ML20247F200

Rev 2 to Reg Guide 8.12,Task CE 801-5, Criticality Accident Alarm Sys

ML20247F200
Person / Time
Issue date:	10/31/1988
From:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
References
TASK-CE-801-5, TASK-RE REGGD-08.012, REGGD-8.012, NUDOCS 8907270106
Download: ML20247F200 (2)

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RIvisiin 2 g#"% U.S. NUCLEAR REGULATORY COMMISSION october 1988 O @.,_ A$) REGULATORYGUIDE

%.+ OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 8.12 (Task CE 8015)

CRITICALITY ACCIDENT ALARM SYSTEMS A. INTRODUCTION Alarm System," is generally acceptable to the NRC staff, subject to the following limitations:

Section 70.24, " Criticality Accident Requirements," of 10 CFR Part 70, " Domestic Licensing of Special Nuclear Material," requires licensees who an: authorized to possess 1. Section 70.24 of 10 CFR Part 70 requires alarm special nuclear material in excess of certain amounts to coverage "in each area in which such licensed special maintain a criticality accident alarm system. This guhle nuclear material is handled, used, or stored . . ." whereas describes a system acceptable to the NRC staff for meeting paragraph 4.2.1 of the standard states that the need for the Commission's requirements for a criticality accident criticality alarms must he evalue for stuch areas. If such alarm system. an evaluation does not deterrnme that a potential for criticality exists, as for example where the quar.tities or Any information collection activities mentioned in this form of special nuclear material make criticality practically regulatory guide are contained as requirements in 10 CFR impossible or where geometric spacing is used to preclude Part 70, which provides the regulatory basis for this guide, criticality, such as in some storage spaces for unitradiated The information collection requirements in 10 CFR Part 70 nuclear power plant fuel, it is appropriate to request an have been cleared under OMB Clearance No. 3150-0009. exemption from 5 70.24.

B. DISCUSSION

2. Paragraph 70.24(a)(1) of 10 CFR Part 70 requires

[s} Section 70.24 requires, in part, a monitoring system that each area be covered by two detectors, whereas para-(U f capable of detectmg a criticality that produces an absorbed graph 4.5.1 of the standard termits coverage by a reliable dose in soft tissue of 20 rads of combined neutron and single detector.

gamma radiation at an unshielded distance of 2 meters from the reacting material witidn 1 minute. Cnticality accident alarm systeras are also discussed in American National D. IMPLEMENTATION Standard ANSI /ANS-8.3-1986, " Criticality Accident Alarm System,"1 which has the same detection criterion. The punose of this section is to provideinformation to applicants regarding the NRC staff's plans for using this C. REGULATORY POSITION regulatory guide.

The guidance on criticality accident alarm systems contained in ANSI /ANS-8.3-1986, " Criticality Accident Except in those cases in which an apphcan-t proposes an acceptable alternative method for complyir g with 5 70.24 of 10 CFR Part 70, the method described in this guide will 1Copes anay tw obtained from the American Nuclear Soci. be used in the evaluation of designs of criticality accident ety,555 North Kensington Avenue, La Grange Park, Illinois 60525. alarm systems.

USNRC REGULATORY GU! DES The guides are issued in the following ten broad 06vis4cns Regulatory Guides are issued to describe and make available to the public methods acceptable to the NRC staff of implementing 1. Power Reactors 6. Products specific parts of the Commiss6on's regulations to denneate tech- 2. Research and Test Reactors 7. Transportation n6 ques uset by the staff an evaluating specif6c problems c't postu- 3. Fuels and Mater 6ats Facilities a. Occupational Health lated accidents or to provide guidance to appucants. Regulatorv 4. Environmental and Sit 6ng 9. Antitrust and F inancial Rev6ew ou6 des are noi substitutes for regulations, and compliance with 5. Materiais and Plant Protection 10. Generat them is not reauired. Methods and solutions different from those set out in the gu6 des will be acceptable if they provide a basis for the findings rooutsite to the issuance or continuance of a permit or copies of issued guidos rnay be purchased from the Governenent incense by the Commission. Pr6nting ONace at the current GPO price. Information on current GPO prices may be obtained by contactmg the Superintendent of This guide was issued after consideration of comments received from t

/m\ the pubHc. Comments ar d suggestions for improvements in these Documents, U.S. Government Printing Of flca, Post Off 6ce Box 37082, Washington, DC 20013-7082, telephone (202)275-2060 or guides are encouraged at all times, and guides wiH De revised. as (2c.7)275-2171.

( appropr6 ate, to acc.ommodate comments and to reflect new informa.

A tion or experience.

Written comments may be submitted to the Rules and Procedures information Serv 6ce on a stand 6ng order basis. Details on this Branch, DRR ADM, U.S. Nuclear Regulatory Cornmtssaon, service may ;be obtained by writing NTis, 5285 Port RoyM Road, wasnnngton, Dd 20bbb. Springfleid. VA 22161.

8907270106 881031 PDR RECGD 08.012 R PDR

VAltJE/lMPAC1 STATEMENT -

A draft value/ impact statement was published wi'ih he proposed Revision 2 to Regulatory Guide 8.12 (Task CE 801-5) when the draft guide was publisN for public comment in May 1988, No changes were necessary, so a separate value/impEt statement i r the final guide has not been prepared. A copy of the draft value/ impact statement is available for insp. tion and copying for a fee ,at the Commissiocrs Public Document Room at 2120 L Street NW., Washingt ,n, DC, under Task (T 801-5.

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UNITED 6TATES ,,,,, ca.. ..,t conaos a reis emio NUCLEAR REGULATORY COMMISSION "*"*

WASHINGTON, D.C. 20555 -

etRMTV he. 0 87 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 1

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