ML19246B041
| ML19246B041 | |
| Person / Time | |
|---|---|
| Issue date: | 07/31/1976 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| References | |
| REGGD-02.004, REGGD-2.004, NUDOCS 7907110214 | |
| Download: ML19246B041 (6) | |
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!)o p) OFFICE OF STANDARDS DEV DE (This page reissued May 1977)
REGULATORY GUIDE 2.4 REVIEW OF EXPERIMENTS FOR RESEARCH REACTORS A.
INTRODUCTION Section 50.36, " Technical Specifications," of 10 CFR Part 50,
" Licensing of Production and Utilization Facilities," requires that each applicant for a license authorizing operation of a production or utiliza-tion facility include in his application proposed technical specifica-tion;.
If acceptable, these technical specifications, along with any other such specifications that the Commission finds appropriate, are in-corporated into the facility license that is issued by the Commission and are conditions of the license.
Paragraph (c)(5), " Administrative controls," of 5 50.36 of 10 CFR Part 50 requires that technical specifications for nuclear reactors in-clude provisions relating to the organization and management procedures, recordkeeping, review and audit, and reporting necessary to ensure operation of the facility in a safe tanner.
Section 50.59, " Changes, tests and experiments," of 10 CFR Part 50 permits each holder of a license authorizing operation of a production or utilization facility to make changes in the facility and procedures as described in the safety analysis report (SAR) and to conduct tests or experiments not described in the SAR, without prior Concission approval, unless the proposed change, test, or experiment involves a change in the technical specification incorporated in the license or an unreviewed safety question.
This guide describes procedures acceptable to the NRC staff for the licensee's review and approval of experiments performed at research reactor facilities.
B.
DISCUSSION Standard AFSI N401-1974 (ANS-15.6), " Review of Experimeh Lfor) b Research Reactors,"* was prepared by Work Group ANS-15.6 and sponsored by Copies may be obtained from the American Nuclear Society, 244 East Ogden Avenue, Hinsdale, Illinois 60521.
USNRC REGUL AToRY GUIDES
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The first page of this guide is being reissued with the words "For Comnent" deleted.
The stat *'s consideration of coninents received during the initial public cor. ment period has resulted in the determination that there is no need for a revision at this time.
It is suggested that you attach this page to the first page of the complete guide.
No changes have been made to the text of either this page or the remainder of the guide.
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O.S. NUCLEAR REGULATORY COMMISSION July 19 76 g
REG TE'ORY G1 : 0DE OFFICE OF STANDARDS DEVELOPMENT REGULATORY GUIDE 2.4 REVIEW OF EXPERIMENTS FOR ESEARCH REACTORS A.
INTRODUCTION Section 50.36, " Technical Specifications," of 10 CFR Part 50,
" Licensing of Production and Utilization Facilities," requires that each applicant for a license authorizing operation of a production or utiliza-tion facility include in his application proposed technical specifica-tions.
If acceptable, these technical specifications, along with any other such specifications that the Co nission finds appropriate, are in-corporated into the facility licent. that is issued by the Commission and are conditions of the license.
Paragraph (c)(5), " Administrative controls," o f 5 50. 36 o f 10 CFR Part 50 requires that technical specifications for nuclear reactors in-clude provisions relating to the organization and management procedures, recordReeping, review and audit, and reporting necessary to ensure operation of the facility in a safe canner. Section 50.59, " Changes, tests and experiments," of 10 CFR Part 50 permits each holder of a lice.
authorizing operation of a production or utilization facility to make changes in the facility and procedures as described in the safety analysis report (SAR) and to conduct tests or experiments not described in the SAR, without prior Commission approval, unless the proposed change, test, or e xperiment involves a change in the technical specification incorporated in the license or an unreviewed safety question.
This guide describes procedures acceptable to the NRC staf f for the licensee's review and approval of experiments performed at research reactor facilities.
B.
DISCUSSION
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Standard ANSI N401-1974 (ANS-15.6), " Review of Experiments for Research Reactors,"* was prepared by Work Group ANS-15.6 and sponsored by
- Copies may be obtained from the American Nuclear Society, 244 East Ogden Avenue, Hinsdale, Illinois 60521.
USNHC REGULATORY GUIDES comm.nii.houid b...nt to the s.oet ar, oe the comm.s..on u s N,....t
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Subcommittee ANS-15 (Research Reactors) of the American Nuclear Society (ANS.
This standard was approved by the American National Standards Committee N17, Research Reactors, Reactor Physics and Radiation Shielding, and its Secretariat in March 19 74.
It was s ubsequently approved and designated ANSI N401-1974 5y the Ame rican Na tional S tandards Institute (ANSI) on November 19, 1974 The standard pcovides guidance for the licensee's review and approval of experiments performed at research reactor facilities by identifying substantive areas f or each expe rioent that should be reviewed to provide assurante that the experiment (1) falls within the limits delineated in the technical specifications, (2) does not present an unreviewed sa fe ty ques tion as defined in 550.59, " Changes, tests and experiments," o f 10 C FR Pa r t 50, ( 3) does not constitute a th eat to tue health and safety of any individuals, and (4) does not constitute a hazard to the reactor f acility or other equipment.
In addition, this standard recommends a sys tem f or classi f ying expe rimen ts to es tablish le vels of licensee review and approval con =ensurate with the level of risk inherent in the experiment.
Both the requirements anc the recoamendations of the standard have been evaltated by the staff la evaluating the acceptability of this standard.
C.
REGULA1'ORY POSITION The requirements and recommendations provided in ANSI N401-19 74,
" Review of Experiments f or Research Reactors," are 3;enerally acceptable to the NRC staff.
The guidance provides an adequate basis for the revies and approw.1 of research reactor experiments perforacd in accordance with 5 550. 36 and 50.59 o f 10 CFR Part 50, subject to t5e following:
1.
The last sentence of the paragraph defining, "shall, should and niy," as 3;ivan in dection 3, " Definitions," of ANSI N401-19 74 should be modified to read as follows:
"To con form to this standard, experiment review shall be performed in accordance with the standard's requirements and r eco=aenda tions."
2.
The definition of nen-secured experiment, as given in Section 3,
" Definitions," should be modified to read as follows:
" Any e xpe rimen t,
experimental facility, or component of an experiment is considered to be unsecured when it is not secured as defined under secured experiment in Section 3."
3.
Subsection 4.1, " Classification System," should be modified by adding the following sentence:
"The experiment classification system to deternine level of approval for the experiments should be reviewed and approved by the Reactor Safety Committee designated in the Technical Specifications."
4.
In addition to the exp;riment plan (Section 5, "The Experimen tal Plan"), there should also exist detailed procedures for carrying out an 2.4-2 142 i66
experiment, and these procedures should be reviewed as required by the facility's technical specifications. A single experimental procedure may be used for rmre than one exposure er rmre t.mn one identical expe riment, but such a procedure should expire after a specified interval.
5.
Subsection 6.1, " Review Procedure," should be modified by adding the following sentence:
"The experiment review p roce du re should be reviewed and approved by the Reac to r Sa f e ty Cocalit tee designa ted in the Technical Specifications."
6 Paragraph (3) of Suboection 6.2, "Conside rations," should be replaced with the following "Does the experiment meet all criteria rega rding reac tivi ty ef f ects' These criteria include assurance that (1) the potential reactivity worth of each secured experiment would be less than that value of reactivity which, if introduced as a positive step change, could result in a transient that would be likely to lead to doses in any restricted or unrestricted area in excess of the limits set forth in 10 CFR Part 20; (2) the nignitude of the potential reactivity worth of each non-secured experiment would be less than that value which, if intro-
'"ced as a positive step change in reactivity, would cause a violation of a safety linit or of the ninimum shutdown nirgin; and (3) the rate of change and engnitude of reac tivity of any moseable expe riment, r.m cable parts of experiments, or any combination of such experiments introduced by intentionally setting the experiments in motion relative to the reactor would not exceed the capacity of the con.o1 system to provide compensation."
7.
In S ub sec tion 6. 3,
" Review Personnel," the last paragraph should be replaced with the following:
"Me mb e rs of the Committee should dis-qualify themselves from the review of experiments in which they are directly involved.
They may act as c ons ul tan ts to the review group but should not be involved with the final decision for approval or disapproval of the experiment."
8.
The specific applicability or acceptability of items 1, 3 4, and 5 of Section 9, "Re f erences," of ANSI N401-19 74 will be covered separately in other regulatory guides, where appropriate.
D.
IMPLEMENTATION The purpose of this section is to provide guidance to applicants regarding the NRC staff's plans for using this regulatory guide in the review of research reactor facility applications. The staf f will use this guide in evaluating applications submitted af ter the date shown below.
Hoaever, all or part of this guide ray be u3ed by the staff to the extent reasonable and practicable for evaluating prior applications.
Such use is usually reflected in the staf f review questions and subsequent evaluations
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for specific cases.
Backf it t ing; ac tion, if required, will be considered separately pursuant to Section 50.109 of 10 C FR l'a r t 50.
Except in those caset in which the applicant proposes an acceptable alternative method for complying wi th specified portions of the Commission's regulations, the method tescribed herein will be used by the staff in evaluating applications in connection with research reactor facility con-struction pernits, operating licenses, or proposed amendments thereto submitted for approval af ter March 1, 1977.
UNITED STATES
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NUCLE AR HEGULATORY COMMtSSION W ASHING TON. D. C.
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