ML20129A234

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Forwards Draft Guidance Dealing W/Use of Highly Enriched U at Research Reactors,Per 840118 Request.Draft Guidance Will Serve as Basis for Discussion at Commission 840206 Meeting
ML20129A234
Person / Time
Issue date: 02/01/1984
From: Dircks W
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To: Palladino
NRC COMMISSION (OCM)
Shared Package
ML20127B589 List:
References
FOIA-84-784 AB60-2-318, NUDOCS 8507150249
Download: ML20129A234 (4)


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February 1, 1984 NOTE TO: Chairman Palladino FROM: W. J. Dircks Executive Director for Operations

SUBJECT:

DRAFT GUIDANCE FOR FEBRUARY 6~, 1984 COMMISSION MEETING Enclosed is draft guidance dealing with the use of HEU at research reactors.

As you requested in your memo of January 18, 1984, staff has prepared draft guidance which would serve as a basis for discussion at the Comission meeting on February 6, 1984.

(51sned) T. A, Rehm William J. Dircks D Executive Director for Operations

Enclosure:

As stated Distribution EDO R/F WDircks JRoe TRehm

. RMinogue JDavis cc: Comissioner Gilinsky Commissioner Roberts Commissioner Asselstine Commissioner Bernthal SECY .

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E , wAsectow. o. c.nosss MEMORANDUM FOR: William J. Dircks Executive Director for Operations l

l FROM: Samuel J. Chilk Office of the Secretary

SUBJECT:

. DEVELOPMENT OF PROPOSED RULE ON HEU AT DOMESTIC l RESEARCH REACTORS AND INTERIM SECURITY MFASURES By memorandum dated June 21, 1983, I reported that the Comission agreed that a proposed rule be developed to implement the Commission's policy for reduction of the use of high enriched uranium (HEU) at domestic research reactors. The Chaiman also requested that the staff brief the Comission on the matter before extensive effort was expended in developing the proposed rule. The briefing was held on December 19, 1983, and January 27, 1984, and you are requested to proceed

. expeditiously with development of the proposed rule.

A. proposed Rule on HEU at Domestic Research Reactors In addition to the provisions set out in the memorandum of June 21,1983, thd~ proposed rule should, to the extent feasible, minimize the licensi. ng burden that could result. Consideration should'be given to providing in the rule for automatic extension of existing licenses to cover LEU if

  • prescribed conditions are met. Those conditions should assure that present safety margins are not significantly reduced. To this end the staff should act promptly to initiate a generic safety evaluation report

( setting forth safety envelopes for the plants under consideration, and the rule package should ask for comment on dealing with the limited.

changes in safety margins in this manner.

The fomission wishes to review two options:

a. A rule requiring the conversion to LEU fuel of all licensed research and training reactors other than those exempted because of a unique purpose. Under this option, reactors that regularly replace burned up fuel would be required to replace such fuel with low enrichment uranium fuel as the HEU fuel is used up, and as the replacement fuel is available.

The schedule for such replacements shall be developed with the Director of NRR who will coordinate such actions with DOE.

If a suitable replacement fuel is not expected to be available within the overall schedule for the DOE RERTR program, the licensee shall use a replacement fuel at an enrichment that is as low as technically achievable, based on the technology developed by DOE, until such time as improved technology, permitting

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operation with fuel at enrichnent of 20 percent or less, is available. For reactors that do not expect to require the acquisition of new fuel during the term of their license, a schedule shall be developed with the Director of NRR to provide for as prompt conversion to LEU as is reasonable. The schedules for conversion shall take into account such factors as: scheduling of shipping casks, replacement fuel fabrication, financial support, and reactor usage. It is expected that this schedule will be co.ordinated with DOE.

A rule similar to the option developed above, but restricted b.

to those reactors that expect to acquire new fuel during the term of their license should also be developed.

Further, the proposed rule should establish a schedule for conversion of the higher-powered reactors.

On the basis of information presented at the briefing on December 19, 1983, it is anticipated that the National Bureau of Standards reactor and perhaps the Union Carbide reactor should be considered as serving " unique purposes" and be permitted to continue use of'HEU.

For the purposes of this rule, " unique purpose" should account for such characteristics as neutron flux levels and energy spectrum specifically

. designed to facilitate research or irradiations. not readily performed elsewhere 'in the U.S. The Director of NRR should determine whether the reactor has a " unique purpose." - -

B. Interim Security Measures at Domestic Research Reactors Staff should also investigate physical protection requirements applicable during the interim preceding the completion of conversion to LEU. Since nearly all nonpower reactors possessing high enriched fuel currently iglement the Category II physical protection requirements of 10 CFR 73.67 (a), these should be addressed,before the proposed Category I nonpower amendments are made final. Staff should assess the impact and benefit ~of alternative measures to be added to the Category II requirements to increase the level of protection at these facilities. The alternatives should include the following:

1. Reduce Holdings of Fresh HEU Fuel at Nonpower Reactors
2. Tamper-Proof Detection Systems and Provide Line-Supervision
3. Assure Presence of Two-Persons During Access to Material
4. Improve Communications Capability
5. Provide Access Barriers over the Reactor Core

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. Staff shall also investigate whether Interim Category I requirements should be amended:

1. To require submittal for NRC ' review and approval of the specific measures that the licensee would apply to meet the requirements of 10 CFR.73.60; and
2. To require licensees which apply the 100 rem / hour at 3 feet exemption, to meet only Category II requirements, to demonstrate how they determine that radiation levels are abo've the level stipulated in the exemption; and
3. To require licensees to notify the NRC at least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> before they expect a change in requirement category.

Upon completion of the above efforts, staff should propose a program to the Comission for the implementation of any improvements deemed necessary.

Work permanent on the rulefinal rule for theft replacement to 10 at CFRCategor)y 73.60 shall I nonpower be deferredreactors (the and a schedule

.for completion of that effort should be included when staff presents its proposals for Category II changes.

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Samuel J. Chilk Office of the Secretary .

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