|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20198A3731997-12-0404 December 1997
Summary of 971119 Meeting W/Westinghouse Owners Group Re Completion of WOG Topical Rept WCAP-14572,rev 1,conclusions from Results of Surry Pilot Plant Submittal & Schedule for Approving Surry Submittal & Associated WCAP
ML20136A8611996-11-27027 November 1996
Partially Withheld Summary Meeting W/Florida Power & Light Held on 961121 Re General Update on FPL Nuclear Plants
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
ML20129G4921996-08-29029 August 1996
Summary of 433rd ACRS Meeting on 960808-10 Re Design Changes Proposed by Asea Brown Boveri - C-E Re Certification of Sys 80+ Design,Secy 96-128,proposed Rev 3 to Reg Guide 1.8,revs to Reg Guides 1.84,1.85 & 1.147 & Rev 3 to Reg Guide 1.105
ML20129G5261996-07-31031 July 1996
Summary of ACRS Plant Operations Subcommittee Meeting on 960521 to Review Proposed Rule on Shutdown Operations & Associated Reg Guide as Well as Studies on Shutdown Risk at Surry & Grand Gulf Nuclear Plants
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
ML20056E2121993-06-15015 June 1993
Summary of Operating Reactors Events Meeting 93-21 on 930609
ML20056D8341993-05-26026 May 1993
Summary of Operator Reactors Event Meeting 93-18 on 930519
ML20056D9841993-05-18018 May 1993
Summary of Operating Reactors Events Meeting 93-17 on 930512
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
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
ML20247E3641989-09-0606 September 1989
Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals
ML20247D5291989-09-0505 September 1989
Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified
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
ML20246K2171989-08-24024 August 1989
Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson
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
ML20248B5171989-08-0303 August 1989
Summary of 890725 Interface Meeting W/Util in Birrmingham,Al Re Sonopco/Util Corporate Organization Including Generic Activities & Initiatives Re Plants.Agenda & Viewgraphs Encl
ML20246P7771989-07-13013 July 1989
Summary of Operating Reactors Events Meeting 89-26 on 890712.Events Discussed & Significant Elements of Events Presented in Encl 2.List of Attendees Also Encl
ML20246F8691989-06-22022 June 1989
Summary of Operating Reactors Events Meeting 89-24 on 890621.On 890615,potential Unmonitored Primary Coolant Release Path to Environ Discovered at WPPSS-2.On 890617,loss of Offsite Power Occurred at Brunswick,Unit 2
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
ML20245F2221989-06-0808 June 1989
Summary of Operating Reactors Events Meeting 89-21 on 890531.List of Attendees & Related Info Encl
ML20245A3851989-05-30030 May 1989
Summary of Operating Reactors Events Meeting 89-20 on 890524.List of Meeting Attendees & Viewgraphs Encl
ML20247M7961989-05-24024 May 1989
Summary of 890502 Meeting W/Util,Sargent & Lundy & Rl Cloud Assoc in Rockville,Md Re Nonlinear Piping Analyses Used to Justify Removal of Snubbers & Pipe Supports.List of Attendees & Presentation by Licensee & Contractors Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247J6991989-05-19019 May 1989
Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl
ML20247J7051989-05-19019 May 1989
Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20247D3441989-05-16016 May 1989
Summary of Operating Reactors Events Meeting 89-19 on 890510.List of Attendees,Events Discussed & Significant Elements of Events & Rept of long-term Followup Assignments & Summary of Scrams for Wk Ending 890507 Encl
ML20246L7281989-05-0505 May 1989
Summary of 890503 Meeting W/Util in Rockville,Md Re Containment Vessel Structural Integrity Tech Specs for Plants.List of Attendees & Licensee Presentation Encl
ML20246C3261989-05-0404 May 1989
Summary of Operating Reactors Events Meeting 89-18 on 890503
ML20246B5161989-04-28028 April 1989
Summary of 890419 Operating Reactors Events Meeting 89-16. List of Attendees & Handouts 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
ML20245H8011989-02-23023 February 1989
Summary of Operating Reactors Events Meeting 89-08 on 890222.Attendee List & Events Discussed & Significant Elements of Events Encl
ML20235M1671989-02-17017 February 1989
Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl
ML20196B9821988-12-0101 December 1988
Summary of Operating Reactors Events Meeting 88-47 on 881129.List of Attendees,Events Discussed & Significant Elements of Events,Two Events Suggested for long-term Followup & Summary of Reactor Scrams Encl
ML20206L9831988-11-25025 November 1988
Summary of Operating Reactors Events Meeting 88-45 on 881115.List of Attendees & Handouts Encl
ML20195H0271988-11-25025 November 1988
Summary of Operating Reactor Events Meeting 88-46 on 881122
ML20206E3591988-11-10010 November 1988
Summary of Operating Reactors Events Meeting 88-44 on 881108.List of Meeting Attendees,Significant Events & Summary of Reactor Scrams Encl.One Significant Event Identified for Input to Performance Indicator Program
ML20205H7521988-10-18018 October 1988
Summary of Operating Reactors Events Meeting 88-41 on 881018.No Significant Events Identified for Input to NRC Performance Indicator Program
ML20207M0771988-10-0505 October 1988
Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl
ML20207K9461988-10-0404 October 1988
Summary of 880830 Meeting W/Util in Rockville,Md Re Fire protection-related Issues.Draft Fire Protection Engineering Evaluation, Cables on Svc Bldg Outside Wall & List of Attendees Encl
ML20245D8411988-09-28028 September 1988
Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920
ML20155B8231988-09-20020 September 1988
Summary of Operating Reactors Events Meeting 88-37 on 880920.Info Encl Includes rept-to-date of long-term Followup Assignments & Summary of Reactor Scrams
ML20154F7971988-09-15015 September 1988
Summary of 880901 QA Meeting W/Util in Rockville,Md to Discuss Rev 2 of Util Operational QA Plan for Plants.Agenda & List of Participants Encl
ML20154N4471988-09-0707 September 1988
Summary of Operating Reactors Events Meeting 88-036 on 880906 Re Events Which Occurred Since Last Meeting on 880830.List of Attendees Encl
ML20153G6331988-08-30030 August 1988
Summary of Operating Reactor Events Meeting 88-35 on 880830, Including Summary of Reactor Scrams for Wk Ending 880828. Significant Event Identified for Input to NRC Performenance Indicator Program
1997-12-04
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20198A3731997-12-0404 December 1997
Summary of 971119 Meeting W/Westinghouse Owners Group Re Completion of WOG Topical Rept WCAP-14572,rev 1,conclusions from Results of Surry Pilot Plant Submittal & Schedule for Approving Surry Submittal & Associated WCAP
ML20136A8611996-11-27027 November 1996
Partially Withheld Summary Meeting W/Florida Power & Light Held on 961121 Re General Update on FPL Nuclear Plants
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
ML20129G4921996-08-29029 August 1996
Summary of 433rd ACRS Meeting on 960808-10 Re Design Changes Proposed by Asea Brown Boveri - C-E Re Certification of Sys 80+ Design,Secy 96-128,proposed Rev 3 to Reg Guide 1.8,revs to Reg Guides 1.84,1.85 & 1.147 & Rev 3 to Reg Guide 1.105
ML20129G5261996-07-31031 July 1996
Summary of ACRS Plant Operations Subcommittee Meeting on 960521 to Review Proposed Rule on Shutdown Operations & Associated Reg Guide as Well as Studies on Shutdown Risk at Surry & Grand Gulf Nuclear Plants
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
ML20056E2121993-06-15015 June 1993
Summary of Operating Reactors Events Meeting 93-21 on 930609
ML20056D8341993-05-26026 May 1993
Summary of Operator Reactors Event Meeting 93-18 on 930519
ML20056D9841993-05-18018 May 1993
Summary of Operating Reactors Events Meeting 93-17 on 930512
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
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
ML20247E3641989-09-0606 September 1989
Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals
ML20247D5291989-09-0505 September 1989
Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified
ML20246K2171989-08-24024 August 1989
Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson
ML20248B5171989-08-0303 August 1989
Summary of 890725 Interface Meeting W/Util in Birrmingham,Al Re Sonopco/Util Corporate Organization Including Generic Activities & Initiatives Re Plants.Agenda & Viewgraphs Encl
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
ML20246P7771989-07-13013 July 1989
Summary of Operating Reactors Events Meeting 89-26 on 890712.Events Discussed & Significant Elements of Events Presented in Encl 2.List of Attendees Also Encl
ML20246F8691989-06-22022 June 1989
Summary of Operating Reactors Events Meeting 89-24 on 890621.On 890615,potential Unmonitored Primary Coolant Release Path to Environ Discovered at WPPSS-2.On 890617,loss of Offsite Power Occurred at Brunswick,Unit 2
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
ML20245F2221989-06-0808 June 1989
Summary of Operating Reactors Events Meeting 89-21 on 890531.List of Attendees & Related Info Encl
ML20245A3851989-05-30030 May 1989
Summary of Operating Reactors Events Meeting 89-20 on 890524.List of Meeting Attendees & Viewgraphs Encl
ML20247M7961989-05-24024 May 1989
Summary of 890502 Meeting W/Util,Sargent & Lundy & Rl Cloud Assoc in Rockville,Md Re Nonlinear Piping Analyses Used to Justify Removal of Snubbers & Pipe Supports.List of Attendees & Presentation by Licensee & Contractors Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247J7051989-05-19019 May 1989
Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy
ML20247J6991989-05-19019 May 1989
Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl
ML20247D3441989-05-16016 May 1989
Summary of Operating Reactors Events Meeting 89-19 on 890510.List of Attendees,Events Discussed & Significant Elements of Events & Rept of long-term Followup Assignments & Summary of Scrams for Wk Ending 890507 Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20246L7281989-05-0505 May 1989
Summary of 890503 Meeting W/Util in Rockville,Md Re Containment Vessel Structural Integrity Tech Specs for Plants.List of Attendees & Licensee Presentation Encl
ML20246C3261989-05-0404 May 1989
Summary of Operating Reactors Events Meeting 89-18 on 890503
ML20246B5161989-04-28028 April 1989
Summary of 890419 Operating Reactors Events Meeting 89-16. List of Attendees & Handouts 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
ML20245H8011989-02-23023 February 1989
Summary of Operating Reactors Events Meeting 89-08 on 890222.Attendee List & Events Discussed & Significant Elements of Events Encl
ML20235M1671989-02-17017 February 1989
Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl
ML20196B9821988-12-0101 December 1988
Summary of Operating Reactors Events Meeting 88-47 on 881129.List of Attendees,Events Discussed & Significant Elements of Events,Two Events Suggested for long-term Followup & Summary of Reactor Scrams Encl
ML20195H0271988-11-25025 November 1988
Summary of Operating Reactor Events Meeting 88-46 on 881122
ML20206L9831988-11-25025 November 1988
Summary of Operating Reactors Events Meeting 88-45 on 881115.List of Attendees & Handouts Encl
ML20206E3591988-11-10010 November 1988
Summary of Operating Reactors Events Meeting 88-44 on 881108.List of Meeting Attendees,Significant Events & Summary of Reactor Scrams Encl.One Significant Event Identified for Input to Performance Indicator Program
ML20205H7521988-10-18018 October 1988
Summary of Operating Reactors Events Meeting 88-41 on 881018.No Significant Events Identified for Input to NRC Performance Indicator Program
ML20207M0771988-10-0505 October 1988
Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl
ML20207K9461988-10-0404 October 1988
Summary of 880830 Meeting W/Util in Rockville,Md Re Fire protection-related Issues.Draft Fire Protection Engineering Evaluation, Cables on Svc Bldg Outside Wall & List of Attendees Encl
ML20245D8411988-09-28028 September 1988
Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920
ML20155B8231988-09-20020 September 1988
Summary of Operating Reactors Events Meeting 88-37 on 880920.Info Encl Includes rept-to-date of long-term Followup Assignments & Summary of Reactor Scrams
ML20154F7971988-09-15015 September 1988
Summary of 880901 QA Meeting W/Util in Rockville,Md to Discuss Rev 2 of Util Operational QA Plan for Plants.Agenda & List of Participants Encl
ML20154N4471988-09-0707 September 1988
Summary of Operating Reactors Events Meeting 88-036 on 880906 Re Events Which Occurred Since Last Meeting on 880830.List of Attendees Encl
ML20153G6331988-08-30030 August 1988
Summary of Operating Reactor Events Meeting 88-35 on 880830, Including Summary of Reactor Scrams for Wk Ending 880828. Significant Event Identified for Input to NRC Performenance Indicator Program
ML20207J1611988-08-25025 August 1988
Summary of 880818 Meeting W/Util in Rockville,Md Re Tech Specs Conversion.List of Attendees & Agenda Encl
1997-12-04
[Table view] |
Text
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MEMORANDUM.FOR:' Charles E. Rossi, Director, Division 'of Operational. Events Assessment j .
lFROM: Wayne Lanning, Acting Chief j d- ., Events Assessment Branch (1]f Division of Operational Events Assessment
SUBJECT:
' THE-OPERATING REACTORS EVENTS MEETING 87-17
,- JUNE 2, 1987 On June 2, 1987, anL0perating Reactors Events meeting (87-17) was held to !
brief senior manageristfrom NRR, RES, AE0D and Regional Offices on events' l C' : which occurred stnce' cur'last ineeting on May 26, 1987. The list of attendees- '
'is included, as Enclosure 1. j J .
The results of the June 1,1987 Monday meeting for the transfer of long-term . 3
- ' eventa followup were reviewed. In addition, the format and content for reporting. J the weekly reactor scram summary and statistics were discussed.- 1 m
i The events discussed and the significant elements of these events are' presented in Enclosure 2. ' Enclosure. 3 provides a sumary of reactor scrams and' "significant events" that will be' input to NRC's performance indicator program.
Original Signed by Wayne D. Lanning Wayne Lanning, Acting Chief-Events Assessment Branch Division of Operational Events Assessment 1
Enclosures:
As stated l cc w/ Encl.: $
See Next Page. )
l
' DISTRIBUTION icentrah E11e3 NRC PDP.
EAB Rdg Oudinot Rdg w/o Enclosure.-
'EAB Members t i
(SEE ATTACHED FOR PREVIOb5 CONCURRENCE *) l PWR:EAB *-
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, MEMORANDUM FOR: Charles E. Rossi, Director j
\ Division of Operational Events Assessment FROM: Wayne Lanning, Acting Chief
\ Events Assessment Branch i- Division of Operational Events' Assessment
SUBJECT:
x THE OPERATING REACTORS EVENTS MEETING 87-17
'\
JUNE 2, 1987 x
\ .
On June 2,1987, an Operating Reactors' Events meeting (87-17) was held to brief senior managers from NRR, RES, AE00 and Regional Offices on events which occurred hince our 'iast meeting on May 26, 1987. .The list of attendees ;
is included as Eiiclosure 4.
. X :
1 The results' of the ' June 1,1987, Monday meeting for the transfer of long-term h event followup wera ' reviewed. In addition, the forinat and content for reporting l the weekly reactor scram summary and statistics were discussed.
p The events discussed and.the si0nificant elements of these events are presented in Enclosure 2. Enclosube 3 provides a summary of. reactor scrams and "significant events", that 'will be input.to NRC's performance indicator program. :
\'
l- \ s
'\
\
\ Wayne.Lc.nning, Acting Chief
\ Events Assessment Branch yivision of Operational Events Assessment.
\
Enclosures. s
.As stated- 1
\
cc w/ Encl.: \
See Next Page ( \
DISTRIBUTION \
Central File \
'NRC PDR \
EAB Rdg '\~
Oudinot Rdg w/o. Enclosure EAB Members c
3 PWT: B SL:PWR:EAB SL:BWR:EAB ACT.BC:EAB
-WSWENSON:mk RLOBEL pBARAN0WSKY WLANNING o(/o4/87 / /87 / /87 / /87
__--_--__---_ ~
1 1
} _
Charles E. Rossi Jgy g 1987
. e c .. T. Murley L. Rubenstein J. Sniezek D.-Mcdonald R. Starostecki C. Patel J. Taylor. R. Capra. l
.E.-Jordan M. Slosson E. Beckjord ,
W.' Russell,-Reg. I J. Nelson Grace,, Reg. II B.-. Davis, Reg.,III l
R. D. Martin, Reg. IV J. B. Martin, Reg. V .
W. Kane, Reg. I L. Reyes, Reg. II-C. Norelius, Reg.-III E.' Johnson, Reg..-IV l D. Kirsch, Reg. ~ V i
S. Va.rga j D. Crutchfield ,j
^B. Boger G. Lainas G. Holahan U F. Schroeder L. $hao J. Partlow B. Grimes
>F. Congel.
H. Miller ,
E.-Weiss S. Black T. Martin, EDO F. Miraglia E. .Merschoff R..Hernan t
)
I i
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' I
,,1-t-
. ,i u
Un ENCLOSURE 1 LIST OF ATTENDEFS.
OPERATING REACTORS EVENTS BRIEFING (87-17)
JUNE ~2,-1987 NAME DIVISION: NAME DIVISION
. C; Rossi :NRR R. Lobel NRR-W. Lanning NRR S. Rubi~n AE0D.
B. Grimes NRR- J. Partlow NRR
, - R.:Bosnak RES J. Roe. NRR F.!Miraglia NRR' S. Varga NRR.
R; Scholl NRR C.-Patel- NRR
~J. 'Smenta' ARM- S. Black NRR T. Novak' AEOD W. Troskoski DEDRO J.'Heltemes AEOD D. Mcdonald NRR F. Schroeder NRR R. W. Stevens, Jr. .NRR
, .P. Baranowsky NRR m
L. .
u
.n ENCLOSURE 2' s
'0PERATING REACTORS EVENTS BRIEFING 87-17 JUNE 2, 1987, TURKEY P0lNT.3/4 SAFETY SYSTEM REVIEW WESTINGHOUSE' POST-LOCA ECCS SWITCHOVER PROCEDURES SURRY I HOT LEG ISOLATION VALVE FAILURE - UPDATE SURRY I BORON ACCUMULATION.
INDIAN POINT 3 IRRADIATED FUEL PARTICLE OTHER EVENT OF INTEREST MULTIPLEL
' INATTENTIVE OPERATORS AND WATCHMEN l
)
.,i .
FLORIDA POWER 8 LIGHT COMPANY TURKEY POINT PLANT SAFETY SYSTEM REVIEW E
INITIATING EVENT
-1SSFI' AUXILIARY FEEDWATER SYSTEM SUMMER 1985 SELECTED SYSTEMS (3 4)
INSTRUMENT: AIR - CHEMICAL VOLUME CONTROL SYSTEM-
--INTAKE COOLING WATER - EMERGENCY POWER j j .
-. COMPONENT COOLING WATER - EMERGENCY FILTERS l
- SAFETY INJECTION - CONTAINMENT ISOLATION
--CONTAINMENT SPRAY - VITAL AC/DC
- EMERGENCY l CONTAINMENT COOLERS- .- REACTOR PROTECTION SYSTEM-
- RESIDUAL HEAT-REMOVAL - MAIN STEAM ISOLATION L
PROCESS-
- REVIEW SYSTEM BOUNDARIES
- - KEY SYSTEM. DOCUMENT APPLICABILITY EVALUATION
- REVIEW LICENSING CORRESPONDENCE AND COMMITMENTS
. REVIEW DESIGN AND ACCIDENT ANALYSES
- ESTABLISH SYSTEM PERFORMANCE CRITERIA USING DESIGN BASIS, AND COMMITMENTS
- EVALUATION SYSTEMS TESTING
- VERIFY CONSISTENCY BETWEEN SYSTEM DOCUMENTS AND THE DESIGN BASIS:
DRAWINGS TECHNICAL SPECIFICATIONS PROCEDURES Q-LIST VENDOR DOCUMENTS
- RESOLVE INCONSISTENCIES AND MODIFY SYSTEM AS REQUIRED PRODUCT t
-- RECONSTITUTED DESIGN BASIS CONSISTENT WITH LICENSING COMMITMENTS i AND ANALYSES-
- CONSISTENCY BETWEEN DESIGN BASIS AND AS-BUILT-DRAWINGS s
- VERIFICATION OF SYSTEM PERFORMANCE
- . l
FLORIDA POWER 8 LIGHT-COMPANY TURKEY POINT PLANT SAFETY' SYSTEM REVIEW !
STATUS
- SAFETY' ENGINEERING GROUP COMPREHENSIVE REVIEW
- COMPREHENSIVE REVIEW COMPLETE U-3 CLOSE00T IN PROGRESS (10%)
U-4 CLOSE0VT SCHEDULED 1988
- ISSUES IDENTIFIED (PUNCHLIST) 2400 TOTAL 53% RESOLVED IN EXCESS OF 200,000 MANHOURS EXPENDED TO DATE 1
- SCHEDULED COMPLETION FALL 1988
- CONFIRMATORY-ORDER OF 8/86 ADDED THREE SYSTEMS NORMAL CONTAINMENT COOLERS PROCESS RADIATION MONITORING l AREA RADIATION MONITORING SIGNJFICANT FINDINGS (1) COMPONENT COOLING WATER FLOW BALANCE NOT ADEQUATE (2) INTAKE COOLING WATER TEMPERATURE CONTROL VALVES FAILED NONCONSERVATIVELY ON LOSS OF. AIR (3) POTENTIAL EXISTED FOR OVERLOADING EMERGENCY DIESEL GENERATORS UNDER CERTAIN ACCIDENT CONDITIONS (4) MAIN STEAM ISOLATION VALVE OPERATIONAL TIME NOT ASSURED ON LOSS OF INSTRUMENT AIR (5) CONTAINMENT SPRAY PUMP DISCHARGE COULD EXCEED PUMP RUNOUT LIMIT (6) COMPONENT COOLING WATER FLOW EXCESS CAPABILITY IDENTIFIED
..(7)-ENVIRONMENTAL COOLING SYSTEM FOR INSTRUMENT INVERTERS NOT t SAFETY RELATED AND MAY NOT BE AVAILABLE UNDER ALL ACCIDENT CONDITIONS (8) SWITCH 0VER FROM INJECTION TO RECIRCULATION COULD RESULT i IN UNC0VERING CORE
WESTINGHOUSE -' POST LOCA ECCS.
SWITCH 0VER PROCEDURES PROBLEM PROCEDURES PERMIT ALL ECCS PUMPS TO BE STOPPED FOR UP TO 10 M!NUTES ;
'FOR MANUAL.SWITCHOVER FROM RWST TO THE CONTAINMENT' SUMP, ONLY ABOUT 2~ MINUTES MAY BE AVAILABLE.
CAUSE' NONCONSERVATIVE CORE BOILOFF CALCULATION WHICH DID NOT CONSIDER CONTINUED FLOW FROM BREAK,
' SIGNIFICANCE ECCS INTERRUPTION COULD LEAD TO CORE UNC0VERY.
DISCUSSION TURKEY POINT EMERGENCY LOCA PROCEDURES REVIEWED AS PART OF DESIGN BASIS RECONSTITUTION. EFFORT (DBRE).
PROCEDURES PERMITTED ECCS PUMPS TO BE SWITCHED OFF FOR UP.T0 10 MINUTES FOR REALIGNMENT TO COLD LEG RECIRCULATION AND !
HOT LEG RECIRCULATION, APPROXIMATELY.18 MINUTES WAS THOUGHT TO BE AVAILABLE BEFORE CORE UNC0VERY BASED ON POT BOILING MODEL.
FLOW OUT OF BREAK DUE TO DENSITY DIFFERENCES BETWEEN CORE AND DOWNCOMER WAS SHOWN TO OCCUR DURING POST REFLOOD AT LAPGE SCALE TESTS IN JAPAN, (CCTF)
LICENSEE IS REVISING PROCEDURES S0 THAT HPI REMAINS RUNNING
-WHILE LPI PUMPS ARE REALIGNED S0 THAT ALL ECCS FLOW IS NOT l LOST FOLLOWING LARGE BREAK LOCAS, WESTINGHOUSE SENT A NOTIFICATION LETTER TO CUSTOMERS.
FOLLOWUP >
RSB TO FOLLOWUP SAFETY ANALYSES SUPPORTING PROCEDURE REVISIONS.
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5 SURPY J-POT LEG ISOLATION VALVE FAILDRE UPDATE PROBLEM FAILURE OF HOT LEG-ISOLATION VALVE RESULTED IN LOW FLOW CONDITION AND SUBSEQUENT REACTOR TRIP..
CAUSE VALVE STEM SHEARED SIGNIFICANCE. REDUCED THERMAL MARGIN DISCUSSION LICENSEE PERFORMED CONSERVATIVE CALCULATION OF MINIMUM DNBR AS A RESULT OF THIS TRANSIENT.
STEADY STATE " SNAP SHOT" CALCULATION AT COMBINATION OF WORST {q CONDITIONS OF POWER, AXIAL POWER SHAPE, PRESSilRE, COOLANT l FLOW, TEMPERATURE, AND F-DELTA H.
MINIMUM DNBR = 1.46 THIS EVENT IS BOUNDED BY LOCKED ROTOR ACCIDENT EVEN FOR CASE OF COMPLETE BLOCKAGE OF ONE LOOP. .
FOLLOWUP
- REGION II PREPARING INFORMATION NOTICE. l I
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SURRY 1 - BORON ACCUMULATION PROBLEM LEAKAGE FROM HEAD VENT VALVES RESULTED IN BUILDUP'0F:
BORIC ACID CRYSTALS ON TOP 0F VESSEL HEAD SAFETY SIGNIFICANCE POTENTIAL DEGRADATION OF PRESSURE BOUNDARY CAUSE 0UESTIONABLE TAILPIPE DESIGN FOR DIRECTING HEAD VENT LEAKAGE SEQUENCE OF EVENTS CIRCUMSTANCES ARE SIMILAR TO THE MARCH 13, 1987 TURKEY P0lNT i EVENT 0.5 GPM UNIDENTIFIED LEAKAGE OCCURRED BETWEEN SUMMER 1986 REFUELING OUTAGE AND DECEMBER 1986 PIPE INSPECTION EVIDENCE OF BORIC ACID COMING FROM HEAD VENT DRAIN LINE DURING DECEMBER PIPE INSPECTION OUTAGE RESULTED IN REPLACEMENT OF TARGET ROCK SOLEN 0ID VENT VALVES REEXAMINED ACID PROBLEM IN MAY 1987 SHUTDOWN BECAUSE INFORMATION NOTICE SENSITIZED MANAGEMENT TO LOOK MORE CLOSELY BUILDUP FOUND AT SEAM 0F HEAD FLANGE STUDS MIRROR INSULATION, INSULATION WAS REMOVED ABOUT 70 POUNDS OF BORIC ACID (POWDER) FOUND, EN0 UGH TO COVER A STANDARD DESK TOP 2-INCHES DEEP PRELIMINARY EVIDENCE IS THAT ACID HAD NOT CONTACTED THE FLANGE AREA OR ITS SEALS TUBE HAS BEEN FITTED TO TAILPIPE TO REDIRECT FUTURE LEAKAGE BELOW VESSEL FOLLOWUP THE LICENSEE IS PREPARING A SEQUENCE OF EVENTS AND A ROOT CAUSE EVALUATION. SRI IS MONITORING SITUATION.
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..t INDIAN POINT 3 - IRRADIATED FUEL PARTICLE PROBLEM ;
- EXPOSURE 0F A MAINTENANCE FOREMAN..
4 REM DOSE T0 NECK (5/23/87)-
CAUSE
' SMALL RADI0 ACTIVE. PARTICLE ~
SIG'NIFICANCE
. POTENTIAL.FOR PLANT: WIDE DISPERSAL OF' IRRADIATED FUEL PART.tCLES-I DISCUSSION i MAINTENANCE FOREMAN WORKING IN-STEAM GENERATOR MANWAY AREA-PARTICLE FOUND DURING ROUTINE EXIT SURVEY PAPsTICLE COUNT RATE:- 100,000 CPM t PARTICLE THOUGHT TO BE ZIRCONIUM (FROM SPECTRUM' ANALYSIS)-
RECENT FUEL' PROBLEMS:
5/26 1 YANKEE R0WE: ONE FUEL-ASSEMBLY FROM BAFFLE JETTING-5/27 MCGUIRE: 'THREE FUEL RODS FROM BAFFLE JETTING FOLLOWUP LICENSEE CONTINUING INVESTIGATION PRPB PREPARING INFORMATION NOTICE .
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ENCLOSURE 3 REACTOR SCRAM
SUMMARY
WEEK ENDING 05/31/87
- 1. PLANT SPECIFIC DATA DATE SITE UNIT POWER EPS CAUSE COMPLI- YTD YTD YTD CAT 10NS ABOVE BELOW TOTAL 151 151 05/25/67 WATERFORD 3 100 A EQUIPMENT / ELECT ND 5 0 5 05/27/E7PEEEY !. 60 A EQUIPMENT / ELECT ND 4 2 6 05/28/67 W2LF CEEEK 1 100 A EQUIPMENT / ELECT N3 5 0 5 05/29/87 LASALLE 1 59 A EDVIfMENT/ MECH ND 4 0 4 05/30/87 PALD VERDE 1 100 A EQUIPMENT / ELECT NO 2 0 2 i
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II. . COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 05/31/87 SCRAM CAUSE POWER NUMBER 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE AVERAGE YTD (3)(4) (8) (9) 4* POWER >15%
EQUIP. RELATED #15% 5 3.8 4.3 5.4 PERS. RELATED(6) >15% 0 1.6 1.8 2.0 OTHER(7) >15% 0 1.1 0.4 0.6 44 Subtotal **
5' 6.5 6.5 8.0
EQUIP. RELATED <:15% 0 1.1 1.4 1.3 PERS. RELATED <:15% 0 0.7 0.8 0.9 OTHER <15% 0 0. 3 0.2 0.2 $
O 2.1 2.4 2.4 44* Total ***
5 8.6 8.9 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE YTD MANUAL SCRAMS O 1.6 1.0 1.0 AUTOMATIC SCRAMS 5 7.0 7.9 9.4 1
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- 1. PLANT SPECIFIC DATA BASED,0N 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 R0D MOTION, AND EXCLUDE PLANNED <
TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.
- 2. RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
- 3. 1986 INFORMATION DERIVED FROM ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1986. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
- 4. IN 1986, THERE'WERE AN ESTIMATED TOTAL OF 461 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 104 REACTORS (HOLDING OPERATINGLICENSES). THIS YIELDS AN AVERAGE RATE OF 4.4 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 6.8 TRIPS PER WEEK FOR ALL REACTORS.
- 5. BASED ON 107 REACTORS HOLDING AN OPERATING LitENSE.
- 6. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL -
DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
- 7. "OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL
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CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
- 8. 1985 INF0PMATION DERIVED FROM AN ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
- 9. IN 1985, THERE WERE AN ESTIMATED TOTAL 0F 541 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER
-flCENStd. THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR Y 8 2 F AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.
.Page No,=. 1 i06/01/87 PERFORMANCE INDICATORS SIGNIFICANT EVENTS-PLANTNAME' ' EVENT EVENT DESCRIPTION GTR CAUSE DATE
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INDIAN POINT 3' 05/23/87 EIPDSURE OF MAINTENANCE FOREMAN DUE TO RAD 10 ACTIVE 1 INADEQUATE CONTAMINAT10N CONTROL PARTICLE FOUND ON HIS CLOTHING.
LSURRYl
~ 05/23/87 BORIC ACID ACCUMULAT!DN AT SEAM OF REACTOR VESSEL 2 EQUIPMENT HEAD FAILURE FLANGE STUDS AND MIRROR INSULATION.
. TURKEY POINT 3 05/19/87 ORIFICES IN CONTAINMENT SPRAY WERE NEVER INSTALLED. 1 DESl6N/ CONSTRUCTION / INSTALLATION COULD RESULT IN INADEQUATE NPSH TO CONTAINMENT SPRAY EER0R PUMPS.
TURKEY POINT 4 05/19/87 DRIFICES IN CONIA]NMENT SPRAY WERE NEVER INSTALLED. ! DESIGN / CONSTRUCTION / INSTALLATION COULD RESULT IN INADEQUATE NPSH TO CONTAINMENT SPRAY ERROR PUMPS.
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