Regulatory Guide 3.57
| ML12220A066 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1986 |
| From: | Office of Nuclear Regulatory Research |
| To: | |
| References | |
| CE-501-4 RG-3.057 | |
| Download: ML12220A066 (4) | |
AU.S. NUCLEAR REGULATORY COMMISSIONOctober 1986) REGULATORY GUIDEOFFICE OF NUCLEAR REGULATORY RESEARCHREGULATORY GUIDE 3.57(Task CE 501-4)ADMINISTRATIVE PRACTICES FOR NUCLEAR CRITICALITY SAFETYAT FUELS AND MATERIALS FACILITIES
A. INTRODUCTION
Section 70.22, "Contents of Applications," of 10 CFRPart 70, "Domestic Licensing of Special Nuclear Mate-rial," requires that applications for a specific licenseto own, acquire, deliver, receive, possess, use, or initiallytransfer special nuclear material contain proposed proce-dures to avoid accidental conditions of criticality.Section 70.24, "Criticality Accident Requirements," of10 CFR Part 70 requires licensees who are authorizedto possess special nuclear material in excess of certainamounts to maintain emergency procedures for eacharea in which such licensed special nuclear material ishandled, used, or stored to ensure that all personnelwithdraw to an area of safety upon the sounding of acriticality accident alarm.The above procedures are elements of ? nuclearcriticality safety program for operations with fissionablematerials at fuels and materials facilities (i.e., fuel cyclefacilities other than nuclear reactors) in which thereexists a potential for criticality accidents. This guidedescribes pra9tices acceptable to the NRC staff foradministration of such a program.Any information collection activities mentioned inthis regulatory guide are contained as requirements in10 CFR Part 70, which provides the regulatory basis forthis guide. The information collection requirements in10 CFR Part 70 have been cleared under OMB ClearanceNo. 3150-0009.
B. DISCUSSION
ANSI/ANS-8.19-1984, "Administrative Practices forNuclear Criticality Safety,"* was prepared by Subcom-mittee 8, Fissionable Materials Outside Reactors, of the*Copies may be obtained from the American Nuclear Society,555 North Kensington Avenue, La Grange Park, Illinois 60525.Standards Committee of the American Nuclear Society.ANSI/ANS-8.19-1984 was approved by the AmericanNational Standards Committee N16, Nuclear CriticalitySafety, in early 1984 and by the American NationalStandards Institute (ANSI) on October 1, 1984.ANSI/ANS-8.19-1984 provides guidance for administra-tion of a nuclear criticality safety program for operationsoutside of reactors in which there exists a potential forcriticality accidents. This guidance includes delineation ofthe responsibilities of management, supervision, and thenuclear criticality safety staff as well as objectives andcharacteristics of operating and emergency procedures.
C. REGULATORY POSITION
The delineation of responsibilities of management,supervision, and the nuclear criticality safety staff aswell as objectives and characteristics of operating andemergency procedures contained in ANSI/ANS-8.19-1984describe practices generally acceptable to the NRC stafffor administration of a nuclear criticality safety programfor operations with fissionable materials at fuels andmaterials facilities in which there exists a potential forcriticality accidents.Section 11 of ANSI/ANS-8.19-1984 lists additionaldocuments referred to in the standard. Endorsement ofANSI/ANS-8.19-1984 by this regulatory guide does notconstitute an endorsement of these documents.
D. IMPLEMENTATION
The purpose of this section is to provide informationto applicants and licensees regarding the NRC staff'splans for using this regulatory guide.The methods described in this guide were applied toa number of specific cases during reviews and selectedUSNRC REGULATORY GUIDES The guides are issued In the following ten broad divisions:Regulatory Guides are Issued to describe and make available to thepublic methods acceptable to the NRC staff of Implementing 1. Power Reactors 6. Productsspecific parts of the Commission's regulations, to delineate tech- 2. Research and Test Reactors 7. Transportationniques used by the staff In evaluating specific problems or postu- 3. Fuels and Materials Facilities 8. Occupational Healthlated accidents or to provide guidance to applicants. Regulatory 4. Environmental and Siting 9. Antitrust and Financial ReviewGuides are not substitutes for regulations, and compliance with 5. Materials and Plant Protection 10. Generalthem Is not required. Methods and solutions different from those setout in the guides will be acceptable If they provide a basis for thefindings requisite to the Issuance or continuance of a permit or Copies of Issued guides may be purchased from the Governmentlicense by the Commission. Printing Office at the current GPO price. Information on current.GPO prices may be obtained by contacting the Superintendent ofThis guide was Issued after consideration of comments received from Documents, U.S. Government Printing Office, Post Office Boxthe public. Comments and suggestions for Improvements In these 37082, Washington, DC 20013-7082, telephone (202)275-2060 orguides are encouraged at all times, and guides will be revised, as (202)275-2171.appropriate, to accommodate comments and to reflect new Informa-tion or experience.Issued guides may also be purchased from the National TechnicalWritten comments may be submitted to the Rules and Procedures information Service on a standing order basis. Details on thisBranch, DRR ADM, U.S. Nuclear Regulatory Commission, service may be obtained by writing NTIS, 5285 Rort Royal Road,Washington, D6 20555. Springfield, VA 2216 licensing actions. These methods reflect the latest gen-eral NRC approach to administration of nuclear critical-ity safety programs for operations with fissionablematerials at fuels and materials facilities. Therefore,except in those cases in which the applicant proposesan acceptable alternative method for complying withspecified portions of the Commission's regulations, themethods described in this guide will be used in theevaluation of submittals in connection with licenseapplications submitted, under 10 CFR Part 70.i.3.5 7-2 VALUE/IMPACT STATEMENTThe NRC staff performed a value/impact assessment todetermine the proper procedural approach for providingguidance on administration of nuclear criticality safetyprograms for operations with fissionable materials at fuelsand materials facilities. The NRC staff has been involvedin the development, review, and approval of ANSI/ANS-8.19-1984, "Administrative Practices for Nuclear CriticalitySafety," which was approved by the American NationalStandards Institute on October 1, 1984. The assessmentresulted in a decision to develop a regulatory guide thatwould endorse, with possible supplemental provisions,ANSI/ANS-8.19-1984. The results of this assessment wereincluded in a draft regulatory guide on this subject,CE 501-4, that was issued for public comment inFebruary 1986. Comments received from the public andadditional NRC staff review have shown no need tochange the value/impact statement published with theproposed regulatory guide. Therefore, the value/impactstatement published with the proposed guide is stillapplicable. A copy of the draft regulatory guide (identi-fied by its task number, CE 501-4) and its associatedvalue/impact statement is available for inspection andcopying for a fee at the NRC Public Document Roomat 1717 H Street NW., Washington, DC.3.57-3
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