|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210P1611999-08-0404 August 1999
Summary of 990415 Meeting with Utils in Knoxville,Tn Re Status of Mark 3 Program Designed to Determine & Validate Submerged Structure Drag Loads of Newley Installed ECCS Strainers at Perry,Grand Gulf & Clinton Facilities
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
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
ML20198G5501998-12-18018 December 1998
Summary of 981201-02 Workshop with Entergy Operations,Inc in Taft,La Re Licensing Processes,Licensing Submittals & Other Topics That May Affect Licensing Processes & Submittals. Copy of Slides Presented During Workshop 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
ML20155H3931998-11-0202 November 1998
Summary of 981007 Meeting with Util Re Review Status of Standard Quality Assurance Manual for All Util Sites.List of Meeting 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
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
ML20154C4771998-10-0202 October 1998
Summary of 980908 Meeting with Cleveland Electric Illuminating Co,Entergy Operations,Inc & Illinois Power Co Re Joint Effort to Propose TSs to Reduce Requirements on Secondary Containment Integrity During Refueling
ML20151X0011998-09-10010 September 1998
Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees Encl
ML20237E0271998-08-25025 August 1998
Summary of 980625 Meeting W/Entergy Operations,Inc to Discuss Bulletin 96-003 Re Installation of ECCS Suction Strainer in Ninth Refueling Outage for Plant.List of Attendees & Licensee Handout
ML20236M0501998-07-0808 July 1998
Summary of 980702 Meeting W/Entergy Operations,Inc to Discuss Review Status of Std QA Manual for All Entergy Sites.List of Attendees Encl
ML20236F8171998-06-24024 June 1998
Summary of 980331 Meeting W/Util to Brief NRC on Licensee Risk Mgt of Upcoming Ninth Refueling Outage.List of Attendees & Handouts Encl
ML20217K3461998-04-24024 April 1998
Summary of 980401 Meeting W/Entergy Operations,Inc Re Licensing Issues & Regulatory Performance Efficiencies.List of Attendees & Agenda for Meeting Encl
ML20217K5141998-04-24024 April 1998
Summary of 980416 Meeting W/Entergy Corp Re Standardization of site-specific Security Plans.List of Meeting Attendees & Agenda for Meeting Encl
ML20217F4811998-03-26026 March 1998
Summary of 980319 Meeting W/Licensee to Discuss Status of Development of Std QA Manual for All Entergy Sites.List of Attendees Encl
ML20216C6471998-03-0505 March 1998
Summary of 980123 Meeting W/Entergy Operations,Inc Re EP Changes Being Considered by Licensee.List of Meeting Attendees,Meeting Agenda & Info Provided by Licensee at Meeting in Handout Encl
ML20203B5741998-02-11011 February 1998
Summary of 980122 Meeting W/Entergy in Rockville,Maryland Re Licensing Issues & Standardization of Licensing Documents. List of Meeting Attendees & Meeting Agenda 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
ML20198A3731997-12-0404 December 1997
Summary of 971119 Meeting W/Westinghouse Owners Group Re Completion of WOG Topical Rept WCAP-14572,rev 1,conclusions from Results of Surry Pilot Plant Submittal & Schedule for Approving Surry Submittal & Associated WCAP
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
ML20212G8521997-10-29029 October 1997
Summary of 971022 Meeting W/Entergy Svcs,Inc Re Development & Implementation of Common or Std QAP for All Sites.List of Meeting Attendees & Viewgraphs Encl
ML20217E0131997-09-29029 September 1997
Trip Rept of 970825-26 Visit to Plant,Unit 1 for Interviews in Preparation of Salp.Agenda for Interviews Encl
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
ML20198R3481997-09-0404 September 1997
Trip Rept of 961121 Visit to GGNS to Discuss Implementation Methodologies Employed for Graded Aq in Procurement Area
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
ML20141H3661997-07-17017 July 1997
Summary of 970710 Meeting W/Util to Discuss Licensee Emergency Plan Change 28.001-95 & to Determine If Change Reduces Effectiveness of Emergency Plan for Plant,Unit 1. List of Attendees,Agenda & Info Provided by Licensee Encl
ML20137U1331997-04-10010 April 1997
Summary of 970325 Meeting W/Util in Clariborne County,Ms to Discuss Entergy Operations,Inc MOV Thrust Methodology Used for GL 95-07 for Plant.List of Attendees & Info Provided by NRC Staff Encl
ML20137F2351997-03-24024 March 1997
Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants
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
ML20132D1421996-12-17017 December 1996
Summary of 960827 Meeting W/Util in Rockville,Md Re Graded Quality Assurance Initiative at Facility.W/Attendees List, Summary of Licensee Presentation & Licensee Expert Panel Guidance Document
ML20149M3611996-12-11011 December 1996
Summary of 96111 Meeting W/Licensee in Rockville,Md to Discuss Comments Developed in Response to NRC Advance Notice of Proposed Rulemaking on Financial Assurance Requirements for Decommissioning Nuclear Reactors.List of Attendees Encl
ML20134N5661996-11-21021 November 1996
Summary of 961003 Meeting W/Licensee in Rockville,Md to Discuss Licensee Upcoming Eighth Refueling Outage for Ggns,Unit 1
ML20134M6611996-11-21021 November 1996
Summary of 961114 Meeting W/Listed Licensees in Rockville,Md to Discuss Results of Self Assessment of Accuracy of Info in FSARs for Four Nuclear Reactor Sites.List of Attendees & Licensee Handout Encl
ML20129G5261996-07-31031 July 1996
Summary of ACRS Plant Operations Subcommittee Meeting on 960521 to Review Proposed Rule on Shutdown Operations & Associated Reg Guide as Well as Studies on Shutdown Risk at Surry & Grand Gulf Nuclear Plants
ML20059H7581994-01-0303 January 1994
Summary of Operating Reactors Events Meeting 93-48 on 931222
ML20059C4041993-12-27027 December 1993
Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md to Discuss Licensee Proposed Changes to Security Plans for Plant,Units 1 & 2.List of Attendees Encl
ML20058P4491993-12-15015 December 1993
Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md Re 931021 Submittal of Proposed Alternative to 10CFR50.55a(f) & (g),10-Year Inservice Insp & Inservice Testing Update. List of Attendees Encl
ML20058G3081993-11-19019 November 1993
Summary of Operating Reactors Events Meeting 93-43 on 931117
ML20056H5721993-08-0505 August 1993
Summary of Operating Reactors Events Meeting 93-28 on 930728
ML20059C8321993-07-21021 July 1993
Summary of 398th ACRS Meeting on 930610-11 in Bethesda,Md Re SECY-93-113,public Comments on Advanced LWR Severe Accident Plant performance,SECY-93-067 & Reactor Operating Experience Related to Salem Unit 2 & Indian Point Unit 3
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
ML20056E2121993-06-15015 June 1993
Summary of Operating Reactors Events Meeting 93-21 on 930609
ML20056D6661993-06-0101 June 1993
Summary of Operating Reactors Events Briefing 93-19 on 930526
ML20127D1321993-01-12012 January 1993
Summary of Operating Reactors Events Meeting 93-01 on 930106
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
ML18096A8711992-06-17017 June 1992
Summary of 920602 Meeting W/Nrc & Pse&G Re Sea Turtle Conservation Plan.Major Points Discussed in Meeting Listed
1999-08-04
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210P1611999-08-0404 August 1999
Summary of 990415 Meeting with Utils in Knoxville,Tn Re Status of Mark 3 Program Designed to Determine & Validate Submerged Structure Drag Loads of Newley Installed ECCS Strainers at Perry,Grand Gulf & Clinton Facilities
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
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
ML20198G5501998-12-18018 December 1998
Summary of 981201-02 Workshop with Entergy Operations,Inc in Taft,La Re Licensing Processes,Licensing Submittals & Other Topics That May Affect Licensing Processes & Submittals. Copy of Slides Presented During Workshop 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
ML20155H3931998-11-0202 November 1998
Summary of 981007 Meeting with Util Re Review Status of Standard Quality Assurance Manual for All Util Sites.List of Meeting 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
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
ML20154C4771998-10-0202 October 1998
Summary of 980908 Meeting with Cleveland Electric Illuminating Co,Entergy Operations,Inc & Illinois Power Co Re Joint Effort to Propose TSs to Reduce Requirements on Secondary Containment Integrity During Refueling
ML20151X0011998-09-10010 September 1998
Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees Encl
ML20237E0271998-08-25025 August 1998
Summary of 980625 Meeting W/Entergy Operations,Inc to Discuss Bulletin 96-003 Re Installation of ECCS Suction Strainer in Ninth Refueling Outage for Plant.List of Attendees & Licensee Handout
ML20236M0501998-07-0808 July 1998
Summary of 980702 Meeting W/Entergy Operations,Inc to Discuss Review Status of Std QA Manual for All Entergy Sites.List of Attendees Encl
ML20236F8171998-06-24024 June 1998
Summary of 980331 Meeting W/Util to Brief NRC on Licensee Risk Mgt of Upcoming Ninth Refueling Outage.List of Attendees & Handouts Encl
ML20217K5141998-04-24024 April 1998
Summary of 980416 Meeting W/Entergy Corp Re Standardization of site-specific Security Plans.List of Meeting Attendees & Agenda for Meeting Encl
ML20217K3461998-04-24024 April 1998
Summary of 980401 Meeting W/Entergy Operations,Inc Re Licensing Issues & Regulatory Performance Efficiencies.List of Attendees & Agenda for Meeting Encl
ML20217F4811998-03-26026 March 1998
Summary of 980319 Meeting W/Licensee to Discuss Status of Development of Std QA Manual for All Entergy Sites.List of Attendees Encl
ML20216C6471998-03-0505 March 1998
Summary of 980123 Meeting W/Entergy Operations,Inc Re EP Changes Being Considered by Licensee.List of Meeting Attendees,Meeting Agenda & Info Provided by Licensee at Meeting in Handout Encl
ML20203B5741998-02-11011 February 1998
Summary of 980122 Meeting W/Entergy in Rockville,Maryland Re Licensing Issues & Standardization of Licensing Documents. List of Meeting Attendees & Meeting Agenda 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
ML20198A3731997-12-0404 December 1997
Summary of 971119 Meeting W/Westinghouse Owners Group Re Completion of WOG Topical Rept WCAP-14572,rev 1,conclusions from Results of Surry Pilot Plant Submittal & Schedule for Approving Surry Submittal & Associated WCAP
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
ML20212G8521997-10-29029 October 1997
Summary of 971022 Meeting W/Entergy Svcs,Inc Re Development & Implementation of Common or Std QAP for All Sites.List of Meeting Attendees & Viewgraphs Encl
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
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
ML20141H3661997-07-17017 July 1997
Summary of 970710 Meeting W/Util to Discuss Licensee Emergency Plan Change 28.001-95 & to Determine If Change Reduces Effectiveness of Emergency Plan for Plant,Unit 1. List of Attendees,Agenda & Info Provided by Licensee Encl
ML20137U1331997-04-10010 April 1997
Summary of 970325 Meeting W/Util in Clariborne County,Ms to Discuss Entergy Operations,Inc MOV Thrust Methodology Used for GL 95-07 for Plant.List of Attendees & Info Provided by NRC Staff Encl
ML20137F2351997-03-24024 March 1997
Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants
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
ML20132D1421996-12-17017 December 1996
Summary of 960827 Meeting W/Util in Rockville,Md Re Graded Quality Assurance Initiative at Facility.W/Attendees List, Summary of Licensee Presentation & Licensee Expert Panel Guidance Document
ML20149M3611996-12-11011 December 1996
Summary of 96111 Meeting W/Licensee in Rockville,Md to Discuss Comments Developed in Response to NRC Advance Notice of Proposed Rulemaking on Financial Assurance Requirements for Decommissioning Nuclear Reactors.List of Attendees Encl
ML20134N5661996-11-21021 November 1996
Summary of 961003 Meeting W/Licensee in Rockville,Md to Discuss Licensee Upcoming Eighth Refueling Outage for Ggns,Unit 1
ML20134M6611996-11-21021 November 1996
Summary of 961114 Meeting W/Listed Licensees in Rockville,Md to Discuss Results of Self Assessment of Accuracy of Info in FSARs for Four Nuclear Reactor Sites.List of Attendees & Licensee Handout Encl
ML20129G5261996-07-31031 July 1996
Summary of ACRS Plant Operations Subcommittee Meeting on 960521 to Review Proposed Rule on Shutdown Operations & Associated Reg Guide as Well as Studies on Shutdown Risk at Surry & Grand Gulf Nuclear Plants
ML20059H7581994-01-0303 January 1994
Summary of Operating Reactors Events Meeting 93-48 on 931222
ML20059C4041993-12-27027 December 1993
Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md to Discuss Licensee Proposed Changes to Security Plans for Plant,Units 1 & 2.List of Attendees Encl
ML20058P4491993-12-15015 December 1993
Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md Re 931021 Submittal of Proposed Alternative to 10CFR50.55a(f) & (g),10-Year Inservice Insp & Inservice Testing Update. List of Attendees Encl
ML20058G3081993-11-19019 November 1993
Summary of Operating Reactors Events Meeting 93-43 on 931117
ML20056H5721993-08-0505 August 1993
Summary of Operating Reactors Events Meeting 93-28 on 930728
ML20059C8321993-07-21021 July 1993
Summary of 398th ACRS Meeting on 930610-11 in Bethesda,Md Re SECY-93-113,public Comments on Advanced LWR Severe Accident Plant performance,SECY-93-067 & Reactor Operating Experience Related to Salem Unit 2 & Indian Point Unit 3
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
ML20056E2121993-06-15015 June 1993
Summary of Operating Reactors Events Meeting 93-21 on 930609
ML20056D6661993-06-0101 June 1993
Summary of Operating Reactors Events Briefing 93-19 on 930526
ML20127D1321993-01-12012 January 1993
Summary of Operating Reactors Events Meeting 93-01 on 930106
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
ML18096A8711992-06-17017 June 1992
Summary of 920602 Meeting W/Nrc & Pse&G Re Sea Turtle Conservation Plan.Major Points Discussed in Meeting Listed
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20058K1841990-12-0404 December 1990
Summary of 901107 Meeting W/Util in Rockville,Md Re Steam Generator Tube Collapse Under Combined LOCA & Safe Shutdown Earthquake Loads
1999-08-04
[Table view] |
Text
4
. p p ence
+ o, UNITED STATES
! ' ,q NUCLEAR REGULATORY COMMISSION 5" j WASH!NGTON, D. C. 20555 g, . v j u tC 3 o 1987 PEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Wayne Lanning, Chief Events Assessment Branch Division of.0perational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING December 15, 1987 - MEETING.87 ad On December 15, 1987 an Operating Reactors Events meeting (87-44) was held to brief senior managers from NRR, RES, AE0D and Regional Offices on events which occurred since our last meeting on December 8, 1987. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2. The Enclosure 3 provides a summary of reactor scrams and a comparison of this week's statistics with industry averages. No significant '
events were identified for input to NRC's performance indicator prograta.
i 1
a ning, Chief.
Events Assessment B h l Division of Operational Events Assessment
Enclosures:
,H As stated i cc w/ Encl.: l See Next Page 6'\
V n===7aam'a, gi j'$$
gy .
l
Y '. . ,
cc:
'T. Murley J. Sniezek F. Miraglia L. Kintner E. Jordan L. Pubenstein J. Taylor C. Patel E..Beckjord D. Fischer W. Russell, RI W. Butler J. Nelson Grace, RII E. Reeves B. Davis, RIII E. Adensam 3 R. D. Martin, RIV )'
J. B. Martin, RV W.'Kane, RI L. Reyes, RII C. Norelius, RIII J. Callan, RIV-i D. Kirsch, RV I l S. Varga )
I D. Crutchfield j B. Boger G. Lainas G. Holahan L. Shao J. Partlow 1 B. Grimes 1 F. Connel E. Weiss S. Black T. Martin J. Stone R. Hernan j H. Bailey 1 J. Guttmann A. Thadani l
1
)
, . L MEMORANDUM FOR: Charles E. Rossi, Director Director of Operational Events Assessment FROM: Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING December 15, 1987 - MEETING 87 44 On December 15, 1987 an Operating Reactors Events meeting (87-44) was held to brief senior managers from NRR, RES, AE0D and Regional Offices on events which occurred since our last meeting on December 8,1987. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2. The Enclosure 3 provides a summary of reactor scrams and a i
comparison of this week's statistics with industry averages. No significant i events were identified for 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 EABReadingEile ]
Circulating Copy EAB Staff MLReardon, EAB D0udinot, EAB LKilgore, SECY, PDR i
I 0FC :EAB/NRR :C:E //(RR : : : : : :
.....:.fwa'g....:. V.___.:..._______..:__.......___:..........__:.. .._______......__....
NAME:MLR7a*rdon :W ing : : : : :
i .__..:..__........:.....______.:..__ ...__..: .__....____:.__________.:........____:.-_____..__.
DATE :12//4 /87 :12/17'/87: : : : : :
OFFICIAL RECORD COPY s
ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (87-44)
December 15, 1987 NAME ORGANIZATION NAME ORGANIZATION J. Sniezek NRR/DONRR. P. Baranowsky. NRR/D0EA M.L. Reardon NRR/EAP. E. Weiss AE0D W. Jensen NRR/DOEA G. Lainas NRR/ADR II F. Miraglia NRR/ADP B. Grimes NRR/DRIS A. Thadani NRR/DLPQ C. Schulten NRR/DOEA
- 0. Chapra NRR/SELB B. Buckley NRR/PD 2-1 J. Thompson NRR/DOEA . D. Moran 'NRR/PD 4 M. Sanchez Spanish C.S.N. G. Lanik AEOD/ROAB i J. Heltemes AE0D T.M. Novak AEOD C. Willis NRR/PRPB L.J. Cunningham NRR/RPP l T. Silko AEOD J. Roe -NRR/DLP0 N. Fields NRR/DOEA R. Scholl, Jr. NRR/DOEA l
l l
l l
l L__-__________________-_____________.
ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 87 TUESDAY, DECEMBER 15, 1987, 31 A.M.
THE AGENDA INFORMATION MAY ALSO BE 0BTAINED BY DIALING EXTENSION 27]74, GRAND GULF 1 MISALIGNED FUEL ASSEMBLY
)
SURRY 1 8 2 STEAM GENERATOR' TUBE RUPTURE' '
l ANALYSIS DEFICIENCY EALEM 1 & 2 DEFICIENCIES IN ONSITE ELECTRICAL DISTRIBUTION SYSTEM FARLEY 2 SAFETY INJECTION LINE PIPE CRACK
\
)
l i
l l 1
FRAND GULF UNIT 1 i MISALIGNED FUEL ASSEMBLY NOVEMBER 20, 1987-PROBLEM A PERIPHERAL FUEL ASSEMBLY WAS MISALIGNED.
SIGNIFICANCE POTENTIAL GENERIC IMPLICATIONS TO BWR-6 OWNERS. CONCERN FOR FUEL ASSEMBLY AND SUPPORT STRUCTURE DAMAGE UPON IMPLEMENTING PROCEDURES TO FREE ASSEMBLY. THERMAL HYDRAULIC PERFORMANCE.
DISCUSSION o CLINTON AND PERRY LICENSEES CHECKING PREVIOUS CORE LOADING VIDE 0 TAPES.
o ONLY BWR-6s AFFECTED DUE TO UPPER CORE PLATE DESIGN.
o GE PERFORMED A SAFETY ANALYSIS AND DETERMINED THAT AN ADEQUATE MARGIN OF SAFETY WAS MAINTAINED AT ALL TIMES DUE TO THE FLOW DESIGN CHARACTERISTICS OF THE CORE.
o THIS EVENT HAS OCCURRED AT FOREIGN GE BWR-6 PLANTS (JUNE 1985) l WITH ADEQUATE SAFETY MARGINS MAINTAINED.
o THE MtJOR CONCERN WAS DAMAGE-T0 THE FUEL ASSEMBLY ASSOCTATED WITH RETRIEVAL OPERATIONS.
FOLLOWUP o GE IS PLANNING TO NOTIFY BPR-6 CUSTOMERS AFTER STUDYING THE-FEASIBILITY OF AN ENGINEERING FIX.
o U.S. BWR-G LICENSEES NOTIFIED VIA EACH OF THE RESPECTIVE PROJFCT MANAGERS.
l CONTACT: J. THOMPSON
e, , m,,-m._ ..
4' ' ,
. 7. .... . ....
. .g...,.... ,
'"lf,II,$.f17 l .
I
.m @
O -
lN,p&;L '
!!p8l "s
,e t;i lyss 1 4 -
g<j s se es38 ! !
ji e
re:gr i
'$f}syl.k(?$$
m
~~~~
GRAND GULF UNIT 1 1,g ,
. N .
4
,f
- f. . .
KUD5H2.NCs STUC.K SUNDL6. RBMOVR L.
f
. me J- Pounos~put. t 7 LUA5 SRM1 DIRGu". TION AS BUNbl.E 1
OLD FULL GRRPi1G Caste
- 1. ,
}
f -
e j C/S HOOK r :
, g '.
.s -
.R. NGEE .
A / t ? l t 8l'
~"
. ..a o
3
.\
C
{
SllRRY llNITS 1 8 '
STEAM GENERATOR TUBE RUPTURE ANALYSIS DEFICIENCY s, i PROBLEM BREAK LOCATION NOT PREVIOUSLY CONSIDERED IN STEAM GENERATOR TUBE O ((t '
RUPTURE ANALYSIS. BREAK COULD BECOME UNCOVERED DllRING EVENT, !
L
~ SIGNIFICANCE WHEN THE BREAK IS NOT COVERED BY WATER, lHE AMOUNT OF-RADIOACTIVE' '
O
?g' IODINE RELEASED TO THE ATMOSPHERE CAN INCREASE BY A FACTOR OF 10,0.
]
Q DISCUSSION f, f f' l -
I o ON DECEMBER 9, 1987 THE LICENSEE REPORTED THAT NEW STEAM I GENERATOR TUBE RUPTURE ANALYSES ARE IN PROGRESS.tTOR SURRY.
o THESE INDICATE STEAM GENERATOR TUBE'UNC0VERY FffR1A3 LONG AS 14 MINUTES.
O PROBLEM FIRST IDENTIFIED AT NORTH ANNA F01. LOWING STEAU,'6ENERATOR MODIFICATION REANALYSIS. s , s I
o SURRYSTEAMGENERATORDIFFERENTDESIGNFPONNORTHANNA.
o MINIMUM STEAM GENERATOR MASS WAF USED :N TH E NEWAplYj%h 1 o
PREVIOUSANALYSESUSEDMAXIMUMSTEAMGENERATORfBSSTO\ CALCULATE MAXIMUM OVERFILL. ;'
] a o FOLLOWINGTURBINETRIPINCREASEDSECONDM,v(PRESSUREMUSkS,i.EYEL SHRINK WHICH CAN CAUSE TUBE UNC0VERY. t
,s o SHRINK WOULD BE MAXIMIZED BY CONDENSER DUMF FAILURE AND PED!)CED g AFW FLOW.
o PLANT DATA INDICATE TUBE UNC0VERY MAY HAVE OCCURRED FOLLOWING TURBINE TRIP EVENTS AT SURRY. V o LICENSEE PLANS TO COMPLETE ANALYSES BY DECEMBER 18 AND THEN '
MEET WITH THE STAFF. <
- i o LICENSEEDOESNOTEXPECT10CFR100,LIMITSTOBEEXCEEDEDe$0R SURRY'.
(-
CONTACT: F. JENSEN
s k
_2_
l t '
o WESTINGHOUSE BELIEyES SOME' CUT NOT ALL OTHER PLANTS MAY HAVE Tile K
./ SAME PROBLEM.
o WESTINGHOUSE SAFETY REVIEW. COMMITTEE TO MEET THIS WEEK AUD.WILI.
DECIDE ON METHOD OF REPORTING.
o WESTINGHOUSE DOES NOT Bf.LIEVE 10 CFR 100 LIMITS WILL BE EXCEEDED FOR ANY PLANT. s f_0LL01 P t )-
o " NRR IS CONTINUING TO DISCUSS THIS ISSilE WITH VIRGINI A POWER 'AND WESTINGH0llSES o NRRWILLDETEk'.INEIFICEi'LANTSCOULDBEAFFECTED.
i
$ .; \ !/ ,
s - :
\
) .s s
\ %.
T .' t . ,
(
L i[,
J
)
L j
t 4
i, -
p i
1
\ 'l t
,. \
1 \ ,g i
, ( ,,
. s l x ,
_ _ - - - - - - - - - - ab "
-- m--
%, t<
3 i
4 .s
<<. l
.m . .
)
J , j
-i 1 St[Au OUTLif i
.') 1 f % !
- 4'4k _stri
, , N0 y CARRYOVER I pggagg53 sgpagatoa
= ~ .j Y)r s,..
Lis[L INDICAT M $ 9 ,
j g 46.6 f j P((PL($$ {&1 N$ p $wiRL tAhi A$$[NBLy DRAIN PIP [ SEAL Puta[ft% * '
s A f v -
J g Fi[CraffR INTRODUCfD INTO ffEDWATERINLitji 7In<u
% {(["'b D0an[0MER insouGa Annut AR RaC 39.e-L(#[L CONTROL INDICaf0*
f([DtAf(R RihC-E a ffN 36.03 .
l ; 33.4
) 74 Jr$1T ION wtAPP[1. -+ /,,4 00W800WIR FLOW
.. / ,
R'3451ANCE Platt 455EuBLY E
- ) __ 27,3, !
- Pr-- - -
W l ,
v tats -'y ] TU8I $UPPOR15 23 'O
-- : A
$1[8W-6AllR f Ml'47t;4[ ~ % l <
i f94 wat99tR Yh.~.. 0 l
ij 4 aa ~
- - STAT f00 f
}
l- 8..tB l .
) [ \ <{
I j
' *j'% $Pa[!R
- J fi-i li - 1 I-10.*7 1 ,,
D Al[F f h?[R$ MF AltWy Jpp 80 t t f 6 ',[C7:04.-- _
. h - l?
2.06 i
M j*PL dh i k- li dlL lhDatatot i ,
l sew 21 $) ear <smwa -
... y,gy
! . _ = _ .
PARiaison PL47C %
I
{ C00LAN' tai-ita (I C I
PRiuAuf (catan; nozztt - '
n .
L J
p .
I:
y Fnye 4.1-1 51 Senes Steam Generator Schemat.c l'
F
-SURRY UNITS 1 & 2
.8
. I i
Ie
---m--.--.---. 4-ik
SALEM UPTTS 1 8 '
PROBLEM CERTA 1M SAFETY RELATED MOTOR CONTROL CENTERS COULD EXPERIENCE ,
UNDERVOLTAGE CONDITIONS DURING LOCA COINCIDENT WITH DEGRADED GRID VOLTAGE.
SIGNIFICANCE THIS SITUATION COULD IMPA!R THE ABILITY OF REDUNDANT SAFETY RELATED EQUIPMENT TO SAFELY SHUTDOWN THE PLANT FOLLOWING ACCIDENT /
TRANSIENT.
DISC!!SSION O PRESENTLY BOTH SALEM UNITS ARE SHUT DOWN.
l o ON NOVEMBEP ?7, 1987, THE LICENSEE REPORTED A DESIGN DEFICIENCY l
(0MITTED CALCULATIONS) IN THE DEGRADED GRID VOLTAGE PROTECTTON PROVIDED FOR SALEM UNITS 1 8 1.
o IF THE VOLTAGE AT THE SAFETY RELATED 4KV BUSES. REMAINS JUST AB0VE THE SECOND LEVEL UNDERVOLTAGE RELAY SETPOINT OF 91.6%
(DEGRADED GRID AND FAILURE OF 0FFSITE TRANSFORMER TAP CHANGER)
COINCIDENT WITH LOCA, THE OPERATION OF CERTAIN SAFETY RELATED VALVES COULD BE IMPAIRED.
o THE LICENSEE HAS DETERMINE THAT THE 230V, "1A", "1B", AND "1C" SERVICE WATER CONTROL CENTERS COULD MAINTAIN VOLTAGES AS. LOW AS 87.5% OF DESIGN (MIN. ALLOWED IS 89%).
o PROBLEM LIKELY EXISTS AT OTHER CONTROL CENTERS AND HAS BEEN PRESENT AT SALEM UNIT 1 8 2 FOR SOME TIME.
O CONDITION MAY BE ATTRIBUTED TO LICENSEE FAILURE TO PERFORM A )
COMPREHENSIVE DESIGN ANALYSIS OF'THE ELECTRICAL DISTRIBUTION !
SYSTEM AFTER ADDITIONAL LOADS WERE ADDED (LOAD CREEP) TO THE )
SYSTEM SINCE THE LAST VOLTAGE STUDY WAS DONE.
i FOLLOWUP l 0 ENGINEERING EVALUATION (VOLTAGE DROP CALCULATIONS) 0F THE ELECTRICAL DISTRIBUTION SYSTEM FOR BOTH UNITS BY THE LICENSEE. :
CONTACT: N. FIELDS
1 I
(
IS CONTINUING IN AN EFFORT TO RESOLVE THIS ISSUE BEFORE RESTART o
ESF WILL REVIEW AND EVALUATE LICENSEE's SHORT TERM CORRECTIVE ACTIONS AND LONG TERM RESOLUTION, I 1
I 1
l i
I i
i l
'J Attachment'1. v- ~
~ -
IN 86-100 l
December 12, 1986 '
1
. i C O w
g 2 l O
' *'-i > 0 A 3 g 2 j Hn v 1 g I N
D k k n m4 --4 >
5 h h O g g 9@ 2 3 . _ , q H% _ _ - . . . A q ,
ma . .
e p' U t >---
r4
" n 2 w
-i l , % ^g , e
\
L F 0 .J i r m
< 2
- 2. m 4f
- n. 2 ^q > c O.
b2E w^-q i 2 > (
Zoo O 4 D o n. g 2 p' *A O' y V F a
E '
w 3 o z e r j J c w
< w i
~n-i i m j a 1
M$ o D y 46
(/) Do 2 CD n F A D-o
<f y'
' ~~~""
$ 1 z g e, )
y
- -A
^ >
O $ y.
C a, W 2 E p w h Om
=D E, z OE 3 w Q o b 2 $ g'
F wb k . N - CC 4
> p CD W
> -c2 !
2 3w 4 DF0 j i
l
~
e j l !
I
a
- k4o D
I t+ w* \\\j 1
- ~
g m W W V gLi S Q, $14dwbe s s E o
4
~e .
% v Ks -
0 o
' n o ,
'N 3 1. -
3ts
. o- , , ,_
aa
%,dj D
r[ <
s t
? E.
'- a d o
. _ _ _ -_ . ~
M,< ' Ekl o C
4 Wo a uM %
$l J Ml sN 13:e .
\
- I- To cd d
{ O
.jp p)
. / )- Q f, %, , ,,
j s .
l ^O 's. $
a &
- 1. 1,
~
.s ,
4 fg -
~
e
-\ -
1 gga =';. [
t
' g
?, o o a eJ adWs%a tT% 5: ;
u) ~3
~
9
Updated 12/15/87 LONGTERM FOLLOWUP ASSIGNMENTS TO BE COMPLETED ORGANIZATION LONGTERM FOLLOWUPS OUTSTANDING 12/01/87 12/08/87 12/15/87 SPLBl 7 7 6 i
EMTB 2 2 1 OGCB ' 16 ' 16 7 RVIB 11 11 8 SRXB 5 ~6 3 PD3-2 1 1 0 DRIS 2 2 0 PD2-3 2 3 2 OSP 1 1 1 ESGB 2 2 2 AEOD 2 2 3 SICB 6 6 4 PRPB 2 3 0 SELB 8 9 9 OTSB 2 1 0 RES 1 1 1 PD2-2 1 1 I j 1
PD5 1 1 3 :
RV 1 1 1 SICB 0 2 0 PD3-2 0 1 1 EWEB O 1 0 LHFB 0- 1 3
1 F.EA: TOR ECKAn SU3XAF.V Ef1 CLOSURE 3 EEEr ENJIN512/14167
- 1. PLANT EFECIFIC LATA LATE SITE UNIT FCsEE SISKAL CAUEE COMPLI- YTD YTD YTD CAT 10N5 AIOVI IELOW TOTAL 151 151
~
l 12/07/B7 NINE MILE F01NT 1 94 A EDUlFMENT NG 2 0 2 12/07/37 LAVISIESEE 1 E2 A ECU1F5ENT ND 4 0 4 12/0?!57 FEFE CEEEL 1 100 A E991PMENT~ h2 5 2 7 12/07/27 FITIFATEICr 1 100 A FERSONNEL !;0 6 0 6 12/10/E7 OL'A3 Cli1EE 2 100 A EQUITEENT YES 5 0 5 12/11/37 EATE:.FCEL 3 90 A EDUlFMENT NG 7 0 7 12/1 1E7 LIAIL0 CANYCN 1 100 A UNKNOWN E0 - 5 0 5
SUMMARY
0F COMPLICATIONS SITE UNii CCMFLICATIDK3 DUAD CITIES 2 KFW EES VALVE LO:KEL OFEN l
l l
l l
1 l
l 1
l l
1 i
~
\
~
1
s II. cot 1PARIEON DC WEEKLY STATISTICS WITH INDUSTRY .'E P W E SCRAME COR WEEF ENDING 12/1;/E7 SCRAM CAUSE FOWER NUMEER 1957 1986 1985 OF WEEKLY WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE AVERAGE YTD (3) (4) (8) (9)
EQUIP. RELATED >15% 5 4.O' 4.3 5.4 PERS. RELATED(6) >15% 0 1.2 1.8 2.0 OTHER(7) >15% 2 1.2 0.4 0.6
7 6.4 6.5 G.O
EQUIP. RELATED <15% 0 1.1 1.4 1.3 PERS. RELATED <15% O O.6 O.8 O.9 6THER <15% .O O.3 O.2 0. 2
O 2.0 2.4 2.4
7 8.4 2.9 10.4 l
MANUAL VS AUTO SCRAMS TYPE NUMBER -1987 1986 1985 OF WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE YTD MANUAL SCRAMS O 1.4 1.O 1.O AUTOMATIC SCRAMS 7 7.1 7.9 9.4
l NOTES -
! 1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY ~ THROUGH ',
MIDNIGHT SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.
E. RECOVERY 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 DETEP. MINED BY TAXING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
- 4. IN 1986, THERE WERE AN ESTIMATED TOTAL OF 461 AUTOMATIC AND f%NUAL UNPLANNED REACTOR TRIPS AT 104 REACTORS (HOLDING OPERATING LICENSES). THFS YIELDS AN AVERAGE RATE OF 4.4 TRIPS PER REACTOR PER YEAR AND AN-AYERAGE RATE OF 8.8 TRIPS PER WEEK FOR ALL REACTORS.
- 5. BASED ON 109 REACTORS HOLDING AN OPERATING LICENSE.
- 6. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
- 7. "0THER" INCLUDES AUT0!!ATIC S01 AMS 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 ESTIllATED TOTAL OF 541' AUTOMATIC AND MANUAL 'j 8 UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5.0 TRIPS PER REACTOR YEAR AND AN AVERAGE RATE OF 10.a TRIPS PER WEEK FOR ALL REACTORS.
I gr I
t.
]
. :_.__ _ _