Similar Documents at Zion |
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
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Summary of 990713 Conference Call with Util Re Licensee Proposed Exemption Request ,as Supplemented by Ltr Re Emergency Preparedness
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Summary of 980203 Meeting W/Util Re Plans to Decommmission Plant,Units 1 & 2.List of Attendees & Licensee Visual Aids Encl
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Summary of 980113 Meeting W/Util Re Plans & Preparations to Implement Zion Improved Ts.List of Attendees & Meeting Handouts Encl
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ML20217D4531992-03-0606 March 1992
Summary of 920305 Meeting W/Commonwealth Edison Co Re Items of Mutual Interest Re Performance of Utilities Nuclear Power Plants.General Topics Included,Performance of Zion & Dresden Stations
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20217D4381990-11-16016 November 1990
Summary of 901114 Meeting W/Commonwealth Edison Co Re Utility Response to Zion Station Diagnostic Evaluation Team Rept,Dtd Aug 1990.Specifically,utility Highlighted Activities & Corrective Actions,Resulting from Findings
ML20245H8011989-02-23023 February 1989
Summary of Operating Reactors Events Meeting 89-08 on 890222.Attendee List & Events Discussed & Significant Elements of Events Encl
ML20153C1861988-08-23023 August 1988
Summary of Operating Reactors Events Meeting 88-34 on 880823
ML20151N0521988-07-26026 July 1988
Summary of Operating Reactors Events Meeting 88-30 on 880726.List of Attendees & Summary of Reactor Scrams Encl
ML20150C0371988-03-0808 March 1988
Summary of 880105 Meeting W/Util Re Features of Isap Ii.List of Attendees Encl
ML20214P6121987-05-27027 May 1987
Summary of Operating Reactors Events Meeting 87-14 on 870512 W/Nrr,Res,Aeod & Regional Ofcs Re Events Which Occurred Since 870507 Meeting.List of Attendees & Viewgraphs Encl
ML20214F6731987-05-18018 May 1987
Summary of 870514 Meeting W/Util Re Review of Status of Pending Licensing Actions on Util Plants.Meeting Agenda & List of Attendees Encl
ML20207A5221987-05-15015 May 1987
Summary of Operating Reactors Event Meeting 87-13 on 870507 Re Events Which Occurred Since 870428.List of Attendees, Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20214E5711986-11-18018 November 1986
Summary of 861103 Operating Reactors Events Meeting 86-38 Re Briefing of Ofc & Div Directors on Events Occurring Since 861027 Meeting.List of Attendees,Viewgraphs & Addl Documentation Encl
ML20215D9171986-10-0606 October 1986
Summary of 860929 Operating Reactors Events Meeting 86-34 Re Events Since Last Meeting on 860922.Assignees Should Review Identified Responsibilities & Completion Dates & Advise If Dates Cannot Be Met.Viewgraphs Encl
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
ML20141F4091986-04-10010 April 1986
Summary of Operating Reactors Events Meeting 86-10 W/Ofc Director,Div Directors & Representatives Re Events Since 860324.Viewgraphs & Supporting Documentation Encl
ML20210J0261986-03-24024 March 1986
Summary of Operating Reactor Events Meeting 86-08 on 860317 to Discuss Events Occurring Since Last Meeting on 860310
ML20141N6831986-03-0707 March 1986
Summary of Operating Reactors Events Meeting 86-05 on 860224.Lists of Attendees,Events & Significant Elements Discussed & Assignment of Followup Review Responsibility Encl
ML20153E3391986-02-12012 February 1986
Summary of 860130 Meeting W/Util in Bethesda,Md Re Program to Develop in-house PWR Transient & Safety Analysis.Official Submittal Needed for Commitments to Schedule.First of Three Topical Repts Expected in June 1986
ML20151N3021985-12-19019 December 1985
Summary of 851216 Operating Reactor Events Meeting 85-27. Attendance List,Viewgraphs of Events Discussed,Significant Event Elements,Assignment of Followup Review Responsibility & Status of Previous Assignments Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20148N4601978-11-13013 November 1978
Summary of 781025 Meeting W/Subcomm on Plant Arrangements of Advisory Comm on Reactor Safeguards Re Sandia Labs Presentation of Sys Interaction Methodology Appl in Nuc Pwr Plants & Subj Facil Sys Interaction Study
ML20196H3981978-07-0505 July 1978
Summary of 780622 Meeting W/Westinghouse Owners Group to Discuss Results of Phase a of three-phase Plan & Current Schedule for Resolution of Asymmetric LOCA Loads Isssue.List of Attendees Encl
ML20245C3211977-07-11011 July 1977
Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls
ML20196H3251976-06-29029 June 1976
Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl
1999-08-10
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210Q7891999-08-10010 August 1999
Summary of 990713 Conference Call with Util Re Licensee Proposed Exemption Request ,as Supplemented by Ltr Re Emergency Preparedness
ML20217N9551998-03-23023 March 1998
Summary of 980317 Meeting W/Ceco at Opus Ofc of Ceco Re Update on Current Station Decommissioning Status & Plans. Generic Timeline,Collection of Decommissioning Plans & Description of Backlog Evaluation Process Encl
ML20203H5141998-02-23023 February 1998
Summary of 980203 Meeting W/Util Re Plans to Decommmission Plant,Units 1 & 2.List of Attendees & Licensee Visual Aids Encl
ML20203G0581998-02-23023 February 1998
Summary of 980113 Meeting W/Util Re Plans & Preparations to Implement Zion Improved Ts.List of Attendees & Meeting Handouts Encl
ML20147E8501997-03-17017 March 1997
Summary of Operating Reactors Events Meeting 97-02 on 970312.List of Attendees,Significant Elements of Discussed Events & Reactor Scram Statistics for Weeks Ending Feb 16, 23,Mar 2 & 9 Encl
ML20137D5231997-01-23023 January 1997
Summary of 970103 Meeting W/Util in Lisle,Il Re Findings from Util Contracted ISA & Effects of Recently Identified Technical Issue Involving Degraded Containment Paint Coatings on Readiness for Restart of Unit 2
ML20138H6081997-01-0202 January 1997
Summary of 961115 Meeting W/Util Re Results of Steam Generator Tube Insp & Repairs of Plant
ML20128L1911996-10-0909 October 1996
Summary of 960828 Meeting W/Ceco to Discuss Plant Improved Std Ts.List of Attendees & Licensee Handout Encl
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
ML20059L2351993-11-0808 November 1993
Summary of 930930 Meeting W/Util at Zion Nuclear Power Station Re Electronic Fire Watch Sentry Program Being Considered for Use at Zion Nuclear Power Station.List of Attendees Encl
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
ML20059C9301993-08-13013 August 1993
Summary of ACRS Subcommittee on Computers in Nuclear Power Plant Operations 930721 Meeting W/Numarc,Comm Ed,Impr & NRC Re Guidelines for analog-to-digital Retrofits
ML20126G8631992-12-24024 December 1992
Summary of 921208 Meeting W/Util in Rockville,Md to Discuss Plant TS Amends Dealing W/High Radiation Areas,Protection of Divers in Spent Fuel Pool & Source & Intermediate Range Nuclear Instrumentation.Attendees Listed in Encl 1
ML20217D4531992-03-0606 March 1992
Summary of 920305 Meeting W/Commonwealth Edison Co Re Items of Mutual Interest Re Performance of Utilities Nuclear Power Plants.General Topics Included,Performance of Zion & Dresden Stations
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20217D4381990-11-16016 November 1990
Summary of 901114 Meeting W/Commonwealth Edison Co Re Utility Response to Zion Station Diagnostic Evaluation Team Rept,Dtd Aug 1990.Specifically,utility Highlighted Activities & Corrective Actions,Resulting from Findings
ML20245H8011989-02-23023 February 1989
Summary of Operating Reactors Events Meeting 89-08 on 890222.Attendee List & Events Discussed & Significant Elements of Events Encl
ML20153C1861988-08-23023 August 1988
Summary of Operating Reactors Events Meeting 88-34 on 880823
ML20151N0521988-07-26026 July 1988
Summary of Operating Reactors Events Meeting 88-30 on 880726.List of Attendees & Summary of Reactor Scrams Encl
ML20150C0371988-03-0808 March 1988
Summary of 880105 Meeting W/Util Re Features of Isap Ii.List of Attendees Encl
ML20214P6121987-05-27027 May 1987
Summary of Operating Reactors Events Meeting 87-14 on 870512 W/Nrr,Res,Aeod & Regional Ofcs Re Events Which Occurred Since 870507 Meeting.List of Attendees & Viewgraphs Encl
ML20214F6731987-05-18018 May 1987
Summary of 870514 Meeting W/Util Re Review of Status of Pending Licensing Actions on Util Plants.Meeting Agenda & List of Attendees Encl
ML20207A5221987-05-15015 May 1987
Summary of Operating Reactors Event Meeting 87-13 on 870507 Re Events Which Occurred Since 870428.List of Attendees, Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20214E5711986-11-18018 November 1986
Summary of 861103 Operating Reactors Events Meeting 86-38 Re Briefing of Ofc & Div Directors on Events Occurring Since 861027 Meeting.List of Attendees,Viewgraphs & Addl Documentation Encl
ML20215D9171986-10-0606 October 1986
Summary of 860929 Operating Reactors Events Meeting 86-34 Re Events Since Last Meeting on 860922.Assignees Should Review Identified Responsibilities & Completion Dates & Advise If Dates Cannot Be Met.Viewgraphs Encl
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
ML20141F4091986-04-10010 April 1986
Summary of Operating Reactors Events Meeting 86-10 W/Ofc Director,Div Directors & Representatives Re Events Since 860324.Viewgraphs & Supporting Documentation Encl
ML20210J0261986-03-24024 March 1986
Summary of Operating Reactor Events Meeting 86-08 on 860317 to Discuss Events Occurring Since Last Meeting on 860310
ML20141N6831986-03-0707 March 1986
Summary of Operating Reactors Events Meeting 86-05 on 860224.Lists of Attendees,Events & Significant Elements Discussed & Assignment of Followup Review Responsibility Encl
ML20153E3391986-02-12012 February 1986
Summary of 860130 Meeting W/Util in Bethesda,Md Re Program to Develop in-house PWR Transient & Safety Analysis.Official Submittal Needed for Commitments to Schedule.First of Three Topical Repts Expected in June 1986
ML20151N3021985-12-19019 December 1985
Summary of 851216 Operating Reactor Events Meeting 85-27. Attendance List,Viewgraphs of Events Discussed,Significant Event Elements,Assignment of Followup Review Responsibility & Status of Previous Assignments Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20148N4601978-11-13013 November 1978
Summary of 781025 Meeting W/Subcomm on Plant Arrangements of Advisory Comm on Reactor Safeguards Re Sandia Labs Presentation of Sys Interaction Methodology Appl in Nuc Pwr Plants & Subj Facil Sys Interaction Study
ML20196H3981978-07-0505 July 1978
Summary of 780622 Meeting W/Westinghouse Owners Group to Discuss Results of Phase a of three-phase Plan & Current Schedule for Resolution of Asymmetric LOCA Loads Isssue.List of Attendees Encl
ML20245C3211977-07-11011 July 1977
Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls
ML20196H3251976-06-29029 June 1976
Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl
1999-08-10
[Table view] |
Text
-
. . *y
y fun %% UNITED STATES j
NUCLEAR REGULATORY COMMISSION
, ! WASHINGTON, D.C. 30666s1001 August 10, 1999
%.....+o MEMORANDUM TO: Michael T. Masnik, Chief Decommissioning Section Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Dino Scaletti, Senior Project Manag ,
Decommissionirg Section eq Project Directorate IV and Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL WITH COMMONWEALTH EDISON COMPANY REGARDING THE ZION NUCLEAR POWER STATION SPENT FUEL POOL The staff held a conference call with Commonwealth Edison on Tuesday, July 13,1999, to discuss the licensee's proposed exemption request dated April 13,1999, as supplemented by letter dated July 8,1999, regarding emergency preparedness. Those participating in the conference call were Diane Jackson, A. Gill, and George Hubbard from the NRC and K. Ainger and others from Commonwealth Edison Company.
The following questions and answers were discussed:
- 1. For the loss of spent fuel pool (SFP) inventory and cooling, describe the alternative methods / personnel actions that are proceduralized, if any, (and what criterion triggers them to occur) to instruct personnel to implement altemate methods of pool cooling to demonstrate that the time available is adequate to restore cooling.
Licensee's Resoonse The licensee indicated that the level is monitored by instrumentation and by personnel. The abnormal operating procedure for loss of pool cooling level is entered on a low level alarm.
The proposed defueled station emergency plan submitted July 8,1999, stated that if the level reaches 613-foot elevation, a station " Unusual Event" would be initiated. Although the licensee is planing to modify the SFP makeup systems, at least two sources of water will be available for SPF makeup. For the Zion pools, the 613-foot elevation maintains water 23 feet above the spent fuel. Approximately 289 hours0.00334 days <br />0.0803 hours <br />4.778439e-4 weeks <br />1.099645e-4 months <br /> would be needed to reduce the level from 24 feet (Iow level alarm at 614'-4") to 4 feet above the fuel due to boil off (approximately 77 hours8.912037e-4 days <br />0.0214 hours <br />1.273148e-4 weeks <br />2.92985e-5 months <br /> would be needed to reduce the level from 8 feet to 4 feet above the fuel due to boil off). The licensee stated that radiation alarms also could alert personnel to low water level. The licensee stated that the time available and the increased level of station attention would be adequate for personnel to restore cooling prior to reaching a water level that would limit personnel access. 1 qfC\ D 9908160120 990810
{DR ADOCK 0500 5 h
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Michael T. Masnik August 10, 1999 l
- 2. A cask drop accident was not considered in the submittal. Explain why a cask drop would not be an accident that needs to be considered for offsite consequences for your plant. 1 Licensee's Response A cask drop analysis is included in the defueled safety analysis report. The analysis concluded that due to the pool design and cask movement procedures that a dropped cask cannot I damage the fuel stored in the spent fuel storage pool. The licensee stated that because the cask drop analysis was part of its licensing basis and no fuel damage could occur, that they did not consider the cask drop again in the submittal.
- 3. For the fuel handling accident, the assembly was dropped onto the pool floor, as opposed to the top of the spent fuel storage racks. Typically, a licensee evaluates the bounding scenario or both scenarios. Explain why this adequately bounds a spent fuel i handling accident for your pool. If it does not bound a release from a drop on top of the I storage racks, please provide this evaluation. l I
Licensee's Resoonse i The licensee stated that the analysis for the spent fuel assembly drop and the resultant ;
complete release of radioactive gases assumed that no water was in the spent fuel pool for iodine scrubbing. Because no scrubbing or shielding benefits were credited, the licensee stated that there would be negligible difference in dose between an assernbly drop on the floor and on top of the racks for this scenario.
The staff concluded that the information provided by the above responses in addition to the information provided in the submittals provides sufficient information for a staff safety determination and no further information is necessary.
Docket Nos. 50-295 and 50-304
b....
) .- .-
D:Ck b Michael T. Masnik August 10, 1999 We
- 2. A cask drop accident was not considered in the submittal. Explain why a cask drop would not be an accident that needs to be considered for offsite consequences for your plant.
Licensee's Response A cask drop analysis is included in the defueled safety analysis report. The analysis concluded that due to the pool design and cask movement procedures that a dropped cask cannot damage the fuel stored in the spent fuel storage pool.' The licensee stated that because the cask drop analysis was part of its licensing basis and no fuel damage could occur, that they did not consider the cask drop again in the submittal.
- 3. For the fuel handling accident, the assembly was dropped onto the pool floor, as opposed to the top of the spent fuel storage racks. Typically, a licensee evaluates the bounding scenario or both scenarios. Explain why this adequately bounds a spent fuel handling accident for your pool. If it does not bound a release from a drop on top of the storage racks, please provide this evaluation.
Licensee's Response The licensee stated that the analysis for the spent fuel assembly drop and the resultant complete release of radioactive gases assumed that no water was in the spent fuel pool for iodine scrubbing. Because no scrubbing or shielding benefits were credited, the licensee stated that there would be negligible difference in dose between an assembly drop on the floor and on top of the racks for this scenario.
The staff concluded that the information provided by the above responses in addition to the
~
information provided in the submittals provides sufficient information for a staff safety determination and no further information is necessary.
Docket Nos. 50-295 and 50-304 DISTRIBUTION:
Docket File PUBLIC PDIV-D r/f DScalleti EPeyton DJackson AGill GHubbard To receive a copy of tnis cocument, indicate "c" in the box OFFICE PDIV-2(Py , PDIV-2/LA PDIV-2/SC NAME DScalqttk EPeytoY MMasnik M DATE R^ / IS /99 8/D /99 $ / N /99 DOCUMENT NAME: G:\PDIV-3\ Zion \e-plan telecon.wpd OFFICIAL RECORD COPY i
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