|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20198J1651998-12-15015 December 1998
Summary of 981118 Meeting with Util in Rockville,Md Re Ampacity Validation Analyses.List of Attendees & Handouts Provided by Util Encl
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
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
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
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
ML20059B0971993-10-20020 October 1993
Summary of Operating Reactors Events Meeting 93-39 on 931013
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
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
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
ML20128H6211993-02-0808 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Positions on Operator Licensing Issues & to Solicit Input
ML20126K5111992-12-30030 December 1992
Summary of Operating Reactors Events Meeting 92-022 on 921223.Reactor Scram Statistics for Wk Ending 921230 Encl & List of Attendees Encl
ML20126F1241992-12-10010 December 1992
Summary of 921201 Meeting W/Util in Rockville,Md Re Various Licensing Activities.List of Attendees Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20195H0271988-11-25025 November 1988
Summary of Operating Reactor Events Meeting 88-46 on 881122
ML20205C9601988-10-20020 October 1988
Summary of 881019 Meeting W/Util in Rockville,Md Re Util 880907 Submittal Re Protection from Degraded Voltage Conditions.List of Attendees & Agenda Encl
ML20151M0321988-07-28028 July 1988
Summary of 880519 Meeting W/Util in Rockville,Md to Discuss Licensee Plan for Facility Restart.List of Attendees, Agenda & Viewgraphs Encl
ML20195B2211988-06-0808 June 1988
Summary of Operating Reactors Events Meeting 88-23 on 880607.List of Attendees,Events Discussed & Summary of Reactor Scrams Encl
ML20196D3841988-02-10010 February 1988
Summary of Operating Reactors Events Meeting 88-05 on 880202 on Events Since 880126 Meeting.List of Attendees, Events Discussed,Tabulation of long-term Followup Assignments & 10CFR50.72 Rept Tabulation & Summary Encl
ML20196A2161988-01-0505 January 1988
Trip Rept of Commissioner Carr & T Elsasser 871215 Site Visit to Util & 871216 Attendance at Region I Periodic Regional Resident Counterpart Meeting
IA-88-478, Trip Rept of Commissioner Carr & T Elsasser 871215 Site Visit to Util & 871216 Attendance at Region I Periodic Regional Resident Counterpart Meeting1988-01-0505 January 1988
Trip Rept of Commissioner Carr & T Elsasser 871215 Site Visit to Util & 871216 Attendance at Region I Periodic Regional Resident Counterpart Meeting
IR 05000277/19850231987-09-14014 September 1987
Summary of 870730 Meeting W/Util at Site Re Containment Leakage Testing,Fire Protection Issues,Insp Repts 50-277/85-23 & 50-278/85-23 & Util 860915 & 1010 Amended Requests for Changes to Tech Specs.Attendance List Encl
ML20239A0231987-09-10010 September 1987
Summary of Operating Reactor Events Meeting 87-30 on 870908, Re Briefing Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870825 Meeting.Attendees List,Summary of Reactor Scrams & Viewgraphs Encl
ML20236F2181987-07-26026 July 1987
Summary of 870715 Meeting W/Util in Bethesda,Md Re Status of Util Recovery Program for Facility Operations.List of Attendees,Viewgraphs & Meeting Transcript Encl
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20214J4991987-05-15015 May 1987
Summary of Operating Reactors Events Meeting 87-09 on 870330 Re Events Which Occurred Since 870316 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20214P9371986-11-21021 November 1986
Summary of Operating Reactor Events Meeting 86-39 on 861110.List of Attendees,Events Discussed & Significant Elements of Events Encl
ML20213F0641986-11-10010 November 1986
Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl
ML20215G0561986-10-0707 October 1986
Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed
ML20212K3101986-08-13013 August 1986
Summary of 860708 Meeting W/Util in Bethesda,Md Re Topical Reload Program for Plant.List of Attendees,Proposed Meeting Agenda & Slide Presentation Encl
ML20205Q4541986-05-13013 May 1986
Summary of 860506 Meeting W/Util in Bethesda,Md Re Special Circumstances for Util Requested Exemptions to 10CFR50, App R
ML20197F7721986-05-0808 May 1986
Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20197F1691986-05-0808 May 1986
Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors
ML20203M9431986-04-25025 April 1986
Summary of Operating Reactors Events Meeting 86-13 on 860421 Re Events Occurring Since 860414 Meeting.Attendance List, Viewgraphs & Supporting Documentation Encl
ML20203P6801986-04-22022 April 1986
Summary of 860410 Meeting W/Project Managers & Utils in Bethesda,Md Re Automated Tracking,Integrated Schedules & Tech Specs.Attendees List,Viewgraphs & Meeting Agenda Encl
ML20203E8051986-04-18018 April 1986
Summary of Operating Reactors Events Meeting 86-12 on 860414 Re Events Since 860407.List of Attendees,Viewgraphs & Supporting Documentation Encl
ML20154N8751986-03-12012 March 1986
Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl
ML20137Y5861986-03-0404 March 1986
Summary of Nrc/Idcor 851210 Meeting Re Preliminary Results & Differences of Risk Analysis for Facilities.Viewgraphs Encl
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20141K0981986-01-14014 January 1986
Summary of 851219 Meeting W/Util in Bethesda,Md Re Shroud Head Bolt Cracks & RHR Wear Ring Cracks.List of Meeting Attendees & Viewgraphs Encl
ML20141K0461986-01-0808 January 1986
Summary of 851031 Meeting W/Util in Bethesda,Md Re IGSCC Cracking.List of Meeting Attendees & Viewgraphs Encl. Viewgraphs Withheld
ML20151N3021985-12-19019 December 1985
Summary of 851216 Operating Reactor Events Meeting 85-27. Attendance List,Viewgraphs of Events Discussed,Significant Event Elements,Assignment of Followup Review Responsibility & Status of Previous Assignments Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20138P0081985-10-21021 October 1985
Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007
ML20205E7101985-10-0909 October 1985
Summary of 851001 Meeting W/Util & GE in Bethesda,Md Re Cracking Identified in 316 L Grade Stainless Steel Recirculation Outlet Safe Ends.Proprietary Viewgraphs Encl. Viewgraphs Withheld (Ref 10CFR2.790)
ML20133F9941985-10-0707 October 1985
Summary of Operating Reactors Events Meeting 85-16 on 850916 Re Briefing of Director,Div Directors & Representatives on Events Occurring Since 850909 Meeting.List of Attendees & Viewgraphs Encl
1998-12-15
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20198J1651998-12-15015 December 1998
Summary of 981118 Meeting with Util in Rockville,Md Re Ampacity Validation Analyses.List of Attendees & Handouts Provided by Util Encl
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
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
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
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
ML20059B0971993-10-20020 October 1993
Summary of Operating Reactors Events Meeting 93-39 on 931013
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
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
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
ML20128H6211993-02-0808 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Positions on Operator Licensing Issues & to Solicit Input
ML20126K5111992-12-30030 December 1992
Summary of Operating Reactors Events Meeting 92-022 on 921223.Reactor Scram Statistics for Wk Ending 921230 Encl & List of Attendees Encl
ML20126F1241992-12-10010 December 1992
Summary of 921201 Meeting W/Util in Rockville,Md Re Various Licensing Activities.List of Attendees Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20195H0271988-11-25025 November 1988
Summary of Operating Reactor Events Meeting 88-46 on 881122
ML20205C9601988-10-20020 October 1988
Summary of 881019 Meeting W/Util in Rockville,Md Re Util 880907 Submittal Re Protection from Degraded Voltage Conditions.List of Attendees & Agenda Encl
ML20151M0321988-07-28028 July 1988
Summary of 880519 Meeting W/Util in Rockville,Md to Discuss Licensee Plan for Facility Restart.List of Attendees, Agenda & Viewgraphs Encl
ML20195B2211988-06-0808 June 1988
Summary of Operating Reactors Events Meeting 88-23 on 880607.List of Attendees,Events Discussed & Summary of Reactor Scrams Encl
ML20196D3841988-02-10010 February 1988
Summary of Operating Reactors Events Meeting 88-05 on 880202 on Events Since 880126 Meeting.List of Attendees, Events Discussed,Tabulation of long-term Followup Assignments & 10CFR50.72 Rept Tabulation & Summary Encl
IR 05000277/19850231987-09-14014 September 1987
Summary of 870730 Meeting W/Util at Site Re Containment Leakage Testing,Fire Protection Issues,Insp Repts 50-277/85-23 & 50-278/85-23 & Util 860915 & 1010 Amended Requests for Changes to Tech Specs.Attendance List Encl
ML20239A0231987-09-10010 September 1987
Summary of Operating Reactor Events Meeting 87-30 on 870908, Re Briefing Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870825 Meeting.Attendees List,Summary of Reactor Scrams & Viewgraphs Encl
ML20236F2181987-07-26026 July 1987
Summary of 870715 Meeting W/Util in Bethesda,Md Re Status of Util Recovery Program for Facility Operations.List of Attendees,Viewgraphs & Meeting Transcript Encl
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20214J4991987-05-15015 May 1987
Summary of Operating Reactors Events Meeting 87-09 on 870330 Re Events Which Occurred Since 870316 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20214P9371986-11-21021 November 1986
Summary of Operating Reactor Events Meeting 86-39 on 861110.List of Attendees,Events Discussed & Significant Elements of Events Encl
ML20213F0641986-11-10010 November 1986
Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl
ML20215G0561986-10-0707 October 1986
Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed
ML20212K3101986-08-13013 August 1986
Summary of 860708 Meeting W/Util in Bethesda,Md Re Topical Reload Program for Plant.List of Attendees,Proposed Meeting Agenda & Slide Presentation Encl
ML20205Q4541986-05-13013 May 1986
Summary of 860506 Meeting W/Util in Bethesda,Md Re Special Circumstances for Util Requested Exemptions to 10CFR50, App R
ML20197F1691986-05-0808 May 1986
Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors
ML20197F7721986-05-0808 May 1986
Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20203M9431986-04-25025 April 1986
Summary of Operating Reactors Events Meeting 86-13 on 860421 Re Events Occurring Since 860414 Meeting.Attendance List, Viewgraphs & Supporting Documentation Encl
ML20203P6801986-04-22022 April 1986
Summary of 860410 Meeting W/Project Managers & Utils in Bethesda,Md Re Automated Tracking,Integrated Schedules & Tech Specs.Attendees List,Viewgraphs & Meeting Agenda Encl
ML20203E8051986-04-18018 April 1986
Summary of Operating Reactors Events Meeting 86-12 on 860414 Re Events Since 860407.List of Attendees,Viewgraphs & Supporting Documentation Encl
ML20154N8751986-03-12012 March 1986
Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl
ML20137Y5861986-03-0404 March 1986
Summary of Nrc/Idcor 851210 Meeting Re Preliminary Results & Differences of Risk Analysis for Facilities.Viewgraphs Encl
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20141K0981986-01-14014 January 1986
Summary of 851219 Meeting W/Util in Bethesda,Md Re Shroud Head Bolt Cracks & RHR Wear Ring Cracks.List of Meeting Attendees & Viewgraphs Encl
ML20141K0461986-01-0808 January 1986
Summary of 851031 Meeting W/Util in Bethesda,Md Re IGSCC Cracking.List of Meeting Attendees & Viewgraphs Encl. Viewgraphs Withheld
ML20151N3021985-12-19019 December 1985
Summary of 851216 Operating Reactor Events Meeting 85-27. Attendance List,Viewgraphs of Events Discussed,Significant Event Elements,Assignment of Followup Review Responsibility & Status of Previous Assignments Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20138P0081985-10-21021 October 1985
Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007
ML20205E7101985-10-0909 October 1985
Summary of 851001 Meeting W/Util & GE in Bethesda,Md Re Cracking Identified in 316 L Grade Stainless Steel Recirculation Outlet Safe Ends.Proprietary Viewgraphs Encl. Viewgraphs Withheld (Ref 10CFR2.790)
ML20133F9941985-10-0707 October 1985
Summary of Operating Reactors Events Meeting 85-16 on 850916 Re Briefing of Director,Div Directors & Representatives on Events Occurring Since 850909 Meeting.List of Attendees & Viewgraphs Encl
ML20133E5661985-10-0303 October 1985
Summary of 850905 & 17 Meetings W/Util in Bethesda,Md Re Recent Detection of IGSCC on Recirculation & RHR Sys Piping & Cracks on Core Spray Line,Respectively.List of Participants & Presentation Encl
ML20133E4631985-10-0101 October 1985
Summary of Operating Reactors Events Meeting 85-17 on 850923.List of Attendees & Viewgraphs Encl
1998-12-15
[Table view] |
Text
_ - _ - - _ _ _ _ _
x e
( DEC 3 01992 i
MEMORANDUM FOR: Brian K. Grimes, Director Division of Operating Reactor Support FROM: Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Suppo,rt -
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING DECEMBER 23, 1992 - BRIEFING 92-22 On December 23, 1992, we conducted an Operating Reactors Events Briefing (92-22) to inform senior managers from offices of the Commission, AEOD, ACRS, NRR, and regional offices of selected events that occurred since our last briefing on December 16, 1992. Attachment 1 lists the attendees. Attachment 2 presents the significant elements of the discussed events.
Attachment 3 contains reactor scram statistics for the week .
ending 12/20/92. No significant events were identified for input into the NRC performance indicator program.
Original signed by Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support Attachments: As stated DISTRIBUTION:
Central Files cc w/ attachments: PDR See next page EAB R/F KGray JCarter LKilgore, SECY bob 110 g
M F- / DORS (B/gRS EAB/ DORS KGray:kag Dengig AChaffee 12/g'g/92 124tT/92 12/3b/92 OFFICIAL RECORD COPY -r - -
DOCUMENT NAME: ORTRANS.KAG (G:KAG) _I O r '7 ' ~ C' #
d: 7 . .
~
9301070157 Wid3b h ,
i PDR ORG NRRB PDR
cc:
T. Murley, NRR (12G18) J. Shea, (PDI-2)
F. Miraglia, NRR (12G18) C. Miller, (PDI-2)
F. Gillespie, NRR (12G18)
J. Partlow, llRR (12G18)
S. Varga, llRR (14E4)
J. Calvo, NRR (14A4)
G. Lainas, NRR (14H3)
J. Roe, NRR (13E4)
J. Zwolinski, NRR (13H24)
. M. Virgilio, URR (13E4)
W. Russell, NRR (12G18)
J. Richardson, NRR (7D26)
A. Thadani, NPR (BE2)
S. Rosenberg, NRR (10E4)
C. Rossi, NRR (9A2)
B. Boger, NRR (10H3)
F. Congel, NRR (10E2)
D. Crutchfield, NRR (11H21)
W. Travers, NRR (11B19)
D. Coe, ACRS (P-315)
E. Jordan, AEOD (MN-3701)
T. Novak, AEOD (MN-9112)
L. Spessard, AEOD (MN-3701)
K. Brockman, AEOD (MN-3206)
S. Rubin, AEOD (MN-5219)
M. Harper, AEOD (MN-9112)
J. Grant, EDO (17G21)
R. Newlin, GPA (2GS)
E. Beckjord, RES (NLS-007)
A. Bates, SECY (16G15)
G. Rammling, OCM (16G15)
T. Martin, Region I W. Kane, Region I C. Hehl, Region I S. Ebneter, Region II E. Merschoff, Region II B. Davis, Region III E. Greenman, Region III J. Milhoan, Region IV B. Beach, Region IV J.B. Martin, Region V K. Perkins, Region V bcc: Mr. Sam Newton, Manager Events Analysis Department Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, GA 30339-3064
_ . . . . . . - . . ~ . . . . _ . .-_
ATTACHMENT 1 LIST OF ATTENDEES.
OPERATING REACTORS EVENTS FULL BRIEFING'(92-22)
DECEMBER 23, 1992 l!NiE OFFICE FAME OFFICE R. DENNIG NRR C. MILLER NRR J. CARTER NRR G. MARCUS NRR K. GRAY NRR F..RINALDI NRR T. KOSHY NRR C. THOMAS NRR '
E. GOODWIN NRR S. LONG NRR J. TSAO NRR G. ~HUBBARD NRR C. BERLINGER NRR S. BAJWA NRR B. GRIMES riRR M. FLEISHMAN OCM/KR
.; S. VARGA NRR V. BENAROYA AEOD G. ZECH NRR D. COE ACRS C. ROSSI NRR TELEPHONE ATTENDANCE I
(AT ROLL CALL)
Reciong Resident Insoectors Region I Peach' Bottom (J. Lyash)
Region II '
Region III ,
Region IV Region V AIT Team Leaders Misc.
, _. . _ , _,_..___._____r . _ , , _ . , . _ _ _ . ._
- ATTACHMENT 2 OPERATING REACTORS EVENTS BRIEFING 92-22' EVENTS ASSESSMENT-BRANCH LOCATION: 10 B11, WHITE FLINT WEDNESDAY, DECEMBER 23, 1992, 11:00 A.M.
PEACH BOTTOM, UNIT 3 EXCEEDING BOTTOM HEAD PRESSURE / TEMPERATURE-LIMITS VARIOUS PLANTS ELECTRICAL CABLE DEFICIENCY
92-22 PEACH BOTTOM, UNIT 3 EXCEEDING BOTTOM HEAD PRESSURE / TEMPERATURE LIMITS OCTOBER 16, 1992 PRO.B1E14 DURING A C00LD0WN F0LLOWING A REACTOR SCRAM, THE TEMPERATURE OF THE REACTOR VESSEL BOTTOM HEAD WENT BELOW THE MINIMUM TEMPERATURE / PRESSURE VALUES SPECIFIED BY TECHNICAL SPECIFICATIONS FOR ASSURING REACTOR VESSEL INTEGRITY.
CAUSE INADEQUATE PROCEDURES AND OPERATOR AWARENESS OF REACTOR VESSEL BOTTOM HEAD PRESSURE / TEMPERATURE LIMITATIONS.
SAFETY-SIGNIFICANCE REDUCTION IN NDT MARGIN OF SAFETY.
DISCUSSION e REACTOR EXPERIENCED A CONTAINMENT ISOLATION CAUSED BY BUMPING A SWITCH MSIVs CLOSED AND REACTOR SCRAMMED e HPCI AhD RCIC AUTOMATICALLY INITIATED AND RECIRC PUMPS WERE STOPPED ON LOW LOW WATER LEVEL.
e SAFETY RELIEF VALVES LIFTED AND RESEATED.
CONTACTS: J. CARTER, NRR/ DORS 'AIT: EQ J. LYASH, SRI SIGEVENT: TBD
REFERENCES:
10 CFR 50.72 #24437 AND LER-92-008
92-22 f' PEACH BOTTOM e HPCI, RCIC, AND SAFETY VALVES USED TO CONTROL LEVEL AND PRESSURE.
- CRD WATER CONTINUED TO FLOW INTO THE REACTOR BOTTOM HEAD AREA.
- RESULTING THERMAL STRATIFICATION (>145 F) PREVENTED RESTARTING RECIRC PUMPS.
o SUBSEQUENT EVALUATION OF RECORDED DATA BY REACTOR INSPECTOR IDENTIFIED THAT THE BOTTOM HEAD TEMPERATURE DECREASED TO ABOUT 112 F WITH A SYSTEM PRESSURE OF 600 PSI THIS IS ABOUT 40 F LOWER THAN TECHNICAL SPECIFICATION LIMIT TEMPERATURE BELOW LIMIT CURVE FOR ABOUT 6 HOURS e NOTICE OF VIOLATION ISSUED.
e LICENSEE ENGAGED GE TO EVALUATE THE EFFECT ON REACTOR INTEGRITY PRELIMINARY RESULTS ARE THAT ADEQUATE SAFETY MARGIN EXISTED FINAL REPORT DUE IN MARCH e OPERATORS LOGGED TEMPERATURES BUT DID NOT ASSOCIATE THEM WITH BOTTOM HEAD LIMITS; PROCEDURES DID NOT REQUIRE CHECKING LIMIT CURVE FOR ACCEPTABILITY.
I
- - - - - - - - - - _ _ _ _ _ . _ ~ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _
PEACH BOTTOM 92-22 e RECORDED DATA AVAILABLE IN CONTROL ROOM; COMMINGLED WITH OTHER DATA.
e INP0 EVALUATED EVENT AND ISSUED SEN 0N 12/15/1992
-- GE PREVIOUSLY ISSUED SIL 251 IN 1977 AND SIL 430 IN 1985 e LICENSEE REVISING PROCEDURES AND ALERTING OPERATORS.
SIMILAR EVENTS e STRATIFICATION EVENTS OCCURRED AT HATCH AND SUSQUEHANNA.
FOLLOWUP e REGION IS EVALUATING EVENT PLANS TO ASSESS CURRENTLY AVAILABLE INFORMATION CONCERNED ABOUT WHAT IS CRITICAL CRACK SIZE e NEED FOR INFORMATION NOTICE IS BEING EVALUATED.
- NRR WILL ASSIST REGION IN EVALUATING GE ANALYSIS.
l l
1
1 i
BRIEFING 92-22 PEACH BOTTOM. UNIT 3 4
1600 ; g g ,
I 14CO -
g ,
I n .!
cn J
'm I O 1200- .
a ' lf '
b ! l
= 1
- c. I 3 1000 - / ,
s I W
tn i m
Il 800 l f ct 8 - NON-NUCLEAR HEATUP/
j coOtocwN uuiT
_O ,
-f (BASED ON F# NCZZLE)
._: r b
% . B., - NON-NUCLEAR HEATUP/
/ COOLDOWN uMIT FOR Z ovv J j ECTTCM r M KE ,.Ch
,{,, ,/ T WITH RTNOT = $#F 3 / i Z i* , ! I i
l VE5SEL C.5CCNT..NLITt N
400 t uuiTs
{ l m l - - SCfrOM HEAD g ...-.a DISCCNTINUITY UMITS cc C
CURVES B AND B,,, ARE VAUD 200 FOR 32 EFFY OF OPERATION BOLTUP=
70'r ! 32 EFPY BELTUNE CURVE 15 LESS UMITING THAN Y-- O!5 CONTINUITY CURVE S 0 i ,
i i i i 0 100 200 300 400 500 600 MINIMUM REACTOR VE3SEL ME"TAL TE,MPERATURE ('F)
Figura 3.6.2 Peach Bottorn 3 vinier.um Temocrcture for Mechanicci Hectup or Cooldown Following Nuclear Shutcown Amendment No. 45, 164 -164a-
___J_U_ N 2 7_mt_
'j i
POTENTIAL DEFICIENCY- ;
OF ELECTRICAL 1 CABLES WITH BONDED JACKETS (Ref.10 CFR 50.49) ,
b GEORGE HUBBARD
- PLANT SYSTEMS BRANCH 5
1 i
i SAFETY SIGNIFICANCE
,k y
RECENT SANDIA TEST RESULTS INDICATE THAT BONDED-JACKET CABLES.MAY Fall DURING A LOCA BEFORE 40 YEARS !F THESE. CABLES ARE USED AT TEMPERATURES GREATER THAN 50' C (122 F) i .
t
+
T _ _ m 4 _
SANDIA TEST PROGRAM ACCELERATED AGING TESTS OF OKONITE SINGLE-CONDUCTOR, 12 GAUGE,600V CONTROL CABLES WITH BONDED HYPALON JACKET WERE PERFORMED TO DETERMINE: l i
e THE POSSIBILITY OF EXTENDING CABLE QUALIFICATION TO 60 YEARS FOR LICENSE RENEWAL.
e THE EFFECTS OF CABLE DAMAGE DURING INSTALLATIOPJ NOTE: TESTING BY SANDIA WAS CONSISTENT WITH IEEE 323-1974 REQUIREMENTS
I TEST RESULTS ALL OKONITE CABLES PASSED AT THESE TEST CONDITIONS:
a
-*' 100 C/212 F FOR 3 MONTHS FOLLOWED BY LOCA TEST (EQUIVALENT TO 40 YEARS AT 48 C/118 F)
.* 100 C FOR'6 MONTHS FOLLOWED BY LOCA TEST
, .(EQUIVALENT TO 40 YEARS AT 52 C/126 F) ,
FAILURES OCCURRED AT MORE SEVERE AGING CONDITIONS:
- ONE OF FOUR SAMPLES. FAILED DURING LOCA TEST, AGED AT 100 C/212 F FOR 9 MONTHS FOLLOWED BY LOCA TEST (EQUIVALENTTO 40 YEARS AT 56 C/133 F)
- ALL SAMPLES FAILED DURING LOCA TEST, AGED AT 158 C/316 F FOR 336 HOURS FOLLOWED BY LOCA TEST
.(EQUIVALENT TO 40. YEARS AT 69 C/156 F)
., j I
.i
. . _ , ~ . . .
TEST RESULTS (CONTINUED)
DEKORON DEKORAD CABLES:
- ONE OF THREE SAMPLES FAILED DURING LOCA TEST, AGED AT 100 C/212 F FOR 3 MONTHS FOLLOWED BY LOCA TEST (EQUIVALENT TO 40 YEARS AT 48 C/118 F)
- ALL CABLES PASSED, AGED AT 100 C FOR 6 MONTHS FOLLOWED BY LOCA TEST (EQUIVALENT TO 40 YEARS AT 52 C/126 F)
- ONE OF FOUR CABLES FAILED DURING LOCA TEST, AGED AT 100 C FOR 9 MONTHS FOLLOWED BY LOCA TEST l (EQUIVALENT TO 40 YEARS AT 56 C/133 F) t
1 t
OKONITE. QUALIFICATION
SUMMARY
. QUALIFICATION PERFORMED ON 600-VOLT, #12, 30-Mil EPR SINGLE-1 CONDUCTOR. CONTROL' CABLE AND 2KV, #6, 55-Mll EPR POWER CABLE WITH '30-Mil BONDED JACKET .
AGING-e 3 WEEKS AT.150 C t
'e -200 MEGARADS AT <1 MEGARAD/ HOUR LOCA TEST. 1 e IEEE 323-1974 30-DAY LOCA TEST PLUS 100 DAYS
~
-QUALIFIED FOR 40 YEARS' AT 90 C i
ji y -
. l + , . _ . -
l I
DEKORON QUALIFICATION
SUMMARY
A G I N G_
- 163 C FOR 7 DAYS, EPR ONLY
- JACKET APPLIED BEFORE RADIATION AGING
- 175 MEGARADS ACCIDENT DOSE
_LOCA TE_S_T
QUALIFIED FOR 40 YEARS AT 52 C
y SHORT-TERM SAFETY SIGNIFICANCE :
1
- MOST SIGNIFICANT FOR CABLES IN CONTAINMENT ;
e- FEW SAFETY-RELATED CABLES IN CONTAINMENT ARE AFFECTED e CABLES IN CONTAINMENT HAVE BEEN IN SERVICE FOR <40 YEARS
- BWR DRYWELL TEMPERATURES TYPICALLY 57-66 C
-* PWR CONTAINMENT TEMPERATURES 37-43 .C OUTSIDE REACTOR ~
CAVITY a
- l
.. \ 6 -
s-. . +-
. a a
e
! SHORT-TERM SAFETY SIGNIFICANCE .
(CONTINUED) 4
- PROBABILITY OF A LARGE-BREAK LOCA IS APPROXIMATELY 10 PER i REACTOR YEAR
- THERE ARE UNCERTAINTIES IN ESTIMATING CABLE LIFE USING THE ARRHENIUS EQUATION. '
t
- BASED ON EPRI DATA, OKONITE CABLE IS USED IN CONTAINMENT.
AT 25 POWER REACTORS. !
DO NOT KNOW HOW MUCH OF THIS CABLE IS JACKETED OR i
.HOW.MUCH IS IN SAFETY APPLICATIONS LONG-TERM. SAFETY SIGNIFICANCE DEPENDS ON PLANT-SPECIFIC i APPLICATIONS. :
l 1
i j
1
L M . N E LJ M ACTIONS TAKEN e MEETING WITH OKONITE, SANDIA, AND NUMARC 11/23/92 e MEMO TO COMMISSION 12/10/92 e INFORMATION NOTICE ISSUED 12/11/92
k i
i OKONITE'S CONCERNS q
. 1 e AGING RADIATION & ACCIDENT RADIATION DOSE WAS APPLIED BEFORE ANY THERMAL AGING. l e THE CABLE WAS'OVERAGED DURING THERMAL AGING (336 HOURS-VS 200 HOURS) ;
5
1 a
i INFORMATION NOTICE e SANDIA TEST PROGRAM e FAILURES OF OKONITE EPR/HYPALON CABLES e FAILURES OF DEKORON EPR/HYPALON CABLES CONCLUSION e BONDED JACKETS' MAY CAUSE CABLE FAILURES a
e SOME BONDED-JACKET CABLES HAVE BEEN QUALIFIED WITHOUT A JACKET e .QUALIFIC'ATION TESTS PERFORMEDLWITHOUT THE BONDED JACKET l t
ARE NOT REPRESENTATIVE OF-ACTUAL CABLE PERFORMANCE e CONCERNS AT SERVICE TEMPERATURES > 50 C .
l'
j ACTIONS PLANNED LETTER DRAFTED ASKING NUMARC TO TAKE THE LEAD IN COORDINATING INDUSTRY'S RESPONSE e IDENTIFY.WHICH PLANTS ARE USING THIS CABLE
- - IDENTIFY SPECIFIC APPLICATIONS e INSPECT TO DETERMINE MATERIAL CONDITION OF CABLES BASED ON INDUSTRY ACTIONS, THE STAFF WILL CONSIDER ADDITIONAL ACTIONS
- ASSESS NEED FOR ADDITIONAL GENERIC COMMUNICATIONS ]
l e DETERMINE LONG TERM SAFETY SIGNIFICANCE a
- DETERMINE AND IMPLEMENT ACTION REQUIRED FOR RESOLUTION t
i t
' ATTACHMENT 3 I.
REACTOR SCRAM
SUMMARY
WEEK ENDING 12/20/92
- 1. PLANT SPECIFIC DATA")
DATE SITE UNIT POWER SIGNAL CAUSE COMPL1-(3) YTD YTD YTD C ATIONS AB0VE BELOW TOTAL 15% 15%
2 100 A PERSONNEL NO 2 0 2 12/14/92 CATAWBA 2 0 2 1 70 A PERSONNEL NO - - - -
12/20/92 PILGRIM sem
-- ___._-_..___.___._____m _ _ _ _ _ . _ _ _ _ _ _ _ _
. +
!!. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 12/20/92 NUMBER 1992 1991 1990 1989 1988 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
POSER GREATER THAN 15%
EQUIPMENT RELATED 0 2.6 2.9 3.4 3.1 3.0 PERSONNEL RELATED (2) 2 0.8 0.6 0.5 1.0 1.0 OTHER (4) 0 0.0 0.0 0.0 0.1 0.4 Subtotal 2 3.4 3.5 3.9 4.2 4.4 POSER LESS THAN 15%
EQUIPMENT RELATED 0 0.5 0.3 0.4 0.3 0.6 PERSONNEL RELATED (2) 0 0.2 0.2 0.1 0.3 0.4 OTHER (4) 0 0.0 0.0 0.0 0.0 0.2 Subtotal 0 0.7 0.5 0.5 0.6 1.2 TOTAL 2 4.1 4.0 4.4 4.8 5.6 MANUAL VS AUTO SCRAMS 1992- 1991 1990 1989 1988 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY TYPE- SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
MANUAL SCRAMS 0 1.0 0.7 1.2 0.9 1.1
- AUTOMATIC SCRAMS 2 3.1 3.3 3.2 3.9 4.5 l
l l
e e.
t!9.1El
- 1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 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 M0110N, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. -THERE ARE 111 REACTORS HOLDING AN OPERATING LICENSE.
- 2. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
- 3. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
- 4. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
OEAB SCRAM DATA Manual and Automatic Scrams for 1987 ------------------ 435 Manual and Automatic Scrams for 1988 ------------------ 291 Manual and Automatic Scrams for 1989 ------------------ 252 Manual and Automatic Scrams for 1990 ------------------ 226 Manual and Automatic Scrams for 1991 ------------------ 206 Manual and Automatic _ Scrams for 1992 --(YTD 12/20/92)-- 207
