|
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20196J4111999-06-30030 June 1999
Summary of 990524 Meeting with Util in Rockville,Md to Discuss Technical Issues Re Proposed Rerack of Spent Fuel Pool at Plants.List of Attendees & Handouts Encl
ML20217H8081998-03-31031 March 1998
Summary of 980306 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Byron Station,Units 1 & 2 & Braidwood Station,Units 1 & 2.List of Attendees Encl
ML20199A5071998-01-16016 January 1998
Summary of 971211 Meeting W/Comed in Rockville,Maryland Re Additional Justification for Proposed Methodology for Estimating voltage-dependent Growth Rates of Outer Diameter Stress Corrosion Crack Indications Left in Service
ML20211P3421997-09-23023 September 1997
Summary of 970904 Meeting W/Commonwealth Edison Co in Rockville,Md Re Methodology for Calculating Radiation Doses in Control Room & at Eab & LPZ in Event of Msb Outside Containment.List of Attendees & Licensee Presentation Encl
ML20210Q1281997-08-25025 August 1997
Summary of 970723 Meeting W/Util in Rockville,Md Re Util Assessment of Spring 1997 Eddy Current Insp of Plant SG Tubes.List of Attendees & Handouts Presented Encl
ML20141F3641997-06-27027 June 1997
Summary of 970430 Meeting W/Licensee in Rockville,Md to Discuss Various Aspects of SG Eddy Current Insp Conducted at Plants During Spring 1997 Refueling Outage.List of Attendees & Licensee Handouts Encl
ML20138L0741997-02-18018 February 1997
Summary of 970123 Meeting W/Commonwealth Edison Co to Discuss Plant Amend Request to Convert Current TSs
ML20134M3841997-02-13013 February 1997
Summary of 970128 Meeting W/Util to Discuss Program to Dispose of Weapons Grade Pu Through Use as Mixed Oxide Fuel. List of Attendees & Matl Used in Presentation Encl
ML20134G7011997-02-0707 February 1997
Summary of 970122 Meeting W/Util Re Program for Replacement of SG at Licensee Facilities.List of Attendees & Matl Used in Presentation Encl
ML20133J0641997-01-13013 January 1997
Summary of 960821 Meeting W/Comed to Discuss Status of SG Replacement Program W/Nrc Staff.List of Attendees & Util Presentation Encl
ML20149M3131996-12-10010 December 1996
Summary of 961114 Meeting W/Representives of CE in Rockville,Md to Discuss Status of Ongoing Braidwood,Unit 1, SG Tube Insp.List of Attendees & Slides Encl
ML20129F9431996-10-25025 October 1996
Summary of 961004 Meeting W/Representatives of CE in Rockville,Md to Discuss Technical Basis for Licensee Pending Proposal to Delete Braidwood Unit 1 mid-cycle SG Eddy Current Insp.List of Attendees & Matls Discussed Encl
ML20129G8501996-07-0505 July 1996
Summary of ACRS Joint Subcommittee Matl & Metallurgy & Severe Accidents Meeting on 960603-04 to Gather Info on Status of Activities Associated W/Development of Proposed Rule Re SG Integrity
ML20217D4661995-12-0404 December 1995
Summary of 950911 Meeting W/Commonwealth Edison Re Util Commitment to Improving Dresden,Matl Condition at Zion, Declining Performance at Braidwood & Comed Resources
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
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
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
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
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
1999-06-30
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20196J4111999-06-30030 June 1999
Summary of 990524 Meeting with Util in Rockville,Md to Discuss Technical Issues Re Proposed Rerack of Spent Fuel Pool at Plants.List of Attendees & Handouts Encl
ML20217H8081998-03-31031 March 1998
Summary of 980306 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Byron Station,Units 1 & 2 & Braidwood Station,Units 1 & 2.List of Attendees Encl
ML20199A5071998-01-16016 January 1998
Summary of 971211 Meeting W/Comed in Rockville,Maryland Re Additional Justification for Proposed Methodology for Estimating voltage-dependent Growth Rates of Outer Diameter Stress Corrosion Crack Indications Left in Service
ML20211P3421997-09-23023 September 1997
Summary of 970904 Meeting W/Commonwealth Edison Co in Rockville,Md Re Methodology for Calculating Radiation Doses in Control Room & at Eab & LPZ in Event of Msb Outside Containment.List of Attendees & Licensee Presentation Encl
ML20210Q1281997-08-25025 August 1997
Summary of 970723 Meeting W/Util in Rockville,Md Re Util Assessment of Spring 1997 Eddy Current Insp of Plant SG Tubes.List of Attendees & Handouts Presented Encl
ML20141F3641997-06-27027 June 1997
Summary of 970430 Meeting W/Licensee in Rockville,Md to Discuss Various Aspects of SG Eddy Current Insp Conducted at Plants During Spring 1997 Refueling Outage.List of Attendees & Licensee Handouts Encl
ML20138L0741997-02-18018 February 1997
Summary of 970123 Meeting W/Commonwealth Edison Co to Discuss Plant Amend Request to Convert Current TSs
ML20134M3841997-02-13013 February 1997
Summary of 970128 Meeting W/Util to Discuss Program to Dispose of Weapons Grade Pu Through Use as Mixed Oxide Fuel. List of Attendees & Matl Used in Presentation Encl
ML20134G7011997-02-0707 February 1997
Summary of 970122 Meeting W/Util Re Program for Replacement of SG at Licensee Facilities.List of Attendees & Matl Used in Presentation Encl
ML20133J0641997-01-13013 January 1997
Summary of 960821 Meeting W/Comed to Discuss Status of SG Replacement Program W/Nrc Staff.List of Attendees & Util Presentation Encl
ML20149M3131996-12-10010 December 1996
Summary of 961114 Meeting W/Representives of CE in Rockville,Md to Discuss Status of Ongoing Braidwood,Unit 1, SG Tube Insp.List of Attendees & Slides Encl
ML20129F9431996-10-25025 October 1996
Summary of 961004 Meeting W/Representatives of CE in Rockville,Md to Discuss Technical Basis for Licensee Pending Proposal to Delete Braidwood Unit 1 mid-cycle SG Eddy Current Insp.List of Attendees & Matls Discussed Encl
ML20129G8501996-07-0505 July 1996
Summary of ACRS Joint Subcommittee Matl & Metallurgy & Severe Accidents Meeting on 960603-04 to Gather Info on Status of Activities Associated W/Development of Proposed Rule Re SG Integrity
ML20217D4661995-12-0404 December 1995
Summary of 950911 Meeting W/Commonwealth Edison Re Util Commitment to Improving Dresden,Matl Condition at Zion, Declining Performance at Braidwood & Comed Resources
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
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
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
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
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
1999-06-30
[Table view] |
Text
-
o November 3, 1986 Docket Nos. STN 50-454 DISTRIBUTION STN 50-455 _ Docket m e: L. Olshan STN 50-456 NRC~PDR' "" OGC -
m and STN 50-457 PD#3 Rdg. E. Jordan <
Y J. Partlow B. Grimes se LICENSEE: Comonwealth Edison Company S. Varga ACRS(10) t E. Rossi J. Knight ,
t, FACILITIES: Byron Station, Units 1 and 2 A. Gill R. Karsch, .: 'l Braidwood Ststion, Units 1 and 2 F. Rosa R. Lobel J. Stevens
SUBJECT:
MEETING
SUMMARY
- DESIGN OF DIESEL GENERATORS TO ,
INSURE THAT TESTING DOES NOT IMPAIR CAPABILITY 0F PROVIDING EMERGEhCY POWER >( "
, r.
On October 21, 1986, a meeting was held in Bethesda, Maryland, to discuss the Q J' capability of the Byron /Braidwood diesel generators to provide emergency power ,
if they are being tested. Members of the NRC, Comonwealth Edison (the licensee) and Sargent & Lundy (the architect-engineer) were present. Meeting attendees are listed in Enclosure 1. The material-handed out by the licensee and used during the meeting is included. in Enclosure 2.
The licensee described the actions that take place if a loss-of-coolant accident '*
(LOCA) and loss of offsite power (LOOP) occur while a diesel generator is being -
testing. All the actions needed to enable the diesel generator to provide ,i '
emergency power occur automatically, with one exception: The operator must take. '
manual action to place the diesel generator breaker control switch from the "after close" to the "after trip" position. ThelicenseesaidthatthisprevenO;.
.the diesel generator from being closed onto a faulted bus. The licensee stated ~
that the operators have been trained to take this action and that there is a high likelihood that the correct action will be taken in the required time.
The NRC state 1 that the Byron /Braidwood design is not acceptable because reliance on manual action does not . satisfy the NRC position. The NRC position, as stated in FSAR Question 40.181, is that all of these actions must be automatic. 1 s
8611070060 861103 PDR P ADOCK 05000454 ppg
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th'e 4 sign licensee 'on the agreed to submit four Byron a letter within
/Braidwood units so 10that daysallthat will commit actions neededto toaltering.
allow a dieseli;geneiator to supply emergency power when it is being tested will occur automatically. . The proposed design will also prevent the diesel generator from y
. e,. ..s closing onto as faulted bus. The NRC concurred with this approach.
v %
' - - , '; Leonard Olshan, Project Manager
, -3
, ,,, / -
Division o.f PWR Licensing-A
. 1, :- ' Enclosuite$:
he p z' w As stated cc: See ne.it page
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, t i s
Mr. Dennis L. Farrar liyron Station Comonwealth Edison Company '
Units 1 and 2 CC' '
Mr. William Kortier Ms. Diane Chavez Atomic Power Distribution 528 Gregory Street Westinghouse Electric Corporation Rockford, Illinois 61108 Post Office Box 355 Pittsburgh, Pennsylvania 15230 Regional Administrator, Region III i
U. S. Nuclear Regulatory Comission Michael Miller l 799 Roosevelt Road Isham, Lincoln & Beale < Glen Ellyn, Illinois 60137 One First National Plaza l 42nd Floor Joseph Gallo, Esq.x l Chicago, Illinois 60603 Isham, Lincoln & Beale l Suite 1100 Mrs. Phillip B. Johnson 1150 Connecticut Avenue, N.W.
1907 Stratford Lane Washington,:D. C. 20036 Rockford, Illinois 61107 ,
Douglass Cassel, Esq..
Dr. Bruce von Zellen 109 N. Dearborn Street Department of Biological Sciences Suite 1300 Northern Illinois University Chicago, Illinois' 60602 DeKalb, Illinois 61107 Ms. Pat Morrison Mr. Edward R. Crass 5568 Thunderidge Drive Nuclear Safeguards & Licensing Rockford, Illinois 61107 Sargent & Lundy Engineers 55 East Monroe Street Ms. Lcrecine Creek Chicago, Illinois 60603 Rt. 1, Box 182 '
Manteno. Illincis 60950 Mr. Julian Hinds U. S. Nuclear Regulatory Commission Byron / Resident Inspectors Offices '
4448 German Church Road Byron, Illinois 61010 Mr. Michael C. Parker, Chief Division of Engineering 3 Illinois Department of Nuclear Safety 1035 Outer Park Drive Springfield, Illinois 62704 s
1
- t ENCLOSURE 1 DESIGN OF BYRON /BRAIDWOOD DIESEL GENERATORS OCTOBER 21, 1986 NRC COMMONWEALTH EDISON A.- Gill K. Ainger; -
R. Karsch* J. Dennehy J. Knight D. Farrar R. Lobel* T. Weis-L. Olshan F. Rosa SARGENT & LUNDY E. Rossi J..Stevens D. Galanis-B. G. Treece ;
- Part-Time Attendance f .l. '
i
- sARGENTO LUNDY cuo,ncen. Prepared by: D. P. Golanis emcaco Date: October 17, 1986
> BYRON /BRAIDWOOD - UNITS 1 & 2 Design of Diesel Generator Breaker Control Scheme Relative to Periodic Testing of the Diesel Generator Unit
- 1. Design Basis Requirements a) Regulatory Guide 1.108, Position C.l.b. (3)
" Periodic testing of diesel generator units should not impair the capability of the unit to supply emergency power within the required time. Where necessary, diesel generator unit design should include an emergency override of the test mode to permit response to bona fide signals."
b) IEEE STD 387-1977, Section 5.6.2._2_
"Upon receipt of a start-diesel signal the automatic control system shall provide automatic startup and automatic adjustment of speed and voltage to a ready-to-load condition."
(1) A start-diesel signal shall override all other operating modes and return control of the diesel-generator unit to the automatic control system.
c) FSAR Ouestion 040.181 d) FSAR Section 8.3.1.1.1 (Pages 8.3-2 through 8.3-7)
- 2. Design Description (Reference Schematic Diagram 20E-1-4030DG01)
During periodic testing, the Diesel Generator is synchronized with the preferred offsite power source and the Diesel Generator breaker is manually closed onto the 4.16kV bus via the control switch at the main control board. The breaker control switch ~
is then released in the "after close" position. A " Diesel Generator Trouble" alarm activates and a message (DG breaker auto-closure circuit not available) is printed by the Sequential Events Recorder alerting the operator that the Diesel Generator breaker is. incapable of responding to an automatic emergency closure signal. While operating in this mode, a simultaneous or sequential occurrence of a) a design basis accident (LOCA),
and (b) loss of offsite power, will result in the following:
The Diesel Generator governor is automatically shifted from the droop (test) to the isochronous (emergency) mode.
Page 1 of 2
October 17, 1986
.o 2 ~. Design Description (Reference Schematic Diagram 20E-1-4030DG01)
(Cont'd)
The voltage regulator is shifted to the automatic mode.
The Diesel Generator breaker is automatically tripped.
Undervoltage relays automatically trip all loads on the bus (except the 4160/480V transformer) and open the offsite source feed breaker.
An alarm is activated in the main control room alerting the operator that the Diesel Generator breaker has auto-matically tripped.
Emergency procedures require the operator to acknowledge the above alarm by placing the Diesel Generator breaker control switch from the "after close" to the "after trip" position.
The above operator action arms the Diesel Generator breaker auto-closing circuit and the breaker automatically re-closes
.onto the 4.16kV bus.
Sequential loading of the diesel generator is automatically performed with services required for the safe shutdown of the reactor.
In the existing (above) design, operator action is required to ensure the Diesel Generator breaker recloses onto the 4.16kV bus.
Automatic re-closure of the Diesel Generator breaker is prevented by the presence of the "STP" control switch contact in the breaker auto-closure control scheme. The purpose of the "STP" control switch contact is to prevent the breaker from automatically reclosing onto the bus (after it has automatically tripped) without the operator first investigating the cause of the trip (possibly a bus fault). Furthermore, the "STP" control switch contact safe-guards against cycling of the circuit breaker under certain operating conditions, (e.g., an overload / fault while the Diesel Generator is connected onto the 4.16kV bus after a loss of offsite power condition).
Page 2 of 2
2 j B/B-FSAR AMENDMENT 37 .
MARCH 1982 QUESTION 040.181 l
"IEEE-387-77 Section 5.6. 2. 2 (1) and Regulatory Gu.ide 1.108 position C.l.b.3 recommend that the periodic testing of diesel generator units should not impair the capability ,
of the unit to supply emergency power within the required time. :
guidelines The following discussion provides the necesary (requirements) to meet the objective of the- !
above referred Industry Standard and Regulatory Guide.
"The diesel generator unit design should include an emergency override of the test mode to permit response to bona fide emergency signals and return control of the diesel-generator unit to the automatic control system.i A-design which does not have such a feature would neces-sitate operator action of varying levels of complexity depending on the specific design and plant conditions, in order to enable a diesel-generator in the test mode to respond to a bona fide emergency signal. The concern
, here is the possible consequent disabling of a D/G due to operator's inaction or wrong action thereby reducing the available safety margin with regard to onsite a-c i power at a time when it is most needed. l I
"Each die a frequen,sel generator must be periodically tested at .
cy as specified in R.G. 1.108. I is normally once per month but could be as high as onceThis test frequency every three days.
hour. The duration of each test is one
- . During a normal successful test the diesel generator is loaded on its bus with the governor operating in
! a droop mode, and the load carried by the diesel engine
, is a function of governor speed and speed droop setting. ;
In order to enable a diesel generator in the test mode
.to respond to 'a bona fide emergency signal, the design must incorporate the following features for the stated plant conditions:
1
- 1. Accident Conditions t..
During the periodic testing of a diesel generator, if a safety injection signal is generated, the diesel generator breaker should be tripped automatically.
'This will permit the unit to be cleared from parallel y operation with the system and enable the diesel generator to attain the emergency standby mode.
In this mode of operation, the diesel governor control should change automatically to the isochronous mode
\mil which will maintain the ' engine running at a synchronous speed corr,esponding to 60 Hz at the generator terminals.
All noncritical protective trips except engine overspeed 4
and generator differential should be bypassed for Q40.181-1 l
d -
B/B-FSAR AMENDMENT 37 MARCH 1982 this accident' condition. Additionally, the voltage regulator should change to the automatic mode thereby maintaining the generator at a preset constant voltage.
With the above actions complete, the diesel generator /
unit will be ready to accept the required load in the event of a loss of offsite power. {
J
- 2. Loss of Offsite Power (LOOP) Conditions Normally, during periodic testing of diesel generator, the diesel generator is paralleled with the offsite power system. During such a test, should a LOOP occur, a LOOP signal would probably not be generated because the D/G would attempt to provide power to the bus and to the offsite system through the closed offsite power feedbreaker. In-this case, the D/G breaker will trip on overcurrent or underfrequency and in some designs the D/G breaker also locks out for this condition. To assure the continued avail-ability of the D/G unit it is essential that the diesel generator breaker should not be locked out for such overload conditions. At the same time, the governor is shifted automatically from droop to isochronous mode and the voltage regulator to automatic mode. With the above actions complete, the diesel generator unit will be ready to accept e its required load for LOOP conditions.
- 3. Accident Conditions / LOOP For simultaneous accident / LOOP condition or sequential i accident and LOOP condition, the requirements stated in items 1 and/or 2 uould be adequate to assure the restoration of the diesel generator from the !
test mode to the emergency mode.
Provide a discussion how you meet the above stated guidelines." .
RESPONSE
We agree with the guidelines set forth in this question-to meet the requirements of IEEE-387 Section 5.6.2.2(1) and Regualtory Guide 1.108 Position C.l.b.3. The Byron /
Braidwood diesel-generator system design includes emergency override of the test mode for both accident conditions (Safety N-}-
Injection) and loss of offsite power (LOOP) to permit response to bona fide emergency signals and return control of the diesel-generator to the automatic control system. Upon Q40.181-2
s i -
B/B-FSAR AMENDMENT 37 MARCH 1982 receipt of either a safety injection signal or a loss of offsite power signal, the governor is auto-matically shifted from droop to the isochronous mode and the voltage regulator is shifted to the automatic mode. Therefore, the diesel-generator breaker controls will be revised to trip the breaker upon receipt of a safety injection signal concurrent with the diesel generator operating in the test mode. Also, the Byron /Braidwood diesel-generator breaker control scheme does not lock out the diesel-generator breaker on overcurrent or underfrequency which assures the availability of the diesel generator to accept its required load for LOOP conditions.
.O 040.181-3 l