Regulatory Guide 3.58

Criticality Safety for Handling, Storing, and Transporting LWR Fuel at Fuels and Materials Facilities.

ML12220A067
Person / Time
Issue date:	10/31/1986
From:	Office of Nuclear Regulatory Research
To:
References
CE 407-4 RG-3.058
Download: ML12220A067 (4)

V* t~. ~ ~Lb Z U.S. NUCLEAR REGULATORY

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October 166 REGULATORY

GUIDE OFFICE OF NUCLEAR REGULATORY

RESEARCH REGULATORY

GUIDE 3.58 (Task CE 407-4)CRITICALITY

SAFETY FOR HANDLING, STORING, AND TRANSPORTING

LWR FUEL AT FUELS AND MATERIALS

FACILITIES

A. INTRODUCTION

Section 70.22, "Contents of Applications," of 10 CFR Part 70, "Domestic Licensing of Special Nuclear Material," requires that applications for a specific license to own, acquire, deliver, receive, possess, use, or initially transfer special nuclear material contain proposed proce-dures to avoid accidental conditions of criticality.

This regulatory guide provides guidance for complying with this portion of the Commission's regulations by describing procedures acceptable to the NRC staff for preventing criticality accidents in operations involving handling, storing, and transporting light water reactor (LWR) fuel at fuels and materials facilities, i.e., fuel cycle facilities other than nuclear reactors.Any information collection activities mentioned in this regulatory guide are contained as requirements in 10 CFR Part 70, which provides the regulatory basis for this guide.The information collection requirements in 10 CFR Part 70 have been cleared under OMB Clearance No.3150-0009.

B. DISCUSSION

ANSI/ANS-8.17-1984, "Criticality Safety Criteria for the Handling, Storage, and Transportation of LWR Fuel Outside Reactors," I was prepared by Subcommittee

8, Fissionable Materials Outside Reactors, of the Standards Committee of the American Nuclear Society. ANSI/ANS-8.17-1984 was approved by the American National Standards Committee N16, Nuclear Criticality Safety, in 1983 and by the American National Standards Institute (ANSI) on January 13, 1984.'Copies may be obtained from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60525.ANSI/ANS-8.

17-1984 provides guidance for preventing criticality accidents in operations involving handling, storing, and transporting LWR fuel rods and units in any phase of the fuel cycle outside reactor cores. This guidance includes general safety criteria and criteria to establish subcriticality.

C. REGULATORY

POSITION The general safety criteria and criteria to establish subcriticality contained in ANSI/ANS-8.17-1984 provide procedures acceptable to the NRC staff for preventing accidental conditions of criticality in handling, storing, and transporting LWR fuel at fuels and materials facilities.

The only exception is that credit for fuel burnup may be taken only when the amount of burnup is confirmed by reactivity measurements that are appropriate for each type of fuel assembly in the environment in which it is to be stored. Use of ANSI/ANS-8.17-1984, however, is not a substitute for detailed nuclear criticality safety analyses for specific operations.

Section 6 of ANSI/ANS-8.17-1984 lists additional documents referred to in the standard.

The specific appli-cability or acceptability of two of these listed documents has been addressed in the latest version of the regulatory guides identified below: Standard ANSI/ANS-8.1-19831 Regulatory Guide 3.4 -Nuclear Criticality Safety in Operations with Fissionable Materials at Fuels and Ma-terials Facilities ANSI/ANS-8.3-1979

1 8.12 -Criticality Accident Alarm Systems USNRC REGULATORY

GUIDES Regulatory Guides are issued to describe and make available to the public methods acceptable to the NRC staff of Implementing specific parts of the Commission's regulations, to delineate tech-niques used by the staff In evaluating specific problems or postu-lated accidents or to provide guidance to applicants.

Regulatory Guides are not substitutes for regulations, and compliance with them Is not required.

Methods and solutions different from those set out In the guides will be acceptable If they provide a basis for the findings requisite to the Issuance or continuance of a permit or icense by the Commission.

This guide was Issued after consideration of comments received from the public. Comments and suggestions for Improvements in these guides are encouraged at all times, and guides will be revised, as appropriate, to accommodate comments and to reflect new informa-tion or experience.

Written comments may be submitted to the Rules and Procedures Branch DRR ADM, U.S. Nuclear Regulatory Commission, Washington, D6 20555.The guides are Issued In the following ten broad divisions:

1. Power Reactors 6. Products 2. Research and Test Reactors

7. Transportation

3. Fuels and Materials Facilities

8. Occupational Health 4. Environmental and Siting 9. Antitrust and Financial Review 5. Materials and Plant Protection

10. General Copies of Issued guides may be purchased from the Government Printing Office at the current GPO price. information on current GPO prices may be obtained by contacting the Superintendent of Documents, U.S. Government Printing Office, Post Office Box 37082, Washington, DC 20013-7082, telephone

(202)275-2060

or (202)275-2171.

Issued guides may also be purchased from the National Technical Information Service on a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Rort Royal Road.Springfield, VA 22161.

D. IMPLEMENTATION

The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for using this regulatory guide.The methods described in this guide were applied to a number of specific cases during reviews and selected licensing actions. These methods reflect the latest general NRC approach to criticality safety in operations with LWR fuel at fuels and materials facilities.

Therefore, except in those cases in which the applicant proposes an acceptable alternative method for complying with speci-fied portions of the Commission's regulations, the meth-ods described herein will be used after the issuance of this guide in the evaluation of submittals in connection with license applications submitted under 10 CFR Part 70.3.58-2 VALUE/IMPACT

STATEMENT The NRC staff performed a value/impact assessment to determine the proper procedural approach for provid-ing guidance on criticality safety for handling, storing, and transporting LWR fuel at fuels and materials facili-ties. The NRC staff has been involved in the develop-ment, review, and approval of ANSI/ANS-8.17-1984,"Criticality Safety Criteria for the Handling, Storage, and Transportation of LWR Fuel Outside Reactors," which was approved by the American National Stan-dards Institute on January 13, 1984. The assessment resulted in a decision to develop a regulatory guide that would endorse, with possible supplemental provisions, ANSI/ANS-8.17-1984.

The results of this value/impact assessment were included in a draft regulatory guide on this subject, CE 407-4, entitled "Criticality Safety for Handling, Storing, and Transporting LWR Fuel Outside Reactors," that was issued for public comment in July 1985. The title of the guide was changed subsequently to clarify its applicability.

The value/impact statement published with the pro-posed guide is still applicable.

A copy of the draft regu-latory guide (identified by its task number, CE 407-4) and its associated value/impact statement is available for inspection and copying for a fee at the NRC Public Document Room at 1717 H Street NW., Washington, DC.3.58-3 UNITED STATES NUCLEAR REGULATORY

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