Letter Sequence Approval |
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MONTHYEARML17219A7041987-07-16016 July 1987
Requests Addl Info Necessary to Complete Review of 870612 Submittal Re Spent Fuel Storage Capacity.Response Requested within 45 Days to Ensure That Review Schedule Maintained
Project stage: Approval
ML17221A3621987-08-20020 August 1987
Forwards Request for Addl Info Re 870612 Submittal Re Spent Fuel Pool Capacity Expansion.Response Expected within 45 Days of Ltr Receipt
Project stage: RAI
ML17221A3511987-08-20020 August 1987
Notification of 870902 Meeting W/Util in Bethesda,Md,To Discuss Util Response to Questions Re Rerack of Facility Spent Fuel Pool
Project stage: Meeting
ML17221A3571987-08-25025 August 1987
Forwards Notice of Consideration of Issuance of Amend to License DPR-67 & Proposed NSHC Determination & Opportunity for Hearing Re 870612 Request to Modify Spent Fuel Pool to Expand Storage Capacity from 728 to 1,706 Fuel Assemblies
Project stage: Other
ML17221A3691987-09-0101 September 1987
Forwards Request for Addl Info Re Util 870612 Submittal on Expanding Spent Fuel Pool Storage Capacity at Facility. Response Requested within 45 Days of Ltr Receipt.Nrc Prepared to Meet W/Util to Expedite Review
Project stage: RAI
ML17221A4151987-09-11011 September 1987
Summary of NRC 870902 Meeting W/Util in Bethesda,Md Re Reracking of Spent Fuel Pool.Lists of Attendees,Questions & Draft Answers to NRC 870716 Questions Encl
ML17221A4201987-09-21021 September 1987
Forwards Request for Addl Info Needed to Continue Review of 870612 Submittal Re Expanding Spent Fuel Pool Storage Capacity.Response Requested by 871016
Project stage: RAI
ML17221A4221987-09-25025 September 1987
Notification of 871002 Meeting W/Util in Bethesda,Md to Discuss Licensee Responses to NRC Questions Re Rerack of Unit Spent Fuel Pool
Project stage: Meeting
ML17221A4811987-10-21021 October 1987
Summary of 871002 Meeting W/Util in Bethesda,Md Re Licensee Proposal to Rerack Spent Fuel Pool.List of Meeting Attendees & Questions Discussed at Meeting Encl
Project stage: Meeting
ML17221A4821987-10-23023 October 1987
Requests Addl Info Re Util 870612 Request to Expand Spent Fuel Pool Storage Capacity.Response Requested within 30 Days of Ltr Receipt
Project stage: Other
ML20195G6161987-10-28028 October 1987
Forwards Safety Evaluation Re Util Proposed Spent Fuel Pool Reracking.Proposal Acceptable from Critical Standpoint.Util May Be Required to Perform Addl Analysis to Verify Required Subcriticality Margin Can Be Maintained.Salp Input Encl
Project stage: Approval
ML17221A5111987-11-16016 November 1987
Notification of 871124 Meeting W/Util in Bethesda,Md to Discuss Licensee Response to NRC Questions Re Rerack of Facility Spent Fuel Pool
Project stage: Meeting
ML17221A5261987-11-25025 November 1987
Forwards Request for Addl Info Re 870612 Submittal Concerning Spent Fuel Pool Storage Capacity at Plant. Response Requested by 871216 in Order for NRC to Maintain Review Schedule
Project stage: RAI
ML17221A5431987-12-0404 December 1987
Summary of 871029-30 Audit of Util Consultants,J Oats & Holtec,Re Review of Rack Fabrication Process & Details of Structual Analysis Calculations
Project stage: Approval
ML17221A5481987-12-0909 December 1987
Summary of 871124 Meeting W/Util & Holtec in Bethesda,Md Re Reracking of Spent Fuel Pool.Meeting Agenda & List of Attendees Encl
Project stage: Meeting
1987-12-09
[Table View] |
Text
.
O o,
OCT 2 8 401 MEMORD. CUM FOR:
Hertert N. Etrkcw Project Director Project Directorate !! 2 Divisten of Reactor Projects - I/l!
FSCM:
M. W. Hodges. Chief Reactor Systees Branch Divisten of Dgineering a systees Technology SL'BJE CT :
SER FOR ST. LUCit UNIT 1 SPENT FUEL FOCL PERACK Plant Naee:
St. Lucie Unit 1 Occhet No.:
50 335 TAC No.:
65587 Project Directorate:
Freject Directorate !!-2 Freject Panager:
- f. Tourigny Review Eranch:
SEX 8/0EST Peview Status:
reeplete Tre Ge3ctor Systems Branch has reviewed the proposed rerackirg of the St.
Lucie Unit I spent fuel storage pool and finds it acceptable f-cra a criticality standpoint. However, recent aroralies have ter entified in the Quad Cities spent fuel pool due to Ecraflex shrinkage caun! k, irradiation and subsequent gap formatien. This, of course, recutes the neutron absorptien effectiver.ess of the Boraflex and causes a decrease in the eargin of subcriticality of the fuel pool.
If as a result of ongoing Eoraflex studies, the staf f finds that gaps could develcp in the Boraflex installed at the St.
Lucie Unit fuel storage f acility, the licensee ray be required to perfom acdttienal analyses to verify that the required subtriticality r.argin can te raintained.
It should be rentiened that although the staff has approved it o criticality aspects of storage of fuel enriched to as ruch as 4.5 weight percent U 235, this enrichtent ray te in conflict with Table 54 of 10 CFR 51 and the data used by the licensee in assessing the envircreental effects of transprtation of uranium fuel and waste. Therefore, this aspect of the enricheent increase should te investigated further by the apprcpriate HEC staff.
Centact:
L. repp SRXB. 24204 O7_110:0109 871opa j/(fp
A /d '
Herbert N. Berkow This corpletes the staf f's effort on TAC No. 65587. A SALP input is also
- enclosed, csW egno W bl%rk Mine M. W. Hodges. Chief Reacter Systems Branch Division of Engineering & Systems Te:hnology
Enclosures:
As stated cc w/ enclosures:
A. Thadant S. Varg3 G. Lainas E. Tcurigny
$ RIB Fe-ters 015TG19UTICN Docket Filt4 SDIP. P/F M. W. Fodges T. Collins L. Kopp L. Kopp R/F St. Lucie P/F i
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