|
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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
ML20196F6101998-12-0101 December 1998
Summary of 981029 Meeting with Northern States Power, Wisconsin Electric,Wisconsin Public Service & Alliant-IES in Rockville,Md Re Various Aspects of Potential Regulatory Issues Associated with Ongoing Cooperative Efforts
ML20236L1061998-06-29029 June 1998
Summary of 980204 Meeting W/Util in Rockville,Md Re Methodologies Being Implemented by Ies Utilities,Inc to Resolve Issued Identified by NRC Bulletin 96-003.List of Meeting Participants & Handouts Encl
ML20199F4081997-11-10010 November 1997
Summary of 971105-06 Meeting W/Ies Utilities,Inc Re Responses Provided by Licensee on Following DAEC ITS sections,1,2,3.0,3.1,3.2,3.4,3.5,3.7,3.9,4 & 5.List of Attendees Encl
ML20211P0621997-10-10010 October 1997
Summary of 970909-10 Meeting W/Licensee Re Portions of DAEC Improved TS That Seek to Delay Entry Into LCO When Performing Surveillances Required by Improved TS
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
ML20148U5351997-06-30030 June 1997
Summary of 970618 Meeting W/Ies Util,Inc Re Unique Aspects of Duane Arnold Energy Ctr Design Wrt Loop Select Logic. List of Attendees & Licensees Handout 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
ML20147J1981997-04-0909 April 1997
Summary of 970403 Meeting W/Ies Utilities,Inc Re Current Fuel Storage Status & Options at Duane Arnold Energy Ctr. List of Attendees Encl
ML20137Q0341997-04-0303 April 1997
Summary of 970320 Meeting W/Util Re TS Setpoints & Practice of Not Entering LCO Action Statements During Certain Surveillances.List of Attendees Attached
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
ML20086N7091995-06-0606 June 1995
Trip Rept of 950523-25 Visit to DAEC Re Const Details & Standoff Calculations
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
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
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
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20058D2851990-10-29029 October 1990
Summary of Operating Reactors Events Meeting 90-26 on 901024.List of Attendees & Rept of Reactor Scram at Facility Also 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
ML20151N0521988-07-26026 July 1988
Summary of Operating Reactors Events Meeting 88-30 on 880726.List of Attendees & Summary of Reactor Scrams 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
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
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
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
ML20215D9171986-10-0606 October 1986
Summary of 860929 Operating Reactors Events Meeting 86-34 Re Events Since Last Meeting on 860922.Assignees Should Review Identified Responsibilities & Completion Dates & Advise If Dates Cannot Be Met.Viewgraphs Encl
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
1998-06-29
[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
ML20196F6101998-12-0101 December 1998
Summary of 981029 Meeting with Northern States Power, Wisconsin Electric,Wisconsin Public Service & Alliant-IES in Rockville,Md Re Various Aspects of Potential Regulatory Issues Associated with Ongoing Cooperative Efforts
ML20236L1061998-06-29029 June 1998
Summary of 980204 Meeting W/Util in Rockville,Md Re Methodologies Being Implemented by Ies Utilities,Inc to Resolve Issued Identified by NRC Bulletin 96-003.List of Meeting Participants & Handouts Encl
ML20199F4081997-11-10010 November 1997
Summary of 971105-06 Meeting W/Ies Utilities,Inc Re Responses Provided by Licensee on Following DAEC ITS sections,1,2,3.0,3.1,3.2,3.4,3.5,3.7,3.9,4 & 5.List of Attendees Encl
ML20211P0621997-10-10010 October 1997
Summary of 970909-10 Meeting W/Licensee Re Portions of DAEC Improved TS That Seek to Delay Entry Into LCO When Performing Surveillances Required by Improved TS
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
ML20148U5351997-06-30030 June 1997
Summary of 970618 Meeting W/Ies Util,Inc Re Unique Aspects of Duane Arnold Energy Ctr Design Wrt Loop Select Logic. List of Attendees & Licensees Handout 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
ML20147J1981997-04-0909 April 1997
Summary of 970403 Meeting W/Ies Utilities,Inc Re Current Fuel Storage Status & Options at Duane Arnold Energy Ctr. List of Attendees Encl
ML20137Q0341997-04-0303 April 1997
Summary of 970320 Meeting W/Util Re TS Setpoints & Practice of Not Entering LCO Action Statements During Certain Surveillances.List of Attendees Attached
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
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
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
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20058D2851990-10-29029 October 1990
Summary of Operating Reactors Events Meeting 90-26 on 901024.List of Attendees & Rept of Reactor Scram at Facility Also 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
ML20151N0521988-07-26026 July 1988
Summary of Operating Reactors Events Meeting 88-30 on 880726.List of Attendees & Summary of Reactor Scrams 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
ML20215D9171986-10-0606 October 1986
Summary of 860929 Operating Reactors Events Meeting 86-34 Re Events Since Last Meeting on 860922.Assignees Should Review Identified Responsibilities & Completion Dates & Advise If Dates Cannot Be Met.Viewgraphs Encl
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
1998-06-29
[Table view] |
Text
' ~ '
October 20, 1993
- s
-MEMORANDUM FOR: Brian K. Grimes, Director Division of Operating Reactor Support FROM: Alfred lE. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support-
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING OCTOBER 13, 1993 - BRIEFING 93-39 On October 13, 1993, we conducted an Operating Reactors Events Briefing (93-39) to inform senior managers from offices of the ACRS, NRR, AEOD, RES, and regional offices of selected events that occurred since our last briefing on October 6, 1993. l Enclosure 1 lists the attendees. Enclosure 2 presents the significant elements of the discussed events.
Enclosure 3 contains reactor scram statistics for the week ending October 10, 1993. Two significant events were identified for input into the NRC Performance Indicator Program (Enclosure 4).
[ original signed by]
Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating .
Reactor Support
Enclosures:
As stated DISTRIBUTION:
Central Files cc w/ enclosures: PDR ,
See next page LKilgore, SECY EAB R/F KGray RDennig EGoodwin DSkeen Nilunemuller
,f' g(hk l3/ DORS DA EA -QO S EAB/ DORS KGraf R'-nnig. AChaffee 002053 10/ /93 10/ /93 10/)O/93 OFFICIAL RECORD COPY [
DOCUMENT NAME: ORTRANS.KAG (G:\KAG) d3f8 5 /. / g,,jg ,,u,,y j
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9310280031 931020 J PDR ORO NRRB y < . E
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. sl "
CC:
T. Murley, NRR (12G18)
F. Miraglia, NRR (12G18)
R. Pulsifer (PDIII-3).
Gillespie, NRR (12G18)
J. Hannon (PDIII-3)
F. J. Shea (PDI-2)
J. Partlow, NRR (12G18) M. Boyle (PDI-2) i S. Varga, NRR (14E4)
J. Calvo, NRR'(14A4)
J. Roe, NRR (13E4)
J. Zwolinski, NRR (13H24)
E. Adensam, NRR (13 E4 ).
W. Russell, NRR (12G18)
J. Wiggins, NRR (7D26)
A. Thadani, NRR (SE2)
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) '
G. Holahan,-AEOD (MN-9112)
L. Spessard, AEOD (MN-3701)
K. Brockman, AEOD (MN-3206)
S. Rubin, AEOD (MN-5219)
M. Harper, AEOD (MN-9112) ,,
G. Grant, EDO (17G21)
R. Newlin, GPA (2G5)
E. Beckjord, RES (NLS-007)
A. Bates, SECY (16G15)
T. Martin, Region I W. Kane, Region I R. Cooper, Region I S. Ebneter, Region II E. Merschoff, Region II i S. Vlas, Region II J. Martin, Region III E. Greenman, Region III J. Milhoan, Region IV B. Beach, Region IV B. Paulkenberry, Region V K. Perkins, Region V bec: Mr. Sam Newton, Manager Events Analysis Department Institute of Nuclear. Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957
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-0 ! E UNITED STATES -
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! NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 0001 Os ober 20, 1993 MEMORANDUM FOR: Brian K. Grimes, Director Division of Operating Reactor Support FROM: Alfred E. Chaffee, Chief ,
Events Assessment Branch Division of Operating Reactor Support
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING OCTOBER 13, 1993 - BRIEFING 93-39 On October 13, 1993, we conducted an Operating Reactors Events Briefing (93-39) to inform senior managers from offices of the ACRS, NRR, AEOD, RES, and regional offices of selected evenu that occurred since our last briefing on October 6, 1993.
Enclosure 1 lists the attendees. Enclosure 2 presents the significant elements of the discussed events.
Enclosure 3 contains reactor scram statistics for the week ending '
October 10, 1993. Two significant events were identified for input into the NRC Performance Indicator Program (Enclosure 4).
! w Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support
Enclosures:
As stated cc w/ enclosures:
See next page
ENCLOSURE 1 i LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (93-39)
OCTOBER 13, 1993 NAME OFFICE NAME OFFICE >
N. HUNEMULLER NRR F. MIRAGLIA NRR ,
R. DENNIG NRR J. PARTLOW NRR ,
A. CHAFFEE NRR B. BOGER NRR -
K. GRAY NRR J. WIGGINS NRR E. GOODWIN NRR L. CALLAN NRR M. VIRGILIO NRR M. CULLINGFORD NRR G. MARCUS NRR R. PULSIFER NRR D. GAMBERONI NRR J. SHEA NRR M. JOHNSON NRR W. MINNERS RES S. VARGA NRR V. BENAROYA AEOD C. ROSSI NRR J. MATHIS ACRS I TELEPHONE ATTENDANCE ;
(AT ROLL CALL) '
Recions - Resident Insoectors Region I C. Miller (Duane Arnold)
Region II W. Schmidt (Peach Bottom)
Region III Region V 1
J_IT/AIT Team Leaders Misc.
NRC Technical Training Center 6
, 4 . , .- , .- - , - - , -- , - ~ - - ---- - - - - - - - - - - - - - - - - -
ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 93-39 LOCATION: 10 B11, WHITE FLINT WEDNESDAY, OCTOBER 13, 1993, 11:00 A.M.
DUANE ARN0LD MISADJUSTMENT OF 4160V BREAKERS PEACH BOTTOM, VALVE Y0KE CRACKING UNITS 2 AND 3 i
PRESENTED BY: EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR SUPPORT, NRR l
l l
l
93-39 DUANE ARNOLD MISADJUSTMENT OF 4160V BREAKERS SEPTEMBER 28, 1993 PROB _LEM MISADJUSTMENT OF 4160V BREAKER RENDERED THE 'B' DIESEL GENERATOR (DG) IN0PERABLE BECAUSE ITS OUTPUT BREAKER WOULD NOT AUTO CLOSE.
CAUSE o
ROUTINE PREVENTATIVE MAINTENANCE PERFORMED ON AN EMERGENCY BUS ALTERNATE SUPPLY BREAKER RESULTED IN INADEQUATE CLEARANCE BETWEEN THE AUXILIARY CONTACTS OPERATING R0D AND THE BREAKER PLUNGER.
o THEREFORE, AN AUXILIARY CONTACT ON THE ALTERNATE SUPPLY BREAKER DID NOT MAKE UP WHEN THE BREAKER OPENED AND DID NOT SIGNAL THE DG OUTPUT BREAKER CLOSING LOGIC THAT THE ALTERNATE SUPPLY BREAKER WAS OPEN.
SAFETY SIGNIFICANCE o BETWEEN JULY 21 AND JULY 31, THE PLANT WAS AT POWER WITH THE 'B' DG IN0PERABLE (UNKNOWN) AND THE APPLICABLE TECHNICAL SPECIFICATIONS WERE NOT MET.
- BETWEEN AUGUST 7 AND AUGUST 11, THE LICENSEE WAS MOVING FUEL AND THE 'A' DG WAS UNDERG0ING MAINTENANCE.
THEREFORE, WITH CORE ALTERATIONS IN PROGRESS, NEITHER DG WAS OPERABLE.
CONTACT: NEAL HUNEMULLER, NRR/ DORS /0EAB AIT: H0
REFERENCE:
10 CFR 50.72 #26137 SIGEVENT: TBD
. DUANE ARNOLD 93-39 o POTENTIAL COMMON MODE FAILURE OF 4160V BREAKERS EQUIPPED WITH AUXILIARY CONTACTS.
DISCUSSION o ON JULY 21, THE STANDBY TRANSFORMER SUPPLY BREAKER TO THE EMERGENCY BUS WAS ADJUSTED DURING PREVENTATIVE MAINTENANCE (3 YEAR INSPECT AND LUBE).
o POST MAINTENANCE TESTING WAS NOT PERFORMED, THE ACCEPTANCE CRITERIA REQUIRED OPERATING THE BREAKER BEFORE INSTALLING IT INTO THE CUBICLE. THE PLUNGER TO OPERATING R00 CLEARANCE WAS NOT VERIFIED TO BE 0 TO 1/8 INCH IN THE OPEN POSITION AS REFERENCED IN THE GENERAL ELECTRIC (G.E.) METAL-CLAD SWITCHGEAR TECHNICAL MANUAL (NOT IN THE BREAKER TECHNICAL MANUAL). BOTH MANUALS WERE LISTED AS REFERENCES IN THE PLANT-SPECIFIC PROCEDURE. THE PLUNGER "AS-LEFT" WAS PUSHING UP DN THE OPERATING R0D APPR0XIMATELY 3/16 INCH.
o ON SEPT. 16 AND 22, LOOP /LOCA TESTS WERE PERFORMED.
THE OUTPUT BREAKER ON THE 'B' DG WOULD NOT AUTO CLOSE.
o ON SEPT. 23 THE STANDBY TRANSFORMER SUPPLY BREAKER TO THE EMERGENCY BUS WAS READJUSTED.
o ON SEPT. 28, THE LICENSEE DETERMINED THAT THE 'B' DG HAD BEEN IN0PERABLE FROM JULY 21 TO SEPT. 25, DUE TO THE INABILITY OF ITS OUTPUT BREAKER TO AUTO CLOSE.
o OPERATORS COULD HAVE MANUALLY LOADED THE 'B' DG TO THE EMERGENCY BUS.
o SIMILAR ADJUSTMENTS HAD BEEN MADE ON OTHER BREAKERS.
DUANE ARNOLD 93-39 FOLLOWUP o CONVERSATIONS BETWEEN THE LICENSEE AND G.E. DETERMINED THAT THERE ARE ADDITIONAL DIMENSIONAL CHECKS, NOT !
CONTAINED IN EITHER THE G.E. METAL-CLAD SWITCHGEAR l TECHNICAL MANUAL OR THE G.E. MAGNE-BLAST AIR CIRCUIT '
BREAKER TECHNICAL MANUAL, THAT WOULD PROVIDE ADDITIONAL ASSURANCE OF PROPER AUXILIARY CONTACT OPERATION.
o THE LICENSEE REVIEWED THE OPERABILITY OF THE OTHER BREAKERS; 25 0F 49 WERE FOUND TO BE OUTSIDE OF THE DESIRABLE RANGE BUT FUNCTIONAL.
o THE NRC IS PREPARING AN INFORMATION NOTICE.
o A PRELIMINARY CONDITIONAL CORE DAMAGE PROBABILITY OF 1.6E-06 WAS CALCULATED ASSUMING A LOSS OF 0FFSITE POWER WHILE THE PLANT WAS AT POWER WITH THE 'B' DG IN0PERABLE FOR 10 DAYS. THE P0TENTIAL RISK ASSOCIATED WITH THE OTHER 25 BREAKERS IS NOT EASILY QUANTIFIED.
o THE DUANE ARNOLD RESIDENT INSPECTOR, WHILE PERFORMING BACKUP DUTIES AT QUAD CITIES, FOUND 5 0F 8 SIMILAR, BUT NON-SAFETY, BREAKERS OUT OF TOLERANCE ON THE 0 TO 1/8 INCH CLEARANCE BETWEEN THE OPERATING R0D AND PLUNGER.
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93-39 I PEACH BOTTOM, UNITS 2 AND 3 VALVE YOKE CRACKING i SEPTEMBER 29, 1993 l PROBLEM CRACKS WERE DISCOVERED IN SEVERAL YOKES ON WALWORTH GATE l VALVES INSTALLED IN SAFETY-RELATED SYSTEMS.
l CAUSE I APPEARS TO BE A COMBINATION OF:
A MARGINAL DESIGN RESULTING IN HIGH STRESS IN THE AREA 0F THE CRACKS; i
INSUFFICIENT BOLT TOROUE WHICH INCREASED THE STRESS; AND L
MANUFACTURING (CASTING) DEFECTS.
SAFETY SIGNIFICANCE CRACKS IN THE VALVE Y0KE CAN RESULT IN THE INABILITY OF THE M0V TO PERFORM ITS SAFETY FUNCTION. THE OBSERVED CRACKS WOULD NOT HAVE CAUSED MALFUNCTIONS WITHOUT FURTHER PROPAGATION.
DISCUSSION e BETWEEN SEPT. 21 AND 30, THE LICENSEE IDENTIFIED CRACKS IN THE Y0KES OF SEVFRAL WALWORTH PRESSURE SEAL VALVES AT UNIT 3 AND ONE AT UNIT 2.
CONTACT: NEAL HUNEMULLER, NRR/ DORS /0EAB AIT: HQ
REFERENCE:
MORNING REPORT 10/05/93 SIGEVENT: TBD
. PEACH BOTTOM 93-39 UNITS 2 AND 3 o ON OCT. 1, ADDITIONAL CRACKS WERE IDENTIFIED ON UNIT 2.
o THE CRACKS WERE OBSERVED IN THE CAST Y0KE ASSEMBLY, MIGRATING FROM THE ENDS OF THE Y0KE STRUTS INTO THE OPERATOR MOUNTING PLATE.
o THE CRACKING WAS INITIALLY OBSERVED WHILE VIEWING OPERATION OF A CORE SPRAY VALVE DURING A TEST.
o UNIT 3 WAS IN A REFUELING OUTAGE AND UNIT 2 SHUT DOWN ON OCT. 2, TO INSPECT ALL WALWORTH VALVE Y0KES.
o THE LICENSEE INSPECTED 62 WALWORTH PRESSURE SEAL VALVES, 9 WERE FOUND TO HAVE CRACKS:
UNIT 2
- RHR 20" SHUTDOWN COOLING OUTBOARD PCIV
- RHR 'B' 24" OUTB0ARD INJECTION PCIV
- RCIC 4" TURBINE STEAM ADMISSION VALVE
- CS 'B' 12" REMOTE BLOCKING VALVE
- HPCI 4" MINIMUM FLOW RECIRCULATION VALVE UNIT 3
- RHR 20" SHUTDOWN COOLING OUTB0ARD PCIV
- CS 'A' 12" REMOTE BLOCKING VALVE
- CS 'B' 12" REMOTE BLOCKING VALVE
- HPCI 12" INBOARD INJECTION PCIV o THE FAILURE MODE APPEARS TO BE FATIGUE AND NOT A RAPID FAILURE MECHANISM.
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FOLLOWUP o THE LICENSEE REPAIRED THE CRACKS BY GRINDING AND WELDING.
o THE LICENSEE LOOKED AT 39 VALVES OF OTHER DESIGNS AND IT APPEARS THAT THE CRACKING IS LIMITED TO THE WALWORTH PRESSURE SEAL VALVES.
o THE LICENSEE IS EVALUATING PART 21 REPORTABILITY.
NOTE: PILGRIM EXPERIENCED A CRACKED Y0KE IN AN 18" WALWORTH PRESSURE SEAL VALVE Y0KE IN 1988. THE CAUSE WAS ATTRIBUTED TO THE ADDITION OF A MOTOR OPERATOR FOR WHICH THE VALVE WAS NOT DESIGNED.
o THE NRC IS PREPARING AN INFORMATION NOTICE. -
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ENCLOSURE 3 REACTOR SCRAM '
J Reporting Period: 10/04/93 to 10/10/93 YTD YTD 1 ABOVE BELOW YTD !
E PLAWT 8 UNIT POWER E M COMPLICATIONS 11} jig E-l 10/05/93 MILLSTOWE 1 100 SA Equipment Failure YES 1 0 1 10/08/93 CAVIS BESSE 1 100 SA Ecpipnent Failure ko 2 0 2 l 1
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I DE2CRIPTIDW 0F COMPLICATION (S) 10/04/93 70 10/10/93 1.1.1[
W.ll COMPL ICATIONS t!LLSTONE 1 FA1 LORE OF A FAST TRANSFER OF THE 14C SUS TO THE RESERVE STATION l TRANSFORMER.
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1sar To Date (YTD) Totals IrcLts$e Events Within The Celerdar Year 3rdicated By The Erd Date of The Spectif ed Report 0
p.g.:1 10/13/93
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COMPARISDN OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES J L?
PERIOD ENDING 10/10/93 WUMBER 1993 ,
1992 1991* 1993*' 1989*
OF WEEKLY WEEKLY WEEKLY' WEEKLY WEEKLY SCRAM CAUSE SCRAMS AVERAGE AVERACE AVERAGE AVERAGE AVERAGE (YTD)
POWER GREATER THAN OR EQUAL TO 15%
EQUIPMENT FAILURE
DESIGN /lN3TALLATION ERROR
OPERATING ERROR
- 0 0.3 0.2 0.6 0.5 1.0 MAINTENANCE ERROR
EXTERNAL
OTHER* O 0.0 0.2 - -
0.1 Subtotal 2 2.8 3.4 3.5 3.9 4.2 POWER LESS THAN 151 EQUIPMENT FAILURE
- 0 0.3 0.4 0.3 0.4 0.3 DESIGN / INSTALLATION ERROR
OPERATING ERROR
- O 0.2 0.1 0.2 0.1 0.3 KAINTENANCE ERROR
EXTERNAL
OTHER* 0 0.0 0.1 - - -
Subtotal 0 0.5 0.7 0.5 0.5 0.6 TOTAL 2 3.3 4.1 4.0 4.4 4.8 1993 1992 1991 1990 1989 Wo. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
TOTAL AUTOKAfic SCRAMS 2 2.5 3.1 3.3 32 3.9 TOTAL KANUAL SCRAMS 0 0.9 1.0 0.7 1.2 0.9 TOTALS MAY DIFFEP BECAUGE OF ROUNDING OFF
- Detailed breakdown not in database for 1991 ard earlier
- EXTERNAL cause included in EQUIPMENT FAILURE
- MAINTENANCE ERROR ard DESIGN / INSTALLATION ERROR causes included in OPERATING ERROR
- OTHER cause inchded in EQUIPMENT FAILURE 1991 and 1990 S-16 Page 1 10/13/15
HQ.IM
- 41. 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 MOTION, 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. PERSONELL 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 SCPJW.
4.
"OTHER" 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 19 8 9 ----- ------------- 2 5 2 Manual and Automatic Scrams for 19 9 0 --- --------------- 2 2 6 Manual and Automatic Scrams for 1991 ------------------ 206 Manual and Automatic Scrams for 1992 ------------------ 212 Manual and Automatic Scrams for 1993 --(YTD 10/10/93)-- 140 F
F3 CLOSURE 4 OPERATING REACTOR PLANTS SIGNIFICANT EVENTS SORT > Event Date '
QUERY > Event Type SIG & Close Out Date >= 08/12/93 & Close out Date <= 10/12/93 & Event Date >= 07/01/93 & Event Date <=
PLAW & UNIT Mb R DESCRIPTION OF EVENT SIGNIFICANCE BRt ING PRESENTER hE PAlt9ADES 1 07/01/93 25725 HIGMLY RADI0 ACTIVE DEBRIS FCUND IN TRANSFER PIT. Fuel Cladding 93-26 RAMSEY J. MIGMLIGHT CtLLSTONE 2 08/04/93 25886 (JNISOLABLE LEAK OF RC THROUGH 2" VALVE 800f- Safety-Related Cooling System 93-31 BENEDICT R. HIGMLIGHT CONNET JOINT. "FURMANITE" REPAIRS INEFFECTIVE.
ETS-11 Page:1 10/18/93
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