ML20151W555

Environ Assessment & Finding of No Significant Impact Re Exemption from Requirements of 10CFR70.24, Criticality Accident Requirements

ML20151W555
Person / Time
Site:	Three Mile Island
Issue date:	04/26/1988
From:	Ferguson R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20151W528	List: ML20151W525 ML20151W555
References
NUDOCS 8805030426
Download: ML20151W555 (4)

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UNITED STATES NUCLEAR REGULATORY COMMISSION GPU NUCLEAR CORPORATION DOCKET NO. 50-320 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (the Comission) is considering issuance of an exemption from the requirements of 10 CFR 70.24, Criticality accident requirements relative to Facility Operating License No. DPR-73, issuedtoGPUNuclearCorporation(thelicensee),fortheThreeMileIsland Nuclear Station Unit 2 (TMI-2), located in Londonderry Township, Dauphin County, Pennsylvania. By Order for Modification of License, dated July 20, 1979, the licensee's authority to operate the facility was suspended and the licensee's authority was limited to maintenance of the facility in the present shutdown cooling mode (44 FR 45271). By further Order of the Director, Office of Nuclear Reactor Regulation, dated February 11, 1980, a new set of fonnal license requirements was imposed to reflect the post-accident condition of the facility and to assure the continued maintenance of the current safe, stable, long-term cooling condition of the facility (45 FR 11292). The license provides, among other things, that it is subject to all rules, regulations and l

Orders of the Comission now or hereafter in effect.

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ENVIRONMENTAL ASSESSMENT Identification of Propp,s.ed, Action:

The action being considered by the Commission is exemption from 70.24 Criticality accident requirements relating to requiren.ents for a monitoring system capable of detecting a criticality.

Specifically, 10 CFR 70.24 requires licensees authorized to possess special nuclear material above a minimum quantity to raintain a redundant monitoring system that is capable of detecting a criticality in each area in which such licensed special nuclear material is handled, used or stored. The redundant monitoring systems, using gamma-or neutron sensitive radiation detectors, are required to energize clearly audible alarn, signals if accidental criticality occurs. The regulations applicable to TMI-2 further f;iine the sensitivity of the monitoring system and require the licensee to have emergency procedures for the protection of personnel.

The Need for the Prppp, sed Action:

TMI-2 is currently in a post-accident, cold shutdown, long-term recovery mode. Exen;ption from 10 CFR 70.24 is requested after the conclusion of the licensee's current defueling program which will renove greater than 99% of the l

original core material and preclude the possibility of an inadvertent criticality.

Once defueling is completed the reactor building will be entered infrequently by personnel readying the building for long-term storage and for periodic nonitoring. Remaining fuel in areas accessible to personnel will be contaired in the primary system, with the majority of the material in the

'l reactor vessel. Personnel entering the building will be required to possess radiation survey instruments. Although the amount of special nuclear material will exceed limits of 10 CFR 70.24, the material will be distributed in a i

number of locations in a configuration that would preclude a criticality.

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Furthermore, the buildirg will be unoccupied and personnel entries will occur on an infrequent basis. Personnel that do enter will possess appropriate monitoring equipment that would detect a criticality.

Principal quantities of fuel are located in areas that are inaccessible to personnel and well shielded.

Paintenance of the current internediate and source range neutron flux monitors wculd prove an unnecessary burden and expense on the licensee with no concomitant benefit in terms of achieving the purpose of the requirement.

Environrental_ Jmpact of the PropoMetjgn:

The staff has evaluated the proposed exemption and concludes that in light of the current and future condition of the facility described above, there are no significant radiological or nonradiological inpacts to the environn.ent as a result of this action.

The proposed exemption renoves the specific feature of the Commission's requirement to maintain criticality monitors in areas where special ruclear raterial above certain amcunts is handled, used or stored.

Alternatives to the Prop,osed Action:

Since the Commission has concluded that there is no significant environ-nental inpact associated with the proposed exemption, any alternatives to this action will have either no significant environmental impact or greater environnental impact.

Agencies and Persons Consulted:

The Commission's staff reviewed the licensee's request and did not consult other agencies or persons.

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Alternative Use of Resourcy:

This action does not involve the use of resources not previously considered in connection with the Final Progrannatic Environnental Impact Staten(nt for TMI-2, dated March 1981.

FINDING OF NO SIGNIFICANT IMPACT The Connission has determined not to prepare an environmental impact i

statentnt for the proposed exemption.

Based upon the foregoing environmental assessnent, we conclude that this action will not have a significant effect on the quality of the human environment.

For further details with respect to this action see the letter from GPUN, Technical Specification Change Request No. 53, dated April 23, 1987 and revised October 26, November 9 and December 4, 1987. These documents are available for public inspection at the Corrinission's Public Document Room,1717 H Street, N.W.,

Washington, D.C., and the State Library of Pennsylvania, Governrrent Publications Section Education Building, Con 1ronwealth and Walnut Streets Harrisburg, Pennsylvania 17126, i

Dated at Rockville, Maryland, this 26 day of April 1988.

FOR THE h0 CLEAR REGULATORY COMMISSION

[-o VW Robert L. Ferguson, Ac i Director Project Directorate I-Division of Reactor Projects I/II 4

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