ML20195G616

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

ML20195G616
Person / Time
Site:	Saint Lucie, 05000000
Issue date:	10/28/1987
From:	Hodges M Office of Nuclear Reactor Regulation
To:	Berkow H Office of Nuclear Reactor Regulation
Shared Package
ML20151V292	List: IA-88-497, Forwards Safety Evaluation Accepting Proposed Reracking of Spent Fuel Storage Pools from Criticality Standpoint.Fuel Enrichment May Be in Conflict W/Table 54 of 10CFR51 & Data Used by Util to Assess Environ Effects.Salp Input Also Encl ML20151V290 ML20154F927 ML20195G296 ML20195G389 ML20195G536 ML20195G546 ML20195G550 ML20195G553 ML20195G616 ML20196B968
References
FOIA-88-497 TAC-65587, NUDOCS 8711020106
Download: ML20195G616 (2)

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> 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.

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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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