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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
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
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
, . _ _ , _. - _ _ _ . _ __ _ .
, Eo g
. MINLTTES OF ME 2162 ACRS MEETING APRIL 6-7r 1978 V. Meeting with the NRC Staff on Recent Operating Experience, Licensing Actions, Generic Matters Relating to IMRs and Future Agenda (Open to Public)
[ Note Romas G. McCreless was the Designated Federal' Employee for.
this portion of the meeting.]
A. Davis-Besse-1: Implementation of ACRS Recommendations from the ACRS Report of January 14,-1977 i
L. B. Engle, NRC Staff, discussed the inglenentation of the '
l ACRS recommendations ircluded in the Committee'ai report of January
.14, 1977. (For background,'see Appendix XXVI.) He said that the purpose of this report is to update the Ccamittee to the current status. He noted that Supplement No.1 to the SER was issued on April 22,1977, the same date that an OL was issued for Davis-Besse, Unit 1. Although the OL was issued authorizing' full power, 960 MNe, the operetion of the facility was restricted to a sequence of operational modes . until preoperational test, startup test, and other items were completed to the satisfaction of the .
. .NRC Staff. h is OL stipulated 19 conditions that imposed limita '
tions on plant operations, and required special reports and/or modifications to be completed at specific times following the date of the issuance of the license. -Since the issuance of the' license, 6 conditions to the license have been removed by amendments, supported by SERs, and 2 conditions have been revised.
%e reactor attained criticality on August 12, 1977, initial i electricity was produced on August 23, and 75% of full power was attained on January 23, 1978. A reactor power of 90% was obtained for 2 days on February 15 and 16, 1977. However, condenser prob-
-lems required the Licensee to reduce operating power to 75%, until
-April 3, when power was increased. 100% of rated power was reached on April 4. Based on recommendations by Babcock and Wiloox (B&W),
the NSSS vendor, on April 5 the Licensee reduced plant operation to 3 pumps to reduce flow and is currently oprating at about 75%
of full rated power. Rwis-Besse has burnable poison rod assemb-lies, and is therefore affected by the failure of one of these assemblies in the Crystal River Plant. Se cumulative service factor has been about 75f and the unit forced-outage rate has been about 25%. ne shuviowns were required for repairing 'and servicing equipment primarily in the secondary system. The first scheduled refueling' outage is planned for late 1979.
In answer to a question, L. B. Engle said .that the condenser problems to which he referred involved some tube ' leaks. It has not yet been determined whether these leaks are from flow-induced vibration as a function of power. Tubes will.be inspected during a planned. outage.
24 f 781120069 a .
,,.s ,ww.. < .--wwm me ,,--an -,m,> ,-~ w ,-m -,n- e. -ee n .---e-- , wm er - w,- -,,e - mww ,, m <-n,- -mm n *- t-
e s.
I MINUTES OF THE 216TH ACRS MEETING '
APRIL 6-7, 1978 L. B. Engle reviewed the items raised in the Committee's January 14, 1977 report e Increase of seismic design basis from 0.15g to 0.2g. The NRC Staff stipulated in the operating license that the Licen-see shall submit a seismic reanalysis and evaluation to the l NRC for its review in sufficient time to obtain Commission l approval of the adequacy of the plant systems needed to l accomplish safe shutdown of the plant and continued shutdown heat renoval prior to startup following the first regularly scheduled refueling outage. In performing the reanalysis, a safe shutdown earthquake of 0.2g shall be applied at the foundation level of the plant, and the response spectra shall be as specified in Reg. Guide 1.60. The NRC Staff is in the process of developing guidelines for this seismic reanalysis.
e ECCS. The NRC Staff has reviewed revised nucleate boilirg logic proposed by B&W, which does not allow return to nucle-ate boiling after critical heat flux conditions are reached.
The NRC Staff has determined that the revised logic was an appropriate change to be incorporated in the B&W evaluation model, that the overall effect of the change on peak clad c temperature was insignificant, and that it met the Acceptance Criteria. The Applicant has submitted additional analyses correcting for fuel pin pressure errors and erroneous flow resistance values for the reactor vessel inlet nozzle. The NRC Staff has determined that the ECCS analysis for Davis-Besse, Unit 1, is in accordance with Appendix K.
e Large Break Analysis. The operating license stipulated that, within six months from its issuance, the Licensee shall provide additional supporting analysis for the large break spectrum to document the exact margins, and should provide to the NRC Staff reactor coolant system flow data. The Licensee subnitted the large-break spectrum oni October 21, but, be-cause of delays in plant operation, the coolant system flow data were not available. The license condition was revised to require that within 30 days following 2 weeks of sustained reactor power operation at a power level of 90% or greater of rated thermal power, the Licensee provide operating reactor l system coolant flow data. However, during the 2 days that l the plant was at 90% rated thermal power, the Licensee was able to obtain the system flow data, and is getting ready to j subnit the information to the NRC Staff by mid-April.
25 l
i
MINUTES OF THE 216TH ACRS MEL'rItG APRIb6-7,1978
- e Improved Radiation Surveillance in Ohio. The State of Ohio f has indicated to the NRC Staff that it is initiating a pro-gram which will eventually qualify for an NRC state contract for technical aid, e Iong Term Capability of Hermetic Seals. Environmental quali-fication of equipment is being pursued by the NRC Staff as part of a Category A generic activity, Task Action Plan A-24, Qualification of Class IE Safety-Related Equipment, to assure proper performance of seal materials during plant operation.
e Instrumentation to Folica the Course of an Accident. The NRC Staff has issued Regulatory Guide ~ 1.97 (Rev.1), and a technical activities steering committee was established on August 22, 1977. The NRC Staff has concluded that the instrumentation to monitor post-accident conditions met the NRC Staff criteria and was acceptable. However, Davis-Besse 1 does not meet Position C.3 of Regulatory Guide 1.97, Revision 1, and guidance is being developed in this area.
e AWS. This is a generic matter. The NRC Staff has prepared a draft generic technical report on AtiS which incorporatas the comments and concerns of the industry, including the ,
Babcock and Wilcox Company. This draft report is currently being reviewed by NRC management and the NRC Staff. An open meeting will be held on April 19, 1977, to discuss the stud-ies concerning ABiS.
e Fire Protection. The Licensee has submitted its fire hazard analysis report, and the NRC Staff has determined that the report was not adequate for determining the fire protec-tion program in accordance with Appendix A to the Branch Technical Position. Therefore, a condition was placed on the license, stipulating that within three years from the date of issuance of the license, the Licensee shall increase the level of fire protection in the facility to the levels recom-mended in Appendix A, or with alternatives acceptable to the NRC Staff. Prior to startup following a first regularly scheduled refueling outage, the Licensee shall implement Section B of Appendix A, Admiristrative Procedures, ' Controls, and F.4.re Brigade, and Section C of Appendix A, Quality Assuranco Program. Since the issuance of the OL, the reevalu-ation of the fire protection program has continued. The Licensee has presented additional information on the installa-tion of fire retardant seals for electric penetrations. The 26
MINtJTES OF THE 216TH ACRS MEETING ,
APRn,6-7,1978 NRC Staff has concluded that these seals through fire barri-ers as installed at Davis-Besse are conditionally acceptable.
However, the NRC Staff has required that the Licensee perform certain full-scale testing to verify the adequacy of the configuration and installation of the seals that represented the worst-case departure from sections originally tested under the ANSI E119 standard. The NRC Staff is scheduled to complete the Davis Besse Unit 1 fire protection review before the end of of calendar year 1978.
e Industrial Security. The NRC Staff has reviewed the Licen-see's amended security plan as required by NCFR 5073.55, and completed their Phase 1 review in September of 1977. The Licensee has subnitted a modified security plan. This plan is being evaluated.
i h
6 27
.
