ML20151V379
| ML20151V379 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1986 |
| From: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| References | |
| TASK-CE-404-4, TASK-RE REGGD-03.004, REGGD-3.004, NUDOCS 8808220260 | |
| Download: ML20151V379 (4) | |
Text
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[p, U,S. NUCLEAR REGULATORY COMMISSION March 1986
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REGULATORY GUIDE 3 A I
(Task CE 4044)
NUCLEAR CRITICALITY SAFETY IN OPERATIONSWITH FISSIONABLE MATERIALS AT FUELS AND MATERIALS FACILITIES A. lNTRODUCTION reactors. The standard presents generalized basic criteria and specific limits (maximum suberitical) for some single 233U, 2 3 s U, 2 3'Pu, Section 70.22, "Contents of Applications," of 10 CFR units of simple shape containing Part 70, "Domcstic Licensing of Special Nuclear Material,"
but not for multi-unit arrays. Further, the subcriticallimits requires that applications for a specific license to own, specified in the standard allow for uncertainties in the acquire, deliver, receive, possess, use, or initial;y transfer calculations and experimental data used in their derivation special nuclear material contain proposed procedures to but not for contingencies such as double batching or failur; avoid accidental criticality. This guide describes procedures of analytical techniques to yield accurate values.
acceptable to the NRC staff for preventing accidental criticahty in operations with fissionable materials at fuels This standard also delineates requirements for estab-and materials facilities (i.e., fuel cycle facilities other lishing the validity and area of applicability of a calcula-than nuclear reactors) and for validating calculational tional method used in assessing nuclear criticality safety, methods used in assessing nuclear criticality safetv.
Ilowever, it is concerned only with validating calculational methods and does not address important related questions Any information collection activities mentioned in this such as the margin of safety to be used with the method cr regulatory guide are contained as requirements in 10 CFR the qualifications of the personnel responsible for the data Part 70, which provides the regulatory basis for this guide.
input.
The information collection requirements in 10 CFR Part 70 n\\
have been cleared under OMB Clearance No. 3150 0009.
This standard does not apply to the assembly of fission-
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able materials under controlled conditions, e.g., in critical B. DISCUSSION experiments. Nor does the standard include the details of administrative controls, the design of processes or equip-ANSI /ANS-8.1 1983, "Nuclear Criticality Safety in ment, the description of instrumentatic,,i for lirocess Operations with Fissionable Materials Outside Reactors,""
control, or detailed criteri.i to be met in transporting was prepared by Subcommittee 8, Fissionable Materials multi-unit arrays of fissionable materials.
Outside Reactors, of the Standards Committee of the American Nuclear Society as a consolidation of revisions to C REGULATORY POSITION ANSI N16.11975/ANS 8.1 and ANSI N16.91975/ANS 8.11.
ANSI /ANS-8.1 1983 was approved by the American The nuclear criticality safety practices, the single-National Standards Committee N16, Nuclear Criticality parameter limits for fissionable nuclides, and the guidance Safety, in 1982 and by the American National Standaids for multiparameter controlconttined in ANSI /ANS 8.11983 Institute (ANSI) on October 7,1983.
provide procedures acceptable to the NRC staff for pre-venting accidental conditions of criticality in handling, ANSI /ANS 8.1 1983 applies to handling, storing, proc-storing, processing, and transporting special nuclear essing, and transporting fissionable materialoutside nuclear materials at fuels and materials facilities. Ilowever, use of 8808220260 880631 ~
ANSIIANS-8.1 1983 is not a substitute for detailed nuclear PDR RECCD criticality safety analyses for specific operations.
03.004 R PDR Unes indicate substantive changes from uvtsuin a.
Cogies may be obtained from the A netican Nuclear Society, sss North Kensington Avenue, La Gr.nge Park. lutnois 60525.
nuclear criticality safety contained in ANSI /ANS-8.11983 USNRC REGULATORY GUIDES The guides are issued in the following ten broad civisions pu i m thc s accepta e no R
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o enents an u 9esti r mp nts a t 7 2 a ni ton or gu6 des are encoura?ed at all times. and guid9s will be revised, as (202) 2'7 5-21 r 2 por riat t ac ommodate comments and to reflect new 6nforma-lesued guides may also be purchased from the National Technical Written comments may be submitted to the Rules and Procedures tnformation Serv 6ce on a standing order *> asis. Det ails on tnis Estanch, ORR
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Nuclear R egulatory C om mission, serv 6ce may be obtained by writing NTIS. 52a5 Port Royal Head,
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Springfield. V A 22161.
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m-provide a procedure acceptable to the NRC staff for D. IMPLEMENTATION establishing the validity and area of applicability of cal-culational methods used in assessing nuclear criticality The purpose of this section is to provide information to safety. Ilowever, it will not be sufficient merely to refer applicants and licensees regarding the NRC staff's plans for to this guide in describing the validation of a method.
using this regulatory guide.
The details of validation indicated in Section 4.3.6 of the st andard should be provided to demonstrate the The methods described in this guide were applied to a adequacy of the safety margins relative to the bias and number of specific cases during reviews and selected li-criticality parameters and to demonstrate that the cal-censing actions. These methods reflect the latest general culations embrace the range of variables to which the NRC approach to criticality safety in operations with meth(d will be applied.
fissionable materials at fuels and materials facilities.There-fora, except in those cases in which the applicant proposes an acceptable alternative method for complying with section 7 of ANSI /ANS 8.1-1983 lists additional docu-specified portions of the Commission's regulations, the ments referred to in the standard. Endorsement of methods described in this guide will be usedin the evaluation ANSI /ANS 8.1-1983 by this regulatory guide does not of submittals in connection with license applications constitute an endorsement of these documents.
subrnitted under 10 CFR Part 70.
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i VALUE/ IMPACT STATEMENT
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The NRC staff performed a value/ impact assessment to of this assessment were included in a proposed Revision 2 determine the proper procedural approach for updating to Regulatory Guide 3.4 that was issued for public comment Revision 1 of Regulatory Guide 3.4, "Nuclear Criticality in April 1985. No comments have been received from the Safety in Operations with Fissionable Materials Outside public, and additional NRC staff review has shown that, Reactors," issued in February 1978, which endorsed except for minor clarifications, there was no need to change ANSI N16.11975/ANS 8.1. The NRC staff has been in-the regulatory position of the proposed Revision 2 to Regu-volved in the development review, and approval of a revision latory Guide 3.4. Therefore, the value/ impact statement to ANSI N 16.1 1975/ANS-8.1 (designated ANSI /
published with the proposed revision is applicable. A copy AN S-8.1 198 3), which was approved by the American cf the draft regulatory guide and the associated value/ impact National Standards Institute on October 7,1983. The statement (identified by its task number, CE 404-4) is assessment resulted in a decision to develop a revision to available for inspection or copying for a fee it the Com-Regulatory Guide 3.4 that would endorse, with possible mission's Public Document Room at 17i711 Street NW.,
r.pplernental provisions, ANSI / ANS-8.1 1983. The results Washington, DC.
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