ML20148K705

Responds to 780920 Request by Licensee for Info Re Safety Data for Renewal Appl for Lic SNM-1266 for GE Morris Oper. Present Csar,Updated to Incl All Detailed Info Specified in Proposed Reg Guide Under Each Section,Will Suffice

ML20148K705
Person / Time
Site:	07001308
Issue date:	10/18/1978
From:	Starostecki R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Dawson D GENERAL ELECTRIC CO.
References
NUDOCS 7811170271
Download: ML20148K705 (2)

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4 UNITED STATES y9 NUCLEAR REGULATORY COMMISSION g j WASHINGTON, D. C. 20555

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% * * * * * **' OCT 18 B70 Docket No. 70-1308 License SNM-1266 General Electric Company ~

Nuclear Energy Programs Division ATTN: D. M. Dawson, Manager Licensing and Transportation Mail Code 851 175 Curtner Avenue San Jose, CA 95125

. Gentlemen:

SUBJECT:

RENEWAL APPLICATION, GENERAL ELECTRIC MORRIS OPERATION A meeting was held on September 20, 1978 at Silver Spring, Maryland, between representatives of the General Electric Company and the.

, Nuclear Regulatory Commission. In this meeting, it was agreed that NRC would furnish GE with information regarding the required content of the renewal application. This letter is written to furnish information as to the scope and content of the safety portion of the application which GE expects to submit in early March 1979.

It is emphasized that the application for renewal should be complete when first submitted. In addition, it should be submitted in a timely manner so that the NRC review can progress' with all of the needed information available. A complete application is of particular importance for this renewal because of the tight schedule (March to August) involved in completing the review so that a renewal decision may be made before the expiration date of the license, August 31,1979.

Assuming a favoraDie decision, renewal before the expiration date will not be possible if the renewal must go to_ hearing.

Scope and criteri;a for ISFSI applications are spelled out in the f proposed regulatJon,10 CFR Part 72, which was published for comment J in the Federal Register on October 6,1978 (FR 43 46309). As stated at the 3eptember 20, 1978 meeting, criteria for t,he licensing review will follow to the maximum extent possible the spirit and intent of the requirements of proposed 10 CFR Part 72.

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General Electric Company Comparison of the present Consolidated Safety Analysis Report with the proposed RG 3.24.1 indicates that the CSAR is very similar to the prcposed organization for an ISFSI in the regulatory guide. Section titles are the same or very similar and appear in approximately the same sequence. Exceptions are Chapter 2 of the CSAR, Summary Safety Analysis, which is not called for in the regulatory guide and Chapter 5 of the CSAR, Facility Design and Description, which compares with Chapter 4, Installation Design and Chapter 5, Operations Systems, as outlined in the regulatory guide.

In summary, the present organization of the CSAR, if updated to include all detailed information specified in the proposed regulatory guide under each section, should be satisfactory.

Sincerely, w' ,

Richard W. Starostecki, Chief Fuel Reprocessing and Recycle Branch Division of Fuel Cycle and Material Safety i