ML19249D640

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Forwards List of green-dotted Document Boxes Reviewed by NRC to Date Showing Number of Pages Retained by Nrc.Each Box Will Contain Statement of Number of Pages Retained
ML19249D640
Person / Time
Issue date: 08/23/1979
From: Goldberg J
NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To: Meiss R
PACIFIC GAS & ELECTRIC CO.
References
PROJECT-564M NUDOCS 7909250142
Download: ML19249D640 (3)


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August 23, 1979 f

Richard L. Meiss, Esq.

Pacific Gas & Electric Company 77 Beale Street San Francisco, California 94106 Re:

Pacific Gas and Electric Company, Stanislaus Nuclear Project, Unit No. 1, NRC Docket No. P-564A

Dear Rich:

Attached is a list of the green-dotted document boxes reviewed by the NRC Staff to date showing the number of pages retained by the Staff. As I told you, in the future, each box returned to PG&E will contain a state-ment of the number of pages retained by the Staff.

Very truly yours, j}C ck R. Goldberg

  • - Counsel for NRC Staff Enclosure i

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MEMORANDUM FOR:

R. Reid, Chief, Operating Reactors Branch #4, Division of Operating Reactors FROH:

G. Lainas, Chief, Plant Systems Branch, Division of Operating Reactors

SUBJECT:

SAFETY EVALUATION OF SPENT FUEL STORAGE RACK Plant Name: Crystal River, Unit 3

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Docket No.: 50-302 TAC No.:

7468 Project Manager:

C. Nelson Status:

Complete Enclosed is the Plant Systems Branch input to the Safety Evaluation Report for the Florida Power Corporations (FPC) proposed modification to the spent fuel storage racks for Crystal River Unit 93.

We have reviewed the issues of criticality, cooling, rack installation, and fuel handling as they are discussed in the licensee's submittal supporting its proposed amendment to the facility's operating license. We find FPC's application for the license amendment acceptable with respect to the above listed issues, provided that the uranium-235 loading in fuel assemblies that are to be placed in the pool is limited to the amount established as acceptable in this report and the neutron attenuation test, which is described in this report, is satisfactorily perfomed at the Crystal River site.

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/ G. Lainas, Chief Plant Systems Branch Division of Operating Reactors

Contact:

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Enclosure:

As stated cc s/ enclosure:

D. Eisenhut

8. Grimes G. Lainas MIPC T. Telford
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