|
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210D7601999-07-16016 July 1999
Summary of 990616 Meeting with TVA in Rockville MD to Brief Staff on Planned SG Replacement.List of Attendees & Handout Provided by TVA Encl
ML20210D7801999-07-16016 July 1999
Summary of 990715 Meeting with TVA Re TVA Evaluation of Fee Structure Compared with Recent Actual Fees & NRC Guidance in Estimating Review Effort for Licensing Actions.List of Attendees & Matl Used in Presentation Enclosed
ML20210E0201999-07-16016 July 1999
Summary of 990629 Meeting with Util in Rockville,Md Re Ongoing Efforts in Planning Sf Storage Strategy,Including Licensing of Isfsi,At Plant.With Attendance List & TVA Handout
ML20237E9811998-08-25025 August 1998
Summary of 980708 Meeting W/Tva & Framatome Cogema Fuel in Rockville,Md Re Ongoing Efforts W/Doe to Fabricate & Install Four Lead Test Assemblies in Plant,Unit 2 Core During Cycle 10 Refueling Outage in Spring of 1999.Attendance List Encl
ML20217J5781997-10-15015 October 1997
Summary of 971008 Meeting W/Util in Rockville,Md Re Licensee USAR Rebaselining Project for Plant.List of Attendees & Licensee Handouts Encl
ML20217B1521997-09-11011 September 1997
Trip Rept of 970820-22 Visit to Cooper Site to Attend Engineering Mgt Focus Meeting Held on 970821
ML20216H5261997-08-26026 August 1997
Summary of 970822 Meeting W/Util in Rockville,Md Re Followup to Series of Conference Calls on 970418,discussing Results of Recent Steam Generator Insps at Sequoyah Unit 1.List of Attendees,Handouts & Staff Questions Encl
ML20140B4701997-06-0404 June 1997
Summary of 970530 Meeting W/Tva in Rockville,Md to Discuss Status of Thermo-Lag Fire Barrier Corrective Action Program at Plant & Schedule for Completion of Program.W/Attendance List & TVA Handout
ML20140G5621997-05-0808 May 1997
Summary of 970227 Meeting W/Tva in Rockville,Md to Discuss Sequoyah Conversion to Framatome Cogema Fuel.List of Attendees Encl
ML20134J7451996-11-0808 November 1996
Summary of 961104 Meeting W/Tva in Rockville,Md Re Status of Thermo-Lag Fire Barrier Upgrades at Plant.List of Attendees & Copies of Handouts Encl
ML20129H5211996-10-29029 October 1996
Summary of Operating Reactors Events Meeting 96-13 on 961023,informing Senior Managers from Ofcs of Commission,Oe, NRR & Regional Ofcs of Selected Events That Occurred Since Last Briefing
ML20217D1931994-03-0707 March 1994
Summary of Sequoyah Restart Panel 940303 Meeting in Region II Ofc Re Status of NRC & Licensee Activities for Restart of Unit 1.Meeting Minutes & Unit 1 Restart Action Plan Encl
ML20059H7581994-01-0303 January 1994
Summary of Operating Reactors Events Meeting 93-48 on 931222
ML20059C2141993-12-17017 December 1993
Summary of Operating Reactors Events Meeting 93-47 on 931215.List of Attendees Encl
ML20059K3131993-11-0505 November 1993
Summary of Operating Reactors Events Meeting 93-42 on 931103
ML20056G9331993-08-13013 August 1993
Summary of Operating Reactors Events Meeting 93-30 on 930811
ML20056H5721993-08-0505 August 1993
Summary of Operating Reactors Events Meeting 93-28 on 930728
ML20059C8321993-07-21021 July 1993
Summary of 398th ACRS Meeting on 930610-11 in Bethesda,Md Re SECY-93-113,public Comments on Advanced LWR Severe Accident Plant performance,SECY-93-067 & Reactor Operating Experience Related to Salem Unit 2 & Indian Point Unit 3
ML20217D2111993-06-16016 June 1993
Summary of Sequoyah Restart Panel 930614 Meeting in Region II Ofc Re Plant Restart & Listed Items.List of Attendees & Checklists Encl.Next Meeting Will Be Held on 930622
ML20056E2121993-06-15015 June 1993
Summary of Operating Reactors Events Meeting 93-21 on 930609
ML20127D1321993-01-12012 January 1993
Summary of Operating Reactors Events Meeting 93-01 on 930106
ML18096A8711992-06-17017 June 1992
Summary of 920602 Meeting W/Nrc & Pse&G Re Sea Turtle Conservation Plan.Major Points Discussed in Meeting Listed
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20058J8621990-11-27027 November 1990
Summary of 901005 Meeting W/Util in Rockville,Md Re Cable Conduit Testing Program.Viewgraphs & Attendee List Encl
ML20058K0311990-11-23023 November 1990
Summary of Operating Reactors Events Meeting 90-28 on 901114 Re Reactor Scrams for Wk Ending 901111.Attendees Listed
ML20062C8111990-10-16016 October 1990
Summary of Operating Reactors Events Meeting 90-25 on 901010.List of Attendees,Reactor Scram Statistics & Tabulation of Events Encl
ML20059N2091990-09-21021 September 1990
Summary of 900919 Operating Reactors Events Meeting 90-023 to Discuss Significant Elements
ML20059D8121990-09-0505 September 1990
Summary of 900817 Meeting W/Util in Rockville,Md Re Schedules of Certain Mods Committed for Completion in Unit 2 Cycle 4 Refueling Outage.Engineeering for Unit 2 Will Be Completed Before Restart from Outage
ML20056B4101990-08-20020 August 1990
Summary of 900723 Meeting W/Util in Rockville,Md Re Plant Cable/Conduit Testing Program for safety-related Cable.List of Attendees,Tva & NRR Handouts & Transcript of Meeting Encl
ML20055E2081990-07-0505 July 1990
Summary of 900531 Meeting W/Tva in Rockville,Md Re Plant safety-related Cable Inside Containment.List of Attendees, & Handouts Presented at Meeting Encl
ML20247K2471989-08-24024 August 1989
Trip Rept of Staff 890718-19,21 & 0801-02 Visits to Nuclear Power Plants to Gather Info Re Industry Actions to Address Loss of Oil Malfunctions of Rosemount Models 1153 & 1154 Transmitters
ML20246J8031989-07-12012 July 1989
Summary of 890609 Meeting W/Util in Rockville,Md Re Dissolution of Engineering Assurance Organization.List of Meeting Attendees,Util Handout,Agenda & Transcript Encl
ML20245F9761989-06-22022 June 1989
Summary of 890614 Meeting W/Util & Westinghouse in Rockville,Md Re Future Work for Facility Cycle 4 Refueling Outage
ML20245G6411989-06-15015 June 1989
Summary of Operating Reactors Events Meeting 89-23 on 890614.On 890607,multiple Electrical Distribution Sys Problems Occurred at Oconee,Units 1,2 & 3.On 890610,unit Power Signal Caused Scram
ML20245A3851989-05-30030 May 1989
Summary of Operating Reactors Events Meeting 89-20 on 890524.List of Meeting Attendees & Viewgraphs Encl
ML20247M1001989-05-26026 May 1989
Summary of 890511 Meeting W/Util in Rockville,Md Re Performance of Best Estimate Calculations for App K Analyses.Proposed Plan for LOCA Analyses,Meeting Handouts & 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
ML20245C6541989-04-12012 April 1989
Summarizes 890313 Meeting w/C-E to Discuss Results of Salem Project & Licensing of Future C-E Projects Re RTD Bypass Elimination.Agenda & Viewgraphs Encl
ML20207L0291988-10-0505 October 1988
Trip Rept of 880921-23 Visit to Cooper-Bessemer Plant to Attend Diesel Generators Users Group Meeting Re Sets Which Utilize Ksv Diesel Engines.Nrc Should Conduct Audit of Bendix Corp to Ensure Licensees Notified of Cracked Nozzles
ML20155A8081988-09-29029 September 1988
Summary of 880915 Meeting W/Util in Rockville,Md Re Microbiological Influenced Corrosion Program at Plant.List of Attendees & Viewgraphs Encl
ML20154M9231988-09-21021 September 1988
Summary of 880913 Meeting W/Util at Site Re Unit 2 Shutdown Margin & Unit 1 Restart Readiness,Per Insp Repts 50-327/88-35 & 50-328/88-35.List of Attendees & Related Info Encl
ML20154H4341988-09-16016 September 1988
Summary of 880908 Meeting W/Util in Rockville,Md Re Changes to Conditions Adverse to Quality Program.List of Attendees Encl
ML20206B1961988-07-29029 July 1988
Summary of ACRS Subcommittee for TVA Organizational Issues 880722 Meeting in Washington,Dc Re Generic Lessons Learned from NRC Review of Util Concerning Restart of Facility
ML20150D7171988-07-0707 July 1988
Summary of Operating Reactors Events Meeting 88-26 on 880628
ML20153A8371988-07-0101 July 1988
Summary of 880622 Meeting W/Util in Rockville,Md Re TVA Commitments on Facility.List of Attendees & Util Handout Encl
ML20150E2321988-06-21021 June 1988
Summary of 880613 Meeting W/Util to Discuss Restart of Facility in Light of Recent Scrams from Power.Transcript of Meeting Encl
ML20196A9201988-06-17017 June 1988
Summary of Operating Reactors Events Meeting 88-24 on 880614.Two Significant Events Identified for Input to NRC Performance Indicator Program.No Events Suggested for long-term Followup.List of Attendees Encl
ML20154A4061988-05-0404 May 1988
Summary of 880414 Meeting W/Util in Rockville,Md Re Differences Between Units 1 & 2 Nuclear Performance Plan. List of Attendees & Licensee Handout Encl
ML20151D2701988-03-12012 March 1988
Summary of ACRS Subcommittee on TVA Organizational Issues Meeting on 880202-03 in Chattanooga,Tn Re Review of TVA Mgt Reorganization & Issues Re Restart of Unit 2
1999-07-16
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210D7601999-07-16016 July 1999
Summary of 990616 Meeting with TVA in Rockville MD to Brief Staff on Planned SG Replacement.List of Attendees & Handout Provided by TVA Encl
ML20210D7801999-07-16016 July 1999
Summary of 990715 Meeting with TVA Re TVA Evaluation of Fee Structure Compared with Recent Actual Fees & NRC Guidance in Estimating Review Effort for Licensing Actions.List of Attendees & Matl Used in Presentation Enclosed
ML20210E0201999-07-16016 July 1999
Summary of 990629 Meeting with Util in Rockville,Md Re Ongoing Efforts in Planning Sf Storage Strategy,Including Licensing of Isfsi,At Plant.With Attendance List & TVA Handout
ML20237E9811998-08-25025 August 1998
Summary of 980708 Meeting W/Tva & Framatome Cogema Fuel in Rockville,Md Re Ongoing Efforts W/Doe to Fabricate & Install Four Lead Test Assemblies in Plant,Unit 2 Core During Cycle 10 Refueling Outage in Spring of 1999.Attendance List Encl
ML20217J5781997-10-15015 October 1997
Summary of 971008 Meeting W/Util in Rockville,Md Re Licensee USAR Rebaselining Project for Plant.List of Attendees & Licensee Handouts Encl
ML20216H5261997-08-26026 August 1997
Summary of 970822 Meeting W/Util in Rockville,Md Re Followup to Series of Conference Calls on 970418,discussing Results of Recent Steam Generator Insps at Sequoyah Unit 1.List of Attendees,Handouts & Staff Questions Encl
ML20140B4701997-06-0404 June 1997
Summary of 970530 Meeting W/Tva in Rockville,Md to Discuss Status of Thermo-Lag Fire Barrier Corrective Action Program at Plant & Schedule for Completion of Program.W/Attendance List & TVA Handout
ML20140G5621997-05-0808 May 1997
Summary of 970227 Meeting W/Tva in Rockville,Md to Discuss Sequoyah Conversion to Framatome Cogema Fuel.List of Attendees Encl
ML20134J7451996-11-0808 November 1996
Summary of 961104 Meeting W/Tva in Rockville,Md Re Status of Thermo-Lag Fire Barrier Upgrades at Plant.List of Attendees & Copies of Handouts Encl
ML20129H5211996-10-29029 October 1996
Summary of Operating Reactors Events Meeting 96-13 on 961023,informing Senior Managers from Ofcs of Commission,Oe, NRR & Regional Ofcs of Selected Events That Occurred Since Last Briefing
ML20217D1931994-03-0707 March 1994
Summary of Sequoyah Restart Panel 940303 Meeting in Region II Ofc Re Status of NRC & Licensee Activities for Restart of Unit 1.Meeting Minutes & Unit 1 Restart Action Plan Encl
ML20059H7581994-01-0303 January 1994
Summary of Operating Reactors Events Meeting 93-48 on 931222
ML20059C2141993-12-17017 December 1993
Summary of Operating Reactors Events Meeting 93-47 on 931215.List of Attendees Encl
ML20059K3131993-11-0505 November 1993
Summary of Operating Reactors Events Meeting 93-42 on 931103
ML20056G9331993-08-13013 August 1993
Summary of Operating Reactors Events Meeting 93-30 on 930811
ML20056H5721993-08-0505 August 1993
Summary of Operating Reactors Events Meeting 93-28 on 930728
ML20059C8321993-07-21021 July 1993
Summary of 398th ACRS Meeting on 930610-11 in Bethesda,Md Re SECY-93-113,public Comments on Advanced LWR Severe Accident Plant performance,SECY-93-067 & Reactor Operating Experience Related to Salem Unit 2 & Indian Point Unit 3
ML20217D2111993-06-16016 June 1993
Summary of Sequoyah Restart Panel 930614 Meeting in Region II Ofc Re Plant Restart & Listed Items.List of Attendees & Checklists Encl.Next Meeting Will Be Held on 930622
ML20056E2121993-06-15015 June 1993
Summary of Operating Reactors Events Meeting 93-21 on 930609
ML20127D1321993-01-12012 January 1993
Summary of Operating Reactors Events Meeting 93-01 on 930106
ML18096A8711992-06-17017 June 1992
Summary of 920602 Meeting W/Nrc & Pse&G Re Sea Turtle Conservation Plan.Major Points Discussed in Meeting Listed
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20058J8621990-11-27027 November 1990
Summary of 901005 Meeting W/Util in Rockville,Md Re Cable Conduit Testing Program.Viewgraphs & Attendee List Encl
ML20058K0311990-11-23023 November 1990
Summary of Operating Reactors Events Meeting 90-28 on 901114 Re Reactor Scrams for Wk Ending 901111.Attendees Listed
ML20062C8111990-10-16016 October 1990
Summary of Operating Reactors Events Meeting 90-25 on 901010.List of Attendees,Reactor Scram Statistics & Tabulation of Events Encl
ML20059N2091990-09-21021 September 1990
Summary of 900919 Operating Reactors Events Meeting 90-023 to Discuss Significant Elements
ML20059D8121990-09-0505 September 1990
Summary of 900817 Meeting W/Util in Rockville,Md Re Schedules of Certain Mods Committed for Completion in Unit 2 Cycle 4 Refueling Outage.Engineeering for Unit 2 Will Be Completed Before Restart from Outage
ML20056B4101990-08-20020 August 1990
Summary of 900723 Meeting W/Util in Rockville,Md Re Plant Cable/Conduit Testing Program for safety-related Cable.List of Attendees,Tva & NRR Handouts & Transcript of Meeting Encl
ML20055E2081990-07-0505 July 1990
Summary of 900531 Meeting W/Tva in Rockville,Md Re Plant safety-related Cable Inside Containment.List of Attendees, & Handouts Presented at Meeting Encl
ML20246J8031989-07-12012 July 1989
Summary of 890609 Meeting W/Util in Rockville,Md Re Dissolution of Engineering Assurance Organization.List of Meeting Attendees,Util Handout,Agenda & Transcript Encl
ML20245F9761989-06-22022 June 1989
Summary of 890614 Meeting W/Util & Westinghouse in Rockville,Md Re Future Work for Facility Cycle 4 Refueling Outage
ML20245G6411989-06-15015 June 1989
Summary of Operating Reactors Events Meeting 89-23 on 890614.On 890607,multiple Electrical Distribution Sys Problems Occurred at Oconee,Units 1,2 & 3.On 890610,unit Power Signal Caused Scram
ML20245A3851989-05-30030 May 1989
Summary of Operating Reactors Events Meeting 89-20 on 890524.List of Meeting Attendees & Viewgraphs Encl
ML20247M1001989-05-26026 May 1989
Summary of 890511 Meeting W/Util in Rockville,Md Re Performance of Best Estimate Calculations for App K Analyses.Proposed Plan for LOCA Analyses,Meeting Handouts & 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
ML20245C6541989-04-12012 April 1989
Summarizes 890313 Meeting w/C-E to Discuss Results of Salem Project & Licensing of Future C-E Projects Re RTD Bypass Elimination.Agenda & Viewgraphs Encl
ML20155A8081988-09-29029 September 1988
Summary of 880915 Meeting W/Util in Rockville,Md Re Microbiological Influenced Corrosion Program at Plant.List of Attendees & Viewgraphs Encl
ML20154M9231988-09-21021 September 1988
Summary of 880913 Meeting W/Util at Site Re Unit 2 Shutdown Margin & Unit 1 Restart Readiness,Per Insp Repts 50-327/88-35 & 50-328/88-35.List of Attendees & Related Info Encl
ML20154H4341988-09-16016 September 1988
Summary of 880908 Meeting W/Util in Rockville,Md Re Changes to Conditions Adverse to Quality Program.List of Attendees Encl
ML20206B1961988-07-29029 July 1988
Summary of ACRS Subcommittee for TVA Organizational Issues 880722 Meeting in Washington,Dc Re Generic Lessons Learned from NRC Review of Util Concerning Restart of Facility
ML20150D7171988-07-0707 July 1988
Summary of Operating Reactors Events Meeting 88-26 on 880628
ML20153A8371988-07-0101 July 1988
Summary of 880622 Meeting W/Util in Rockville,Md Re TVA Commitments on Facility.List of Attendees & Util Handout Encl
ML20150E2321988-06-21021 June 1988
Summary of 880613 Meeting W/Util to Discuss Restart of Facility in Light of Recent Scrams from Power.Transcript of Meeting Encl
ML20196A9201988-06-17017 June 1988
Summary of Operating Reactors Events Meeting 88-24 on 880614.Two Significant Events Identified for Input to NRC Performance Indicator Program.No Events Suggested for long-term Followup.List of Attendees Encl
ML20154A4061988-05-0404 May 1988
Summary of 880414 Meeting W/Util in Rockville,Md Re Differences Between Units 1 & 2 Nuclear Performance Plan. List of Attendees & Licensee Handout Encl
ML20151D2701988-03-12012 March 1988
Summary of ACRS Subcommittee on TVA Organizational Issues Meeting on 880202-03 in Chattanooga,Tn Re Review of TVA Mgt Reorganization & Issues Re Restart of Unit 2
ML20149M6071988-02-22022 February 1988
Summary of 880211 Meeting W/Util Re Load Sequencing of Plant Diesel Generators.Attendance List & Handout Matl Used During Meeting Encl
ML20195J5251988-01-21021 January 1988
Summary of 880120 Meeting Between Commissioner Bernthal & Admiral White of TVA Re Util Request to Retain Ofc of Special Projects as Overseer of Plants After Sequoyah 1 Restart & Invitation to Bernthal to Tour Sequoyah Plant
ML20148Q0801988-01-21021 January 1988
Summary of Operating Reactors Events Meeting 88-03 on 880119.List of Events & Summaries of Presented Events & 1988 Scrams Encl
1999-07-16
[Table view] |
Text
.___ _ _
JAN 121993 I
MEMORANDUM FOR: Brian K. Grimes, Director Division of Operating Reactor Support FROM: Alfred E. Chaffee, Chief Events Assessment Branch Divisjon of Operating Reactor Support
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING JANUARY 6, 1993 - BRIEFING 93-01 On January 6, 1993, we conducted an Operating Reactors Events Briefing (93-01) to inform senior managers from offices of AEOD, ACRS, NRR, RES, and regional offices of selected events that occurred since our last briefing on December 23, 1992.
Attachment i lists the attendeen. Attachment 2 presents the significant elements of the discussed events.
Attachment 3 contains reactor scram statistics for the week ending 12/27/92 and year ending 12/31/92. One significant event was identified for input into the NRC performance indicator program (Attachment 4).
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 DSkeen TKoshy RBenedict LKilgore, SECY 40023
/d RS S EAB/ DOR EAB DORS TG'rhy R ennig EGoodwin AChaffee Oi/yq/93 01/y/93 01/ /93 01/l2(/93 _
[]qQ l OFFICIAL RECORD COPY f ...j DOCUMENT NAME: ORTRANS.KAG (G:KAG) [/[j/y . $ -/
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PDR PDR ~-
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_~_-_:~w_-____-____-________-_-__________________-___ _ _ - _ _ _ _ _ _ -
cc:
T. !!urley, llRR (12G18) R. Devan, PDIV-1 F. liiraglia, llRR (12G18) J. Larkins, PDIV-1 F. Gillespie, llRR (12G18) J. Stone, PDI-2 J. Partlow, llRR (12G18) C. Miller, PDI-2 S. Varga, llRR' (14 E4 ) D. LaBargo, PDII-4 J. Calvo, NRR (14A4) F. liebdon, PDII-4 G. Lainas, NRR (14113)
J. Roe, llRR (13E4)
J. Zwolinski, llRR (131124)
M. Virgilio, NRR (13E4)
W. Ruscell , 11RR (12G18)
J. Richardson, 11PR (7D26)
A. Thadani, 11RR (8E2)
S. Rosenberg , 11RR (10E4)
C. Rossi, NRR (9A2)
B. Boger, 11RR * (10113 )
P. Congel, NRR (10E2)
D. Crutchfield, NRR (111121)
W. Travers, NRR (11B19)
D. Coe, ACRS (P-315)
E. Jordan, AEOD (MN-3701)
T. 11ovak , AEOD ( M11-9112 )
L. Spessard, AEOD (M11-3701)
K. Brockman, AEOD (MN-3206)
S. Rubin, AEOD (M!i-5219 )
M. liarper, 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. llehl, Region I S. Ebneter, Region II E. Merschoff, Region II B. Davis, Region III E. Greenman, Region llI J. Milhoan, Region IV B. Beach, Region IV J.B. Martin, Region V K. Perkins, Region V bec:~Mr. Sam Newton, Manager Events Analysis Department Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, GA 30339-3064 l
p s
'i ATTACNMEllT 1 LIST OF ATTE!4 DEES l 1
OPERATIllG REACTORS EVEllTS FULL BRIEFI!1G (93-01) -
JANUARY 6, 1993 ;
llAME Offl_CE NAME OFFICE B. GRIMES NRR R. ECKENRODE HRR A. CNAFFEE NRR C. YATES 11RR R. DEliNIG liRR J. STEWART NRR E. GOODWILL NRR G. WEST, JR. IIRR D. SKEEN NRR C. DERLINGER NRR T. KOSHY NRR C. ROSSI NRR R. BENEDICT NRR J. ROE NRR K. GRAY NRR S. LONG NRR P. ENG NRR J. CALVO NRR J. GUO NRR J. BONGARRA NRR-J. STONE liRR G. MARCUS NRR S. BAJWA l C. MILLER NRR D. LABARGE let D. COE ACRS R. DEVAN NRR V. BEHAROYA AEOD- -
F. IIEBDON NRR D. ROSS AEOD P. O'CONNOR NRR W. MINNERS RES M. WEBB- NRR TELEPHONE ATTENDANCE (AT ROLL CALL)
Recions Resident Inspectors Region I Region II Region III Region IV Region V '
AIT Team Leaders Misnt Salem (W. Ruland)
+
. - . _ . . . - . . _ . . ,,_,=,.-.---...____,___._,_...._.-,,__._.__-._.,_.._..--x.___ .-,--,_.-,)
AfTACHMENT 2 OPERATING REACTORS EVENTS BRIEFING 93-01 ELENTS ASSESSMENT BRANCH LOCATION: 10 B11, WHITE FLINT WEDNESDAY, JANUARY 6, 1993, 11:00 A.M.
COOPER STATION ROUTING 0F CONTROL WIRING COULD RENDER BOTH EMERGENCY DIESEL GENERATORS INOPERABLE SALEM, UNIT 2 FAILURE OF CONTROL ROOM OVERNEAD ANNUNCIATORS (AIT - UPDATE)
SEQUOYAH, UNITS 1 AND 2 UNDERWEIGHT LOADING OF ICE IN ICE CONDENSER
93-01 COOPER STATION ROUTING 0F CONTROL WIRING COULD RENDER BOTH EMERGENCY DIESEL GENERATORS INOPERABLE DECEMBER 30, 1992 PROBLEM DURING A DESIGN BASIS RECONSTITUTION, IT WAS DETERMINED THAT A SEISMIC, TORNADO, OR INTERNAL MISSILE EVENT COULD RENDER BOTH EMERGENCY DIESEL GENERATORS INOPERABLE.
CAUSE A PORTION OF THE ESSENTIAL AC BUS TIE BREAKER CONTROL WIRING IS LOCATED IN HON-SEISMIC STRUCTURES.
SAFETY SIGNILICANCE LOSS OF 0FFSITE POWER WITH BOTH EDGs IN0PERABLE WOULD RESULT IN A STATION BLACK 0UT.
DJSCUS_Sl0B e LICENSEE lici f RED AN UNUSUAL EVENT AND COMMENCED A POWER REDUCTION WHEN BOTH EDGs WERE DECLARED INOPERABLE.
- THE TRIP CONTROL WIRING FOR THE SAFETY RELATED TIE BREAKERS (IFA & 1GB) WAS ROUTED FROM THE CLASS 1E SWITCHGEAR, THROUGH NON-CLASS 1E SWITCHGEAR, AND BACK TO TllE CLASS 1E SWITCHGEAR TO PICK UP THE UNDERV0LTAGE CONTACTS.
CONTACT: D. SKEEN, NRR/ DORS AIT: R0
REFERENCE:
10 CFR S0.72 #24810 SIGEVENT: TBD
COOPER STATION 93-01 e IF THIS CONTROL WIRING WERE TO OPEN BECAUSE OF A SEISMIC EVENT OR TORNADO, ETC, THE TIE BREAKERS WOULD NOT TRIP OPEN ON AN UNDERVOLTAGE CONDITION.
- THE EDG OUTPUT BREAKERS (EG1 & EG2) WILL NOT CLOSE IF THE TIE BREAKERS ARE CLOSED, THUS, THE SAFETY RELATED POWER SOURCE WOULD BE UNAVAILABLE AND THE PLANT WOULD BE IN A STATION BLACK 0UT CONDITION.
e THE UNUSUAL. EVENT WAS TERMINATED ABOUT FOUR AND ONE HALF HOURS LATER AND THE POWER REDUCTION STOPPED AT 65%
POWER WHEN MODIFICATIONS TO THE CONTROL WIRING FOR ONE OF THE TIE BREAKERS WAS COMPLETED AND THE EDG WAS DECLARED OPERABLE. .
o THE LICENSEE INSTALLED JUMPERS TO PROVIDE A PARALLEL PATH FOR THE TRIP CIRCUIT SUCH THAT THE OPENING 0F THE CIRCUIT IN THE NON-CLASS 1E SWITCHGEAR WILL NOT DISABLE THE CLASS 1E PORTION OF THE CIRCUIT.
EQLLOWUP e HAD THE DESIGN BASIS EVENT OCCURRED, THE CONTROL ROOM WOULD HAVE HAD THE FOLLOWING INDICATIONS:
N0 AC POWER AVAILABLE EDGs RUNNING EDG OUTPUT BREAKERS (EG1 & EG2) NOT CLOSED LOSS OF INDICATION FOR TIE BREAKERS 1FA & 1GB e WITH THE EDGs RUNNING AND THE OUTPUT BREAKERS NOT CLOSED, THE EDGs WOULD NOT HAVE SERVICE WATER FOR COOLING. THE EDGs CAN RUN ABOUT 10 MINUTES WITHOUT OVERHEATING WHEN UNLOADED.
93-01 COOPER STATION e AN OPERATOR WOULD BE DISPATCHED TO THE SWITCHGEAR ROOM TO DETERMINE THE POSITION OF THE TIE BREAKERS AND ENSURE THEY WERE IN THE OPEN POSITION.
- ONCE THE TIE BREAKERS WERE TRIPPED, THE EDG OUTPUT BREAKERS WOULD AUTOMATICALLY CLOSE AND THE EDGs WOULD POWER THE ESSENTIAL AC BUSES.
- A CHECK OF OTHER PLANTS BUILT BY THE SAME A&E FOUND NO SIMILAR CABLE ROUTING PROBLEM.
o REGION IV IS CONDUCTING AN ENGINEERING AND TECHNICAL SUPPORT INSPECTION THIS WEEK AND IS REVIEWING THIS EVENT.
l l
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93-01 SALEM, UNIT 2 FAILURE OF CONTROL ROOM OVERHEAD ANNUNCIATORS (AIT - UPDATE)
DECEMBER 13, 1992 PR0RLEM PLANT OVERHEAD ALARMS (OHA) WERE FR07,EN FOR APPR0XIMATELY ONE AND A HALF HOURS.
CAUSE DESIGN VULNERABILITIES (HARDWARE AND SOFTWARE), FAILURE TO F0LLOW PROCEDURE AND LACK 0F OPERATOR KNOWLEDGE ON THE NEWLY INSTALLED COMPUTER-BASED OVERHEAD ANNUNCIATOR SYSTEM.
SAFETY _ SIGNIFICANCE POTENTIAL ABNORMALITIES MAY REMAIN UNDETECTED UNTIL THE EFFECTS ARE MAGNIFIED.
BACKGROUND e ON DECEMBER 13 AT 9:26 P.M., OPERATORS HEARD ALARM TYPEWRITER PRINTING ALARM STATUS CHANGE, BUT THE CORRESPONDING OHA (ALARM TYPER TYPING) DID NOT LIGHT.
e OPERATORS OBSERVED THAT THE OHA SYSTEM TIME, DISPLAYED ON THE CONTROL ROOM CRT, REMAINED AT 7:45 P.M.
e THE-0PERATORS REBOOTED THE OHA CPU, RETURNING THE OHA SYSTEM TO NORMAL.
CONTACTS: T. K0 SHY, NRR/ DORS AIT: YES W. RULAND, RI/DRS
REFERENCE:
10 CFR 50.72 #24752 SIGEVENT: TBD
SALEM, UNIT 2 93-01 e THERE WERE NO INDICATIONS OF THIS FAILURE IN THE CONTROL ROOM FRONT PANELS OTHER THAN THE FR0 ZEN CRT.
- A 50.72 REPORT WAS MADE AT 5:04 P.M. ON DECEMBER 14.
- AIT INSPECTION WAS COMPLETED ON DECEMBER 23, 1992.
RLSCUSSION o THE NEW OHA SYSTEM WAS PUT INTO SERVICE DURING THE LAST OUTAGE (SUMMER 1992). MANdFACTURER IS BETA PRODUCTS, A DIVISION 0F'HATHAWAY SYSTEMS CORP.
- THE SYSTEM LOCKUP WAS CAUSED BY AN OPERATOR HITTING THE WRONG KEYS ON A SYSTEM COMPUTER WORKSTATION WITH A SWITCH MISPOSITIONED.
- THE OHA SYSTEM IS A REAL-TIME, MULTI-TASKING, DISTRIBUTED PROCESSING COMPUTER SYSTEM WITH 35 MICR0 PROCESSORS AND THE ASSOCIATED SOFTWARE.
o THE SYSTEM PERMITTED THE OPERATOR TO INADVERTENTLY PLACE THE CPU IN A DATA TRANSFER MODE WITHOUT THE NECESSARY CONTROL OR WARNING. OVERHEAD ANNUNCIATORS WERE IN0PERABLE AT THIS TIME.
e OPERATORS WERE NOT TRAINED TO RECOGNIZE SYSTEM PROBLEMS. THEY WERE TOLD THAT THEY COULD NOT AFFECT SYSTEM OPERATION FROM THE COMPUTER WORKSTATION.
- AN ABNORMAL PROCEDURE FOR LOSS OF ANNUNCIATORS WAS NOT AVAILABLE. THERE WAS NO SIGNIFICANT USE OF ANNUNCIATORS IN THE E0Ps.
.l e SALEM, UNIT 2 93-01 e THE LICENSEE DID NOT DECLARE ALERT SINCE THEY HAD RESET THE SYSTEM WITHIN 3 HINUTES OF DISCOVERY.
- A PUBLIC EXIT IS PLANNED FOR JANUARY 7, 1993.
SJMILAR EXERLS CALLAWAY ON OCTOBER 17, 1992, AND SEVERAL OTHER LOSS OF ALL ANNUNCIATORS.
E0LLDRUE EAB WILL COORDINATE GENERIC IMPLICATIONS.
93-01 SEQUOYAH, UNITS 1 AND 2 UNDERWEIGHT LOADING 0F ICE IN ICE CONDENSER ,
DECEMBER 1, 1992 PROBLEH UNDERWEIGHT OF ICE IN SOME BASKETS OF THE CONTAINMENT ICE CONDENSER OVER SEVERAL CYCLES.
CAUSE FAILURE TO EVALUATE THE SIGNIFICANCE OF "AS FOUND" ICE BASKET WEIGHTS.
SAEETY SIGNIFICANCE POTENTIAL FOR AMOUNT AND DISTRIBUTION OF ICE TO BE INADEQUATE TO ASSURE CONTAINMENT ADEQUACY.
DISCUSSION e SAFETY ANALYSIS BASED ON 1,930,000 POUNDS OF ICE TOTAL (993/ BASKET), UNIFORM DISTRIBUTION, AND UNIFORM MELTING.
- INITIAL LOADING 2,245,000 POUNDS TO ACCOUNT FOR SUBLIMATION AND WEIGHING ERRORS (1155/ BASKET).
o TECH SPEC REQUIRES WEIGHING A REPRESENTATIVE SAMPLE OF BASKETS EVERY 18 MONTHS.
CONTACT: R. BENEDICT, NRR/ DORS AIT: HQ
REFERENCE:
10 CFR 50.72 #24680 SIGEVENT: YES
SEQUOYAH, UNITS 1 & 2 93-01
- AFTER PLANT SHUTDOWN, LICENSEE VISUALLY INSPECTED ICE BASKETS AND WEIGHED A SAMPLE TO USE AS INDICATORS FOR NEED TO ADD ICE. THIS "AS FOUND" DATA WAS NOT !
ROUTINELY ANALYZED.
- PRIOR TO STARTUP, LICENSEE PERFORMED THE TECH SPEC REQUIRED WEIGHT SAMPLING ("AS LEFT").
- LICENSEE'S DA AUDIT NOTED THAT "AS FOUND" DATA FOR FOUR PRIOR CYCLES WERE BELOW DESIGN BASIS VALUES.
l FOLLOWQE l REGION II CONSIDERING ACTIONS TO BE TAKEN. WILL PROBABLY REQUEST NRR ASSISTANCE IN ANALYZING LICENSEE'S DATA.
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ATTACHMENT 3 REACTOR SCRAM
SUMMARY
WEEK ENDING 12/27/92 PLANT SPECIFIC DATA )
U 1.
DATE SITE UNIT POWER SIGNAL CAUSE COMPLI 83) YTD YTD YTD CATIONS ABOVE BELOW TOTAL 15% 15%
12/25/92 DRESDEN 3 73 A EQUIPMENT NO 2 0 2 12/27/92 SOUTH TEXAS 2 100 M EQUIPMENT N0 3 0 3 REACTOR SCRAM
SUMMARY
WEEK ENDING 12/31/92*
- 1. PLANT SPECIFIC DATAU )
DATE SITE UNIT POWER SIGNAL CAUSE COMPL1 '3) YTD YTD YTD CATIONS 'ABOVE BELOW TOTAL 15% 15%
12/29/92 CRYSTAL RIVER 3 100 A EQUIPMENT NO 2 0 2 12/31/92 SEQUOYAH 1 100 A EQUIPMENT N0 4 1 5 12/31/92 - SEQUOYAH 2 100- A EQUIPMENT N0 4 1 5
- ,. -. _ _ . - ._..1....____. ._ ._ _.._.____. _ _ _ _ . . _ . _ - _ _ _ ___i
II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOP WEEK ENDING 12/27/92 NUMBER 1992 1991 1990 1989 1988 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE POWER GREATER THAN 15%
EQUIPMENT RELATED 2 2.5 2.9 3.4 3.1 3.0 0 0.8 0.6 0.5 1.0 1.0 PERSONNEL RELATED (2) 0 0.0 0.0 0.0 0.1 0.4 OTHER(4)
Subtotal 2 3.3 3.5 3.9 4.2 4.4 POWER 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 0 0.0 0.0 0.0 0.0 0.2 OTHER (4)
Subtotal- 0 0.7 0.5 0.5 0.6 1.2 TOTAL 2 4.0 4.0 4.4 4.8 5.6 MANUAL VS AUTO SCRAMS l 1992 1991 1990 1989 1988 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE i TYPE-l (YTD)
MANUAL SCRAMS 1 1.0 0.7 1.2 0.9 1.1 AUTOMATIC SCRAMS 1 3.0 3.3 3.2 3.9 4.5
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- 11. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 12/31/92*
NUMBER 1992 1991 1990 1989 1988 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE '
(YTD)
POWER GREATER THAN 15%
EQUIPMENT RELATED 3 2.6 2.9 3.4 3.1 3.0 PERSOHNEL RELATED (2) 0- 0.8 0.6 0.5 1.0 1.0 OTHER (4) 0 0.0 0.0 0.0 0.1 0.4 Subtotal 3 3.4 3.5 3.9 4.2 4.4 POWER LESS THAN 15%
EQUIPMENT RELATED 0 0.4 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 0.6 0.5 0.5 0.6 1.2 TOTAL 3 4.0 4.0 4.4 4.8 5.6 MANUAL VS AUTO SCRAMS 1992 1991 1990 1989 1988 NO. OF WEEKLY WEEKLY WEEKLY kEEKLY WEEKLY TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
ItANUAL SCRAMS 0 1.0 0.7 1.2 0.9 1.1
' AUTOMATIC SCRAMS 3 3.0 3.3 3.2 3.9 4.5
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b91U
- l. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.7?. REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY.
) ':RMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D W TION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN
[h L' ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN OPERATING L'ICENSE.
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- 2. PERS0fthEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND RANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
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- 3. COMPLICATIONS: REC 0VERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL E3PORS UNRELATED TO CAUSE OF SCRAM.
- 4. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE. r OEAB SCRAM j)Alf Manual e..d Automatic Scrams for 1967 ------------------ 435 Manual and Automatic Scrams for 1983 ------------------ 291 Manual and Automatic Scrarrs for 1989 ------------------ 252 - -
Manual and Automatic Scrams for 19 9 0 ------------------ 2 2 6 Manual and Automatic Scrams for 1991 ------------------ 206 Manual and Actomatic Scrams for 1992 --(YTD 12/31/92)-- 212 7
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ATTAC!WENT 4 ,
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OPERATING REACTOR PLANTS SIGNIFICANT EVENTS mo Sort specified QUERY > Event Type SIG & Close out cete n 10/30/92 SIGNIFICANCE BRI FfNG FREst4TER t Y 4 ANT & (MIT fvYNf b6R DESCRIPi!ON OF Evimi WONE CARTER J. IkFORMAL Cont airrnent TRRY 1 03/28/92 23125 THREE OF foUR MSIV PENETRAf!ONS EXHIBITED EXCES$1VE LEACAGE DURING LLRT.
92-17 BENNER E.' ETR 92-038 nfMER - INDICATION MtLAWAY 10/17/92 24453 IMPROPER MAINTENANCF RESULTED IN A CDdPLE1E LCSS l
OF ANNUNCIATORS witch WAS NOT RECOGNIZED BY FLANT l PER$0NNEL. 1
- PREVIOUSLY IDENTIFIED IN TliE PiRFORMANCE INDICATOR REPORT FOR 2ND QUARTER /1992 SQy 01/07/93 Page:1 ETS-11
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