|
---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210E0201999-07-16016 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 ML20210D7601999-07-16016 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 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 ML16343A5411997-11-12012 November 1997 Summary of 971002 Meeting W/Tva in Rockville,Md Re Planned Use of Electrosleeving Process at Sequoyah Nuclear Plant, Units 1 & 2 & Diablo Canyon Power Plant to Repair & Strengthen SG Tubing.List of Attendees & 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 ML20059K3131993-11-0505 November 1993 Summary of Operating Reactors Events Meeting 93-42 on 931103 ML20056H5721993-08-0505 August 1993 Summary of Operating Reactors Events Meeting 93-28 on 930728 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 ML20035F4831993-04-15015 April 1993 Summary of 930412 Meeting W/Util in Rockville,Md Re Assessment & Corrective Actions Re Restart of Plant ML20035B4531993-03-18018 March 1993 Summary of Operator Reactors Events Briefing 93-10 on 930317.List of Attendees Encl ML20035E3771993-03-17017 March 1993 Summary of Operating Reactors Events Meeting 93-09 on 930310 ML20035A7241993-03-0909 March 1993 Summary of Operating Reactors Events Briefing 93-08 on 930303 ML20127D1321993-01-12012 January 1993 Summary of Operating Reactors Events Meeting 93-01 on 930106 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 ML20012E2951990-03-22022 March 1990 Summary of 900226 Meeting W/Util in Rockville,Md Re Eagle 21 Process Protection Sys,Including Eagle 21 Test Cart to Be Installed During Upcoming Cycle 4 Refueling Outage.Agenda & Meeting Handouts 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 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 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 IR 05000327/19880351988-09-21021 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 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 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 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 ML20195J6011987-12-0303 December 1987 Summary of ACRS Subcommittee TVA Organizational Issues 871004 Meeting W/Nrc & Util in Washington,Dc Re Actions Being Taken on Plant Restart Issues ML20236X4741987-12-0202 December 1987 Summary of 871124 Meeting W/Util in Bethesda,Md Re Results of Testing of Silicone Rubber Insulated Cables for Unit 2. Transcript of Meeting Encl ML20236K8951987-11-30030 November 1987 Trip Rept of 871028-30 Site Visit to Gather Info from Files to Facilitate Updating Sims Database ML18032A6091987-10-0606 October 1987 Summary of 870915 Meeting W/Tva Re Differences (Deltas) Between Sequoyah & Browns Ferry Nuclear Performance Plans. Attendance List & Browns Ferry Program Description Encl ML20235B2261987-09-15015 September 1987 Summary of 870910 Meeting W/Util in Knoxville,Tn Re Status of Cable Test Program.List of Attendees & Transcript Encl ML20235B1271987-09-15015 September 1987 Summary of 870911 Meeting W/Tva Re NRC Staff Presentation to TVA Findings from Integrated Design Insp.List of Attendees & Meeting Transcription Encl 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 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 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 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 ML16343A5411997-11-12012 November 1997 Summary of 971002 Meeting W/Tva in Rockville,Md Re Planned Use of Electrosleeving Process at Sequoyah Nuclear Plant, Units 1 & 2 & Diablo Canyon Power Plant to Repair & Strengthen SG Tubing.List of Attendees & 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 ML20059K3131993-11-0505 November 1993 Summary of Operating Reactors Events Meeting 93-42 on 931103 ML20056H5721993-08-0505 August 1993 Summary of Operating Reactors Events Meeting 93-28 on 930728 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 ML20035F4831993-04-15015 April 1993 Summary of 930412 Meeting W/Util in Rockville,Md Re Assessment & Corrective Actions Re Restart of Plant ML20035B4531993-03-18018 March 1993 Summary of Operator Reactors Events Briefing 93-10 on 930317.List of Attendees Encl ML20035E3771993-03-17017 March 1993 Summary of Operating Reactors Events Meeting 93-09 on 930310 ML20035A7241993-03-0909 March 1993 Summary of Operating Reactors Events Briefing 93-08 on 930303 ML20127D1321993-01-12012 January 1993 Summary of Operating Reactors Events Meeting 93-01 on 930106 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 ML20012E2951990-03-22022 March 1990 Summary of 900226 Meeting W/Util in Rockville,Md Re Eagle 21 Process Protection Sys,Including Eagle 21 Test Cart to Be Installed During Upcoming Cycle 4 Refueling Outage.Agenda & Meeting Handouts 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 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 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 IR 05000327/19880351988-09-21021 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 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 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 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 ML20195J6011987-12-0303 December 1987 Summary of ACRS Subcommittee TVA Organizational Issues 871004 Meeting W/Nrc & Util in Washington,Dc Re Actions Being Taken on Plant Restart Issues ML20236X4741987-12-0202 December 1987 Summary of 871124 Meeting W/Util in Bethesda,Md Re Results of Testing of Silicone Rubber Insulated Cables for Unit 2. Transcript of Meeting Encl ML18032A6091987-10-0606 October 1987 Summary of 870915 Meeting W/Tva Re Differences (Deltas) Between Sequoyah & Browns Ferry Nuclear Performance Plans. Attendance List & Browns Ferry Program Description Encl ML20235B2261987-09-15015 September 1987 Summary of 870910 Meeting W/Util in Knoxville,Tn Re Status of Cable Test Program.List of Attendees & Transcript Encl ML20235B1271987-09-15015 September 1987 Summary of 870911 Meeting W/Tva Re NRC Staff Presentation to TVA Findings from Integrated Design Insp.List of Attendees & Meeting Transcription Encl ML20239A6691987-09-0404 September 1987 Summary of 870901 Meeting W/Util,Bechtel & S&W in Bethesda, MD Re Criteria for Pipe Supports.List of Attendees,Handouts & SQN-DC-V-24.2 Supports for Rigorously Analyzed Category I Piping Encl 1999-07-16
[Table view] |
Text
..
O'tobr 29, 1996 t
MEMORANDUM TO:
Thomas T. Martin. Director Division of Reactor Program Management FROM:
Alfred E. Chaffee. Chief [ original signed by]
Events Assessment and Generic Communications Branch Division of Reactor Program Management
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING OCTOBER 23, 1996 - BRIEFING 96-13 On October 23, 1996, we conducted an Operating Reactors Events Briefing (96-13) to inform senior managers from offices of the Commission OE. NRR and regional offices of selected events that occurred since our last briefing on October 16, 1996. Attachment 1 lists the attendees. Attachment 2 presents the significant elements of the discussed events, contains reactor scram statistics for the week ending October 20,
)
1996.
One significant event was identified for input into the NRC Performance Indicator Program (Attachment 4).
Attachments: As stated (4) cc w/atts:
See next page CONTACT:
Kathy Gray. NRR (301) 415-1166 DISTRIBUTION:
(w/atts)
Central" Files PUBLIC LKilgore. SECY t
y3 l
PECB R/F DOCUMENT NAME: G:\\KAG\\0RTRANS To receive a copy of this dccument, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No cop of f[
OFFICE PECB lEj PECB lEl PECB l
C/PECB l N
/
NAME KGray:kag hptp SKoenick y $/L EGoodwin
(*
AChatfee ;) \\
f E
DATE 10/gp /96 10/ 22]/96 10/g4 /96
)
10 $ /96 f
V d {Q-j OFT 6CLAL RECORO COPY f
ptai;ncy n10090 '
-[3) 9611010072 961029 PDR ORO NRRB f
PDR
c e
cc:
)
F. Miraglia, NRR (0-12G18)
R. Hernan NRR (0-14B21)
F. Gillespie, NRR (0-12G18)
F. Hebdon, NRR (0-14B21)
R. Zimmerman, NRR (0-12G18)
A. Thadani, NRR (0-12G18)
B. Sheron, NRR (0-12G18) i S. Varga, NRR (0-14E4)
J. Zwolinski, NRR (0-14H3)
J. Roe, NRR (0-13E4)
E. Adensam. NRR (0-13E4)
G. Lainas NRR (0-7D26)
G. Holahan, NRR (0-8E2)
M. Virgilio NRR (0-8E2)
D. O'Neal, NRR (0-10E4)
- 8. Boger NRR (0-9E4)
M. Markley, ACRS (T-2E26)
E. Jordan, AE00 (T-4D18)
C. Rossi, AEOD (T-4A9)
F. Congel, AEOD (T-4D28)
R. Barrett. AEOD (T-4A43)
S. Rubin, AE00 (T-4D28)
M. Harper AE00 (T-4A9)
W. Leschek, AEOD (T-4A9)
V. McCree, EDO (0-17G21)
J. Gilliland, PA (0-2G4)
D. Morrison, RES (T-10F12)
W. Hill, SECY (0-16G15)
H. Miller, Region I R. Cooper, Region I S. Ebneter, Region II E. Merschoff, Region II S. Vias, Region II A. Beach, Region III J. Caldwell. Acting, Region III L. Callan, Region IV J. Dyer, Region IV K. Perkins. Region IV/WCF0 G. Fader. INPO J. Zimmer. DOE
6 ll LIST OF ATTENDEES I
OPERATING REACTORS EVENTS FULL BRIEFING (96-13)
OCTOBER 23. 1996 l
NAME OFFICE NAME OFFICE A. Chaffee NRR W. Burton NRR K. Gray NRR G. Galletti NRR E. Goodwin NRR S. Sanchez NRR S. Koenick NRR R. Correia NRR T. Koshy NRR J. Wilcox NRR F. Hebdon NRR J. Beall OCM/McGaffigan R. Hernan NRR C. Ogle OCM C. Doutt NRR J. Kauffman OE S. Athavale NRR TELEPHONE ATTENDANCE (AT ROLL CALL)
Reaions Resident Insoectors Region II M. Shannon, Sequoyah Region III Region IV Misc.
1 i
i ATTACHMENT 1 i
l l
l OPERATING REACTORS EVENTS BRIEFING 96-13 l
LOCATION:
0-10B11, WHITE FLINT l
WEDNESDAY, OCTOBER 23, 1996 11:00 A.M.
SEQUOYAH, UNIT 2 REACTOR TRIP WITH i
COMPLICATIONS i
l PRESENTED BY:
EVENTS ASSESSMENT AND GENERIC COMMUNICATIONS BRANCH DIVISION OF REACTOR PROGRAM MANAGEMENT, NRR i
l' 96-13 SEQUOYAH, UNIT 2 REACTOR TRIP WITH COMPLICATIONS OCTOBER 11, 1996 PROBLEM UNEXPECTED TURBINE RUNBACK COINCIDENT WITH INABILITY TO CONTROL THREE AUXILIARY FEEDWATER (AFW) PUMPS LEAD TO l
MANUAL REACTOR TRIP.
CAUSE l
T140 FAILED PRESSURE SWITCHES AND. FEEDWATER PUMP TRIP CAUSED MAIN TURBINE RUNBACK TRANSIENT.
P00R MAINTENANCE PRACTICES COMPLICATED EVENT.
SAFETY SIGNIFICANCE REACTOR TRIP WITH COMPLICATIONS.
CHALLENGE TO SAFETY SYSTEM FROM A NON-1E PRESSURE SWITCH FAILURE.
BACKGROUND LOSS OF A FEED PUMP AT POWER LEVEL > 80% PRODUCES:
- TURBINE RUNBACK;
- ANTICIPATORY START SIGNAL TO AFW SYSTEM FOR POTENTIAL LOSS OF SECONDARY HEAT SINK; AND
- AFW RUNS IN AUTOMATIC STEAM GENERATOR LEVEL CONTROL MODE.
CONTACT:
S. K0ENICK, NRR/DRPM/PECB AIT: N0
REFERENCES:
10 CFR 50.72 #31138 AND SIGEVENT: YES PNO-II-96-071
SEQUOYAH, UNIT 2 96-13 l
SEQUENCE OF EVENTS e
OPERATORS COMMENCED CONTROLLED PLANT SHUTDOWN IN RESPONSE TO REACTOR COOLANT PUMP (RCP) #4 SEAL #2 LEAK 0FF FLOW 0F 1.5 GPM EXCEEDING PROCEDURAL LIMIT OF 0.5 GPM.
e FOLLOWING MANUAL TRIP 0F MAIN FEEDWATER PUMP (BY PROCEDURE BELOW 50% POWER), PLANT EXPERIENCED UNEXPECTED TURBINE RUNBACK AND AUT0 START OF AFW PUMPS.
l e
10 0F 12 STEAM DUMPS OPENED ON DEMAND (PRIOR TO EVENT TWO ISOLATED BECAUSE OF LEAKAGE).
e OPERATORS MANUALLY TRIPPED REACTOR IN RESPONSE TO UNEXPECTED PLANT PERFORMANCE.
MAIN FEEDWATER ISOLATION OCCURRED AT LOW Tavg 550 F:
e ONE MFIV FAILED TO CLOSE.
e OPERATORS WERE UNABLE TO TAKE MANUAL CONTROL OF AFW LEVEL CONTROL VALVES FOR MOTOR DRIVEN AND SPEED CONTROL FOR TURBINE DRIVEN PUMPS.
l e
OPERATORS TRIPPED THE TWO MOTOR DRIVEN PUMPS AND PLACED THEM IN PULL-TO-LOCK AND THROTTLED TURBINE DRIVEN FLOW WITH LEVEL CONTROL VALVES TO FOUR STEAM GENERATORS.
o STEAM DUMPS ATTEMPT TO MODULATE PLANT TO NO LOAD Tavg (547 F) AND INTERLOCK ACTUATES TO BLOCK STEAM DUMPS AT LOWLOW Tavg (540 F).
o REACTOR COOLANT SYSTEM EXPERIENCED C00LDOWN TO APPR0XIMATELY 538 F REQUIRING OPERATORS TO EMERGENCY BORATE.
e SEQUOYAH, UNIT 2 96-13 e
DECAY HEAT WAS REMOVED VIA STEAM DUMPS TO CONDENSER.
DISCUSSION OF COMPLICATIONS RCP #4 SEAL #2 LEAK 0FF FLOW 1.5 GPM EXCEEDING PROCEDURAL LIMIT l
CAUSE:
FAILED 0-RING IN ASCO SOLEN 0ID VALVE CLOSED SEAL RETURN ISOLATION VALVE; EFFECT:
OPERATORS COMMENCED SHUTDOWN IN RESPONSE TO #2 SEAL FLOW ON #4 RCP EXCEEDING PROCEDURAL LIMIT.
UNEXPECTED TURBINE RUNBACK COINCIDENT WITH AUTO START OF ALL AFW PUMPS CAUSE:
2 PRESSURE SWITCH CONTACT FAILURES (M0ISTURE INDUCED CORROSION) LOCKED-IN SIGNAL FOR > 80%
POWER:
EFFECT:
MAIN FEEDWATER PUMP TRIPPED CAUSING TURBINE RUNBACK: AUTO START OF AFW, AND MDAFW FLOW CONTROL VALVES G0ING FULL OPEN AND TDAFW PUMP l
G0ING TO FULL SPEED ACCORDING TO DESIGN.
UNABLE TO RESET AFW START SIGNAL BECAUSE > 80%
POWER SIGNAL NEVER CLEARED.
1 MAIN FEEDWATER ISOLATION VALVE FAILED TO CLOSE CAUSE:
MOISTURE INDUCED CORROSION OF MAGNETIC BRAKE IN MOV BLOCKED ROTOR; EFFECT:
MOV FAILURE (SEIZED MOTOR).
I SEQUOYAH, UNIT 2 96-13 INDICATIONS OF WATER HAMMER ON #11 STEAM DUMP LINE TO CONDENSER I
CAUSE:
LEVEL CONTROL FAILURE ON STEAM DUMP DRAIN TANK CAUSED CONDENSATE TO GACK UP IN STEAM DUMP LINE:
EFFECT:
HANGER DAMAGE: PIPE DEFORMATION: AND TWO CRACKS ON WELD CONNECTING LINE WITH MAIN STEAM HEADER (BOTH LESS THAN TWO INCHES IN LENGTH AND 0.5 l
INCHES DEEP / PIPE THICKNESS NOMINAL 1.25 INCHES).
l FOLLOWUP i
e REGION II CONDUCTED SPECIAL INSPECTION TO REVIEW EVENT.
REGION II TO ISSUE TIA TO NRR TO ASSESS EMERGENCY FEEDWATER CONTROLS.
2 l
e NRR REVIEWING GENERIC IMPLICATIONS.
1 i
l 4
REACTOR SCRAM Reporting Period: 10/14/96 to 10/20/96 YTD YTD ABOVE BELOW YTD QAl[
PLANT & UNIT M
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ggji COMPLICATIONS jj}
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TQTAL 10/14/96 V0GTLE 2 50 SM Equipment Failure NO 1
0 1
10/15/%
PEACH BOTTOM 2 70 SA Equipment Failure NO 2
0 2
10/18/%
COMANCHE PEAK 2 100 SA Equipment Failure NO 3
0 3
10/20/96 Ros!Ns0N 2 20 SA Equipment Failure NO 2
0 2
Nits: Year To Date (YTD) Totals Inchde Events Within The Calendar Year Indicated By The End Date of The Specified Reporting Period ETS 10 Page:1 10/22/96
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l COMPARISON OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES l
l PERIOD ENDING i
10/20/96 l
NUMBER 1996 1995 1994 1993 1992 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCR M CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
POWER GREATER THAN OR EQUAL 70 15%
l EQUIPMENT FAILURE 4
1.57 1.83 1.52 1.83 2.62 DESIGN / INSTALLATION ERROR 0
0.12 0.12 0.08 0.04 OPERATING ERROR 0
0.07 0.15 0.21 0.27 0.31 MAINTENANCE ERROR 0
0.55 0.38 0.54 0.52 0.50 l
EXTERNAL 0
0.17 0.21 0.17 0.13 OTHER 0
0.10 0.06 0.02 Subtotal 4
2.58 2.75 2.52 2.81 3.43 l
l POWER LESS THAN 15%
i EQUIPMENT FAILURE O
0.21 0.10 0.27 0.38 0.42 l
DESIGN / INSTALLATION LRROR 0
0.00 0.02 OPERATING ERROR 0
0.10 0.13 0.08 0.13 0.15 0.02 0.08 l
MAINTENANCE ERROR 0
0.07 0.08 EXTERNAL 0
0.00 0.04 OTHER 0
0.00 I
l
. Subtotat 0
0.38 0.31 0.37 0.57 0.65 l
TOTAL 4
2.96 3.06 2.89 3.38 4.08 1996 1995 1994 1993 1992 NO. OF WEFTLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE j
(YTD)
TOTAL AUTOMATIC SCRAMS 3
1.83 1.92 2.19 2.44 3.06 TOTAL MANUAL SCRANS 1
1.12 1.13 0.69 0.94 1.02 l
l l
TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF 4
ETS-14 Page: 1 10/22/96 l
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l / NOTES 1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST.
PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY.
SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD l
MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN l
IN ACCORDANCE WITH A PLANT PROCEDURE.
THERE ARE 111 REACTORS HOLDING AN OPERATING LICENSE.
l 2.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, l
AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
3.
COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL l
ERRORS UNRELATED TO CAUSE OF SCRAM.
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 Mnnual and Automatic Scrams for 1988 ------------------ 291 Manunl and Automatic Scrams for 1989 ------------------ 252 Manual and Automatic Scrams for 1990 ------------------ 226 Manuel and Automatic Scrams for 1991 ------------------ 206 Manuel and Automatic Scrams for 1992 ------------------ 212 Manual and Automatic Scrams for 1993 ------------------ 175 Manual and Automatic Scrams for 199< ------------------ 150 Manual and Automatic Scrams for 1995 ------------------ 159 Manual and Automatic Scrams for 1996 --(YTD 10/20/96)-- 124 i
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OPERATING REACTOR PLANTS SIGNIFICANT EVENTS L
No Sort Specified QUERY > Event Type SIG & Close Out Date >= 10/09/96 1
DATE OF 50.72 i
PLANT & UNIT EENI NLNESER DESCRIPTION OF EVENT SIGNIFICANCE BRI FING PRESENTER DRESDEN 3 06/11/ %
0 In June 1996 et Dresden 3, a circuit breaker for a Safety-Related Cooling System NODGE V.
MIGMLIGHT
[
low-pressure coolant injection p g failed to open i
on demand from the control room. The licensee fotnd hardened greese in the breaker mechanism.
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ETS-11 Page:1 10/24/96 s
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