ML20137G828

Amend of Order Incorporating Encl Proposed Tech Specs Re Acceptability of Containment Penetration Valve Configurations,Effective on 850812

ML20137G828
Person / Time
Site:	Three Mile Island
Issue date:	07/08/1985
From:	Eisenhut D Office of Nuclear Reactor Regulation
To:	GENERAL PUBLIC UTILITIES CORP.
Shared Package
ML20137G826	List: ML20137G821 ML20137G828 ML20137G833
References
NUDOCS 8508270393
Download: ML20137G828 (4)

Text

Enclosure 1 L'flITED STATES Of AMERICA NUCLEAR REGULATORY COMilISSION In the lidtter of )

GENERAL PUBLIC UTILITIES NUCLEAR Docket No. 50-320 CORPORATION )

)

(Three liile Island Nuclear Station, )

Unit 2) )

AMEND!iENT OF ORDER I.

GPU Nuclear Corporation, Metropolitan Edison Company, Jersey Central Power and Light Company and Pennsylvania Electric Company (collectively, the licensee)aretheholdersofFacilityOperatingLicenseNo.DPR-73,which had authorized operation of the Three Mile Island Nuclear Station, Unit 2

~

(TMI-2) at power levels up to 2772 megawatts thermal. The facility, which is located in Londonderry Township, Dauphin County, Pennsylvania, is a pressurized water reactor previously used for the commercial generation of electricity.

II.

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 shut-downcoolingmode(44 Fed. Reg.45271). By further Order of the Director, Office of Nuclear Reactor Regulation, dated February 11, 1980, a new set of formal 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 Fed.

Reg. 11292).

8508270393 050708 gDR ADOCK 05000320 PDR

Although these requirements were imposed on the licensee by an Order of the Director of Nuclear Reactor Regulation, dated February 11, 1980, the TMI-2 license has not been formally amended. The requirements are reflected in the Recovery Mode Proposed Technical Specifications (PTS) presently pending before the Atomic Safety and Licensing Board. The revisions that are the subject of this order do not give the licensee authorizations that may be -

needed to undertake specific cleanup activities. Hereafter in this Amend-ment of Order, the requirements in question are identified by the applicable Proposed Technical Specification.

III.

By letter dated October 31, 1984, GPU Nuclear Corporation (GPUNC) informed the NRC that certain containment penetration valve configurations presently in use at the Three Mile Island, Unit 2 (TMI-2) do not conform to the July 17, 1984 Amendment of Order which modified the PTS definition of con-tainment integrity. In addition, these configurations do not conform to the staff's Approval of Alternate Design relative to 10 CFR 50, Appendix A, Criteria 55 and 56 also issued on July 17, 1984.

After reviewing the licensee's discussion in the subject letter and performing a safety evaluation addressing the containment isolation configurations, the staff has modified Section 1.7 of the PTS and added Table 3.6-2 which lists exceptions to containment penetration valve configurations.

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The staff review concluded that; (1) The subject penetration valve configurations were previously concurred with by the NRC in HUREG-0107, (2) Many of the systems affected are not in use during the recovery period and are therefore depressurized, and (3) Those systems still in use are primarily used under emergency conditions and will not experience transients as extreme as those previously analyzed in NUREG-0107 for emergency or non-emergency use.

Based on the above, the addition of certain exceptions to the two valve,

,. isolation requirements of the PTS.are warranted and will not'* have an adver e impact on the health and safety of the public. The staff's safety assess-ment of this matter as discussed above is set forth in the concurrently issued Safety Evaluation.

Sin,ce the February 11,_1980 Order imposing the Proposed Technical Specifications is currently pending before the Atomic Safety and Licensing Board, the staff will be' advising the Licensing Board of this Amendment of Order through a Notice of Issuance of Amendment of Order and a Motion to Conform Proposed Technical Specifications in Accordance Herewith.

It is further determined that the modification does not authorize a change j

in effluent types or total amounts nor an increase in power level ard will not result in any significant environmental impact. The staff has deter-mined that this action is insignificant from the standpoint of environ-mental impact and neither an environmental impact statement nor an environmental assessment need be prepared.

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IV.

Accordingly, pursuant to the Atomic Energy Act of 1954, as amended, the Director's Order of February 11, 1980, is hereby revised to incorporate the deletions, additions, and modifications set forth in Enclosure 3 hereto.

This Amendment of Order shall be effective on August 12, 1985.

For further details with respect to this action, see (1) Letter to B. J.

Snyder, USNRC, from F. R. Standerfer, GPUNC, Containment Isolation Valves, and (2) the Director's Order of February 11, 1980.

All the above documents are available for inspection at the Commission's Public Document Room, 1717 H Street, N.W., Washington, DC 20555, and at the Commission's Local Public Document Room at the State Library of Pennsylvania, Government Publications Section, Education Building, Common-wealth and Walnut Streets, Harrisburg, Pennsylvania 17126.

FOR THE NUCLEAR REGULATORY COMMISSION arre G. senhut, eputy Director -

Office of Nuclear Reactor Regulation Effective Date: August 12, 1985 Dated at Bethesda, Maryland Issuance Date: July 8, 1985