|
|---|
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
_
m -
j .
Novtmb::r 21, 1985 h [
Docket No. 50-346 LICENSEE: Toledo Edison Company FACILITY: Davis-Besse Unit No. 1
SUBJECT:
AUXILIARY FEEDWATER (AFW) SYSTEM MODIFICATIONS AND CHANGES MEETING, NOVEMBER 4, 1985 Introduction We met with the licensee to discuss changes which are being incorporated in the AFW system to improve reliability. Copies of.the view graphs are provided as Enclosure 1. The meeting attendees are listed in Enclosure 2.
This was a follow-on meeting to those held on September 25, 1985 and October 16 & 17, 1985.
Discussion The licensee presented a summary of the changes being implemented on AFW and the steam and feedwater rupture control system (SFRCS). Based on the licensee's safety evaluation, all of the changes can be conducted under 10 CFR 50.59. For each change being implemented the licensee presented a summary of their safety evaluation results and a list of the benefits to be gained by implementing the results.
In response to staff concerns expressed in NUREG-1154 about single active failure, the licensee has re-analyzed the main steam line break. The licensee's new analysis shows that SFRCS low pressure initiation during a main steam line break would not have resulted in isolation of AFW from both steam generators.
Some detailed staff comments were provided on fault tree construction and unavailability analyses which had been presented to the staff during the October 16 and 17 reliability meeting.
The licensee committed to provide docketed information on November 8,1985 to support:
- 1. AFW and SFRCS changes under 50.59; I
- 2. Their determination that a single active failure vulnerability did not exist on June 9,1985; and
- 3. Results of the AFW Reliability Analyses. .
l Conrad McCracken l Operating Reactors Branch #4 Division of Licensing
Enclosures:
As Stated cc w/ enclosures:
See next page -
ORB #4:DL 8512050265 PDR ADOCK h oo$346 PDR P
CMcCrack ic 11/g/85 r - -
w - a - -. ,,
s - -
.. e
, ENCLOSURE 1 AGENDA o INTRODUCTION o EVALUATION APPROACH o SYSTEM CONCERNS RELATED TO MODIFICATIONS l
, o AUXILIARY FEEDWATER SYSTEM CHANGES !
l o MOTOR DRIVEN FEEDWATER PUMP o STEAM FEEDWATER RUPTURE CONTROL SYSTEM (SFRCS) CHANGES o
SUMMARY
AND CONCLUSIONS 9
9 AFW/SFRCS Change Identification and Review Process
~
i i TED Event l g
Investigatien 3 7 Conceptural System Review
& Engineering Program-m Independent SM,g,Review r (Proposed r Pr6 cess Review Changes)
Gmup Decay Heat Removal Task J L 3 7 Force A A CNR8 Review
' SR8 Review '
Detailed Engineering &
1Y w 7
esign i
i - - - _ _ _ _ - - _ _ _ _ _ _ _ - _ _ _ _ - _ . _ _ _ _ _ .
RESTART MODIFICATIONS TECHNICAL REVIEW l SAFETY REVIEW GROUP o FORMED TO REVIEW SAFETY EVALUATIONS /10 CFR 50.59 ASSOCIATED WITH THE MODIFICATIONS AS OUTLINED IN THE TOLEDO EDISON COURSE OF ACTION DOCUMENT o BROAD MEMBERSHIP WITH EXPERTISE IN:
ENGINEERING DESIGN OPERATIONS LICENSING o EXPERIENCED PERSONNEL FROM:
TOLEDO EDISON BABCOCK & WILCOX BECHTEL CYGNA o
A SYSTEMATIC GUIDELINE UTILIZED TO ENSURE COMPLETENESS AND CONSISTENCY a
RESULTS OF REVIEW DOCUMENTED FOR TRACEABILITY 5
CRITERIA FOR TECHNICAL REVIEW o CAPABILITY OF THE PLANT SHUTDOWN o RADIOLOGICAL HEALTH AND SAFETY OF PLANT PERSONNEL o RADIOLOGICAL RELEASE / SITE BOUNDARY DOSE o OTHER SAFETY RELATED SYSTEMS AFFECTED o ENVIRONMENTAL QUALIFICATION o ELECTRICAL SEPARATION / ISOLATION CRITERIA ,
o MARGIN OF SAFETY OR TECHNICAL SPECIFICATION LIMITS o SAR SINGLE FAILURE ASSUMPTIONS o SYSTEM RELIABILITY AND TESTABILITY l o HAZARDS HIGH AND MODERATE ENERGY LINE BREAKS SEISMIC EFFECTS WIND / TORNADO EXTERNAL FLOODING MISSILE PROTECTION HEAVY LOADS SECURITY HAZARDOUS MATERIALS ~
AFW MODIFICATION l
HISTORICAL CONCERNS CORRECTIVE ACTIONS o GOVERNOR FAILURES DUE TO - REPLACE WOODWARD PG-GL :
MECHANICAL BINDING AND GOVERNOR WITH A WOODWARD CLUTCH FAILURE PGG MODEL o STRUCTURAL DAMAGE DUE - INSTALL ONE AIR-OPERATED
~
TO STEAM CONDENSATION VALVE IN THE STEAM IN TURBINE STEAM SUPPLY LINE NEAR EACH SUPPLY PIPING AFPT o LOW RELIABILITY OF MOTOR - REPOSITION THE AFW DIS-OPERATED VALVES CHARGE VALVES TO l
NORMALLY OPEN
- REMOVE POWER FROM THE AFP SUCTION VALVES FROM CST I
o SPURIOUS SUCTION
~
- INCREASE MESH SIZE OF THE TRANSFER TO S. W.
CST DISCHARGE STRAINER TO AFP
- ELIMINATE BASKETS FROM THE AFP SUCTION STRAINERS
- REVISE SUCTION TRANSFER LOGIC TO MINIMlZE SPURIOUS TRANSFER TO S.W.
o THE NEED FOR A
- INSTALL A NEW 800 GPM DIVERSE PUMP MOTOR DRIVEN FEED PUMP
, - _ _ _ . . , . _ , . - , _ _ . -_. - _ _ _ . _ , _ . _ - _ , , . _ _ . ,-,_._._,,,,__-_,._-__--p_,,,,,_,-,,._.,,_,,_.%__ ,_,__,_ , , - . _ %,,.-,_ _,,.
, AFW MODIFICATION CONCERNS RELATED TO JUNE 9 CORRECTIVE ACTIONS
- TURBINE OVERSPEED TRIPS - INSTALL ONE AIR-OPERATED DUE TO STEAM CONDENSATION VALVE IN THE STEAM IN TURBINE STEAM SUPPLY SUPPLY LINE NEAR EACH PIPING AFPT
- PERFORMANCE OF THE - RESET THE TORQUE SWITCH MOTOR OPERATED VALVES SETTINGS
- RESET THE LIMIT SWITCH SETTINGS 6
- - - --.--- - . ~ - . - _ _ . ~ . - . . _ - - - - , . , . - . . _ _ - _ - - - - . _ , . . , - - - - . . . . _ . - - - . .
SFRCS MODIFICATION HISTORICAL CONCERN CORRECTIVE ACTION o- SFRCS POWER - PROVIDE FANS TO THE SUPPLY FAILURES SFRCS CABINETS CONCERNS RELATED TO JUNE 9 CORRECTIVE ACTIONS o SPURIOUS SFRCS - ADJUST DAMPING OF ACTUATION THE EXISTING FILTER o SFRCS LOGIC - REMOVE MAIN STEAM AND MAIN FEEDWATER ISOLATION ON SG
~ LOW LEVEL
- DISABLE FEED ISOLATION TO LAST STEAM GENERATOR DEPRESSURIZED
- REARRANGEMENT OF SFRCS MANUAL ACTUATION SWITCHES
._. _ , , , _ , . _ , - - . _ ,----n,. --
STRAINERS IN THE AFP SUCTION LINES l
l DESCRIPTION OF CHANGE _ _
- REPLACING THE STRAINER IN THE COMMON SUCTION LINES FROM THE CST WITH A STRAINER OF COARSER MESH
- REMOVING THE STRAINER BASKETS FROM THE INDIVIDUAL AFP SUCTION LINES BENEFITS GAINED
- MINIMlZES SPURIOUS TRANSFER TO THE SERVICE WATER
- MINIMlZES THE POTENTIAL FOR UNNECESSARlLY INTRODUCING LOWER QUALITY SERVICE WATER TO THE S/G
- MINIMlZE COMMON MODE FAILURE EVALUATION RESULTS :
- NO LICENSING CRITERIA AFFECTED l - LARGER PARTICLES NOT AFFECT COMPONENT PERFORMANCE i
l
. _ _ _ _ _ _ --. - - - . . - - - - - . - - - - - - - - - - - - - - ~ - - - - - - - - - - - ~ - - - - - - ~ ~ " ~ - ~ ~ ' ' ~ ~ ~ ~ ~ ~ ' ' ~ ~
AUXILIARY FEED POMP SUCTION DESCRIPTIONS OF CHANGE SUCTION TRANSFER:
REVISES THE AFP SUCTION PRESSURE SWITCH SETPOINT ADDS A TIME DELAY TO THE REVISED SET POINT SUCTION TRIP:
CHANGES THE TIME DELAY FOR CLOSING THE STEAM SUPPLY VALVES TO THE AFPTS 1
BENEFITS GAINED MINIMlZES SPURIOUS TRANSFER TO LOWER QUALITY SERVICE WATER MINIMlZES UNNECESSARY TRIPS OF THE AFP'S RESULTS NO LICENSING CRITERIA AFFECTED ,
AFPT'S GOVERNOR' MODIFICATION DESCRIPTION OF CHANGE INSTALLATION OF WOODWARD MODEL PGG GOVERNOR ON AFPT # 1 DECREASING THE HIGH SPEED STOP RAISING THE LOW SPEED SETTING BENEFITS GAINED INCREASE AFWS RELIABILITY IMPROVES STATION BLACKOUT RELIABILITY (SELF COOLED GOVERNOR)
ENHANCE TURBINE ACCELERATION TO RATED SPEED IMPROVES S / G LEVEL CONTROL FOLLOWING SFRCS l
ACTUATION (S / G) WATER LEVEL UNDERSHOOT)
EVALUATION RESULTS NO LICENSING CRITERIA AFFECTED
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MODIFICATIONS TO THE MOV'S ASSOCIATED WITH THE AFWS DESCRIPTION OF CHANGE REPOSITIONS THE AFP DISCHARGE VALVES TO NORMALLY OPEN l
LOCKS THE HANDWHEELS AND LOCAL STATIONS OF DISCHARGE VALVES IN THE OPEN POSITION REMOVES POWER FROM THE AFP SUCTION VALVES FROM CST RESETS TORQUE AND LIMIT SWITCH SETTINGS BENEFITS GAINED IMPROVES AFWS RELIABILITY IMPROVES MOV'S RELIABILITY RESOLVES A FIRE PROTECTION COMPLIANCE ITEM RESULTS TESTING METHOD REVISED SO TESTABILITY NOT IMPACTED NO LICENSING CRITERIA AFFECTED
AFPT STEAM ADMISSION VALVES DESCRIPTION OF CHANGE INSTALLS NEW AIR-OPERATED, DC POWERED STEAM ADMISSION VALVES ON THE AFPT STEAM LINES CLOSING TO TURBINES l STEAM SUPPLY CROSS CONNECT LINES NORMALLY OPEN RELOCATES AFPT 1-1 CROSS CONNECT TEST LINE ISOLATION VALVE ADDS AND RELOCATES STEAM LINE BREAK DETECTION SWITCHES PROVIDES ADDITIONAL PIPE WHIP RESTRAINTS AND IMPlNGEMENT BARRIERS BENEFITS GAINED lMPROVES AFWS RELIABILITY MINIMlZES POTENTIAL FOR AFPT OVERSPEED ENHANCES GOVERNOR CONTROL ELIMINATES TRANSIENT PIPING LOADS REDUCES DEPENDENCY ON MOV'S ELIMINATES AC DEPENDENCY EVALUATION RESULTS COMPLIANCE WITH THE TECHNICAL SPECIFICATION BASIS REGARDING AFW RESPONSE TIME SINGLE FAILURE ASSUMPTIONS MET -
HIGH ENERGY LINE BREAK AND EQUIPMENT QUAllFICATION CRITERIA COMPLIANCE i
-- _ _ - - - . . - - . . . - - - - - - , , , _ _ _ , . . - ,,,,._,m___,,____. _ . _ . -, ._-_ . _ _ ,. . - , _,,,.~ _, _. , _ , , __ .-._.._. .,,,,
MOTOR DRIVEN FEED PUMP DESCRIPTION OF CHANGE INSTALL NEW MOTOR DRIVEN FEND PUMP IN TURBINE BUILDING BENEFITS GAINED ENHANCES THE CAPABILITY OF DECAY HEAT REMOVAL PROVIDES 100% CAPACITY AUXILIARY FEEDWATER FLOW ELIMINATES HIGH ENERGY LINE BREAK CONCERNS FOR ,
THE EXISTING SUFP RESOLVES OPERATIONAL CONCERNS RESOLVES SOME FIRE PROTECTION COMPLIANCE ITEMS ENHANCES THE CAPABILITY OF DECAY HEAT REMOVAL EVALUATION RESULTS SAFETY SYSTEM INTERFACE CRITERIA NOT AFFECTED COMPLIANCE WITH MODERATE ENERGY LINE BREAK CRITERIA JET IMPINGEMENT AND PIPE WHIP ARE ACCEPTABLE 1
COMPLIANCE WITH APPENDIX R ENVIRONMENTAL HAZARDS ARE ACCEPTABLE j -
DIESEL GENERATOR LOADING IS ACCEPTABLE
l ELECTRONIC FILTERING OF STEAM GENERATOR LEVEL SIGNAL DESCRIPTION OF CHANGE.
ADJUSTS ELECTRONIC DAMPING OF THE EXISTING FILTER BENEFITS GAINED MINIMlZES SPURIOUS SFRCS ACTUATION EVALUATION RESULTS NO LICENSING CRITERIA AFFECTED COMPLIANCE TO THE TECHNICAL SPECIFICATION BASIS FOR THE AFW/SFRCS RESPONSE TIME i
_y___- . __,.. ,_ -_-.--. , -_______ .______._______ _ _ _ _ -___.___.___ _
l VENTILATION OF THE SFRCS CABINETS DESCRIPTION OF CHANGE PROVIDES FANS TO THE SFRCS CABINETS ,
i BENEFITS GAINED MINIMlZES SFRCS ACTUATION DUE TO COMPONENT FAILURES RESULTS NO LICENSING CRITERIA AFFECTED SEISMIC CONSIDERATIONS HAVE BEEN MET ELECTRICAL SEPARATION / ISOLATION HAS BEEN MAINTAINED 9
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~ SF'tCS LOW DRESSURE L0riIC CHANGE DESCRIPTION OF CHANGE
~-
NON-COINCIDENT LOW PRESSURE CONDITION ~
ISOLATE BOTH STEAM GENERATORS 7
, BENEFITS GAINED i
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ISOLATION OF AFW FROM BOTH STEAM GENE
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EVALUATION RESULTS RELIABILITY OF THE SFRCS HAS NOT BEEN DE SINGLE FAILURE ASSUMPTIONS HAVE BEEN MET STEAM SATISFIED LINE BREAK ACCEPTANCE CRITERIA RE l
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ELIMINATES ISOLATION-OF MAIN STEAM AND MAIN FEEDWATER ON LOW STEAM GENERATOR LEVEL TO ENStJRE CONTINUED MFW TO THE S/G BENEFITS GAINED i -
MINIMlZES MS AND MFW ISOLATIONS MAINTAIN FEED CAPABILITY OF MFP'S t :
STEAM PRESSURE CONTROL PROVIDED BY NORMAL STEAM SYSTEM
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- LOFW ACCEPTANCE CRITERIA REMAINS SATISFIED i
SINGLE ACTIVE FAILURES OF THE AFW ISOLATION VALVES CONCERN o POSSIBILITY OF A SINGLE ACTIVE FAILURE FOLLOWING A MAIN STEAM LINE BREAK -
CAUSING COMPLETE LOSS OF AUXlLIARY FEEDWATER FROM BOTH STEAM GENERATORS
, EVALUATION o THE DOUBLE ENDED MAIN STEAM LINE BREAK :
ACCIDENT HAS BEEN REANALYZED o STEAM GENERATOR PRESSURE RESPONSE DETERMINED AND ANALYZED o FRICTIONAL EFFECTS FOR VALVES AND FITTINGS MODELLED RESULTS o CLOSURF. OF TURBINE STOP VALVES FOLLOWING A SFRCS LOW PRESSURE TRIP ON ONE STEAM GENERATOR WILL PREVENT THE UNAFFECTED SG FROM DEPRESSURIZING BELOW 730 PSIA o PREVENTS ISOLATION OF AFW FROM THE UNAFFECTED STEAM GENERATOR o PREVENTS ISOLATION OF AFW FROM THE UNAFFECTED STEAM GENERATOR o SINCE VALVE (AF 599/608) IS NORMALLY OPEN, AND NO SINGLE ACTIVE FAILURE CAN CAUSE ITS CLOSURE, AFW WILL CONTINUE TO BE AVAILABLE TO T_HE UNAFFECTED STEAM GENERATOR l
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Enclosure 2 LIST OF ATTENDEES NAME COMPANY POSITION J. F. Dunne TED Sr. Nucl. Engineer R. H. Ellison B&W Eng. III Faust Rosa NRC/NRR/ICSB Chief, ICSB Walter Paulson NRC/0RBf4 Sr. Project Manager Adel El-Bassioni NRC/RRAB Risk Analyst G. E. Edison NRC/0RBf4 Deputy Chief Sushil C. Jain Toledo Edison Sr. Nuclear Engineer Ali Zarkesh Toledo Edison Sr. Nuclear Engineer Robert Peters Toledo Edison ~ Nuclear Licensing Manager
- Ted Myers Toledo Edison Nuclear Safety and Licen. Dir.
Walt Rogers USNRC SRI Rich Morrison Essex Corp Sr. Human Factors Engineer John Wood Toledo Edison Nuclear Plant Systems William O'Connor Toledo Edison Co. . Ass't. Plant Manager, Operations Jacque Lingenfelter Toledo Edison Operations Eng. Manager Sm Quennoz Toledo Edison GP Dir. Nucl. Eng.
R. Woodruff NRC/EAB Sr. Engineer Jerry Wilson NRC Section Leader /ASB John Ridgely NRC/ASB Engineer
- 0. D. Parr NRC/ASB Branch Chief Conrad McCracken NRC/NRR/0RB#4 Section Leader George Dick NRC Project Manager Joe Williams Toledo Edison Sr. V. P. Nuclear
MEETING
SUMMARY
DISTRIBUTION Licensee: Toledo Edison Company
- Copies also sent to those people on service (cc) list for subject plant (s).
Docket File '
NRC PDR L PDR ORB #4 Rdg Project Manager - CMcCracken JStolz BGrimes (Emerg. Preparedness only)
OELD
- EJordan, TE ACRS-10 NRC Meeting
Participants:
FRosa WPaulson AEl-Bassioni GEdison WRogers 4
RWoodruff JWilson JRidgely OParr 1 GDick 1
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t 1
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