC H. Schreiber TE J. Barron TE L
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1 Pnclosure 2 l To eco Ecison V ee':ing wi: 1 h 9C on Javis-3 esse Resconse to In'ormation No': ice 92-20 Con':ainment Pene':ra': ion Be ows
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Purpose Present Toledo Edison's actions to address -
IN 92-20 for Davis-Besse Actions taken to date Planned actions considering Refueling Outage Schedule and Accessibility Resources Pot':ntial Need for any Regulatory Action l
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BACKGROUND IN 92-20 identifies containment below LLRT problems at Quad Cities (March 1992) lack of flow path between plies of bellows Davis-Besse also has Pathway bellows (later design tMn Quad Cities)
Same LLRT test method LLRT required during 8RFO (non-ILRT outage)
No bellows integrity problem based on-five past ILRTs 6.N i
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I BACKGROUND Davis-Besse Orientation
- Large steel containment with Shield Building (one of nine operating plants)
- Emergency Ventilation System
- No unfiltered leakage path from bellows
- Limited access except during refueling outages
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CENTE R AC-~ O NS ~~AKE N TO DATE Parallel Paths Validation of Current Test Method Consider Modifications / Alternative Tests Simple alternative tests complicated by
- non-concentric configurations
- high Pa (eliminates inflatable seal) 7 Bids - all cumbersome modifications
- repetitive costs Surveyed other utilities (different situations)
Modifications currently last resort
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8RFO Validate Current Test Method
- demonstrate gap in existing bellows ;
> bellows design
> installed configuration ,
- If successful, accept current method as valid 9
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9RFO { Contingent}
lLRT outage Investigate / Develop Alternative Test Methods
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'%annu REGU _ATORY IMPLICATIONS Type B LLRT Exemption
- 8RFO if test validation questionable
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