Letter Sequence Meeting |
|---|
|
|
MONTHYEARML20056E2051993-08-0303 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
Project stage: Meeting
ML20071H9321994-07-14014 July 1994
Updates Toed Response to NRC After Taking Into Consideration Recent Evaluations of Other B&W-type Plants Re GL 90-06 Re Resolution of Generic Issue 70.Withdraws Toed 940330 Application for License Amend
Project stage: Request
1993-08-03
[Table View] |
|
|---|
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
,
August 3, 1993
. Docket No. 50-346 LICENSEE: TOLED0 EDISON COMPANY FACILITY: DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1
SUBJECT:
SUMMARY
OF MEETING HELD ON JULY 29, 1993, TO DISCUSS GL 90-06 RESPONSE (TAC NO. M77346)
On July 29, 1993, NRC staff members met at Rockville, Maryland, with employees of Toledo Edison Company (TE) to discuss TE's response to Generic Letter (GL) 90-06 regarding Technical Specifications (TS) for the power-operated relief valve (PORV). A list of attendees is included as enclosure I. The handout used at the meeting is included as enclosure 2.
During the discussion, the NRC staff stated and TE agreed that the overall use of PORVs is not restricted to design basis events. The majority of the discussion was focused on feed and bleed cooling, and on GL 90-06, Item 3.1.3 action statements. The NRC staff questioned TE regarding the possible hardship of specifying power to the PORV block valve in the TS. Also, the staff stated that it would consider a greater amount of time (for example, 24 or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) for Davis-Besse to deal with an inoperable PORV due to causes other than excessive seat leakage or to deal with an inoperable block valve, based on their design. Finally, the NRC staff stated that it desired to close this issue expeditiously and would be prepared to promptly hold a management meeting, if necessary. TE stated that they would consider the NRC staff comments and get back verbally to the staff within one week.
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:
- 1. List of Attendees DISTRIBUTION:
- 2. Meeting Handout Docket File EJordan OGC NRC & Local PDRs MVirgilio Region III, DRP cc w/ enclosures: PDIII-3 Reading RJones PDIII-3 Gray See next page TMurley/FMiraglia MCaruso JPartlow Llois JRoe CTrammell JZwolinski TDunning JHannon LRaghavan MRushbrook ACRS (10)
JHopkins AGody,Jr., EDO 0FFICE PDIII-3:LA:DRPW PDIII-3:PM:DRPW PDIII-3:PD:DRPW NAME M k k ok JBHopkins/jbh/bj JHannon D rt DATE 9 ) b/93 ['/5/93 M 8 / 3/93 0FFICIAL RECORD DOCUMENT NAME: g:davisbes\dbO729.mts h O(
ggg 9308200258 930803 PDR ADOCK 05000346 P PDR
, g"c w y
? UNITED STATES
((lk1[tjy f.
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2(6 5 0001
'....." August 3, 1993 t
Docket No. 50-346 ,
LICENSEE: TOLED0 EDIS0N COMPANY FACILITY: DAVIS-BESSE NUCLEAR POWER STATION, UNIT I
SUBJECT:
SUMMARY
OF MEETING HELD ON JULY 29, 1993, TO DISCUSS GL 90-06 RESPONSE (TAC NO. M77346)
On July 29, 1993, NRC staff members met at Rockville, Maryland, with employees of Toledo Edison Company (TE) to discuss TE's response to Generic Letter (GL) 90-06 regarding Technical Specifications (TS) for the power-operated relief valve (PORV). A list of attendees is included as enclosure I. The handout used at the meeting is included as enclosure 2.
During the discussion, the NRC staff stated and TE agreed that the overall use of PORVs is not restricted to design basis events. The majority of the discussion was focused on feed and bleed cooling, and on GL 90-06, Item 3.1.3 action statements. The NRC staff questioned TE regarding the possible hardship of specifying power to the PORV block valve in the TS. Also, the staff stated that it would consider a greater amount of time (for example, 24 or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) for Davis-Besse to deal with an inoperable PORV due to causes other than excessive seat leakage or to deal with an inoperable block valve, based on their design. Finally, the NRC staff stated that it desired to close this issue expeditiously and would be prepared to promptly hold a management i meeting, if necessary. TE stated that they would consider the NRC staff comments and get back verbally to the staff within one week.
' ~
~
7 j)l O. //j>i w
/onB.Hopkins,kr.ProjectManager J
Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation '
Enclosures:
- 1. List of Attendees
- 2. Meeting Handout cc w/ enclosures: ,
See next page .
I i
-~ - --.
. 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 ;
i 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 i 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 III Ohio Environmental Protection Agency '
U.S. Nuclear Regulatory Commission DERR--Compliance Unit 799 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 U. 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. Murray 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 Mr. Louis F. Storz, Vice President Nuclear - Davis-Besse Ce'terior Service Company c/o Toledo Edison Company 300 Madison Avenue Toledo, Ohio 43652
Enclosure 1 i r
i ATTENDEES OF JULY 29, 1993 j i
MEETING WITH TOLED0 EDISON COMPANY !
NAME ORGANIZAlION J. Hopkins NRC f M. Virgilio NRC l R. Jones NRC l M. Caruso NRC i L. Lois NRC !
C. Trammell NRC 3 T. Dunning NRC !
L. Raghavan NRC R. Croteau NRC :
D. Wuokko TE i A. Zarkesh TE R. Seba TE 3 A. Stollard TE i
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, Enclosure 2 i l
1 TOLEDO EDISON -
NRC MEETING i
l GENERIC LETTER 90-06 i PORV & BLOCK VALVE I
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i NRC Headquarters
July 29,1993 l i
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GENERIC LEITER 90-06 1
Resolution of:
. GI 70, Power-Operated Relief Valve and Block Valve Reliability, and GI 94, Additional Low-Temperature Overpressure Protection for Light-Water Reactors l
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MEETING OBJECTIVES Discuss Requirements of NRC Generic Letter 90-06 Discuss how Toledo Edison Meets the Generic Letter Discuss Justification for Variances from Generic Letter f
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Generic Letter 90-06, Requirement 3.1.1 !
3.1.1. Include PORV & Block Valve in Appendix B !
- a. Add PORV & Block Valve to QA List PORY & Block Valve Maintained in QA Program .
- b. Implement Maintenance Program for PORV & Block Valve ;
Maintenance Programs Based on Manufacturer !
Recommendations i
- c. Replacement Parts Procured with Original Standards !
Replacement Parts Procured with Original Standards I 4
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i Generic Letter 90-06, Requirement 3.1.2 3.1.2. Include PORV & Block Valve in IST Program Include PORV & Block Valve in IST Included in 10-year Internal Pump & Valve Testing Program .
Stroke Testing in Mode 3 or 4 PORY Cycled in Mode 3 During Cooldown or Heatupfrom Mode 5 if not Cycled within Previous 3 Months :
Stroke Testing Performed in Mode 5 Because it Requires a {
Timed Pressure Drop which could lead to an RCS Pressure '
Transient & Generation ofRadioactive Waste
. Successful EPRI Reliability Testing ofDBNPS Style PORV '
PORY not usedfor LTOP at DBNPS Include Block Valve in GL 89-10 MOV Testing Block Valve included in GL 89-10 Program ;
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l Generic Letter Safety Functions i
Mitigation of Design-Basis Steam Generator Tube Ruptures t Low-Temperature Overpressure Reactor Vessel Protection During Startup and Shutdown Plant Cooldown in Compliance with Branch Technical Position RSB 5-1 ,
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Steam Generator Tube Ruptures Design Basis Analysis (USAR) does not Credit PORV:
Initial RCS Depressurization via Affected Steam Generator Steaming Subsequent RCS Depressurization via Turbine Bypass Valves ,
All Isotopic Activities to Affected Steam Generator Assumed Directly Released to Environment 4
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Steam Generator Tube Ruptures (Continued) t Plant Emergency Procedure Guidance:
. Initial RCS Depressurization via Turbine Bypass Valves or Atmospheric Vent Valves
. Subsequent RCS Depressurization:
t Pressurizer Spray Utilized & Heaters Turned Off(RCPs Available) l Pressurizer Vent Line Utilized & Heaters Turned Off(RCPs Unavailable)
PORV Utilized & Heaters Turned Off(RCPs Unavailable)
. PORV Utilized as Backup to Pressurizer Vent Line a
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l Low-Temperature Overpressure Protection -
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B&W Plants Excluded from Generic Issue 94 i i
Davis-Besse LTOP Protection Provided by Decay Heat Removal -!
System Dropline Relief Valve (DH4849) !
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Plant Cooldown in Compliance with BTP RSB 5-1 (SRP 5.4.7) i Davis-Besse Licensed Prior to Issuance of SRP Natural Circulation Procedural Guidance:
. Prefer Maintaining Hot Standby (Mode 3) Until RCPs are Available
. Turbine Bypass Valves or Atmospheric Valves Utilized to Establish Cooldown Rate RCS Pressure Control via Pressurizer Heaters & Pressurizer Vent Line
. PORV Operation not Specified - Available as Backup i
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Feed & Bleed Cooling (Beyond Design Basis) ,
Makeup System Upgraded Feed & Bleed Cooling Capability Minimum Equipment Requirements: ;
Two Makeup Pumps & RCS Pressurizer Code Safety Valves, or s
One Makeup Pump 'piggybacked' with a Low Pressure Injection Pump
& RCS Pressurizer Code Safety Valves & the PORV Feed & Bleed Cooling not Lost on Failure of one Makeup Pump or ;
die PORV
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l Generic Letter 90-06, Requirement 3.1.3 !
t 3.1.3. Modify PORV & Block Valve TS LCOs to Incorporate )
Staff Position i
Action Statement 3.4.4.a ;
With the PORV inoperable because of excessive seat leakage, within I hour either restore the PORV to Operable status or close the associated block valve :
with power maintained to the block valve; otherwise, be in at least HOT !
STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
. If the PORV Block Valve was Closed due to PORV Leakage, a ;
Second Pressurizer Vent Path Remains Availablefor SGTRs and ;
Natural Circulation Cooldowns - Pressurizer Vent Line i (RC239A & RC200) ;
. DBNPS TS does not Require Power be Reinovedfrom Block Valve l
. DBNPS has 3 RCS Vent Paths which can be used to Restore Natural Circulation Following a SBLOCA or to Enable Cooldown Following an ICC Event
. DBNPS TS Requires all 3 Vent Paths be Operable in Modes 1 - '
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. Feed & Bleed Cooling does not Require PORV
l Generic Letter 90-06, Requirement 3.1.3 (Continued) :
Action Statement 3.4.4.b With the PORV inoperable due to causes other than excessive seat leakage, within I hour either restore the PORV to Operable status or close the associated block valve and remove power from the block valve; and be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> In addition to the Justification Provided in Action Statement a above: ;
DBNPS TS Require Isolation or Initiation ofPlant Shutdown if '
the PORVis Inoperable i
. No Credit is taken in DBNPS Design-Basisfor the PORY & ;
PORV Block Valvefor RCS Depressurization during a SGTR l
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Generic Letter 90-06, Requirement 3.1.3 (Continued) l 1
i Action Statement 3.4.4.c With the block valve inoperable, within I hour restore the block valve to !
Operable status or place the associated PORV in manual control and restore ;
the block valve to Operable status within the next hour; otherwise, be in HOT i STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the j following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> In addition to the Justification Provided in Action Statements a & l b above: '
. DBNPS is Processing a Procedure Change Request to i Require Removing Powerfrom the PORV if the Block Valve can not be Closed i
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1 Generic Letter 90-06, Requirement 3.1.3 (Continued) -
Surveillance Requirement 4.4.4. l.a The PORV shall be demonstrated Operable at least once per 18 months by i operating the PORV through one complete cycle of full travel during Modes 3 i or 4 l DBNPS PORV is Cycled Through Full Travel in Mode 3 During '
a Cooldown or Subsequent Heatupfrom Mode 5 ifit has not i been Cycled within the Previous Three Months ;
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Surveillance Requimment 4.4.4.1.b !
The PORV shall be demonstrated Operable at least once per 18 months by Performing a Channel Calibration of the Actuation Instrumentation This Requirement is Already included in DBNPS TS; a Channel Calibration Check is Required to be Performed Every 18 )
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Generic Letter 90-06, Requirement 3.1.3 (Continued)
Surveillance Requirement 4.4.4.2 The block valve shall be demonstrated Operable at least once per 92 days by j operating the valve through one complete cycle of full travel unless the block valve is closed in order to meet the requirements of Action b in Specification <
3.4.4
. This Requirement is Already included in DBNPS TS; TS 4.0.5 -
, Requires the Block Valve to be Cycled Every 92 Days (IST)
- Surveillance Requirement 4.4.4.3 The emergency power supply for the PORV and block valve shall be demonstrated Operable at least once per 18 months by:
- a. Manually transferring motive and control power form the normal ,
4 to the emergency power bus, and ,
- b. Operating the valve through a complete cycle of full travel j
. The Normal Power Suppliesfor the PORV and Block Valve are Already Class 1E Essential Power Supplies e
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l DBNPS PSA/IPE PSA/IPE Credited Feed & Bleed Cooling
. DBNPS has 2 MFPs,2 AFPs & a MDFP
. PORV not Required for Feed & Bleed l
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. Pressurizer Safety Valves can be used for Feed & Bleed l PSA/IPE Credited PORV in SGTR Sequences 1
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. Only 1% of DBNPS Core-Damage Frequency due to SGTR l Sequences 1
. PORV Failures / Unavailability were not Important in SGTR Sequences PORV is not an Important Contributor to Risk for DBNPS 1 i l
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Conclusions !
DBNPS PORV & Block Valve are included in:
. QA Program
. Plant Maintenance Program
. IST Program DBNPS PORV is not Credited in SGTR USAR Analysis, Proceduraly, PORV Only Used as Backup to Pressurizer Vent Line DBNPS does not use PORV for LTOP ;
PORV is not Required for:
. Feed & Bleed
. Natural Circulation ;
l PORV is not an Important Contributor to Risk for DBNPS !
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