|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20196H1471999-06-24024 June 1999
Summary of 990609 Meeting with Duke Energy Corp Re NRC Conclusions for TIA-98008 on Use of Compensatory Actions for Control Room Emergency Ventilation System & to Present Positions.List of Participants & Licensee Handouts Encl
ML20203C2351999-02-0404 February 1999
Summary of 990127 Meeting with Duke Energy Corp Re Proposed License Amend to Take Credit for Soluble Boron & Partial Credit for Boraflex in Sf Pools at McGuire Nuclear Station. List of Attendees & Handouts Provided by Duke Encl
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
ML20236P1761998-07-13013 July 1998
Summary of 980709-10 Meeting W/Util Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl
ML20249C7711998-06-29029 June 1998
Summary of 980617 & 18 Meetings W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TSs for Catawba & McGuire Nuclear Stations.List of Meeting Attendees Encl
ML20249B4361998-06-17017 June 1998
Summary of 980514 Meeting W/Duke Energy Corp Re Info Related to Ice Condenser Issues,Ice Weight Redistribution & Reduction & Block Ice Utilization.List of Participants & Handout Provided by Util,Encl
ML20248E7911998-06-0101 June 1998
Summary of 980518 Meeting W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl
ML20203L9501998-02-19019 February 1998
Summary of 980204 Meeting W/Util to Discuss Info Re Design, Operabiliy & Qualifications of Grinnell Snubbers at Plant. Meeting Scheduled to Resolve Issues Re Staff Rai.List of Participants & Handouts Provided by Util Encl
ML20203B7081998-02-10010 February 1998
Summary of 980127 Meeting W/Duke Energy Corp Re Proposed Rev of Topical Repts.List of Attendees & DEC Slides Encl
ML20198G2131997-12-23023 December 1997
Summary of 971118 Meeting W/Duke Energy Corp in Rockville, Md,Re non-vital Electrical Bus,Kxa,Dual Unit Reactor Trip on 970906.List of Meeting Attendees & Licensee Handout Encl
ML20202E6761997-11-26026 November 1997
Summary of 971030 Meeting W/Duke Energy Corp Re Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Attendees,Meeting Agenda & Licensee Handout Matl Encl
ML20217P0651997-08-22022 August 1997
Summary of 970709 Meeting W/Util Re Issues Related to 1996 Rev of McGuire Ufsar.List of Attendees & Verbal Response Encl
ML20137F2351997-03-24024 March 1997
Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants
ML20129K3791996-11-21021 November 1996
Summary of 961016 Meeting W/Dpc at Plant Re Ongoing Current Licensing Issues & Safety Initiatives at Three Nuclear Stations.Meeting Attendees,Agenda & Handouts Encl
ML20140H5981996-11-11011 November 1996
Summary of 435th Meeting of ACRS on 961009-12 Re Capability of NRC SCDAP/RELAP5 Code to Predict Temps & Flows in SGs Under severe-accident Conditions
ML20148B5761996-10-0404 October 1996
Summary of 434th Meeting of ACRS on 960912-13 Re Capability of SCAP/RELAP5 Code to Predict SG Temps During Severe Accidents
ML20059L0651994-01-26026 January 1994
Summary of 931201 Meeting W/Util in Rockville,Md Re Presentation by Licensee on SG Replacement Project. Attendees Listed in Encl 1
ML20058N7741993-12-0303 December 1993
Summary of Operating Reactors Events Meeting 93-45 on 931201
ML20059H9901993-10-29029 October 1993
Summary of 930929 Meeting W/Util in Rockville,Md to Discuss Results of Util Investigation Into Unit 1 SG Tube Leaks. Licensee Agreed to Investigate Leakage Monitoring Program
ML20059A5941993-10-14014 October 1993
Summary of 930929 Meeting W/B&W Re Generic Implications for of Steam Generator Leak for Similar Sleeves Installed at Other Facilities.List of Attendees & Meeting Handouts Encl
ML20057F1471993-10-0606 October 1993
Summary of Operating Reactors Events Meeting 93-37 on 930929
ML20058M5891993-09-27027 September 1993
Summary of Operating Reactors Events Meeting 93-36 on 930922
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
ML20057A5221993-07-28028 July 1993
Summary of Operating Reactors Events Meeting 93-27 on 930721
ML20056E2031993-06-15015 June 1993
Summary of Operating Reactors Events Meeting 93-20 on 930602
ML20056D6661993-06-0101 June 1993
Summary of Operating Reactors Events Briefing 93-19 on 930526
ML20128P8491993-02-18018 February 1993
Summary of Operating Reactors Events Briefing 93-05 on 930210
ML20126G7701992-12-21021 December 1992
Summary of 921215 Meeting W/Util Re Status of Plans to Replace Snubbers During Next Scheduled Unit 1 Outage in Mar 1993
ML20210E1761992-06-10010 June 1992
Summary of 920415 Meeting W/Representatives of Util to Discuss a Study by Kalsi Engineering on Capability of MOV Actuators.List of Attendees,Handouts,And Comments/Concerns Encl
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20217B4961991-02-0707 February 1991
Summary of 910204 Meeting W/Util in Atlanta Re self- Assessment of Facility Performance from 891101 - 910202.List of Attendees & Presentation Summary Encl
ML20058B7431990-10-19019 October 1990
Summary of 901010 Meeting W/Util & Consultants in Rockville, MD Re Licensee Plan to Pursue Reload Technology.List of Attendees Also Encl
ML20127J2961990-04-0606 April 1990
Trip Rept of Commissioner Curtiss 900201 Site Visit.Facility Has Undergone Radical Change in Mgt Personnel & Experiencing Problems W/High Attrition of Licensed Operators
ML20248E8521989-10-0202 October 1989
Trip Rept of 890907 Visit to Plant Re Steel Containment Corrosion.Attendee List & Slides Encl
ML20247R0161989-09-21021 September 1989
Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting
ML20245G5421989-08-0303 August 1989
Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247C1091989-05-17017 May 1989
Summary of 890513 Meeting W/Util in Rockville,Md Re 890307 Steam Generator 1B Tube Rupture Event.Nrc Will Support 890504 Restart Only If Further Meetings & Reportings Result Into Effective Corrective Actions
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20245D3881989-04-21021 April 1989
Summary of 890413 Meeting W/Control Components,Inc in Rockville,Md Re Operation of Atmospheric Dump Valves.Agenda, Slides Used During Meeting for Valve Description & Worst Case Model Assumptions Encl
ML20248K3761989-04-10010 April 1989
Summary of Operating Reactors Events Meeting 89-014 on 890405.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams for Wk Ending 890402 Encl
ML20247F1991989-03-24024 March 1989
Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl
ML20247A8971989-03-16016 March 1989
Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl
ML20246N9201989-03-16016 March 1989
Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl
ML20235S7701989-02-21021 February 1989
Summary of 890118 Meeting W/Util at Site Re Certain Human Engineering Deficiencies Identified During Dcrdrs & Not Implemented.Attendees Listed in Encl 1 & Presentation Aids Listed in Encl 2
ML20207G3861988-08-12012 August 1988
Summary of 880803 Meeting W/Util in Rockville,Md Re Facility Auxiliary Transformer Fire & Reactor Trip Event Initiated by Combination of Cracked Insulating Matl & Dirt Accumulation.Briefing Slides Encl
ML20151K6901988-07-18018 July 1988
Summary of Operating Reactors Events Meeting 88-28 on 880712.Viewgraphs & List of Attendees Encl
ML20196B6471988-06-17017 June 1988
Summary of 880531 Meeting W/Licensee in Rockville,Md Re Auxiliary Feedwater Pump Degradation Events.Viewgraphs Encl
ML20154M8471988-05-17017 May 1988
Summary of 880414 Meeting W/Util & BNL in Rockville,Md Re Monitoring Program for Reactor Coolant Pump Shafts.List of Attendees & Related Documents Encl
ML20153G5481988-05-0404 May 1988
Summary of 880427 Telcon W/Utils in Region III Re Personnel Changes,Follow Up on Previous Items,Items of Interest from Sites & New Items
1999-06-24
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20196H1471999-06-24024 June 1999
Summary of 990609 Meeting with Duke Energy Corp Re NRC Conclusions for TIA-98008 on Use of Compensatory Actions for Control Room Emergency Ventilation System & to Present Positions.List of Participants & Licensee Handouts Encl
ML20203C2351999-02-0404 February 1999
Summary of 990127 Meeting with Duke Energy Corp Re Proposed License Amend to Take Credit for Soluble Boron & Partial Credit for Boraflex in Sf Pools at McGuire Nuclear Station. List of Attendees & Handouts Provided by Duke Encl
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
ML20236P1761998-07-13013 July 1998
Summary of 980709-10 Meeting W/Util Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl
ML20249C7711998-06-29029 June 1998
Summary of 980617 & 18 Meetings W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TSs for Catawba & McGuire Nuclear Stations.List of Meeting Attendees Encl
ML20249B4361998-06-17017 June 1998
Summary of 980514 Meeting W/Duke Energy Corp Re Info Related to Ice Condenser Issues,Ice Weight Redistribution & Reduction & Block Ice Utilization.List of Participants & Handout Provided by Util,Encl
ML20248E7911998-06-0101 June 1998
Summary of 980518 Meeting W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl
ML20203L9501998-02-19019 February 1998
Summary of 980204 Meeting W/Util to Discuss Info Re Design, Operabiliy & Qualifications of Grinnell Snubbers at Plant. Meeting Scheduled to Resolve Issues Re Staff Rai.List of Participants & Handouts Provided by Util Encl
ML20203B7081998-02-10010 February 1998
Summary of 980127 Meeting W/Duke Energy Corp Re Proposed Rev of Topical Repts.List of Attendees & DEC Slides Encl
ML20198G2131997-12-23023 December 1997
Summary of 971118 Meeting W/Duke Energy Corp in Rockville, Md,Re non-vital Electrical Bus,Kxa,Dual Unit Reactor Trip on 970906.List of Meeting Attendees & Licensee Handout Encl
ML20202E6761997-11-26026 November 1997
Summary of 971030 Meeting W/Duke Energy Corp Re Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Attendees,Meeting Agenda & Licensee Handout Matl Encl
ML20217P0651997-08-22022 August 1997
Summary of 970709 Meeting W/Util Re Issues Related to 1996 Rev of McGuire Ufsar.List of Attendees & Verbal Response Encl
ML20137F2351997-03-24024 March 1997
Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants
ML20129K3791996-11-21021 November 1996
Summary of 961016 Meeting W/Dpc at Plant Re Ongoing Current Licensing Issues & Safety Initiatives at Three Nuclear Stations.Meeting Attendees,Agenda & Handouts Encl
ML20140H5981996-11-11011 November 1996
Summary of 435th Meeting of ACRS on 961009-12 Re Capability of NRC SCDAP/RELAP5 Code to Predict Temps & Flows in SGs Under severe-accident Conditions
ML20148B5761996-10-0404 October 1996
Summary of 434th Meeting of ACRS on 960912-13 Re Capability of SCAP/RELAP5 Code to Predict SG Temps During Severe Accidents
ML20059L0651994-01-26026 January 1994
Summary of 931201 Meeting W/Util in Rockville,Md Re Presentation by Licensee on SG Replacement Project. Attendees Listed in Encl 1
ML20058N7741993-12-0303 December 1993
Summary of Operating Reactors Events Meeting 93-45 on 931201
ML20059H9901993-10-29029 October 1993
Summary of 930929 Meeting W/Util in Rockville,Md to Discuss Results of Util Investigation Into Unit 1 SG Tube Leaks. Licensee Agreed to Investigate Leakage Monitoring Program
ML20059A5941993-10-14014 October 1993
Summary of 930929 Meeting W/B&W Re Generic Implications for of Steam Generator Leak for Similar Sleeves Installed at Other Facilities.List of Attendees & Meeting Handouts Encl
ML20057F1471993-10-0606 October 1993
Summary of Operating Reactors Events Meeting 93-37 on 930929
ML20058M5891993-09-27027 September 1993
Summary of Operating Reactors Events Meeting 93-36 on 930922
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
ML20057A5221993-07-28028 July 1993
Summary of Operating Reactors Events Meeting 93-27 on 930721
ML20056E2031993-06-15015 June 1993
Summary of Operating Reactors Events Meeting 93-20 on 930602
ML20056D6661993-06-0101 June 1993
Summary of Operating Reactors Events Briefing 93-19 on 930526
ML20128P8491993-02-18018 February 1993
Summary of Operating Reactors Events Briefing 93-05 on 930210
ML20126G7701992-12-21021 December 1992
Summary of 921215 Meeting W/Util Re Status of Plans to Replace Snubbers During Next Scheduled Unit 1 Outage in Mar 1993
ML20210E1761992-06-10010 June 1992
Summary of 920415 Meeting W/Representatives of Util to Discuss a Study by Kalsi Engineering on Capability of MOV Actuators.List of Attendees,Handouts,And Comments/Concerns Encl
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20217B4961991-02-0707 February 1991
Summary of 910204 Meeting W/Util in Atlanta Re self- Assessment of Facility Performance from 891101 - 910202.List of Attendees & Presentation Summary Encl
ML20058B7431990-10-19019 October 1990
Summary of 901010 Meeting W/Util & Consultants in Rockville, MD Re Licensee Plan to Pursue Reload Technology.List of Attendees Also Encl
ML20247R0161989-09-21021 September 1989
Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting
ML20245G5421989-08-0303 August 1989
Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247C1091989-05-17017 May 1989
Summary of 890513 Meeting W/Util in Rockville,Md Re 890307 Steam Generator 1B Tube Rupture Event.Nrc Will Support 890504 Restart Only If Further Meetings & Reportings Result Into Effective Corrective Actions
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20245D3881989-04-21021 April 1989
Summary of 890413 Meeting W/Control Components,Inc in Rockville,Md Re Operation of Atmospheric Dump Valves.Agenda, Slides Used During Meeting for Valve Description & Worst Case Model Assumptions Encl
ML20248K3761989-04-10010 April 1989
Summary of Operating Reactors Events Meeting 89-014 on 890405.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams for Wk Ending 890402 Encl
ML20247F1991989-03-24024 March 1989
Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl
ML20246N9201989-03-16016 March 1989
Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl
ML20247A8971989-03-16016 March 1989
Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl
ML20235S7701989-02-21021 February 1989
Summary of 890118 Meeting W/Util at Site Re Certain Human Engineering Deficiencies Identified During Dcrdrs & Not Implemented.Attendees Listed in Encl 1 & Presentation Aids Listed in Encl 2
ML20207G3861988-08-12012 August 1988
Summary of 880803 Meeting W/Util in Rockville,Md Re Facility Auxiliary Transformer Fire & Reactor Trip Event Initiated by Combination of Cracked Insulating Matl & Dirt Accumulation.Briefing Slides Encl
ML20151K6901988-07-18018 July 1988
Summary of Operating Reactors Events Meeting 88-28 on 880712.Viewgraphs & List of Attendees Encl
ML20196B6471988-06-17017 June 1988
Summary of 880531 Meeting W/Licensee in Rockville,Md Re Auxiliary Feedwater Pump Degradation Events.Viewgraphs Encl
ML20154M8471988-05-17017 May 1988
Summary of 880414 Meeting W/Util & BNL in Rockville,Md Re Monitoring Program for Reactor Coolant Pump Shafts.List of Attendees & Related Documents Encl
ML20153G5481988-05-0404 May 1988
Summary of 880427 Telcon W/Utils in Region III Re Personnel Changes,Follow Up on Previous Items,Items of Interest from Sites & New Items
ML20148H2851988-01-22022 January 1988
Summary of ACRS Subcommittee on Generic Items 871216 Meeting W/Util in Washington,Dc Re Effectiveness of NRC Process That Deals W/Generic Issues & Usis.Viewgraphs & Presentation Schedule Encl
ML20148H6621988-01-15015 January 1988
Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl
1999-06-24
[Table view] |
Text
' ~
p.. -. a e .,
December 3, 1993 MEMORANDUM FOR: Brian K. Grimes, Director Division of Operating Reactor Support i FROM: Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING j DECEMBER 1, 1993 - BRIEFING 93-45 i
On December 1, 1993, we conducted an Operating Reactors Events Briefing (93-45) to inform senior managers from offices'of the Chairman, ACRS, SECY, OE, NRR, AEOD, and regional offices of.
selected events that occurred since our last briefing on.
November 24, 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 November 28, 1993. No significant events were identified for input into the NRC Performance Indicator Program.
original signed by !
Alfred E. Chaffee, Chief i
, Events Assessment Branch 1-Division of Operating '
React >r Support
Enclosures:
As stated DISTRIBt ION:
g; Central _ Files cc w/ enclosures: PDR See next page LKilgore, SECY ,
EAB R/F KGray .
RDennig EGoodwin DSkeen EBenner TKoshy gTig i*grAOsku 73 p {J{J t L.h U WTCDP"? f~
EAE/ DORS EAB/ DORS EAB/ DORS EAB/ DORS
- KGray TKoshy EBenner EGoodwin 12/ /93 12/ /93 12/ /93 12/ /93 r v
nrer s v rd EAB/ DORS ,
AChaffee l l bWI,h{55(! Yk .) '
OFFICIAL RECORD COPY 'c R W '
DOCUMENT NAME: G:\KAG\0RTRANS ( d' i 4. y ,M;v .)
170.,u,? 0 9312220258 931203J eDn one O3 unnB PDR[ \\t
4-P
=s' cc: '
T.'Murley, NRR '(12G18) R. Laufer (PDIII-3). i
'F. Miraglia, NRR (12G18)
.F. Gillespie, NRR (12G18)
J. Hannon (PDIII-3) l V. Nerses-(PDII-3) !
J.' Callan, NRR (12G18) L. Plisco (PDII-3)
S . - Varga , .- NRR ' (14 E4 ) B. Holian (PDV) !
J. Calvo, NRR~ (14A4) T. Quay (PDV)- i G. Lainas, NRR (14H3)
J. Roe, NRR-(13E4)- '!
Zwolinski, NRR (13H24)
J.
l E. Adensam, NRR (13E4) l
'W. Russell, NRR (12G18)
J. Wiggins, NRR (7D26) {
A. Thadani, NRR (8E2) '
j S. Rosenberg, NRR (10E4) 1 C. Rossi, NRR (9A2)
{
B..Boger, NRR (10H3). ;
.F. Congel, NRR (10E2)
D. Crutchfield, NRR (11H21) l W. Travers, NRR (11B19)-
E. Jordan, AEOD (MN-3701) i G.'Holahan, AEOD (MN-9112) ;
L. Spessard, AEOD (MN-3701)
K. Brockman,.AEOD (MN-3206) 1 S. Rubin, AEOD (MN-5219) t M. Harper, AEOD (MN-9112)
G. Grant, EDO (17G21) .!
R. Newlin, GPA (2G5) 'i E. Beckjord, RES (NLS-007) !
A. Bates, SECY-(16G15) !
T. Martin, Region I l W. Kane, Region I R. Cooper, Region I S. Ebneter, Region II E. Merschoff, Region II -
S. Vias, Region.II '
J. Martin, Region III i E. Greenman, Region III .i J. Milhoan, Region IV B. Beach, Region IV ~i B. Faulkenberry, Region V K. Perkins, Region V t bec: Mr. Sam Newton, Manager .
Events Analysis Department ;
Institute of Nuclear Power Operations :
700 Galleria Parkway. '
Atlanta, GA 30339-5957
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o- 4 UNITED STATES
, $ j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205504001 f
December 3, 1993
.....f 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 DECEMBER 1, 1993 - BRIEFING 93-45 On December 1, 1993, we conducted an Operating Reactors Events Briefing (93-45) to inform senior managers from offices of the Chairman, ACRS, SECY, OE, NRR, AEOD, and regional offices of selected events that occurred since our last briefing on November 24, 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 November 28, 1993. No significant events were identified'for input into the NRC Performance Indicator Program.
Sf5 Al red E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support
Enclosures:
As stated cc w/ enclosures:
See next page
. e
. L
' 4 ,. - .
ENCLOSURE'l :
LIST OF ATTENDEES !
OPERATING REACTORS EVENTS FULL BRIEFING-l(93-45)'
DECEMBER 1, 1993 f
NAME OFFICE NAME OFFICE ;
. E. GOODWIN NRR G. ZECH. NRR l E.'BENNER NRR B. GRIMES NRR T.-KOSHY .:
NRR- J. ROE 'NRR K. GRAY NRR J. IBARRA OCM L. TRAN NRR H. ORNSTEIN .AEOD l
'G.-WEST- NRR J. MATHIS ACRS- -
S. WEISS .NRR J. BEALL OE. ;,
A. RAMEY-SMITH 'NRR- K. HART SECY i T. YAMADA NRR
-i l
i TELEPHONE ATTENDANCE :
(AT ROLL CALL) .
i Reaions Resident Inspectors .!
Region.I Region II
' G. Maxwell (McGuire). j A. MacDougall-(Palo Verde). I Region III Region IV !
Region V !
L P
IIT/AIT Team Leaders Misc. .,
c L
i
~.
i S 4 W
l i
OPERATING REACTORS EVENTS BRIEFING 93-45 :
LOCATION:- 10 Bil, WHITE-FLINT- !
WEDNESDAY, DECEMBER 1, 1993 11:00 A.M.
l KEWAUNEE AND STEAM GENERATOR WELDED j MCGUIRE, UNIT 1 TUBE PLUG LEAKS !
f PALO VERDE, UNIT-1 UNCONTROLLED REACTOR COOLANT -i SYSTEM DRAINDOWN i
i i
l PRESENTED BY: EVENTS ASSESSMENT BRANCH -l DIVISION OF OPERATING REACTOR. j SUPPORT, NRR l l
'I
. 1
. 93-45 i l
KEWAUNEE AND MCGUIRE, UNIT 2 !
STEAM GENERATOR WELDED TUBE PLUG LEAKS l APRIL 17, 1993 AND OCTOBER 5, 1993 l
PROBLEM 1 WHILE INCREASING POWER AFTER OUTAGES, KEWAUNEE AND l
MCGUIRE, UNIT 2 IDENTIFIED SIGNIFICA!!T PRIMARY-T0- !
-SECONDARY LEAKAGE. !
CAUSE !
LEAKAGE WAS CAUSED BY LEAKING WELDED STEAM GENERATOR (SG) !
. TUBE PLUGS. i i
SAFETY SIGNIFICANCE i EVENTS CALL-INTO QUESTION PROGRAMS TO ASSURE QUALITY OF SG j TUBE PLUGGING OPERATIONS. .
SEQUENCE OF EVENTS !
i KEWAUNEE: j i 04/17/93 PLANT GENERATOR SYNCHRONIZED TO GRID, PRIMARY- )
T0-SECONDARY LEAKAGE OF 50 GPD.
] 4 06/04/93 PLANT SHUT DOWN TO REPAIR LEAK. LEAK RATE HAD l INCREASED TO 125 GPD. !
o i
)
CONTACT: E. BENNER, NRR/ DORS AIT: RQ_ i
REFERENCE:
PN0 II-93-053 AND SIGEVENT: IBA ;
MORNING. REPORTS 3-93-0136, ;
-0173, AND -0179 .!
-i i
. KEWAUNEE & MCGUIRE- 93-45 !
o 'L'EAK WAS FROM FIRST WELDED TUBE PLUG INSTALLED IN TUBESHEET IN PREVIOUS OUTAGE. !
o PLUG REMOVED, THREE CONSUMABLE POLY INSERTS INSTALLED, REPLACEMENT PLUG WELDED IN PLACE. !
o WELD VISUALLY ACCEPTED AND SG RETURNED TO SERVICE.
i MCGUIRE: I l'
10/5/93 PLANT ESCALATING IN POWER, OPERATORS DETECTED INCREASING ACTIVITY FROM CONDENSER AIR EJECTOR !
l RADIATION MONITOR.
o CHEMISTRY SAMPLES INDICATE POTENTIAL PRIMARY-TO- .
SECONDARY LEAKAGE OF UP TO 410 GPD, PLANT SHUTDOWN :
INITIATED. '
10/6/93 PLANT ENTERS MODE 3, HOT STANDBY o LEAK WAS FROM A WELDED TUBE PLUG INSTALLED IN TUBESHEET ,
IN PREVIOUS OUTAGE. ;
DISCUSSION .
1 '
KEWAUNEE:
o LICENSEE PULLED THREE COLD LEG TUBES-IN PREVIOUS REFUELING OUTAGE TO PROVIDE INPUT FOR REVISED PLUGGING CRITERION. ,
o PLUGS WERE TO BE WELDED DIRECTLY INTO TUBESHEET. !
. l l
. KEWAUNEE & MCGUIRE 93-45 l e DURING FIRST WELD, AUT0 WELDING MACHINE. UNABLE TO ,
MAINTAIN COVER GAS; PERFORMED MANUAL WELD REPAIR. ;
o MANUALLY WELDED REMAINING TWO PLUGS IN TUBESHEET. j o SG RETURNED TO SERVICE AFTER VISUAL INSPECTION OF 1 PLUGS. '
'o WELD REPAIR DID NOT REQUIRE PRF.SSURE-TEST.
1 o TEST WOULD NOT BE VALID DUE TO USE OF CONSUMABLE POLY INSERTS DURING PLUG INSTALLATION: POLY INSERTS DISSOLVE
~
AT ELEVATED TEMPERATURES DURING POWER 0PERATIONS. 1 HCGUIRE:
o LICENSEE PULLED TWO-TUBES IN PREVIOUS OUTAGE TO PROVIDE DA'A FOR PLUGGING CRITERION.
- PLUGS WERE MANUALLY WELDED DIRECTLY INTO TUBESHEET; AUTO WELD NOT USED; MANUAL WELD WAS NOT COMPLETE.
o SG RETURNED TO SERVICE AFTER VISUAL INSPECTION OF PLUGS.
o WE!DED PLUGS DID NOT REQUIRE PRESSURE TEST.
o TEST WOULD NOT BE-VALID DUE TO USE OF PLASTIC PLUGS-DURING PLUG INSTALLATION: PLASTIC PLUGS DISSOLVE AT:
350 *F.
-l
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. KEWAUNEE & MCGUIRE 93-45 l o IN THE FUTURE LICENSEE WILL USE CERAMIC PLUGS DESIGNED !
TO BREAK AT-1500 PSI INSTEAD OF PLASTIC PLUGS. j 1
o SG WAS PRESSURE TESTED TO VERIFY THAT PLUGS WERE LEAK !
TIGHT AFTER REPAIR OF PLUG WELDS. .;
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P 93-45 .
PALO VERDE, UNIT 1 i UNCONTROLLED REACTOR COOLANT SYSTEM DRAINDOWN ;
NOVEMBER 12, 1993 :
PROBLEM !
REACTOR COOLANT SYSTEM (RCS) DRAINDOWN RESULTED IN UNEXPECTED ENTRY INTO REDUCED INVENTORY OPERATION. - !
CAUSE OPERATOR DISTRACTION SAFETY-SIGNIFICANCE I POTENTIAL LOSS OF SHUTDOWN COOLING DISCUSSION
- RCS LEVEL MAINTAINED BETWEEN JUST BELOW FLANGE-(112 - q 113 FT) TO WORK ON STEAM GENERATORS.-
1 o
OPERATORS WERE DRAINING 200 GALLONS 0F RCS ABOUT THREE' -
TIMES A SHIFT BY DIVERTING APPROXIMATELY 110 GPM FROM l LOW PRESSURE SAFETY INJECTION (LPSI) PUMP THROUGH THE- l MINIMUM FLOW RECIRCULATION PATH TO THE REFUELING WATER j TANK . (RWT) . !
o THIS EVOLUTION WAS NORMALLY DONE IN 2 MIN. 1 o THE INCREASE IN INVENTORY WAS BACK LEAKAGE:FROM REFUELING WATER TANK THROUGH THE LPSI: SUCTION ISOLATION, l
VALVE. THIS LEAKING VALVE IS NORMALLY OPEN AND CLOSED ONLY-WHEN THAT LOOP IS'USED FOR SHUTDOWN COOLING.
' CONTACT: - THOMAS KOSHY, NRR/ DORS /0EAB -AIT: _ liq
REFERENCE:
- MORNING REPORT 5-93-0077 SIGEVENT: IBQ q
. - - - . , ----c --,. . .- , .,
. PALO VERDE, UNIT 1 93-45 o O'N NOVEMBER 3, 1993 AT 1:20.A.M,.0PERATOR BEGAN ROUTINE DRAINDOWN OPERATION T0 REDUCE LEVEL TO 112' 6" AND WAS 1 DISTRACTED PRIOR TO SECURING THE DRAIN.
]
o AT 1:28 A.M. SECONDARY OPERATOR OBSERVED RCS LEVEL I DROPPED TO FIVE FEET AB0VE HOTLEG (INDICATED 108' 5") l AND SECURED THE DRAINDOWN. -!
o RCS LEVEL WAS RECOVERED AT 1:32 A.M. !
o ACTUAL LEVEL DROP WAS ONLY TO 111' 8" (REDUCED INVENTORY BEGINS AT 111' 0'9.
e DRAINDOWN EVOLUTION DID NOT HAVE AN OPERATOR BACKUP. l o
FREQUENT DRAINDOWNS COULD HA'!F BEEN AVOIDED BY CLOSING A SECOND ISOLATION VALVE. .
o PROCEDURE ALLOWED THREE OPTIONS FOR DRAINDOWN PATH. l THE OTHER PATHS WERE THROUGH THE PURIFICATION SYSTEM OR 1 THROTTLING THE SHUTDOWN HEAT EXCHANGER BYPASS VALVE. !
o THIS OPERATOR HAD DONE DRAINDOWN OPERATION NINE TIMES IN THE LAST TWO SHIFTS. j o OPERATOR DISTRACTIONS: 1 i
e RESPONDING TO CALL ON VALVE TESTING l i
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ATTENDING TO AN OPERATOR REQUEST TO VERIFY RWI BORON CALCULATION. THIS REQUEST WAS MISINTERPRETED AND HE PROCEEDED TO VERIFY THE NUMBERS USED IN THE CALCULATION USING THE TECHNICAL SPECIFICATIONS.
, PALO VERDE, UNIT 1 93-45 j o' TiiE LICENSEE PROJECTS THE FOLLOWING TO HAVE OCCURRED IF DRAINDOWN CONTINUED--
i e ALARMS AT THREE AND ONE INCH ABOVE MID-LOOP e
SHUTDOWN COOLING PUMP VORTEXING IN 138 MIN. FROM l THE LOWEST LEVEL REACHED. l 34 MIN. FOR CORE BOILING AFTER LOSING SHUTDOWN ,
COOLING (SDC). (BASED ON 60.DAYSLAFTER SHUTDOWN AND A CONCURRENT COLD LEG BREAK) t
- CORE UNC0VERY 4 HOURS AFTER LOSING SDC. '
1 o DURING THIS EVENT THE LICENSEE MAINTAINED THE CAPABILITY FOR GRAVITY FEED AND' CONTAINMENT CLOSURE. I IMMEDIATE LICENSEE' ACTIONS o
CREW WAS REMOVED FROM SHIFT AND IS CURRENTLY INVOLVEDL l IN HIGH INTENSITY TEAM TRAINING.
o-BRIEFED UNIT 1 OPERATIONAL STAFF ON IMPROVING TEAM WORK- 1
& COMMUNICATIONS, EMPHASIZED THE NEED TO~ CONTROL l CRITICAL' SAFETY FUNCTIONS AND REVIEWED POTENTIAL j RESULTS OF THE INCIDENT. j
. 1
. PLANNED LICENSEE ACTIONS
- o UNITS 2 AND 3 PLANT MANAGERS SCHEDULED TO CONDUCT U BRIEFINGS FOR OPERATIONAL STAFF. ;
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. PALO VERDE, UNIT 1 93-45 !
~
o UNIT 1.0PERATIONS MANAGEMENT WILL CLOSELY-REVIEW THE PERFORMANCE.OF ALL CREWS DURING HIGH INTENSITY TEAM
.. TRAINING AND ENSURE EXPECTATIONS REGARDING COMMUNICATIONS STANDARDS AND TEAMWORK ARE MAINTAINED. l
.o z
INCORPORATE LESSONS LEARNED INTO OPERATOR TRAINING. l o
EVALUATE A DESIGN CHANGE TO ADD AN ALARM WHEN ENTERING. ;
REDUCED INVENTORY.
o EVALUATE IMPROVEMENTS TO ELIMINATE RWT ISOLATION VALVE LEAKAGE.
l FOLLOW UP o
A MANAGEMENT CONFERENCE WAS HELD IN THE REGION.
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BRIEFl?iG 93-45' -- '-
j.-
SHUT DOWN COOLING LOOP i
SI SI
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St SI SI 652 654- 656 ,_ ,
4 1."
' TO SDC FROM PURIF RC LOOP - g ;q PURlF.
.d[ 6 1 r LPSI *
- TO SDC A r -
x x' Q -
LNa PUMP.
SI 6 307 y ,
< ' O,n, SI ,
668 CH.
. - Si -' SI 530 l( .TO 625:g 615 659_ RCS RCS LOOP " LOOP '
1 28.- 2A-n ,
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. . . - . . . . _ . . . _ . . , . - --..m. .... . ,, .-.- .._ . - . - - . - , _ . . ~--~...a.-.-..... ,-.....~....__,L.._3.4 ... .....4 , . . . . . , . - . - . . , . - -
.......___~.--J..s~~e.[_-. .-.J.--.u-
~ ' ~ ~ * ~ ~ ~ ' ~
RC RC - ~
108 109 RCS VENT SYSTEM -
- RC 105 To Sciety RC Volves 103 RC
/ 101 1
4 RC TO RDT
- 106
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FLOW .L RC
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ORIFICE u ~ 102 TO CONTAINMENT n
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Porfiolly I I Drained 4 -
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Reduced III '-------- -- ---
Inventory Mid-loop h.f.:: _ ::: '____--_-________ ;;;;;:T[:+.):
Fro m
j' Injection '
From To SDC SDC
-. ENCIDSURE. 3 REACTOR SCRAM ,
eeportIng Period: 11/22/93 to 11/28/93
~
YTD YTD ABOVE BELOW YTD E. PtANT & UNIT POWER TYPE- CAUSE COMPLICATIONS} jj] . TOTAL 11/22/93 c'WWA 1 0 SA Equipment Failure No 1 1 2 11/23/93 BYRON 2 99 SA Equipment Faiture No 2 0 2 b
.e:
Year.To Date (YTD) Totals include Events Within The Calendar Year Indicated By The Erd Date of The Speelfled Reporting Period 10 page:1 12/02/93-
COMPARISON OF WEEKLY SCRAM STATISTICS WITN INDUSTRY AVERAGES PERIOD ENDING
~
11/28/93 l' kUMBER 1993 1992 1991* 1990* -1989*
OF WEEKLY WEEKLY WEEKLY WEEKLY . WEEKLY SCRAM CAU$E SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
POWER GREATER THAN OR EQUAL TO 15%
EQUIPMENT FAILURE
- 1 1.8 2.6 2.9 3.4 3.1 DESIGN / INSTALLATION ERROR
- 0 0.0 - - - -
OPERATING ERROR * .0 0.3 0.2 0.6 0.5 1.0 MAINTENANCE ERROR
ExfERNAL* 0 0.1 - - - -
OTHER* 0 0.0 0.2 - -
0.1 Subtotal 1 2.7 3.4 3.5 3.9 4.2 POWER LESS THAN 15%
EQUIPMENT FAILURE
- 1 0.4 0.4 0.3 0.4 0.3 DESIGN /INSTALLAi!DN ERROR
- O 0.0 - - - -
OPERATING ERRDR* O 0.1 0.1 0.2 0.1 0.3 MAINTENANCE ERROR
Ex1ERNAl* 0 0.0 - - - -
01NER* 0 0.0 0.1 - - -
subtotal 1 0.5 0.7 0.5 0.5 0.6 TOTAL 2 3.2 4.1 4.0 4.4 4.8 1993 1992 1991 1990 1989 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY
(( RAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
-TOTAL AUTOMATIC SCRAMS 2 2.4 3.1 3.3 3.2 3.9 TOTAL MANUAL SCRAMS 0 0.9 1.0 0.7 1.2 0.9 TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF
- Detailed breakdown not in database for 1991 and earlier EXTERNAL cause included in EDU1PMENT FAILURE
. MAINTENAkCE ERROR and DE$1GN/INSTALLAfl0N ERROR causes included in OPERAf!NG ERROR OTHER cause included in EQUIPMENT FAILURE 1991 and 1990 Page: 1 12/02/93
TI.E -
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 M7T10N, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN.'ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN OFF. RATING LICENSE.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS. !
COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
"OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
OEAB SCRAM DATA lual and Automatic Scrams for 1987 ------------------ 435 lual and Automatic Scrams for 1988 ------------------ 291 .
Tual and Automatic Scrams for 1989 ------------------ 252 '
lua) and Automatic Scrams for 1990 ------------------ 226 lual and Automatic Scrams for 1991 ------------------ 206 sual and Automatic Scrams for 1992 ------------------ 212 lual and Automatic Scrams for 1993 --(YTD 11/28/93)-- 158 t
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