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| ML20239A023 |
| Person / Time |
|---|
| Site: |
Davis Besse, Peach Bottom, Perry, San Onofre, 05000000 |
|---|
| Issue date: |
09/10/1987 |
|---|
| From: |
Lanning W
Office of Nuclear Reactor Regulation |
|---|
| To: |
Rossi C
Office of Nuclear Reactor Regulation |
|---|
| References |
|---|
| OREM-87-030, OREM-87-30, NUDOCS 8709170026 |
| Download: ML20239A023 (17) |
|
|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20217H1001999-10-13013 October 1999
Summary of 990930 Meeting with Util in Rockville,Md Re Proposed Five Percent Power Uprate for Plant,Unit 1.List of Meeting Participants & Licensee Meeting Handout Encl
ML20210P1611999-08-0404 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
ML20196J2351999-06-29029 June 1999
Summary of 990617 Meeting with B&Wog & FTI Re B&Wog Emergency Operating Procedure Program.List of Meeting Attendees & Presentation Slides Encl
ML20207H3531999-06-14014 June 1999
Summary of 990317 Meeting with SCE Re Issues Staff Identified in Review of 980910 License Amend Application & Exemption Request to Remove Hydrogen Monitoring & Control Sys from SONGS Licensing Basis.Meeting Attendee List Encl
ML20206P0831999-05-12012 May 1999
Summary of 990428 Meeting with Firstenergy Nuclear Operating Co & Duquesne Light Co in Rockville,Maryland Re Proposed Asset Transfer Between Firstenergy Corp & Dl & Resulting 10CFR50.80 License Transfer of Dl Ownership Interest
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
ML20205D4831999-03-25025 March 1999
Summary of 990222 Public Hearing with Util Re Gathering Addl Info Related to Two Petitions Filed Pursuant to 10CFR2.206 by Ucs Re Operation of River Bend Station & Perry Nuclear Power Plant.List of Attendees & Transcript of Hearing Encl
ML20198S3061999-01-0505 January 1999
Summary of 981204 Meeting with Util in Rockville,Md to Discuss Proposed Changes to Design & Licensing Basis of Containment Isolation Provisions for Feedwater Sys
ML20198J1651998-12-15015 December 1998
Summary of 981118 Meeting with Util in Rockville,Md Re Ampacity Validation Analyses.List of Attendees & Handouts Provided by Util Encl
ML20198D5801998-12-15015 December 1998
Summary of 981119 Meeting with Util in Rockville,Md to Discuss Proposed Changes to Design & Licensing Basis of Containment Isolation Provisions for Feedwater Sys
ML20202D3521998-12-0909 December 1998
Summary of 981123 Petition Review Board Meeting Re 2.206 Petition on Perry Unit 1,submitted on 981109 by Ucs.Meeting Attendees Listed
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
ML20155H3801998-10-29029 October 1998
Summary of 980915 Meeting with Util & Contractor Polestar Applied Technology,Inc in Rockville,Md Re Revised Accident Source Term for Perry Pilot Plant Review.List of Meeting Participants & Nonproprietary Handouts Encl
ML20154J3671998-10-13013 October 1998
Summary of 980910 Meeting W/Cleveland Electric Illuminating Co in Rockville,Md Re Licensee Proposed Changes to Design & Licensing Basis to Containment Isolation Provisions for Feedwater System.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
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
ML20216B8551998-05-0707 May 1998
Summary of 980429 Meeting W/Southern California Edison in Rockville,Maryland Re Proposed Amend to TS to Allow Operation of Plant at Reduced Tcold in Reactor Coolant Sys. W/Meeting Slides & List of Meeting Attendees
ML20203A3531998-01-29029 January 1998
Summary of 971223 Meeting W/Sce in Rockville,Md to Discuss Mechanical Nozzle Seal Assembly Relief Request.List of Attendees & 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
ML20199L2071997-11-24024 November 1997
Trip Rept of 971006 Visit to Perry Site to Gather Info on New & Unique Strainer Design Installed at Perry During Most Recent Outage
ML20199G7121997-11-0606 November 1997
Summary of 971023 Meeting W/Util in Rockville,Md Re Results of Steam Generator Tube Degradation & Run Time Analysis for SONGS Unit 2.List of Attendees & Slides 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
ML20216G5171997-09-0404 September 1997
Summary of 970805 Meeting W/Util Re Thermo-Lag Corrective Actions at Peach Bottom & Limerick.List of Attendees & Meeting Handouts Encl
ML20141E7701997-05-14014 May 1997
Summary of 970508 Meeting W/Cei in Rockville,Md Re Priorities & Schedules of Licensing Issues for Plant,Unit 1. List of Meeting Attendees & Meeting Handout Encl
ML20140H4881997-05-0707 May 1997
Provides Summary of 970401 Telcon Between NRC & BWROG Re Topical Rept NEDC-31858P,Rev 2, BWROG Rept for Increasing MSIV Leakage Rate Limits & Elimination of Leakage Control Sys
ML20140F3561997-04-30030 April 1997
Summary of 970414 Meeting W/Util in Rockville,Md to Discuss Issues Associated W/Use of Thermo-Lag Fire Barrier Matl at Plants.Meeting Attendees & Handouts Encl
ML20138C8081997-04-25025 April 1997
Summary of 970410 Meeting W/Peach Bottom Atomic Power Station in Rockville,Md Re Planned Construction of Sf Dry Cask Storage Facility for Units 2 & 3.List of Attendees & Copy of PECO Meeting Handout Encl
ML20138D9441997-04-23023 April 1997
Summary of 970324 Meeting W/Licensee in Rockville,Md Re ECCS suction-strainer Program for Perry Npp,Unit 1.List of Attendees & Viewgraphs 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
ML20147A7261997-01-22022 January 1997
Summary of 960910 Meeting W/Util in Rockville,Md to Discuss Revised Eal.List of Attendees 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
ML20133G1401997-01-10010 January 1997
Summary of 961025 Meeting W/Peco in Delta,Pa Re Status of Licensing Actions Associated W/Plants.List of Attendees & Copy of Presentation Matl Encl
ML20058N4851993-12-15015 December 1993
Summary of 931119 Meeting W/Sce in Rockville,Md Re Proposed Decommissioning Plan for SONGS 1.List of Attendees Encl
ML20058G7841993-12-0202 December 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Evaluation of Core Shroud Indications at Plant.List of Attendees & Meeting Handouts Encl
ML20058F0451993-11-24024 November 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Submittal Plans for Cost Beneficial Licensing Actions & to Get Feedback from NRC Staff.List of Attendees Encl
ML20062J8701993-11-0808 November 1993
Summary of 931028 Meeting W/Licensee in Rockville,Md Re Licensee Presentation of Summary of Plant Course of Action Plan to NRC Mgt
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
ML20059B0971993-10-20020 October 1993
Summary of Operating Reactors Events Meeting 93-39 on 931013
ML20057F1271993-10-0505 October 1993
Summary of 930902 Meeting W/Util in Rockville,Md Re NRC 930405 Safety Evaluation of Rev 3 to IST Program.List of Attendees Encl
ML20058N0011993-09-30030 September 1993
Summary of 930902 Meeting W/Peco Re Installation of Certain Planned analog-to-digital Retrofit Mods During Scheduled Sept 1993 Facility Outage
ML20057D1681993-09-27027 September 1993
Summary of 930805 Meeting W/Util Re Methods of Providing Control Room Operators W/Optimal Info on Instrument Accuracies Under Harsh Environ Conditions.List of Attendees & Util Slides Encl
ML20058M1861993-09-22022 September 1993
Summary of Operating Reactors Events Meeting 93-35 on 930915
ML20057B4771993-09-15015 September 1993
Summary of 930824 Meeting W/Util Re Implementation of dual-site Senior Reactor Limited to Fuel Handling (Lsr) Program.List of Meeting Attendees & Meeting 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
ML20057A5691993-09-0202 September 1993
Summary of 930809 Meeting W/Util in Wayne,Pa Re Various Licensing Activities Re Plants.List of Attendees Encl
ML20056F8171993-08-0909 August 1993
Summary of Operating Reactors Events Meeting 93-29 on 930804.List of Attendees & Viewgraphs Encl
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
ML20056D9841993-05-18018 May 1993
Summary of Operating Reactors Events Meeting 93-17 on 930512
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
1999-08-04
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20217H1001999-10-13013 October 1999
Summary of 990930 Meeting with Util in Rockville,Md Re Proposed Five Percent Power Uprate for Plant,Unit 1.List of Meeting Participants & Licensee Meeting Handout Encl
ML20210P1611999-08-0404 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
ML20196J2351999-06-29029 June 1999
Summary of 990617 Meeting with B&Wog & FTI Re B&Wog Emergency Operating Procedure Program.List of Meeting Attendees & Presentation Slides Encl
ML20207H3531999-06-14014 June 1999
Summary of 990317 Meeting with SCE Re Issues Staff Identified in Review of 980910 License Amend Application & Exemption Request to Remove Hydrogen Monitoring & Control Sys from SONGS Licensing Basis.Meeting Attendee List Encl
ML20206P0831999-05-12012 May 1999
Summary of 990428 Meeting with Firstenergy Nuclear Operating Co & Duquesne Light Co in Rockville,Maryland Re Proposed Asset Transfer Between Firstenergy Corp & Dl & Resulting 10CFR50.80 License Transfer of Dl Ownership Interest
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
ML20205D4831999-03-25025 March 1999
Summary of 990222 Public Hearing with Util Re Gathering Addl Info Related to Two Petitions Filed Pursuant to 10CFR2.206 by Ucs Re Operation of River Bend Station & Perry Nuclear Power Plant.List of Attendees & Transcript of Hearing Encl
ML20198S3061999-01-0505 January 1999
Summary of 981204 Meeting with Util in Rockville,Md to Discuss Proposed Changes to Design & Licensing Basis of Containment Isolation Provisions for Feedwater Sys
ML20198J1651998-12-15015 December 1998
Summary of 981118 Meeting with Util in Rockville,Md Re Ampacity Validation Analyses.List of Attendees & Handouts Provided by Util Encl
ML20198D5801998-12-15015 December 1998
Summary of 981119 Meeting with Util in Rockville,Md to Discuss Proposed Changes to Design & Licensing Basis of Containment Isolation Provisions for Feedwater Sys
ML20202D3521998-12-0909 December 1998
Summary of 981123 Petition Review Board Meeting Re 2.206 Petition on Perry Unit 1,submitted on 981109 by Ucs.Meeting Attendees Listed
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
ML20155H3801998-10-29029 October 1998
Summary of 980915 Meeting with Util & Contractor Polestar Applied Technology,Inc in Rockville,Md Re Revised Accident Source Term for Perry Pilot Plant Review.List of Meeting Participants & Nonproprietary Handouts Encl
ML20154J3671998-10-13013 October 1998
Summary of 980910 Meeting W/Cleveland Electric Illuminating Co in Rockville,Md Re Licensee Proposed Changes to Design & Licensing Basis to Containment Isolation Provisions for Feedwater System.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
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
ML20216B8551998-05-0707 May 1998
Summary of 980429 Meeting W/Southern California Edison in Rockville,Maryland Re Proposed Amend to TS to Allow Operation of Plant at Reduced Tcold in Reactor Coolant Sys. W/Meeting Slides & List of Meeting Attendees
ML20203A3531998-01-29029 January 1998
Summary of 971223 Meeting W/Sce in Rockville,Md to Discuss Mechanical Nozzle Seal Assembly Relief Request.List of Attendees & 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
ML20199G7121997-11-0606 November 1997
Summary of 971023 Meeting W/Util in Rockville,Md Re Results of Steam Generator Tube Degradation & Run Time Analysis for SONGS Unit 2.List of Attendees & Slides 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
ML20216G5171997-09-0404 September 1997
Summary of 970805 Meeting W/Util Re Thermo-Lag Corrective Actions at Peach Bottom & Limerick.List of Attendees & Meeting Handouts Encl
ML20141E7701997-05-14014 May 1997
Summary of 970508 Meeting W/Cei in Rockville,Md Re Priorities & Schedules of Licensing Issues for Plant,Unit 1. List of Meeting Attendees & Meeting Handout Encl
ML20140H4881997-05-0707 May 1997
Provides Summary of 970401 Telcon Between NRC & BWROG Re Topical Rept NEDC-31858P,Rev 2, BWROG Rept for Increasing MSIV Leakage Rate Limits & Elimination of Leakage Control Sys
ML20140F3561997-04-30030 April 1997
Summary of 970414 Meeting W/Util in Rockville,Md to Discuss Issues Associated W/Use of Thermo-Lag Fire Barrier Matl at Plants.Meeting Attendees & Handouts Encl
ML20138C8081997-04-25025 April 1997
Summary of 970410 Meeting W/Peach Bottom Atomic Power Station in Rockville,Md Re Planned Construction of Sf Dry Cask Storage Facility for Units 2 & 3.List of Attendees & Copy of PECO Meeting Handout Encl
ML20138D9441997-04-23023 April 1997
Summary of 970324 Meeting W/Licensee in Rockville,Md Re ECCS suction-strainer Program for Perry Npp,Unit 1.List of Attendees & Viewgraphs 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
ML20147A7261997-01-22022 January 1997
Summary of 960910 Meeting W/Util in Rockville,Md to Discuss Revised Eal.List of Attendees Encl
ML20133G1401997-01-10010 January 1997
Summary of 961025 Meeting W/Peco in Delta,Pa Re Status of Licensing Actions Associated W/Plants.List of Attendees & Copy of Presentation Matl Encl
ML20058N4851993-12-15015 December 1993
Summary of 931119 Meeting W/Sce in Rockville,Md Re Proposed Decommissioning Plan for SONGS 1.List of Attendees Encl
ML20058G7841993-12-0202 December 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Evaluation of Core Shroud Indications at Plant.List of Attendees & Meeting Handouts Encl
ML20058F0451993-11-24024 November 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Submittal Plans for Cost Beneficial Licensing Actions & to Get Feedback from NRC Staff.List of Attendees Encl
ML20062J8701993-11-0808 November 1993
Summary of 931028 Meeting W/Licensee in Rockville,Md Re Licensee Presentation of Summary of Plant Course of Action Plan to NRC Mgt
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
ML20059B0971993-10-20020 October 1993
Summary of Operating Reactors Events Meeting 93-39 on 931013
ML20057F1271993-10-0505 October 1993
Summary of 930902 Meeting W/Util in Rockville,Md Re NRC 930405 Safety Evaluation of Rev 3 to IST Program.List of Attendees Encl
ML20058N0011993-09-30030 September 1993
Summary of 930902 Meeting W/Peco Re Installation of Certain Planned analog-to-digital Retrofit Mods During Scheduled Sept 1993 Facility Outage
ML20057D1681993-09-27027 September 1993
Summary of 930805 Meeting W/Util Re Methods of Providing Control Room Operators W/Optimal Info on Instrument Accuracies Under Harsh Environ Conditions.List of Attendees & Util Slides Encl
ML20058M1861993-09-22022 September 1993
Summary of Operating Reactors Events Meeting 93-35 on 930915
ML20057B4771993-09-15015 September 1993
Summary of 930824 Meeting W/Util Re Implementation of dual-site Senior Reactor Limited to Fuel Handling (Lsr) Program.List of Meeting Attendees & Meeting 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
ML20057A5691993-09-0202 September 1993
Summary of 930809 Meeting W/Util in Wayne,Pa Re Various Licensing Activities Re Plants.List of Attendees Encl
ML20056F8171993-08-0909 August 1993
Summary of Operating Reactors Events Meeting 93-29 on 930804.List of Attendees & Viewgraphs Encl
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
ML20056D9841993-05-18018 May 1993
Summary of Operating Reactors Events Meeting 93-17 on 930512
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
ML20128H6211993-02-0808 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Positions on Operator Licensing Issues & to Solicit Input
1999-08-04
[Table view] |
Text
q X
1 f g .,o ,
g % UNITED STATES ,
,{}.c l g NUCLEAR REGULATORY COMMISSION j 5
s 4*~
l W ASHINGTON, D. C. 20555 ,]
- a. l l
SEP101g87 !
l l
l i
t;EMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING SEPTEMBER P,1987- MEETING 87-30 On September 8, 1987 an Operating Reactors Events meeting (87-30) was held to brief senior managers from NRR, RES, AEOD and Regional Offices on events which occurred since our last meeting on August 25, 1987. The list of attendees I is included as Enclosure 1. I l
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 ine'icator program.
'(
, L Way Lanning, Chie Events Assessment Br ch Division of Operational Events Assessment
Enclosures:
As stated I cc w/ Encl.:
See Next Page ;
i Y) #fj\h i^ ,
0 -
i 91g268
-.~.___._..._._m___ _ _ _ _ _ . _ . _-
l'EMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessrient FROM: Wayne Lanning, Chief Events Assessment Branch l Division of Operational Events Assessment
SUBJECT:
THE'0PERATING REACTORS EVENTS MEETING
- SEPTEMBER 8,1907 - MEETING 87-30 1
On September 8,1987 an Operatino Reactors Events meeting (87-30) was held to brief senior managers from NRR, RES, AEOD and Regional Offices on everts which occurred since our last meeting on August 25,1987. The list of attendees is included as Enclosure 1 The events discussed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 provides a summary of reactor scrams and "significant events" that will be input to HRC'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 slen' tral File)
L NRC PDR l EAB Rdg l EAB Members l
RUDYKARSCH RD FL N
PWR:EABC40 CSCHULTEN SL:PWR:EAB RLOBEL SLDM[]ABAff_h:
PBARAN011 SKY WtE NING j /}/87 T/([/87 ]/f/87 /p/87
l i
.l Charles E. Rossi i
~
cc: T. Murley. M. Grothenhuis !
J. Sniezek. D. Fuller l F. Miraglia L. 01shan !
'R. Starostecki J. Stevens !
E. Jordan J. Norris 1 J. Taylor D. Muller .
E. Beckjord D. Wiggington i W. Russell, Reg. I D. Hood j J. Nelson Grace, Reg. II B. Youngblood -l B. Davis, Reg. III J. Wermiel -
l R. D. Martin, Reg. IV A. Thadani J. B. Martin, Reg. V W. Kane, Reg. I L. Reyes, Reg. II C. Norelius,. Reg. III i R. Hall, Reg. IV '
D. Kirsch, Reg. V
- S. Varga D. Crutchfield B. Boger G. Lainas !
G. Holahan l F. Schroeder !
L. Shao l J. Partlow l B. Grimes i F. Congel l E. Weiss S. Black '
T. Martin, EDO E. Merschoff ,
R. Hernan H. Dailey J. Guttmann i
i k
. . . _ . . . . _ _ . _ .. ._ . m m ------ T - o
~'
b g ENCLOSURE 1 i
LIST OF ATTENDEES' OPERATING REACTORS EVENTS BRIEFING (87-30)
September 8, 1987 .
l NAME ORGANIZATION NAME ORGANIZATION TT Furley NRR/DONRR G. Holahan NRR/ADR J. Sniezek NRR/DONRR 'J. Kudrick NRR/SPLB
- i. ' R. Starostecki NRR/ADT T. Silko AEOD/IRB C. E. Rossi NRR/DOEA P. Baranowsky NRR/0EAB i W. Lanning NRR/0EAB M. Johnson NRR/ILRB A. DeAgazio. DRSP/PD31C. B. Grimes NRR/DRIS M. McCracken NRR/ECEB J. Partlow NRR/DRIS L. Shao NRR/ DEST G. Klingler NRR/ILRB.
D. A111sen AE0D/DEIIB M. Virgilio NRR/PD31 B. Boger NRR/ADR1 R. Scholl NRR/0EAB J. Roe NRR/DLPQ G. Cwalina NRR/LPEB I
.)
l l
l l
4
-- m - _ - - _ - - _ _ __ _ _ . _ _ _ . _ _ _ _ _ _ _ _ .
ENCLOSURE 2
{
(
OFERATING REACTCRS EVENTS BRIEFING 87-30
]
TUESDAY SEPTEMBER 8, 1987, 11 A.M. l l
THE AGENDA INFDPPATION MAY ALSO BE OBTAltED BY DIALING EXTENSION 2717L1. I I
I SAN ONOFRE 2 UNISOLAELE LEAK FROM RCS DAVIS-BESSE SCPAM WITH COMPLICATI0tE l
PEPRY ] SAFETY / RELIEF VALVE LEAKAGE PEACH BOTTOM 2/3 LOSS OF RHR SHtRIGN COOLING l 1
4 i
a' SAN ONOFRE'2 I UNIS0LABLE LEAK FROM RCS PROBLEM I
l CAUSE
- PACKING FAILbRE IN SHUTDOWN COOLING SYSTEM SUCTION ISOLATION VALVE SIGNIFICANCE )
'* RADI0 ACTIVE RELEASE TO THE PUBLIC AND CONTAMINATION OF PLANT l WORKERS
- PLANT SHUTDOWN FOR REFUELING 8/29; RCS AT 350 PSIG, 125*F
- VALVE MOTOR OPERATOR OVERHEATED AND FAILED I
- PLANT PERSONNEL ATTEMPTED TO OPEN VALVE WITH A WRENCH I
,
- FOLLOWER PLATE HOLDDOWN BOLTS FOUND TO BE CORRODED BY BORIC ACID l
- INITIAL EFFORTS TO REPLACE PACKING UNSUCCESSFUL
- AFTER 12 HOURS RCS DEPRESSURIZED AND VALVE REPACKED STOPPING LEAK
- CONTAINMENT PURGE MAINTAINED INLEAKAGE THROUGH OPEN EQUIPMENT HATCH
- HATCH WAS CLOSED IN 3 HOURS
- LICENSEE BEllEVES THAT NO TECH, SPECS WERE VIOLATED AND NO RADIOLOGICAL RELEASE LIMITS WERE EXCEEDED l
- 18,000 GALLONS SPILLED IN CONTAINMENT FOLLOWUP
- LICENSEE AND REGION ARE CONTINUING TO INVESTIGATE THE EVENT AND THE CAUSE OF VALVE FAILURE
- EAB EVALUATING CONTAINMENT INTEGRITY DURING SHUTDOWN AND EXPANDING INF0 NOTICE ON BORIC ACID CORROSION CONTACT: WALT JENSEN l
E!!! i r 1
)
, . Z . Z Z .Z . Z l
- e mssses. - mme - ~ mmm cs - 1 5 :-:: :.. . . . :4; : {:
l c 2 2 2 2 R R
~
i 1
em. emas.
I ._ __ _
! _ .-_ _ q B 5 1s vg - !
1 IE / \]$il l#
all=5l i l g7 it_ ..___> m _._ __ _ ;
d g,
,2 c --
ora og'1 iirt 5
! M :o: * - --
ae
- i !
1
". . 3 0ill oi:j 2
~
I 5
_ ~odoi:j oi:l*
l [l5 i' ilj S
s= =
l* p()q;j E 7 ,..._ __ . . .
- 01ll oi
- t ig__ - -
i E.%... . .. ..,' s.... ....E f f x A i e x x x
.r - -
- . . .- s- 5 -
s -
r .-
( 5 B q 5 3
3 g ( f ( f)c -q II l 01:g oi :g X X oi:iy o!:l
~ . - .
V M V M x ::
I 1 X X 7- -
~0I 8
T5
. ,a 5
/.. if B: -
ll :ll 01 l oi :l
-1 4
' DAVIS-BESSE SCRAM WITH-COMPLICATIONS I
SEPTEMBER 6, 1987 (1142).
FEED FLOW TRANSMITTER FAILED LOW HIGH FEED FLOW REDUCED TAVE, POSITIVE REACTIVITY INSERTION 1
REACTOR SCRAM ON HIGH FLUX-(105%)
- MAIN STEAM SAFETY VALVE FAILED OPEN LOST NON-VITAL POWER BUS - LOST 2 RCPs SERVICE WATER PUMP FAILED TO AUTO RESTART l
L 1449 ELECTRIC POWER RESTORED 1
1515 AFWS AUTO START ON LOW SG LEVEL TURBINE BYPASS VALVE FAILED'0 PEN STARTUP-FEED VALVES PREVIOUSLY ISOLATED SEPTEMBER 7, 1987 (0730) ,
i PRESSURIZING LEVEL DROPS 16 INCHES.WHEN DHR PUT IN' <
SERVICE VAPOR VENTED FROM DHR PUMP DISCHARGE CONTACT: R.LOBEL E. GREENMAN
PERRY llNIT 1
' SAFETY / RELIEF VALVE LEAKAGE SEPTEMBED ?, 1987 PROBLEM SRV LEAKAGE HAS CAUSED INCREASED TEMPERATURE AND LEVEL IN. SUPPRESSION POOL CAUSE LEAKING SAFETY / RELIEF VALVES SAFETY SIGNIFICANCE
- TECH SPECS DO NOT ADDRESS SRV LEAKAGE
' POTENTIAL DEGRADATION OF ADS-VALVES 1
DISCUSSION -
- ON SEPTEMBER 2 SUPPRESSION POOL LEVEL REACHED HIGH LEVEL SETPOINT DUE TO LEAKAGE VIA SRVs (6 GPM)
- RCIC AUTOMATICALLY TRANSFERED SUCTION FROM CST TO SUPPRESSION POOL
- OPERATOR RENDERED THE AUTOMATIC TRANSFER LOGIC INOPERABLE AND TRANSFERED SUCTION BACK TO CST
- RCIC DECLARED INOPERABLE BECAUSE IT CANNOT AUTOMATICALLY TRANSFER TO I l SUPPRESSION POOL (T.S. REQUIREMENT)
- SUPPRESSION P0OL WATER LEVEL LOWERED USING RHR ;'
- PROBLEM HAS EXISTED SINCE FALL OF 1986 (12 OR 13 SRV WERE WEEPING)
- 18 0F 19 SRVs ARE WEEPING BASED ON TEMPERATURE READINGS IN THE TAILPIPE OF ABOUT 250' F
- FLUID PAST SRV NOT CONSIDERED LEAKAGE FOLLOWUP
- REGION HAS DISCUSSED WITH LICENSEE MANAGEMENT
- EAB STILL EVALUATING CONTACT: TOM GREENE I
l l
.. l l
COMPAPISON OF BKE/ 6s WEEPING SRVs !
1 i
PLANT WEEPING SRVs/_ TOTAL NO, j I
CLINTON 3/16
]
RIVER BEND 12/19 i l
1 GRAh!D GULF 11/20 l l
GRAND GULF (AFTER ALL VALVES 6/20 CHANGED DURING 1sT l REFUELING)
PERRY 18/19 l
l l
l l
I l
l l
1 t
e 4
l b ^
- W ,L ' >Ki>;,
4S
)b,r i
- .$ .$ m -
E i
., g
. O 7 i
l
- I I-I s og" i i
i g a. ----4-----
i
.. J d
g y gg ,
l
. 18 =j i 9 : , =a ,
5 $ !. k. . @a @:5!!!!
ci s- ,, 3;->:e. .
e
-- d. .
- ..! $! g .:gg, d-
' ' r ~a .
$jj M
@f @ 8 $
iT v!
vs" s.
e 3 r : :-
z-st .
a a s, .,. aa ,
'k N.
E! h "W h I 8.
g E L . o
- !! !_! 5
-11l!-
%! I 8
=
w g
u .,
E I h x h'!,r, wg 5 u
I 1
r,r ) <
.Ut g :
E a :
E- .
x l
== -
~. c oi s 5 e O
Cr ! :m
! hk! r' -,
y a-
!$ OA I #'
i
X m,:
l lr / i=
I5*
n
I
\ -l8a
,- 1 I
h t
e
- .- PERRY UNIT 1 SAFETY / RELIEF VALVE ARRANGEMENT I
i l
'l m.
i SRV w- -@
k l Main Steam Line Vacuum
. Breakers D
R Y
.A
\ Supression Pool R .w W E A L Quencher
(.
L O
l l
i
~ . . ,
N g
w . .
nf
- o. -
i PEACH POTTOM LOSS OF RHP SilVTDOWN COOL!NG EVENTS' l
UNIT 2 l 1
3/13/87 GROJ P 2 ISOL, ON VESSEL SHRINK AFTER PLANNED MANUAL SCRAM 3/28/87 INADO MAINT PROCD FOR BUS RELAY COIL REPLACMNT DURING REFUEL OUTAGE
- 3/31/87 NRC ORDER l l l '4/07/87 LOSS-0F 0FFSITE POWER.(220KV -
6/30/87 INADEO MAINT PROCD,DURING RELAY REPLCMNT 7/10/87 LOSS OF PWR TO DIV 2 LOGIC BUS (FUSE)
'7/10/87 LOSS OF 0FFSITE POWER (220KV) (LIGHTNING STRIKE) ,
l 7/28/87 UNKNOWN-BREAKER OPENED l
'8/16/87 LOSS OF 0FFSITE POWER (220KV) 8/20/87 BLOWN FUSE-MAINTENANCE WORK 1
'8/20/87 LOSS OF OFFSITE POWER (220KV)
'l 8/28/87 INADEQUATE MAINT PROCEDURES 1 9/04/87 LOOSE WIRE UNIT 3.
3/31/87 ERROR DURING FILL OF SHUTDOWN COOLING SYST FOR-LINEUP.
- EVENT COMMON TO BOTH UNITS CONTACT: ~ CARL.SCHULTEN
. ENCLOSURE 3 F.EACTOR SCEAM
SUMMARY
WEEL E O IN3 6i/0$!2:
- 1. PLANT SFECIFIC LATA DATE SITE UNIT P0iiEP. EPS CAUSE COMPLI- YTD YTD YTD CATIONS APOVE BELOW TOTAL 151 .R t 09/02/07 MILLSTONE 2 90 A EQUlP N0 4 0 4 09/02/87 SUMMER 1 100 A EQUlFMENT NO 2 0 2 0?/03/87 CATAliBA 2 21 A FERSONNEL ND 7 0 7 03/0's/57 MILLSIONE 1 100 A EQUIP / MECH NO 3 1 4 09/03/07 INDIAN F0lNi 3 0A FERSONNEL N0 3 2 5 09/06/87 NC6UIRE 2 100 A UNKNOWN NO 2 0 2 09/06/87 DAVIS-EEESE ! 100 A UNr.NOWN YES I 0 I l
l l
SUMMARY
OF COMPLICATIONS I SITE UHli COMPLICATIONS l
DAV!3-BESSE 1 ONE MAIN STEAM SAFETY RELIEF VALVE FAILED TO RESEAT AND NON-VITAL BUS 'A' WAS LOST l
i l
l t
or II. COMP / C ISDN OF WEEl.:LY E.TATISTICG UITH INDUSTRY AVEPAGEE 5:~ RAMS F Ofi WEEl . END ! t JG 09 / OwiC'"
SCRAM CAUSE FOWER NUMBER 1937 1986 1985 OF WEEt:LY WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE AVERAGE YTD (3) (4) (8) (9)
EDUIP. RELATED '15% 5 4.5 4.7 5 . /.
PERS. RELATEDt6) r 1 S*. 1 1.4 1.8 2.0 OTHER (7 ) .-15% 2 1.O O.4 O . c- ,
- Subtotal *i l 6 7.O 6.5 8.0 l
EDUIP. RELATED :15% 0 1.~ 1.4 1.~ ;
PERS. RELATED <15% 3 Q.6 O.8 O.o l OTHER .15% O O.3 0.2 O.2 )
l 1 2.2 2.4 2.4
- Total **4 7 9.2 8.9 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE i YTD l
MANUAL SCRAMS O 1.5 1.O 1.O AUTOMATIC SCRAMS 7 7.7 7.9 9.4 l
l l
l l
l s
l 4 NOTES {
-1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS 4
FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY SCRNiS ARE PEFINED AS REACTOR PROTECTIVE I ACTUATIONS WHICP RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITF A PLANT PROCEDURE.
- 2. RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
- 3. 1986 INFORMATION DERIVED-FROM ORAS STUDY OF UNPLANNED REACTOR l
TRIPS IN 1986. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS
)
IN A GIVEN CATEGORY AND DIVIDING BY 5? WEEKS / YEAR.
- 4. IN 1986, THERE WERE AN ESTIMATED TOTAL OF 461 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 104 PEACTORS (HOLDING '
OPERATINGLICENSES). 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.
l
- 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 SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
- 8. 1D85 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 (POLDING FULL POWER LICENSES). THIS Y1 ELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.
o....___
F aa N;. i
- ::!E?
FERFCRMANC: INDICATOR 5 SIGNIFICANT EVENT 3 ,
1 iL A';i hAMI EVENT EVENT LE5;RIFi10h QTR SIGNIFICANCE LATE LAVI5 EESSE 09/06/87 SCRAM COMPLICATED BY MAIN STEAM SAFETY VALVE FAILURE 10 1 SCRAM WITH COMPLICATIONS RESEAi AND LOSS OF THREE RCFs 3AN CNDFRE :- 08/;1/87 UN!50LABLE LEAL IN REACTOR C001. ANT SYSTEM DURINS COLD 1 F0TENTIAL FOR GR ACTUAL LEERADATION SHUTLOWN OF FRIMARY COOLANT FRE55URE FOUNDARY 8
-_-_ ___ ______-__ _____ -_ __ _ __ ______ _ _--- _