|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20137F2351997-03-24024 March 1997
Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants
ML20140H5981996-11-11011 November 1996
Summary of 435th Meeting of ACRS on 961009-12 Re Capability of NRC SCDAP/RELAP5 Code to Predict Temps & Flows in SGs Under severe-accident Conditions
ML20148B5761996-10-0404 October 1996
Summary of 434th Meeting of ACRS on 960912-13 Re Capability of SCAP/RELAP5 Code to Predict SG Temps During Severe Accidents
ML20058N7741993-12-0303 December 1993
Summary of Operating Reactors Events Meeting 93-45 on 931201
ML20057A5221993-07-28028 July 1993
Summary of Operating Reactors Events Meeting 93-27 on 930721
ML20056E2031993-06-15015 June 1993
Summary of Operating Reactors Events Meeting 93-20 on 930602
ML20128P8491993-02-18018 February 1993
Summary of Operating Reactors Events Briefing 93-05 on 930210
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20058B7431990-10-19019 October 1990
Summary of 901010 Meeting W/Util & Consultants in Rockville, MD Re Licensee Plan to Pursue Reload Technology.List of Attendees Also Encl
ML20127J2961990-04-0606 April 1990
Trip Rept of Commissioner Curtiss 900201 Site Visit.Facility Has Undergone Radical Change in Mgt Personnel & Experiencing Problems W/High Attrition of Licensed Operators
ML20247R0161989-09-21021 September 1989
Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting
ML20245G5421989-08-0303 August 1989
Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl
ML20245D3881989-04-21021 April 1989
Summary of 890413 Meeting W/Control Components,Inc in Rockville,Md Re Operation of Atmospheric Dump Valves.Agenda, Slides Used During Meeting for Valve Description & Worst Case Model Assumptions Encl
ML20248K3761989-04-10010 April 1989
Summary of Operating Reactors Events Meeting 89-014 on 890405.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams for Wk Ending 890402 Encl
ML20247F1991989-03-24024 March 1989
Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl
ML20247A8971989-03-16016 March 1989
Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl
ML20246N9201989-03-16016 March 1989
Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl
ML20207G3861988-08-12012 August 1988
Summary of 880803 Meeting W/Util in Rockville,Md Re Facility Auxiliary Transformer Fire & Reactor Trip Event Initiated by Combination of Cracked Insulating Matl & Dirt Accumulation.Briefing Slides Encl
ML20151K6901988-07-18018 July 1988
Summary of Operating Reactors Events Meeting 88-28 on 880712.Viewgraphs & List of Attendees Encl
ML20196B6471988-06-17017 June 1988
Summary of 880531 Meeting W/Licensee in Rockville,Md Re Auxiliary Feedwater Pump Degradation Events.Viewgraphs Encl
ML20154M8471988-05-17017 May 1988
Summary of 880414 Meeting W/Util & BNL in Rockville,Md Re Monitoring Program for Reactor Coolant Pump Shafts.List of Attendees & Related Documents Encl
ML20236W3951987-11-25025 November 1987
Summary of 870909 Meeting W/Util in Bethesda,Md Re Proposed Changes to Organizational Structure for Plant Submitted by & Selected Issues Listed on Meeting Agenda.List of Attendees,Agenda & Licensee Viewgraphs Encl
ML20237G3891987-08-27027 August 1987
Summary of Operating Reactors Events Meeting 87-25 on 870804 Re Events That Occurred Since 870728 Meeting.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl
ML20238A1841987-08-24024 August 1987
Summary of 870812 Meeting W/Util in Phoenix,Az Re Concerns Generated During Assessment of Operating Performance of Units 1 & 2 in Consideration of Pending Licensing Decision for Unit 3.Attendee List & Viewgraphs Encl
ML20237J6901987-08-19019 August 1987
Summary of 870730 Meeting W/Util & C-E in Phoenix,Az Re Util 870629 Submittal of Cycle 2 Reload Analysis & Proposed Tech Spec Changes.List of Attendees,Licensee Draft Responses & Addl Questions Raised by NRC Encl
ML20236J7051987-07-29029 July 1987
Summary of 870707 Operating Reactors Events Meeting 87-21 W/ Nrr,Aeod,Res & Regional Ofcs Re Events Occurring Since 870630 Meeting.List of Attendees,Discussion of Events & Summary of Reactor Scrams Also Encl
ML20214T3801987-06-0303 June 1987
Summary of 870508 Meeting W/Util in Bethesda,Md Re Proposed Tech Spec Changes Re Revised Shutdown Margin Requirements & Variable Overpower Trip Setpoints.List of Attendees Encl
ML20215H7961987-05-0101 May 1987
Summary of 870422 Meeting W/Util in Bethesda,Md Re Schedules for Cycle 2 Core Reloads.List of Attendees & Viewgraphs Encl
ML20204D7201987-03-19019 March 1987
Summary of 870226 Meeting W/Util in Bethesda,Md Re Resolution of NRC 860910 Comments on Plant Emergency Operating Procedures.List of Attendees & Draft Util Response to NRC Comments Encl
ML20212J0331987-03-0202 March 1987
Summary of 870224 Meeting W/Util in Bethesda,Md Re Rept Concerning Licensee Evaluations Performed on Steam Generators at Facilities.List of Meeting Attendees Encl
ML20029A2931987-01-30030 January 1987
Trip Rept of 870120 Briefing Re Emergency Diesel Generator 3B Failure on 861223
ML20210T4031987-01-28028 January 1987
Summary of Operating Reactors Events Meeting 87-02 on 870112 of Events Which Occurred Since 870105.List of Attendees,Events Discussed & Summary of Events Encl
ML20210T3641987-01-16016 January 1987
Summary of Operating Reactors Events Meeting 87-02 on 870112 Re Events Which Occurred Since 870105.List of Attendees,Events Discussed & Summary of Events Encl
ML20207P6271987-01-12012 January 1987
Summary of Operating Reactor Events Meeting 86-46 on 861229.List of Attendees,Events Discussed & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20207B8501986-12-18018 December 1986
Summary of 861209 Meeting W/Util & Eg&G Idaho in Bethesda,Md Re SPDS Testing Program Results,Tech Spec Change Requests & Unit 3 Licensing Submittals.List of Attendees & Viewgraphs Encl
ML20211L2981986-12-0808 December 1986
Summary of 860828 Meeting W/Util,Bechtel,Drexel Univ & Franklin Research Ctr in Bethesda,Md Re Licensee Evaluation of Adequacy of Certain Masonry Walls at Plant.List of Attendees & Viewgraphs Encl
ML20214H5811986-11-19019 November 1986
Summary of 861028 Mgt Meeting W/Util in Phoeniz,Az Re NRC Concerns Generated During Assessment of Operating Performance for Units 1 & 2 & to Identify Needed Improvements Prior to Licensing of Unit 3.Viewgraphs Encl
ML20213F0641986-11-10010 November 1986
Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl
ML20215E3001986-10-0606 October 1986
Summary of 860924 Meeting W/Util & C-E in Bethesda,Md Re Scope & Schedule for Reload Licensing Activities.Viewgraphs Encl
ML20215D1431986-10-0606 October 1986
Summary of 860820 Meeting W/Util in Bethesda,Md to Discuss Util 860619 Submittal Re Adequacy of Masonry Walls. List of Attendees,Agenda & Viewgraphs Encl
ML20205G9551986-08-13013 August 1986
Summary of Operating Reactors Events Meeting 86-28 on 860811 Re Briefing of Ofc Director,Div Directors & Representatives on Events Discussed at 860804 Meeting.List of Attendees & Viewgraphs Encl
ML20211Q6161986-07-23023 July 1986
Summary of Operating Reactor Events Meeting 86-25 on 860721 Re Events Since 860714 Meeting.List of Attendees,Discussion of Events & Status of Assignments Encl.Response Requested for Incomplete Assignments
ML20197F7721986-05-0808 May 1986
Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20154N8751986-03-12012 March 1986
Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20205J3851986-01-23023 January 1986
Summary of ACRS 309th Meeting on 860109-11 in Washington,Dc Re Final Design Approval for Gessar II Design & Proposed Rev 3 to Reg Guide 1.63, Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants
ML20205H8791986-01-22022 January 1986
Summary of Operating Reactor Events Meeting 86-02 on 860116 in Bethesda,Md Re Events Since 860106 Meeting.List of Attendees,List of Significant Elements of Events,Assignments & Status of Previous Assignments Encl
ML20141F0461985-12-30030 December 1985
Summary of Operating Reactors Events Meeting 85-28 on 851223.List of Attendees & Viewgraphs Encl
ML20205J0421985-11-21021 November 1985
Summary of ACRS 307th Meeting on 851107-09 in Washington, DC Re Review of Application of Beaver Valley Power Station 2,EPA Stds for High Level Radwaste Repository & Investigation of Significant Incidents at Power Plants
ML20136C5141985-11-11011 November 1985
Summary of Operating Reactors Event Meeting 85-21 on 851028.List of Attendees,Events Discussed & Completion Dates Assigned Encl
1997-03-24
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20137F2351997-03-24024 March 1997
Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants
ML20140H5981996-11-11011 November 1996
Summary of 435th Meeting of ACRS on 961009-12 Re Capability of NRC SCDAP/RELAP5 Code to Predict Temps & Flows in SGs Under severe-accident Conditions
ML20148B5761996-10-0404 October 1996
Summary of 434th Meeting of ACRS on 960912-13 Re Capability of SCAP/RELAP5 Code to Predict SG Temps During Severe Accidents
ML20058N7741993-12-0303 December 1993
Summary of Operating Reactors Events Meeting 93-45 on 931201
ML20057A5221993-07-28028 July 1993
Summary of Operating Reactors Events Meeting 93-27 on 930721
ML20056E2031993-06-15015 June 1993
Summary of Operating Reactors Events Meeting 93-20 on 930602
ML20128P8491993-02-18018 February 1993
Summary of Operating Reactors Events Briefing 93-05 on 930210
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20058B7431990-10-19019 October 1990
Summary of 901010 Meeting W/Util & Consultants in Rockville, MD Re Licensee Plan to Pursue Reload Technology.List of Attendees Also Encl
ML20247R0161989-09-21021 September 1989
Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting
ML20245G5421989-08-0303 August 1989
Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl
ML20245D3881989-04-21021 April 1989
Summary of 890413 Meeting W/Control Components,Inc in Rockville,Md Re Operation of Atmospheric Dump Valves.Agenda, Slides Used During Meeting for Valve Description & Worst Case Model Assumptions Encl
ML20248K3761989-04-10010 April 1989
Summary of Operating Reactors Events Meeting 89-014 on 890405.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams for Wk Ending 890402 Encl
ML20247F1991989-03-24024 March 1989
Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl
ML20246N9201989-03-16016 March 1989
Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl
ML20247A8971989-03-16016 March 1989
Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl
ML20207G3861988-08-12012 August 1988
Summary of 880803 Meeting W/Util in Rockville,Md Re Facility Auxiliary Transformer Fire & Reactor Trip Event Initiated by Combination of Cracked Insulating Matl & Dirt Accumulation.Briefing Slides Encl
ML20151K6901988-07-18018 July 1988
Summary of Operating Reactors Events Meeting 88-28 on 880712.Viewgraphs & List of Attendees Encl
ML20196B6471988-06-17017 June 1988
Summary of 880531 Meeting W/Licensee in Rockville,Md Re Auxiliary Feedwater Pump Degradation Events.Viewgraphs Encl
ML20154M8471988-05-17017 May 1988
Summary of 880414 Meeting W/Util & BNL in Rockville,Md Re Monitoring Program for Reactor Coolant Pump Shafts.List of Attendees & Related Documents Encl
ML20236W3951987-11-25025 November 1987
Summary of 870909 Meeting W/Util in Bethesda,Md Re Proposed Changes to Organizational Structure for Plant Submitted by & Selected Issues Listed on Meeting Agenda.List of Attendees,Agenda & Licensee Viewgraphs Encl
ML20237G3891987-08-27027 August 1987
Summary of Operating Reactors Events Meeting 87-25 on 870804 Re Events That Occurred Since 870728 Meeting.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl
ML20238A1841987-08-24024 August 1987
Summary of 870812 Meeting W/Util in Phoenix,Az Re Concerns Generated During Assessment of Operating Performance of Units 1 & 2 in Consideration of Pending Licensing Decision for Unit 3.Attendee List & Viewgraphs Encl
ML20237J6901987-08-19019 August 1987
Summary of 870730 Meeting W/Util & C-E in Phoenix,Az Re Util 870629 Submittal of Cycle 2 Reload Analysis & Proposed Tech Spec Changes.List of Attendees,Licensee Draft Responses & Addl Questions Raised by NRC Encl
ML20236J7051987-07-29029 July 1987
Summary of 870707 Operating Reactors Events Meeting 87-21 W/ Nrr,Aeod,Res & Regional Ofcs Re Events Occurring Since 870630 Meeting.List of Attendees,Discussion of Events & Summary of Reactor Scrams Also Encl
ML20214T3801987-06-0303 June 1987
Summary of 870508 Meeting W/Util in Bethesda,Md Re Proposed Tech Spec Changes Re Revised Shutdown Margin Requirements & Variable Overpower Trip Setpoints.List of Attendees Encl
ML20215H7961987-05-0101 May 1987
Summary of 870422 Meeting W/Util in Bethesda,Md Re Schedules for Cycle 2 Core Reloads.List of Attendees & Viewgraphs Encl
ML20204D7201987-03-19019 March 1987
Summary of 870226 Meeting W/Util in Bethesda,Md Re Resolution of NRC 860910 Comments on Plant Emergency Operating Procedures.List of Attendees & Draft Util Response to NRC Comments Encl
ML20212J0331987-03-0202 March 1987
Summary of 870224 Meeting W/Util in Bethesda,Md Re Rept Concerning Licensee Evaluations Performed on Steam Generators at Facilities.List of Meeting Attendees Encl
ML20210T4031987-01-28028 January 1987
Summary of Operating Reactors Events Meeting 87-02 on 870112 of Events Which Occurred Since 870105.List of Attendees,Events Discussed & Summary of Events Encl
ML20210T3641987-01-16016 January 1987
Summary of Operating Reactors Events Meeting 87-02 on 870112 Re Events Which Occurred Since 870105.List of Attendees,Events Discussed & Summary of Events Encl
ML20207P6271987-01-12012 January 1987
Summary of Operating Reactor Events Meeting 86-46 on 861229.List of Attendees,Events Discussed & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20207B8501986-12-18018 December 1986
Summary of 861209 Meeting W/Util & Eg&G Idaho in Bethesda,Md Re SPDS Testing Program Results,Tech Spec Change Requests & Unit 3 Licensing Submittals.List of Attendees & Viewgraphs Encl
ML20211L2981986-12-0808 December 1986
Summary of 860828 Meeting W/Util,Bechtel,Drexel Univ & Franklin Research Ctr in Bethesda,Md Re Licensee Evaluation of Adequacy of Certain Masonry Walls at Plant.List of Attendees & Viewgraphs Encl
ML20214H5811986-11-19019 November 1986
Summary of 861028 Mgt Meeting W/Util in Phoeniz,Az Re NRC Concerns Generated During Assessment of Operating Performance for Units 1 & 2 & to Identify Needed Improvements Prior to Licensing of Unit 3.Viewgraphs Encl
ML20213F0641986-11-10010 November 1986
Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl
ML20215D1431986-10-0606 October 1986
Summary of 860820 Meeting W/Util in Bethesda,Md to Discuss Util 860619 Submittal Re Adequacy of Masonry Walls. List of Attendees,Agenda & Viewgraphs Encl
ML20215E3001986-10-0606 October 1986
Summary of 860924 Meeting W/Util & C-E in Bethesda,Md Re Scope & Schedule for Reload Licensing Activities.Viewgraphs Encl
ML20205G9551986-08-13013 August 1986
Summary of Operating Reactors Events Meeting 86-28 on 860811 Re Briefing of Ofc Director,Div Directors & Representatives on Events Discussed at 860804 Meeting.List of Attendees & Viewgraphs Encl
ML20211Q6161986-07-23023 July 1986
Summary of Operating Reactor Events Meeting 86-25 on 860721 Re Events Since 860714 Meeting.List of Attendees,Discussion of Events & Status of Assignments Encl.Response Requested for Incomplete Assignments
ML20197F7721986-05-0808 May 1986
Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20154N8751986-03-12012 March 1986
Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20205J3851986-01-23023 January 1986
Summary of ACRS 309th Meeting on 860109-11 in Washington,Dc Re Final Design Approval for Gessar II Design & Proposed Rev 3 to Reg Guide 1.63, Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants
ML20205H8791986-01-22022 January 1986
Summary of Operating Reactor Events Meeting 86-02 on 860116 in Bethesda,Md Re Events Since 860106 Meeting.List of Attendees,List of Significant Elements of Events,Assignments & Status of Previous Assignments Encl
ML20141F0461985-12-30030 December 1985
Summary of Operating Reactors Events Meeting 85-28 on 851223.List of Attendees & Viewgraphs Encl
ML20205J0421985-11-21021 November 1985
Summary of ACRS 307th Meeting on 851107-09 in Washington, DC Re Review of Application of Beaver Valley Power Station 2,EPA Stds for High Level Radwaste Repository & Investigation of Significant Incidents at Power Plants
ML20136C5141985-11-11011 November 1985
Summary of Operating Reactors Event Meeting 85-21 on 851028.List of Attendees,Events Discussed & Completion Dates Assigned Encl
ML20141D3991985-11-0606 November 1985
Summary of ACRS Subcommittees on C-E Plants & Palo Verde 851105 Meeting in Washington,Dc to Review Operating Experience at Palo Verde Unit 1 in Consideration of Unit 2 License & Discuss Depressurization of C-E Plants
ML20198A4541985-10-30030 October 1985
Summary of Allegation Review Board 851029 Meeting Re Allegation RV-85-A-065.Initial Ltr Will Be Sent to Alleger Requesting Specific Safety Concerns.Allegation Will Be Considered Closed If No Response Received within 30 Days
1997-03-24
[Table view] |
Text
. .
O
%)
JUN 151333 m w
MEMORANDUM FOR: Brian K. Grimes, Director Division of Operating Reactor Support FROM: Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING JUNE 2, 1993 - BRIEFING 93-20 On June 2, 1993, we conducted an Operating Reactors Events Briefing (93-20) to inform senior managers from offices of the ACRS, EDO, NRR, AEOD, and regional offices of selected events that occurred since our last briefing on May 26, 1993.
Enclosure 1 lists the attendees. Enclosure 2 presents the significant elements of the discussed events.
Enclosure 3 contains reactor scram statistics for the week ending May 30, 1993. No significant events were identified for input into the NRC performance indicator program.
- original signed by Robert-L. Dennig for -
Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support
Enclosures:
As stated DISTRIBUTION:
Central Files cc w/ attachments: PDR See next page LKilgore, SECY EAB R/F KGray RDennig EGoodwin DSkeen EBenner EAB: DOR :NRR IRB:DO.:AEOD PPD:OIP EAB: DORS:NRR KGray JG Te KHenderson EGoodwin (10/t3/ 93 6 /.){793 h/ /93 f/]/93 EA :NRR A
" a-6 /j /93 p ' /x t-OFFICIAL RECORD COPY '
,/
/
^;.f //./'::
- p DOCUMENT NAME: ORTRANS.KAG (G:KAG) pjf g l <x A O 6 0 0 :,
h!RC RLE 05TEil COPY M / V' J
n I
9308200256 930615 PDR ORG NRRB
' hy PDR
=
O &
w cc:
T. Murley, NRR (12G18) C. Trammell (PDS)
F. Miraglia, NRR (12G18) T. Quay (PDS)
F. Gillespie, NRR (12G18) W. Huffman (AEOD)
J. Partlow, NRR (12G18) J. Giitter (AEOD)
S. Varga, NRR (14E4)
J. Calvo, NRR (14A4)
G. Lainas, NRR (14H3)
J. Roe, NRR (13E4)
J. Zwolinski, NRR (13H24)
E. Adensam, NRR (13E4)
W. Russell, NRR (12G18)
J. Richardson, NRR (7D26)
A. Thadani, NRR (8E2)
S. Rosenberg, NRR (10E4)
C. Rossi, NRR (9A2)
B. Boger, NRR (10H3)
F. Congel, NRR (10E2)
D. Crutchfield, NRR (11H21)
W. Travers, NRR (11B19)
D. Coe, ACRS (P-315)
E. Jordan, AEOD (MN-3701)
G. Holahan, AEOD (MN-9112)
L. Spessard, AEOD (MN-3701)
K. Brockman, AEOD (MN-3206)
S. Rubin, AEOD (MN-5219)
M. Harper, AEOD (MN-9112)
G. Grant, EDO (17G21)
R. Newlin, GPA (2GS)
E. Beckjord, RES (NLS-OO7)
A. Bates, SECY (16G15)
G. Rammling, OCM (16G15)
T. Martin, Region I W. Kane, Region I C. Hehl, Region I S. Ebneter, Region II E. Merschoff, Region II S. Vias, Region II J. Martin, Region III E. Greenman, Region III J. Milhoan, Region IV B. Beach, Region IV B. Faulkenberry, Region V K. Perkins, Region V bec: Mr. Sam Newton, Manager Events Analysis Department Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957 !
l l
1 i
O &
- W ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (93-20)
JUNE 2, 1993 NAME OFFICE NAME OFFICE F. MIRAGLIA NRR J. HOLMES NRR B. GRIMES NRR R. PIERSON NRR A. CHAFFEE NRR T. KIM NRR E. BENNER NRR D. SCALETTI NRR K. GRAY NRR G. ZECH NRR E. GOODWIN NRR -
R. GALLO NRR S. WITTENBERG NRR R. ECKENRODE NRR P. ENG NRR G. BAGCHI NRR W. LYON NRR H. CONRAD NRR G. THOMAS NRR W. HUFFMAN AEOD S. LONG NRR J. GIITTER AEOD T. COX NRR V. BENAROYA AEOD C. ROSSI NRR L. PLISCO OEDO W. SCOTT NRR D. COE ACRS E. THROM NRR D. KIRSCH RV TELEPHONE ATTENDANCE (AT ROLL CALL)
Regions Resident Inspectors Region I Palo Verde Region II Region III Region IV Region V IIT/AIT Team Leaders Misc.
~ ' ~ ^^
e,cto,v,, ,
OPERATING REACTORS EVENTS BRIEFING 93-20 LOCATION: 10 B11, WHITE FLINT WEDNESDAY, JUNE 2, 1993, 11:00 A.M.
~
PALO VERDE, UNIT 2 STEAM GENERATOR TUBE RUPTURE (AIT - UPDATE)
NAR0RA ATOMIC POWER STATION FIRE AND BLACK 0UT q
l PRESENTED BY: EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR SUPPORT, NRR
O O
93-20 PALO VERDE, UNIT 2 STEAM GENERATOR TUBE RUPTURE (AIT - UPDATE)
MARCH 14, 1993 PROBLEM STEAM GENERATOR TUBE RUPTURE (SGTR) OCCURRED.
CAUSE CAUSE OF TUBE DEGRADATION AND FAILURE IS CURRENTLY UNKNOWN.
SAFETY SIGNIFICANCE -
SGTRs CAN RESULT IN SIGNIFICANT OFFSITE RELEASES IF Ul1 MITIGATED.
.S_EQUENCE OF EVENTS (ALL TIMES ARE MOUNTAIN STANDARD TIME) 04:25 OPERATORS NOTE DECREASING PRESSURIZER LEVEL AND PRESSURE. THIRD CHARGING PUMP IS STARTED.
PRESSURE AND LEVEL CONTINUE TO DECREASE.
04:47 REACTOR TRIPPED MANUALLY. UNUSUAL EVENT DECLARED.
04:48 SAFETY INJECTION AND CONTAINMENT ISOLATION SIGNALS INITIATED AUTOMATICALLY AT 1837 PSIA.
05:02 ALERT DECLARED BASED ON TUBE LEAK GREATER THAN THE CAPABILITY OF ONE CHARGING PUMP (44 GPM) .
CONTACT: E. BENNER, NRR/ DORS AIT: YES
REFERENCES:
10 CFR 50.72 #25255, SIGEVENT: YES PN59309, AND PN59309A-C
O o PALO VERDE, 93-20 UNIT 2 05:35 PRESSURIZER LEVEL AND PRESSURE STABILIZED AT 8% AND 1900 PSIG, RESPECTIVELY, USING ALL THREE CHARGING PUMPS AND HIGH-PRESSURE SAFETY INJECTION. MINIMUM PRESSURE REACHED WAS 1687 PSIA.
06:05 LICENSEE INITIATED C00LD0WN AND DEPRESSURIZATION USING STEAM BYPASS AND PRESSURIZER SPRAY.
07:28 STEAM GENERATOR 2 ISOLATED.
^
08:00 REACTOR C0OLANT SYSTEM PRESSURE AND TEMPERATURE REDUCED TO 1160 PSIG AND 496*F, RESPECTIVELY.
FOLLOWUP '
AUGMENTED INSPECTION TEAM NOTED THE FOLLOWING WEAKNESSES:
s SGTR WAS A SIMULATOR TRAINING SCENARIO; HOWEVER, !
TRAINING INDICATED THAT RADIATION MONITORING (RM)
ALARMS WOULD OCCUR PROMPTLY UPON EVENT INITIATION.
- RM SYSTEM DOES NOT PROVIDE RELIABLE INDICATION OF SGTR:
SG BLOWDOWN: ISOLATED FOR MOST OF EVENT MAIN STEAM LINE MONITORS: CEASED ALARMING DUE TO H-16 DECAY.
AIR EJECTOR: HIGH SETP0 INT AND CALIBRATION ERRORS WASTE GAS AREA: UNDOCUMENTED SETPOINT CHANGE e WHEN CLASSIFYING EVENT, SOME OPERATORS DISCOUNTED INITIAL INDICATIONS OF A LEAK IN EXCESS OF CHARGING CAPACITY BECAUSE OF INABILITY TO DETERMINE LEAK SOURCE.
l i
l
O O PALO VERDE, 93-20 e INABILITY TO EXIT THE FUNCTIONAL REC 0VERY PROCEDURE l INTO THE SGTR OPTIMAL REC 0VERY PROCEDURE RESULTED IN SIGNIFICANTLY LONGER C00LDOWN AND DEPRESSURIZATION.
PROBABILISTIC SAFETY ASSESSMENT BRANCH PROVIDED CONDITIONAL CORE DAMAGE PROBABILITY OF GENERIC SGTR:
7.7x104 . l
- NRR ACTION PLAN
o CONFIRM EDDY-CURRENT TESTING SKILL 0F ARIZONA PUBLIC SERVICE (APS) AND CONTRACTOR.
e UNDERSTAND AND INFORMALLY ASSESS APS PLAN FOR DETERMINING THE ROOT CAUSE OF THE TUBE FAILURE. AGREE ON THE SPECIFIC TUBE PULLS AND THE REMAINDER OF THE EDDY-CURRENT TESTING TO BE DONE.
e EVALUATE THE ROOT CAUSE OF TUBE DEGRADATION AND FAILURE.
e EVALUATE AN APPROPRIATE OPERATING INTERVAL FOR THE NEXT CYCLE BASED ON THE ROOT CAUSE.
REGION V IS CONSIDERING ESCALATED ENFORCEMENT FOR THE INAPPROPRIATE EMERGENCY CLASSIFICATION.
AN INFORMATION NOTICE IS BEING DRAFTED ON THE INABILITY OF EMERGENCY OPERATING PROCEDURES (E0Ps) TO IDENTIFY A SGTR.
O O l l
l PALO VERDE, 93-20 UlfIT 2 l
COMBUSTION ENGINEERING HAS INDICATED THAT El4ERGENCY PROCEDURE GUIDELINES PROVIDE ADEQUATE DETECTION OF A SGTR.
PALO VERDE E0Ps DID NOT 14EET GUIDELINES IN THAT THERE WERE NO PROVISIONS FOR TRENDING AND THAT ALARii SETP0INTS WERE lion-C0llSERVATIVE.
l
O O 93-20 NARORA ATOMIC POWER STATION (NAPS)
FIRE AND BLACK 0UT .
MARCH 31, 1993 EVEllT i A SEVERE FIRE OCCURRED IN THE UNIT 1 TURBIME BUILDING RESULTING IN AN EXTENDED STATION BLACK 0UT (LOSS OF ALL 0FF SITE AND ONSITE ELECTRICAL POWER). ,
CAUSE ,
CURRENTLY, CAUSE OF THE FIRE AND THE RESULTANT STATION BLACK 0UT ARE UNKNOWN. -
SAFETY SIGi1IFICAllCE -
EXTENDED STATION BLACK 0UT HAS A HIGH POTENTIAL FOR:
- LOSS OF CORE COOLING OR HEAT SINK
- FUEL DAMAGE
- LOSS OF CONTAll1 MENT
- RELEASE OF FISSION PRODUCTS TO THE ENVIRONMENT BACKGROUND e INDIA'S NUCLEAR POWER PROGRAM HAS BEEN SOMEWHAT ISOLATED FROM THE SUPPORT OF WESTERN NATIONS.
CONSEQUENTLY, INDIA'S REACTOR DESIGNS, COMPONENT MANUFACTURING, AND CONSTRUCTION IS ALMOST TOTALLY INDIGEN0US.
- MOST OF INDIA'S COMMERCIAL NUCLEAR POWER PLANTS UTILIZE PRESSURIZED HEAVY WATER REACTORS.
CONTACT: W. HUFFMAN, AE0D/IRB ,
l
~
e o l HARORA 93-20 e THE INDIAN REACTOR DESIGNS HAVE EVOLVED CONSIDERABLY i
FROM THEIR EARLY CANDU ROOTS BUT STILL EMPLOY THE BASIC CANDU PROCESS FEATURES OF:
- NATURAL URANIUM FUEL
- HEAVY WATER COOLANT & MODERATOR
- ON LINE REFUELING e SOME OF THE SPECIFIC FEATURES OF THE NAR0RA PLANTS INCLUDE:
POWER OUTPUT OF 790 MWT/235 MWE PRIMARY PRESSURE / TEMPERATURE 1235 PSI & 520 F DOUBLE CONTAINMENT WITH SUPPRESSION POOL INDEPENDENT AND DIVERSE SHUTDOWN SYSTEMS HIGH, INTERMEDIATE AND LOW PRESSURE ECCS WITH LONG TERM RECIRC CAPABILITY '
DIESEL GENERATORS FOR EMERGENCY POWER e COMMON DESIGN FEATURES WHICH HAR0RA DOES NOT POSSESS INCLUDE:
STEAM TURBINE DRIVEN EMERGENCY INJECTION OR FEED PUMPS PRIMARY SYSTEM ACCUMULATOR INJECTION TANKS i
Q q NAR0RA 93-20 CHRON0 LOGY OF EVENTS e AT 3:31 AM (LOCAL TIME) ON MARCH 31, 1993, PLANT PERSONNEL REPORTEDLY HEARD A LOUD EXPLOSION IN THE TURBINE BUILDING.
UNIT 1 WAS OPERATING AT 85% POWER UNIT 2 WAS SHUTDOWN IN A MAINTENANCE OUTAGE.
- A FIRE WAS OBSERVED IN THE VICINITY OF THE UNIT 1 TURBINE GENERATOR. NO FIRE OR SM0KE DETECTORS ALARMS WERE RECEIVED PRIOR TO THE EXPLOSION.
- THE REACTOR AND TURBINE GENERATOR WERE IMMEDIATELY TRIPPED. (CONFLICTING INFORMATION ON WHETHER TRIP WAS AUT0liATIC OR MANUAL)
- WITHIN FIVE MINUTES OF EXPLOSION, A COMPLETE STATION BLACK 0UT OCCURRED.
i e A SITE EMERGENCY WAS DECLARED.
- FIRE FIGHTING TEAMS WERE DISPATCHED TO THE SCENE. !
l TWO FIRE ENGINES STATIONED AT THE SITE WERE l IMMEDIATELY AVAILABLE TO COMBAT THE BLAZE.
FIVE FIRE ENGINES FROM SURROUNDING COMMUNITIES WERE ALSO CALLED ONTO THE SITE FOR HELP.
O O
NAR0RA 93-20 e LONG TERM NATURAL CIRCULATION COOLING 0F THE CORE (REFERRED TO AS THERM 0 SYPHONING) ESTABLISHED USING STEAM GENERATORS AS A HEAT SINK AND MAKEUP FROM DIESEL ,
DRIVEN FIRE PUMPS.
o ADDITIONAL SHUTDOWN MARGIN WAS PROVIDED BY MANUAL GRAVITY ADDITION OF B0RON TO THE MODERATOR.
- FIRE WAS BROUGHT UNDER CONTROL AT 5:30 AM AND COMPLETELY EXTINGUISHED BY 8:30 AM.
- STATION BLACK 0UT PERSISTED FOR 10 TO 12 HOURS. POWER WAS SOMEH0W FULLY OR PARTIALLY RE-ESTABLISHED TO THE CLASS III BUSES.
e EMERGENCY WAS TERMINATED AT 10:45 PM ON MAR"H 31, 1993. !
- NO ONSITE OR OFFSITE RELEASE OF RADI0 ACTIVE MATERIAL :
WAS REPORTED.
1
. DISCUSSION e
INITIAL RESPONSE TO STATION BLACK 0UT WOULD BE T0:
- VERIFY CORE COOLING VIA THERM 0 SYPHONING
- C00LDOWN/DEPRESSURIZE PRIMARY AND SECONDARY
- ESTABLISH A LONG TERM HEAT SINK e
THERM 0 SYPHONING SHOULD OCCUR WITHOUT ANY SPECIAL OPERATOR ACTIONS ASSUMING A NORMAL POST TRIP STEAM GENERATOR WATER INVENTORY.
l
O O NAR0RA 93-20 1
o INITIAL SHUTDOWN INVENTORY IN THE STEAM GENERATORS WOULD HAVE BEEN SUFFICIENT FOR ~30 MINUTES OF DECAY HEAT REMOVAL.
. SINCE T'AERE ARE NO STEAM DRIVEN TURBINE PUMPS AT l NAR0RA, THE ONLY METHOD 0F SUPPLYING WATER TO THE STEAM GENERATORS WAS WITH THE DIESEL DRIVEN FIRE WATER PUMPS. ;
ACTION REQUIRED TO USE THE DIESEL FIRE PUMPS TO FEED SG's DEPENDS ON PLANT DESIGN. MAY HAVE BEEN HARD-PIPED. MAY HAVE REQUIRED INSERTION OF A SP0OL ;
PIECE; FLANGE REMOVAL; HOSE CONNECTIONS; ETC. l
- OPERATORS WOULD HAVE INITIATED A " CRASH C00LD0WN" TO DEPRESSURIZE THE STEAM GENERATORS BELOW THE DISCHARGE l I
HEAD OF THE FIRE PUMPS. THIS WOULD BE ACCOMPLISHED BY OPENING THE STEAM GENERATOR ATMOSPHERIC RELIEF VALVES.
o LONG TERM CONSIDERATIONS RESULTING FROM THE EXTENDED NATURE OF THIS BLACK 0UT.
BATTERIES WERE PROBABLY LOST WITHIN FIRST TWO HOURS OF EVENT. WITHOUT BATTERIES:
o PROCESS MONITORING WOULD HAVE BEEN LOST o BREAKER MANIPULATION COULD ONLY HAVE BEEN PERFORMED MANUALLY IDENTIFICATION OF LONG TERM FUEL AND WATER SUPPLY FOR THE DIESEL FIRE PUMPS WOULD BE REQUIRED.
. q g NAR0RA 93-20 OTHER CONSIDERATIONS HAD REFUELING BEEN IN PROGRESS AT THE TIME OF THE EVENT, COOLING 0F REFUELING MACHINE SPENT FUEL COULD HAVE BEEN A MAJOR PROBLEM HOW WAS THE FIRE MAIN HEADER PRESSURE MAINTAINED WHEN THE DIESEL FIRE PUMPS WERE SUPPLYING WATER TO THE SG's?
HOW DID THIS AFFECT THE FIRE FIGHTING CAPABILITY?
LOSS OF EMERGENCY LIGHTING WOULD HAVE MADE BUILDING
~
MANEUVERING DIFFICULT.
HOW WERE COMMUNICATIONS MAINTAINED?
SUMMARY
o EVENT WAS A CLOSE CALL. MAY HAVE RESULTED IN FUEL DAMAGE IF DIESEL FIRE PUMPS HAD NOT BEEN AVAILABLE TO PROVIDE MAKEUP FEED TO THE STEAM GENERATORS.
e THE EXPLOSION AND FIRE DAMAGE TO THE TURBINE GENERATOR INCLUDED: DAMAGE TO TURBINE BLADES; BEARING DAMAGE; AND EXTENSIVE DAMAGE -11) ELECTRICAL CABLES.
REPAIR ESTIMATES RANGE FROM $1.5 TO $47 MILLION REPAIR TIME FROM 4 MONTHS TO ONE YEAR
y ,
' NAR0RA 93-20 o LESSONS TO BE LEARNED WILL HAVE TO AWAIT THE RELEASE OF SPECIFIC DETAILS ON THE EVENT.
- A FOLLOWUP PRESENTATION WILL BE PROVIDED WHEN THE EVENT DETAILS BECOME KNOWN.
w BRIEFING 93-20 ,
NARORA ATOMIC P0h'ER STATION L
STEAM PIPES STEAM
-GENERATORS 2 1 l
f %dY "
g% *q y.
l
[l i
k
[ HEAT PUMPS TRANSPORT j
{ l '{ i ,
4 I I I I . ; '
d \ / \ / I :
l l C D FC 3 l _ l
\ !
BLEED CONDENSER [
y K
^
A HEAT TR ANSPORTV V VV HEAT TRANSPORT p' .
HEADERS HEADERS
( ) FEED v r, a :
CALANDRIA c, u n=. .;a.5.~gij ;
q-
~ ww.2rjw% .-
) m.
.)) J
( (( c=- .
c- - (f) .
KEY .;
ij ! '
l 1 NATUR AL WATER STEAM # W#
MO ATOR N E tsATURAL WATER CONDENSATE I i HE AVY WATER COOLANT I v E HEAVY WATER MODERATOR yy;.
MODERATOR HEAT EXCHANGER FIGURE 1.2-3 _ _ , ,
CANDU Reactor Simplified Flow Diagram
~
' ' O A w w ENCLOSURE 3 RE ACfDR SCRM teporting Period: 05/24/93 to 05/30/93 YTD Y1D ABOVE BELOW YTD E risNT & Uw!T PMG M Ca J5E r>Ptitaitows , jjj $ TCTat CS/24/93 FILL 5tDhE 2 100 SA Maintenance Error WO 2 1 3 05/25/93 EROWs FEEDY 2 1 SN Operating Error No 0 1 1 C5/25/73 FITU ATRICt 1 6 5A Equipment Failure NO 2 1 3 k
4 I
i 1
acte: Year to cate (yid) Tetats include Events within the talendar tear Indicated By the Erd cate of the specified Eeporting period ET$ 10 Fage:1 06/C2/73 I
i . .
COMPAR!$0h DF VEEKLY SCR AM STATISTICS VITH INDUSTRY AVERAGES PERICD ENDING 05/30/93 WUMSER 1993 1992 1991* 1990* 1989*
OF WEKLf WEEKLY WEEKLY WEEKLT WEELLY Sgpaw taUSE SCE8% AVE R AGE AVERAGE AVE R AGE AVE RA GE . AVE R AGE (YTD)
F06'EP GREATER ThAh OR EQUAL TO 15%
E0V!PMENT FAltuPE' O 2.1 2.6 2.9 3.4 3.1 LESICA/!hSTAttAT1DA IKRDR* 0 0.1 - - - -
0 FEE ATlkG EE ADR* O 0.4 0.2 0.6 0.5 1.0 MAthTEhAACE ERROR
ENTERNAL* 0 0.1 - - - - l cieER* 0 0.0 0.2 - -
0.1 Subtotal 1 3.2 3.4 3.5 3.9 4.2
E0JIPPEkT F AILURE* 1 0.4 0.4 0.3 0.4 0.3 CESIGA/1hSTALLAT10h ERROR
l Or[aAT!hG EERDR* 1 0.2 0.1 0.2 0.1 0.3 !
PA! ATEAANCE ER ADR* O 0.0 0.1 - - -
)
EXTERhAL* O C.0 - - - -
CTHER* 0 0.0 0.1 - - -
Suttotat 2 0.6 0.7 0.5 0.5 0.6 TOTAL 3 3.8 4.1 4.0 4.4 4.8 1993 1992 1991 1990 19P9 ko. OF WEEKLT WEEKLT WEEKLY WEEKLY WEEKLY ttsaw Tvrf SCRAMS AVE R AGE AVERAGE AVE R AGE AVERAGE AVE R AGE iTTD)
TCTA AUTOMATIC SCRAF5 2 2.5 3.1 3.3 3.2 3.9 TOTAL PAWUAL SCRAMS 1 1.3 1.0 0.7 1.2 0.9 TCTAi$ MAY DIFFER SECAUSE OF F0aN01kG OFF
- Detailed breakdo.<n not in database f or 1991 and earlier
- Eh1EE AAL casse included in 1031PMENT FAltuRE
- WAl%TE AAACE EEROR and DES 104/lkST Att AT10N ERROR causes included in OPER AT1hG ERROR
- OTHER cause ircluded in EQUlrME AT I A! LURE 1991 and 1990 l
E75-14 Fase: 1 06/02/93
. . A a w w 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 MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN OPEPATING LICENSE.
- 2. PERSONELL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
- 3. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF 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 Manual and Automatic Scrans for 1988 ------------------ 291 Manual and Automatic Scrans for 1989 ------------------ 252 Manual and Automatic Scrams for 1990 ------------------ 226 Manual and Autematic Scrats for 1991 ------------------ 206 Manual and Automatic Scrams for 1992 ------------------ 212 Manual and Automatic Scrams for 1993 --(YTD 05/30/93)-- 81 l
l l
1 i
r-
% en w w cc:
T. Murley, NRR (12G18) C. Trammell (PD5)
F. Miraglia, NRR (12G18) T. Quay (PDS)
F. Gillespie, NRR (12G18) W. Huffman (AEOD)
J. Partlow, NRR (12G18) J. Giitter (AEOD)
S. Varga, NRR (14E4)
J. Calvo, NRR (14A4)
G. Lainas, NRR (14H3)
J. Roe, NRR (13E4)
J. Zwolinski, NRR (13H24)
E. Adensam, NRR (13E4)
W. Russell, NRR (12G18)
J. Richardson, NRR (7D26)
A. Thadani, NRR (8E2)
S. Rosenberg, NRR (10E4)
C. Rossi, NRR (9A2)
B. Boger, NRR (10H3) ,
F. Congel, NRR (10E2)
D. Crutchfield, NRR (11H21)
W. Travers, NRR (11B19)
D. Coe, ACRS (P-315)
E. Jordan, AEOD (MN-3701)
G. Holahan, AEOD (MN-9112)
L. Spessard, AEOD (MN-3701)
K. Brockman, AEOD (MN-3206)
S. Rubin, AEOD (MN-5219)
M. Harper, AEOD (MN-9112)
G. Grant, EDO (17G21)
R. Newlin, GPA (2G5)
E. Beckjord, RES (NLS-007)
A. Bates, SECY (16G15)
G. Rammling, OCM (16G15)
T. Martin, Region I W. Kane, Region I C. Hehl, Region I S. Ebneter, Region II E. Merschoff, Region II S. Vias, Region II J. Martin, Region III E. Greenman, Region III J. Milhoan, Region IV B. Beach, Region IV B. Faulkenberry, Region V K. Perkins, Region V bec: Mr. Sam Newton, Manager Events Analysis Department Institute of Nuclear Power Operations 700 Galleria Parkway ;
Atlanta, GA 30339-5957 1
l l
,
