|
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210H6681999-07-29029 July 1999
Summary of 990329 Meeting with Gpu in Forked River,Nj Re Possibility of Decommisssioning of Oyster Creek Nuclear Generating Station.List of Attendees & Licensee Handouts Provided
ML20196H1471999-06-24024 June 1999
Summary of 990609 Meeting with Duke Energy Corp Re NRC Conclusions for TIA-98008 on Use of Compensatory Actions for Control Room Emergency Ventilation System & to Present Positions.List of Participants & Licensee Handouts Encl
ML20206L4921999-05-10010 May 1999
Summary of 990416 Meeting with Util in Rockville MD to Discuss Matter Re SG Operational Assessments for Current Operating Cycle at Plant,Unit 1
ML20206G1181999-05-0505 May 1999
Summary of 990419-20 Meeting with Southern Nuclear Operating Co,Inc in Rockville,Md Re Matters Related to Implementation of Improved Standard TSs at Farley Nuclear Plant,Units 1 & 2
ML20203C2351999-02-0404 February 1999
Summary of 990127 Meeting with Duke Energy Corp Re Proposed License Amend to Take Credit for Soluble Boron & Partial Credit for Boraflex in Sf Pools at McGuire Nuclear Station. List of Attendees & Handouts Provided by Duke Encl
ML20198S2581998-12-31031 December 1998
Summary of 981215 Meeting with Southern Nuclear Operating Co in Rockville,Md to Discuss Technical Issues Associated with Kaowool Fire Barriers Installed at Farley Nuclear Plant, Units 1 & 2
ML20198M7031998-12-29029 December 1998
Summary of 981215 Meeting with Southern Nuclear Operating Co,Inc in Rockville,Md Re Matters Related to Current Steam Generator Tube Insp at Farley Nuclear Plant,Unit 1.List of Attendees & Meeting Handouts,Encl
ML20195J1361998-11-17017 November 1998
Summary of 981026 Meeting with Util in Rockville,Md to Discuss Plant Analysis of Replacement SG & Evaluation of Other Small Changes for FNP Units 1 & 2 Best Etimate Large Break loss-of-coolant Accident
ML20195G1391998-11-16016 November 1998
Summary of 981103 Meeting with Gpu in Rockville,Md Re Possible Shutdown & Decommissioning of Oyster Creek Nuclear Generating Station in Year 2000.List of Attendees & Handout Encl
ML20155C4141998-10-29029 October 1998
Summary of 981014 Meeting W/Southern Nuclear Operating Co, Inc in Rockville,Md Re Justification of Certain TS Changes Needed to Implement Improved Std TS & NRC Staff Request for Addl Info, .List of Attendees Encl
ML20155C2451998-10-29029 October 1998
Summary of 981008 Meeting with Southern Nuclear Operating Co in Rockville,Md Re Util Repair of Joseph M Farley Nuclear Plant,Unit 1 B SG Tubes & Eddy Current Test Data for Tube R25C51 Submitted by .List of Attendees Encl
ML20236P1761998-07-13013 July 1998
Summary of 980709-10 Meeting W/Util Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl
ML20249C7711998-06-29029 June 1998
Summary of 980617 & 18 Meetings W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TSs for Catawba & McGuire Nuclear Stations.List of Meeting Attendees Encl
ML20249B4361998-06-17017 June 1998
Summary of 980514 Meeting W/Duke Energy Corp Re Info Related to Ice Condenser Issues,Ice Weight Redistribution & Reduction & Block Ice Utilization.List of Participants & Handout Provided by Util,Encl
ML20248E7911998-06-0101 June 1998
Summary of 980518 Meeting W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl
ML20203L9501998-02-19019 February 1998
Summary of 980204 Meeting W/Util to Discuss Info Re Design, Operabiliy & Qualifications of Grinnell Snubbers at Plant. Meeting Scheduled to Resolve Issues Re Staff Rai.List of Participants & Handouts Provided by Util Encl
ML20203B7081998-02-10010 February 1998
Summary of 980127 Meeting W/Duke Energy Corp Re Proposed Rev of Topical Repts.List of Attendees & DEC Slides Encl
ML20198G2131997-12-23023 December 1997
Summary of 971118 Meeting W/Duke Energy Corp in Rockville, Md,Re non-vital Electrical Bus,Kxa,Dual Unit Reactor Trip on 970906.List of Meeting Attendees & Licensee Handout Encl
ML20203C5501997-12-0505 December 1997
Summary of 971120 Meeting W/Southern Nuclear Operating Co to Discuss Matters Related to Steam Generator Replacement Projects Proposed for Both Farley Nuclear Units.List of Attendees Enclosed
ML20202E6761997-11-26026 November 1997
Summary of 971030 Meeting W/Duke Energy Corp Re Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Attendees,Meeting Agenda & Licensee Handout Matl Encl
ML20199A0161997-10-30030 October 1997
Summary of 971022 Meeting W/Util in Rockville,Md Re Initiatives That Focus on Planned Licensing Actions & Corrective Measures Re Problems Considered by Mgt to Warrant Special Attention
ML20217E1531997-09-25025 September 1997
Summary of 970916 Meeting W/Southern Nuclear Operating Co, Inc in Rockville,Maryland Re Licensees Improved Std TS Conversion Application & Schedule for Submittal.List of Meeting Attendees & Meeting Handouts Encl
ML20216E3421997-09-0303 September 1997
Summary of 970826 Meeting W/Gpu in Rockville,Md Re Possibility of Decommissioning of Plant.Agenda,Meeting Handouts & Primarily Centered Activities Associated W/Decommissioning Plant in Yr 2000 Encl
ML20217P0651997-08-22022 August 1997
Summary of 970709 Meeting W/Util Re Issues Related to 1996 Rev of McGuire Ufsar.List of Attendees & Verbal Response Encl
ML20217L8701997-08-14014 August 1997
Summary of 970731 Meeting W/Southern Nuclear Operating Co, Inc in Birmingham,Al Re Plant Status,Major Problems & Other Topics at Farley,Hatch & Vogtle Nuclear Plants.List of Attendees & Presentation Handouts Encl
ML20148D8531997-05-28028 May 1997
Summary of 970502 Meeting W/Util to Discuss Status of Implementation Schedule for Completion of Installation of Thermo-lag at Plants.List of Attendees Encl
ML20134K7521997-02-12012 February 1997
Summary of 970205 Meeting W/Util & W for Initial Discussion of Utils Plans & Schedule for Submitting Proposed TS Amend Request Re Use of Direct Tube Repair in Repair of SG Tubes. List of Participants & Matl Presented Encl
ML20129K3791996-11-21021 November 1996
Summary of 961016 Meeting W/Dpc at Plant Re Ongoing Current Licensing Issues & Safety Initiatives at Three Nuclear Stations.Meeting Attendees,Agenda & Handouts Encl
ML20149J5251994-12-29029 December 1994
Summary of 941219 Meeting W/Util Re Status of Licensing Actions.List of Attendees & Activities Encl
ML20059L0651994-01-26026 January 1994
Summary of 931201 Meeting W/Util in Rockville,Md Re Presentation by Licensee on SG Replacement Project. Attendees Listed in Encl 1
ML20058K1831993-11-26026 November 1993
Summary of 931119 Meeting W/Licensee in Rockville,Md Re Licensing Issues Involved in Construction & Loading of Independent Spent Fuel Storage Installation to Be Constructed at Plant
ML20059H9901993-10-29029 October 1993
Summary of 930929 Meeting W/Util in Rockville,Md to Discuss Results of Util Investigation Into Unit 1 SG Tube Leaks. Licensee Agreed to Investigate Leakage Monitoring Program
ML20059F3931993-10-27027 October 1993
Summary of 931020 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Status of Plant Licensing Actions.List of Attendees Encl
ML20059A5941993-10-14014 October 1993
Summary of 930929 Meeting W/B&W Re Generic Implications for of Steam Generator Leak for Similar Sleeves Installed at Other Facilities.List of Attendees & Meeting Handouts Encl
ML20057F1471993-10-0606 October 1993
Summary of Operating Reactors Events Meeting 93-37 on 930929
ML20058M5891993-09-27027 September 1993
Summary of Operating Reactors Events Meeting 93-36 on 930922
ML20056C5231993-06-18018 June 1993
Summary of 930602 Meeting W/Util Re Plant Proposal for Removing 2C Emergency Diesel Generator from TS as Part of Farley Implementation of Station Blackout Rule.List of Attendees Encl
ML20056D6661993-06-0101 June 1993
Summary of Operating Reactors Events Briefing 93-19 on 930526
ML20128K8261993-02-0909 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Region I Positions on Operator Licensing Issues & Solicit Input from Util Training Staffs
ML20059C7311993-01-30030 January 1993
Summary of 391st ACRS Meeting on 921105-07 in Bethesda,Md Re NRC Regulatory Analysis Guidelines & Reactor Operating Events & Occurrences,Shearon Harris Plant Loss of High Head SI & LaSalle Overfill Due to Failure of MFW Pumps to Trip
ML20127M5941993-01-26026 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Reactor Bldg Access Control Mod & Operational Safeguards Response Evaluation.List of Attendees & Handouts Encl
ML20127F6681993-01-14014 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Individuals Participating in Discussion & Marked Up Copy of Staff Pmr Encl
ML20127E1281993-01-13013 January 1993
Summary of 930106 Meeting W/Util in Rockville,Md Re Insp of Plant Core Spray Spargers.List of Discussion Participants & Licensee Agenda Encl
ML20126G7701992-12-21021 December 1992
Summary of 921215 Meeting W/Util Re Status of Plans to Replace Snubbers During Next Scheduled Unit 1 Outage in Mar 1993
ML20125C2461992-12-0707 December 1992
Summary of 921118 Meeting W/Util in Rockville,Md Re Status of Licensing Actions
ML20128A0111992-11-25025 November 1992
Summary of 920727 Meeting W/Util,Westinghouse & Pnl in Rockville,Md Re Discussions on Steam Line Break Leakage Issues Relating to Licensees SG Tube Alternate Plugging Criteria Proposal.List of Attendees Encl
ML20128C1261992-11-25025 November 1992
Summary of 921026 Meeting W/Util in Houston County,Al Re Future Submittals Planned by Util,Status of NRC Review of Previous Submittals,Responses to Generic Communications,Nrc Concerns & General Coordination of Licensing Activities
ML20210E1761992-06-10010 June 1992
Summary of 920415 Meeting W/Representatives of Util to Discuss a Study by Kalsi Engineering on Capability of MOV Actuators.List of Attendees,Handouts,And Comments/Concerns Encl
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20217B4961991-02-0707 February 1991
Summary of 910204 Meeting W/Util in Atlanta Re self- Assessment of Facility Performance from 891101 - 910202.List of Attendees & Presentation Summary Encl
1999-07-29
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210H6681999-07-29029 July 1999
Summary of 990329 Meeting with Gpu in Forked River,Nj Re Possibility of Decommisssioning of Oyster Creek Nuclear Generating Station.List of Attendees & Licensee Handouts Provided
ML20196H1471999-06-24024 June 1999
Summary of 990609 Meeting with Duke Energy Corp Re NRC Conclusions for TIA-98008 on Use of Compensatory Actions for Control Room Emergency Ventilation System & to Present Positions.List of Participants & Licensee Handouts Encl
ML20206L4921999-05-10010 May 1999
Summary of 990416 Meeting with Util in Rockville MD to Discuss Matter Re SG Operational Assessments for Current Operating Cycle at Plant,Unit 1
ML20206G1181999-05-0505 May 1999
Summary of 990419-20 Meeting with Southern Nuclear Operating Co,Inc in Rockville,Md Re Matters Related to Implementation of Improved Standard TSs at Farley Nuclear Plant,Units 1 & 2
ML20203C2351999-02-0404 February 1999
Summary of 990127 Meeting with Duke Energy Corp Re Proposed License Amend to Take Credit for Soluble Boron & Partial Credit for Boraflex in Sf Pools at McGuire Nuclear Station. List of Attendees & Handouts Provided by Duke Encl
ML20198S2581998-12-31031 December 1998
Summary of 981215 Meeting with Southern Nuclear Operating Co in Rockville,Md to Discuss Technical Issues Associated with Kaowool Fire Barriers Installed at Farley Nuclear Plant, Units 1 & 2
ML20198M7031998-12-29029 December 1998
Summary of 981215 Meeting with Southern Nuclear Operating Co,Inc in Rockville,Md Re Matters Related to Current Steam Generator Tube Insp at Farley Nuclear Plant,Unit 1.List of Attendees & Meeting Handouts,Encl
ML20195J1361998-11-17017 November 1998
Summary of 981026 Meeting with Util in Rockville,Md to Discuss Plant Analysis of Replacement SG & Evaluation of Other Small Changes for FNP Units 1 & 2 Best Etimate Large Break loss-of-coolant Accident
ML20195G1391998-11-16016 November 1998
Summary of 981103 Meeting with Gpu in Rockville,Md Re Possible Shutdown & Decommissioning of Oyster Creek Nuclear Generating Station in Year 2000.List of Attendees & Handout Encl
ML20155C4141998-10-29029 October 1998
Summary of 981014 Meeting W/Southern Nuclear Operating Co, Inc in Rockville,Md Re Justification of Certain TS Changes Needed to Implement Improved Std TS & NRC Staff Request for Addl Info, .List of Attendees Encl
ML20155C2451998-10-29029 October 1998
Summary of 981008 Meeting with Southern Nuclear Operating Co in Rockville,Md Re Util Repair of Joseph M Farley Nuclear Plant,Unit 1 B SG Tubes & Eddy Current Test Data for Tube R25C51 Submitted by .List of Attendees Encl
ML20236P1761998-07-13013 July 1998
Summary of 980709-10 Meeting W/Util Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl
ML20249C7711998-06-29029 June 1998
Summary of 980617 & 18 Meetings W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TSs for Catawba & McGuire Nuclear Stations.List of Meeting Attendees Encl
ML20249B4361998-06-17017 June 1998
Summary of 980514 Meeting W/Duke Energy Corp Re Info Related to Ice Condenser Issues,Ice Weight Redistribution & Reduction & Block Ice Utilization.List of Participants & Handout Provided by Util,Encl
ML20248E7911998-06-0101 June 1998
Summary of 980518 Meeting W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl
ML20203L9501998-02-19019 February 1998
Summary of 980204 Meeting W/Util to Discuss Info Re Design, Operabiliy & Qualifications of Grinnell Snubbers at Plant. Meeting Scheduled to Resolve Issues Re Staff Rai.List of Participants & Handouts Provided by Util Encl
ML20203B7081998-02-10010 February 1998
Summary of 980127 Meeting W/Duke Energy Corp Re Proposed Rev of Topical Repts.List of Attendees & DEC Slides Encl
ML20198G2131997-12-23023 December 1997
Summary of 971118 Meeting W/Duke Energy Corp in Rockville, Md,Re non-vital Electrical Bus,Kxa,Dual Unit Reactor Trip on 970906.List of Meeting Attendees & Licensee Handout Encl
ML20203C5501997-12-0505 December 1997
Summary of 971120 Meeting W/Southern Nuclear Operating Co to Discuss Matters Related to Steam Generator Replacement Projects Proposed for Both Farley Nuclear Units.List of Attendees Enclosed
ML20202E6761997-11-26026 November 1997
Summary of 971030 Meeting W/Duke Energy Corp Re Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Attendees,Meeting Agenda & Licensee Handout Matl Encl
ML20199A0161997-10-30030 October 1997
Summary of 971022 Meeting W/Util in Rockville,Md Re Initiatives That Focus on Planned Licensing Actions & Corrective Measures Re Problems Considered by Mgt to Warrant Special Attention
ML20217E1531997-09-25025 September 1997
Summary of 970916 Meeting W/Southern Nuclear Operating Co, Inc in Rockville,Maryland Re Licensees Improved Std TS Conversion Application & Schedule for Submittal.List of Meeting Attendees & Meeting Handouts Encl
ML20216E3421997-09-0303 September 1997
Summary of 970826 Meeting W/Gpu in Rockville,Md Re Possibility of Decommissioning of Plant.Agenda,Meeting Handouts & Primarily Centered Activities Associated W/Decommissioning Plant in Yr 2000 Encl
ML20217P0651997-08-22022 August 1997
Summary of 970709 Meeting W/Util Re Issues Related to 1996 Rev of McGuire Ufsar.List of Attendees & Verbal Response Encl
ML20217L8701997-08-14014 August 1997
Summary of 970731 Meeting W/Southern Nuclear Operating Co, Inc in Birmingham,Al Re Plant Status,Major Problems & Other Topics at Farley,Hatch & Vogtle Nuclear Plants.List of Attendees & Presentation Handouts Encl
ML20148D8531997-05-28028 May 1997
Summary of 970502 Meeting W/Util to Discuss Status of Implementation Schedule for Completion of Installation of Thermo-lag at Plants.List of Attendees Encl
ML20134K7521997-02-12012 February 1997
Summary of 970205 Meeting W/Util & W for Initial Discussion of Utils Plans & Schedule for Submitting Proposed TS Amend Request Re Use of Direct Tube Repair in Repair of SG Tubes. List of Participants & Matl Presented Encl
ML20129K3791996-11-21021 November 1996
Summary of 961016 Meeting W/Dpc at Plant Re Ongoing Current Licensing Issues & Safety Initiatives at Three Nuclear Stations.Meeting Attendees,Agenda & Handouts Encl
ML20149J5251994-12-29029 December 1994
Summary of 941219 Meeting W/Util Re Status of Licensing Actions.List of Attendees & Activities Encl
ML20059L0651994-01-26026 January 1994
Summary of 931201 Meeting W/Util in Rockville,Md Re Presentation by Licensee on SG Replacement Project. Attendees Listed in Encl 1
ML20058K1831993-11-26026 November 1993
Summary of 931119 Meeting W/Licensee in Rockville,Md Re Licensing Issues Involved in Construction & Loading of Independent Spent Fuel Storage Installation to Be Constructed at Plant
ML20059H9901993-10-29029 October 1993
Summary of 930929 Meeting W/Util in Rockville,Md to Discuss Results of Util Investigation Into Unit 1 SG Tube Leaks. Licensee Agreed to Investigate Leakage Monitoring Program
ML20059F3931993-10-27027 October 1993
Summary of 931020 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Status of Plant Licensing Actions.List of Attendees Encl
ML20059A5941993-10-14014 October 1993
Summary of 930929 Meeting W/B&W Re Generic Implications for of Steam Generator Leak for Similar Sleeves Installed at Other Facilities.List of Attendees & Meeting Handouts Encl
ML20057F1471993-10-0606 October 1993
Summary of Operating Reactors Events Meeting 93-37 on 930929
ML20058M5891993-09-27027 September 1993
Summary of Operating Reactors Events Meeting 93-36 on 930922
ML20056C5231993-06-18018 June 1993
Summary of 930602 Meeting W/Util Re Plant Proposal for Removing 2C Emergency Diesel Generator from TS as Part of Farley Implementation of Station Blackout Rule.List of Attendees Encl
ML20056D6661993-06-0101 June 1993
Summary of Operating Reactors Events Briefing 93-19 on 930526
ML20128K8261993-02-0909 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Region I Positions on Operator Licensing Issues & Solicit Input from Util Training Staffs
ML20059C7311993-01-30030 January 1993
Summary of 391st ACRS Meeting on 921105-07 in Bethesda,Md Re NRC Regulatory Analysis Guidelines & Reactor Operating Events & Occurrences,Shearon Harris Plant Loss of High Head SI & LaSalle Overfill Due to Failure of MFW Pumps to Trip
ML20127M5941993-01-26026 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Reactor Bldg Access Control Mod & Operational Safeguards Response Evaluation.List of Attendees & Handouts Encl
ML20127F6681993-01-14014 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Individuals Participating in Discussion & Marked Up Copy of Staff Pmr Encl
ML20127E1281993-01-13013 January 1993
Summary of 930106 Meeting W/Util in Rockville,Md Re Insp of Plant Core Spray Spargers.List of Discussion Participants & Licensee Agenda Encl
ML20126G7701992-12-21021 December 1992
Summary of 921215 Meeting W/Util Re Status of Plans to Replace Snubbers During Next Scheduled Unit 1 Outage in Mar 1993
ML20125C2461992-12-0707 December 1992
Summary of 921118 Meeting W/Util in Rockville,Md Re Status of Licensing Actions
ML20128C1261992-11-25025 November 1992
Summary of 921026 Meeting W/Util in Houston County,Al Re Future Submittals Planned by Util,Status of NRC Review of Previous Submittals,Responses to Generic Communications,Nrc Concerns & General Coordination of Licensing Activities
ML20128A0111992-11-25025 November 1992
Summary of 920727 Meeting W/Util,Westinghouse & Pnl in Rockville,Md Re Discussions on Steam Line Break Leakage Issues Relating to Licensees SG Tube Alternate Plugging Criteria Proposal.List of Attendees Encl
ML20210E1761992-06-10010 June 1992
Summary of 920415 Meeting W/Representatives of Util to Discuss a Study by Kalsi Engineering on Capability of MOV Actuators.List of Attendees,Handouts,And Comments/Concerns Encl
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20217B4961991-02-0707 February 1991
Summary of 910204 Meeting W/Util in Atlanta Re self- Assessment of Facility Performance from 891101 - 910202.List of Attendees & Presentation Summary Encl
1999-07-29
[Table view] |
Text
_ _ - _ _ _ _ -_ _ _ _
!+ g UNITED STATES
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g- NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 o a
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g'en-0 0T i t MEMORANDUM FOR: Charles E. Rossi, Director Division of.0perational Events Assessment FROM: Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
fHE OPERATING REACTORS EVENTS MEETING j SEPTEMBER 22, 1987 - MEETING 87-32 On September 22, 1987 an Operating Reactors Events meeting (87-3h') was held to brief senior managers from NRR, RES, AE0D and Regional Offices on events which occurred sinta our last meeting on September 8,1987. Please note that meeting '87-31 did r> ; occur. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2.. Enclosure 3 provides a summary of reactor scrams and l- "significant events" that will be input to NRC's performance indicator program.
I e' eLanning,Chiffra h Events Assessment Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
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l MEMORANDUM FOR: Charles E. Rossi, Director I Division of Operational Events Assessment FROM: Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS V.ETING SEPTEMBER 22, 1987 - MEETING 87-32 On September 22, 1987 an Operating Reactors Events meeting (87-33) was held to brief senior managers from NRR, RES, AE0D and Regional Offices on events 3 which occurred since our last meeting on September 8, 1987.
meeting 87-31 did not occur. Please note that The list of attendees is included as Enclosure 1.
The events discussed in Enclosure 2. and the significant elements of these events are presented Enclosure 3 provides a summary of reactor scrams and "significant events" that will be input to NRC's performance indicator program.
Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page DISTRIBUTION Central File e NRC.lPDR-EAB Rdg EAB Members l l
l l 1 i
0FC :EAB:NRR :C:EAB:FRR :
5____:_ ..........:..
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/l,.r : .: _ . - . . . . _ - - :: _ . . _ - -- . . . . . :: _ _ _ . . . . . . . . :: . _ _ _ . !
ling : l g . . . . : _ _ _ _ _ _ . . . . . : . . . g. . . - - -- : . . . . . . . - - . . . : . . . . - _ _ . . . - :: -
FATE:10/06/87 :10f / /87 :
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i cc' T. Murley B. Buckley l J. Sniezek K. Eccleston ;
F. Miraglia A. Dromerick j R. Starostecki G. Edison :
E. Jordan D. Hood J. Taylor K. Jabbour E. Beckjord E.'Adensam W. Russell, Reg. I J. Stolz j J. Nelson Grace, Reg. II J. Youngblood i B. Davis, Reg. III l R. D. Martin, Reg. IV :
J. B. Martin, Reg. V j W. Kane, Reg. I L. Reyes, Reg. II C. Norelius, Reg. III R. Hall, Reg. IV l D. Kirsch, Reg. V i S. Varga !
D. Crutchfield i B. Boger l G. Lainas G. Holahan F. Schroeder L. Shao J. Partlow B. Grimes F. Congel l E. Weiss S. Black T. Martin, ED0 E. Merschoff R. Hernan H. Bailey J. Guttmann i l
s
n l' ENCLOSURE 1 LIST OF ATTENDEES t <
OPERATING REACTORS EVENTS BRIEFING (87-31) !
September 29, 1987 NAME ORGANIZATION NAME ORGANIZATION E Starortecki NRR EJankovichD/DLPQ C.E.Rossi NRR/00EA J. Roe NRR/DLPQ J.Partlow NRR E.W.Merschoff NRR/DRIS/VIB l C.Berlinger NRR F.Schroeder NRR/DRSP W.Lanning NRR/DCEA R.Capra NRR/ADRP I/II J P.Barancwsky NRR/EAB J.Craig NRR/SPLB j R.Scholl NRR/EAB W.Hinners RES/DRPS T.,Greene NRR/EAB G.Lanik AE0D/ROAB j N. Fields NRR/EAB J. Knight NRR/ DEST /SELB 1 l
T.S.Rotella OSP/TVA F. Rosa NRR/ DEST /SELB l B.D.Liaw OPS /TVA M. Williams AEOD/OSP/TPAB S. Black NRR/PMAS/PTRB T. Martin . EDO S. Davis NR~t/DREP/RAB
, J.E.Rosenthal AEOD/ROAB D.Tondi DEST /SELB G.R.Klingler PMAS/ILRB R.Baer RES/DE/EIB E.D.Throm RES/DRPS/RPSIB l A.liendiola NRR/DRP i
l i
i I
i
p.:
1 ENCLOSURE 2-OPERATING REACTORS EVENTS BRIEFING 87-32 TUESDAY SEPTEMBER 22, 1987, 11 A.M.
THE AGENDA INFORMATION MAY.ALSO BE OBTAINED BY DIALING. EXTENSION 27174.
1.
SHEARON HARRIS FEEDLINE BREAK ANALYSIS SINGLE FAILURE' ASSUMPTI0ii 1
0YSTER CREEK REACTOR VESSEL WATER LEVEL SAFETY LIMIT VIOLATION (AIT UPDATE) i MCGUIRE 2 HIGH PRESSURIZER PRESSURE SCRAM AND UNCONTROLLED COOLING l
PCGlIIRE I LOSS OF 0FFSITE POWER ;
1 i l 1
- MEETING ON SEPTEMPER 29, ]987 WILL BE IN ROOM P-110 i l
I l
I u
i
f SHEARON HARRIS FEEDWATEP RREAK_ ANALYSIS (SINGLE FAJLURE ASSUMPTION)
PROBLEM SINGLE FAILURE OF A DC BUS COULD CAUSE LOSS OF ALL AFW .
. CAUSE-DESIGN DEFICIENCY SIGNJ FICANCE -
ADEQUATE HEAT SINK RELIED'UPON TO REDUCE REACTOR COOL LOSS THROUGH THE PRESSURIZER SAFETY VALVES FOLLOWING FEEDWATER LINE BREAK AND OTHER DESIGN BASIS EVENTS DISCUSSION FSAR ASSUMES 430 GPM DELIVERED TO TWO INTACT STEAM ;
269 SEC AFTER ACCIDENT FAILURE OF THE B TRAIN 125 VOLT DC BUS WOULD ISOLATE AL l l
- LICENSEE, WESTINGHOUSE AND EBASCO EVALUATED OTHER CHAPTER 15 J ANALYSES AND OTHER EQUIPMENT FAILURES RESULTS ARE BOUNDED BY FSAR ANALYSES 'IF THE A
- LOGIC IS CHANGED ( ENERGIZE TO ISOLATE) FOR THE B DC BUS 1979 ANS DECAY HEAT IS USED l FOLLOWUP i LICENSEE PLANS TO REVISE ANALYSIS UNDER 10CFR 50.59 EAB IS CONTINUING FOLLOWUP CONTACT: WALT JENSEN i
-- - - - - - - - - - - - - - - - - - _ - - _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ - - - - - --m__ __ to
j OYSTER CRE.EK REACTOR VESSEL WATER LEVEL PROBLEM !
MEASUREMENT OF THE WATER LEVEL IN THE CORE REGION OF THE REACTOR WAS JEOPARDIZED CAUSE OPERATOR ACTION INITIATED CLOSURE OF A DISCHARGE VALVE THE TWO REQUIRED LOOPS (THREE OUT OF FIVE LOOPS WERE P ISOLATED)
SIGNIFICANCE
- LOSS OF WATER LEVEL COULD RESULT IN EVENTUAL UNC0VER ?
SUBSEQUENT FUEL DAMAGE DISCUSSION
- REACTOR IN COLD SHUTDOWN SINCE 9/10
- MAINTENANCE ACTIVITY ON 9/11 LED TO COMPONENT COOLING W WITH SUBSEQUENT OPERATOR ACTION
- OPERATORS STOPPED RECIRCULATION PUMPS AND INITIATED RE VALVE CLOSURE WITH SUBSEQUENT ALARM
- TECHNICAL SPECIFICATIONS REQUIRE A A MINIMUM OF TWO RECIR LOOPS TO BE FULLY OPEN TO ASSURE WATER LEVEL MEASURED IS REPRESENTATIVE OF CORE REGION l
- OPERATORS INITIATED ACTION TO OPEN DISCHARGE VALVES OF
- TECH SPECS WORDED IN A MANNER THAT CAUSE VALVE CLOSURE VIOLATION OF SAFETY LIMIT
- IN MAY 1979 A SEQUENCE OF EVENTS LED TO AN INDICATED WAT BELOW THE LOW LOW LOW ALARM SETPOINT
- SAFETY EVALUATION INDICATED ACCEPTABILITY WHEN MORE TH IS OPEN
- FUEL ZONE WATER LEVEL MONITOR (TAP ITEM) OPERABLE FOLLOWUP
- LICENSEE INVESTIGATING COVER UP 0F EVENT BY SHIFT OPERA DESTRUCTION OF PORTIONS OF SEQUENCE-0F-ALARMS RECORD
- AIT REPORT DRAFTED CONTACT: JERRY CARTER
L MCGUIRE 2 HIGH PRESSURIZER PRESSURE SCRAM _AND UNCONTROLLED COOLING PROBLEM BREAKER COORDINATION CAUSE UNKNOWN SIGNIF1CANCE CHALLENGE TO REACTOR PROTECTION SYSTEM DISCUSSION UNIT WAS AT 100% POWER ON 9/6/87-LOAD ON A MOTOR CONTROL CENTER WAS GREATER THAN NORMAL BECAUSE AN INVERTER WAS OUT OF SERVICE FOR PM AN AIR COMPRESSOR MOTOR SHORTED MCC SUPPLY BREAKER OPENED BEFORE AIR COMPRESSOR BREAKER CAUSING LOSS OF CONTROL POWER T0:
TURDINE INTERFACE RELAY AUX FEED REG VALVES PRESSURIZER PORVs SEPERAT0R/ REHEATER VALVES STEAM DUMP VALVES TURBINE GOVERNOR VALVES CLOSED TO PREVENT OVERSPEED BECAUSE LOGIC INDICATED LOSS OF MAIN GENERATOR LOAD REACTOR DID NOT TRIP IMMEDIATELY BECAUSE TURBINE DID NOT RECEIVE A TRIP SIGNAL AUX FEED OVERC00 LED REACTOR BECAUSE OF LOSS OF THROTTLING FOLLOWUP LICENSEE IS REVIEWING DISTRIBUTION OF ELECTRICAL LOADS ELECTRICAL SYSTEMS BRANCH WILL REVIEW BREAKER C0 ORDINATION-CONTACT: ROGER WOODRUFF
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MCGUIRE 1 LOSS OF 0FFSITE POWER PROBLEM ,
LOSS OF 0FFSITE POWER TO UNIT 1- , ;
TRIP OF UNIT 2
_CAUSE
- TESTING 0F MODIFIED SWITCHGEAR FOR '! NIT 1 LOSS OF INSTRUMENT AIR FOR TO UNIT 2 '
SIGNIFICANCE SHARED AIR SYSTEM CAN CAUSE BOTH UNITS TO SCRAM DISCUSSION 1 0F 2 0FFSITE POWER LINES AND 1 0F 2 DIESEL G '
- UNIT l'WERE OUT OF SERVICE FOR MAINTENANCE EVENT OCCURRED ON 9/16/87 WITH UNIT 1.1:2 DAYS l
- REFUELING OUTAGE AND WITH UNIT.2 AT 100% POWER UNIT I WAS DRAINED DOWN TO WITHIN 10 INCHE LINE, WAS NOT MOVING FUEL, AND WAS SUPPLYING POWER T
- SHARED INSTRUMEN) AIR SYSTEM TESTING OF MODIFIED TRANSMISSION TRIPPIN CAUSED LOSS OF THE FUNCTIONING OFFSITE THE AS AVAILABLE DIESEL GENERATOR FOR UNIT 1 REQUIRED 1
RESIDUAL HEAT REMOVAL FOR UNIT I WAS RES 4 MINUTES OF LOSS OF POWER
- INSTRUMENT AIR PRESSURE BLED DOWN CAUSIN VALVES TO CLOSE AND A REACTOR TRIP WITHOU LOW STEAM GENERATOR LEVEL UNIT 2 WAS RESTARTED 2 HOURS LATER FOLLOWUP i RESIDENT INSPELTOR WILL FOLLOWUP AS NECESSARY CONTACT
- ROGER WOODRUFF
l REAC70R SCRAM
SUMMARY
NEEK ENDlW6 09/13/07
- 1. PLANT SPECIFIC DATA DATE SiiE UNIT PONER 516NAL CAUSE COMPL1- YTD iTD ' yid "
CAT 10NS ABOVE BELON TOTAL ;
151 15%
09/07/87 LIMERICK 1 84 A UNKNONN N0 1 0 1 09/07/87 CALVERT CLIFFS -2 100 M EQUIP N0 3 1 4 09/07/97 FITIPATRICK 1 100 A EQUIP N0 3 0 3 09/09/87 BEAVER VALLEY 2 29 A UNKNONN- N0 4 3 7 09/09/07 ARKANSAS 2 100 A EGulP N0 1 1 2 09/07/67 PERRY l' 60 A UNKNONN NO 7' 2 9 09/10/87 BI6 ROCK PDINT 1 0A 'UNKNONN NO O 3 3 i
09/10/87 NOLF CREEK- 1 100 A EQUIP NO '8 0' 0 09/11/87 CALVERT CLIFFS 1 100 A EQUIP NO 5 0 5 09/13/67 TURKEY POINT 3 2A EQUIP NO 2 2 4 l
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II. COMPARISON iM: WEEKLY STATISTICS WITH INDUST'RY AVERAGES SCRAMS FOR WEEK ENDING 09/13/87 SCRAM CAUSE POWER NUMBER 1987 1986 .'. 1985 OF WEEKLY. WEEKLY ' WEEKLY SCRAMS (5) AVERAGE: AVERAGE AVERAGE YTD '(3) (4) (8) (9)
EQUIP. RELATED >15% 5 4.3 4.3 5.4 PERS.-RELATED(6) >15% 0 1.4 1.8, 2.0 OTHER ( 7.) >15% 3- 1.3 0.4 0. 6
8 7.0 6.5 - 8. 0 -
! ** POWER <15%
L EQUIP..RELATED < 15% 1- 1.3 1.4 1.3 PERS. RELATED < 15% 0 0.7 0.8 0.9 OTHER < 15% 1 0.4 0.2 0.2
2 2.4- 2.4 2.4
10 9.4 8.9 10.4.
, MANUAL VS AUTO SCRAMS TYPE NUMBER 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE YTD MANUAL SCRAMS 1 1.5 1.0 1.0 AUTOMATIC SCAAMS 9 7.8 7.9 9.4 1
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REAC70R SCRAM SUMMARV NED: ENDINE 09/20l87 -
I. PLANT SPECIF;C DATA DATE SITE UN!1 POWER S!BNAL CAUSE COMPLI- ' YTD yid YTD '.
- CATIONS ABOVE BELON TOTAL
'151 151 09/15/87 CATAWBA 2 48 M . EQUIP / MECH. NO 8 'O 8 09/16/87 MC6UIRE 2 100 A EQUIP / MECH. N0 3 0 3
. 09/16/87 TMl ! 100 A EQUIPMENT NO . 2 2 4
. 09/17/87 LASALLE 1 5A EGulP/ MECH. ' N0 4 1 5.
09/17/8700ADCITIES 2 93 A PERSONNEL NO ~3. 0 3 09/19/87 LIMERICf 1 90'A- EQUIP / MECH NO 2 0 2 09/20/87 SURR't ! 100 A EQUIP / ELECT . NO 3 0 ~3 j
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' COMPARISON OF ,
WEEKLY STATISTICS WITH SCRAM SCRAMS FOR CAUSE WEEK INDUSTRY POWER 09/20/87 ENDING AVERAGES NUMBER OF SCRAMS (5) 1987 WEEKL Y 1966
- POWER '>15*/ AVERAGE WEEML Y 1985 EQUIP. .
YTD AVERAGE WEEKLY PERS. RELATED (3) (4) AVERAGE
>15%
\ OTHER ( 7)RELATED(6) >
15%
(8) (9)
5 0
1 43 1,4 43
- POWER <15% 1.3 1.8 5.4 EQUIP. 6 O. 4 2. O PERS. RELATED O. 6
<15% 7. 0 OTHER RELATED 65
<15%
<15%
1 8. 0 -$
Total *** 0 06 1.4 03 0. 8 13 1 02 0. 9 22 02 C 7 2. 4 92 2.4
- 8. 9 -
10.4 TYPE MANUAL VS -
AUTO SCRAMS NUMBER OF 1987 SCRAMS WEEKLY 1986 MANUAL WEEKLY 1985 AVERAGE AUTOMATICSCRAMS YTD AVERAGE WEEKL Y SCRAMS AVERAGE .
1 6 1,5
- 7. 7 10 79 1. 0
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- 1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY SCRAM' A.E DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PA T OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.
- 2. REC 0VERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
- 3. 1986 INFORMATION DERIVED FROM ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1986. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
- 4. IN 1986, THERE WERE AN ESTIMATED TOTAL OF 461 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 104 REACTORS (HOLDING OPERATING LICENSES). THIS YIELDS AN AVERAGE RATE OF 4.4 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 8.8 TRIPS PER WEEK .
FOR ALL REACTORS. '
- 5. BASED ON 107 REACTORS HOLDING AN OPERATING LICENSE.
6.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
- 7. "0THER" INCLUDES AUTOMATIC SGIAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
- 8. 1985 INFORMATION DERIVED FROM AN ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
- 9. IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL
- UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERACE RATE OF 5.8 TRIPS PER REACTOR YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.
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IEN,' PERf0Rn4;;;E Jg;c470EE S!SN! Fit 4;;7 EVENT:
E EVENT DESCRIPil0N gyg gyggyp,( ,
FARLEY 2 09/03/87 C001 SERVICE WATER PIPINE TO TRA' s
, S WAS CROSS CONNECTEL, cc ;; ION H 3 El STED Sig,,
IAL FDR DR ACIDAL DE6R 09/06/87 0 g ,.
RELAY C0bRDINAT10N N SCRAM Logg PROBLEM ESULIS I DYSTER CREEK 5.: LOSS OFTRANSIEN!
0'.ERC0XINS CONDENSER STEAM n'#S. LOSS AIM HERic-M/ll/87 CLOS .E OF ECIRCULAi!DN DE COG II!ONSED LOOP DISCHAPLW RES RGE VALVE yj0 LATED 1TECHNICAL GPERAil0# OUTSIDE THE SPECIF1CATIgy5 s
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09/ 1!!7 PERFORMAli E INHCATS*! SIGNIFICA:;T EVENT!
PLANT NATI E"ENT EVENT DESCRIPT10N GTR SIGNIFICA!CE DATE. .
FARLEY 2 09/03/87 SERVICE WATER P! PINE TO TRAIN A AND B BATTERY R00M ! PffENil4L FOR OR ACTUAL DEGRADATION' COOLERS WAS CROSS CONNECTEL. CONDITION HAS EXISTED SIEE OF SAFETY-RELATED EGUIPMENT 03/31/B1.
MCSUIRE 2 09/06/87 RELAY COORDINATION PROBLER RESULTS IN SCRAM LDSS OF 2 IIIEIPECTED PLMI RESPONSE TO A SET PORV'S. LOSS OF CONDENSER STEAM DutlPS. LDSS ATMOSPHERIC OFCONDITIONS DUMFE. AE OVERC00LIN3 TRANSIENT.
075fER CREEK 09/11/B7 CLOSURE OF RECIRCULATION LOOP DI', CHARGE VALVE VIOLATEL ! OPERATION DliTSIDE THE LIMITS OF THE SAFETY LIMIT TECHil! CAL SPECIFICAT!DNS 1.
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