ML20126B585

Discusses ASLB Initial Decision on Steam Generator Repair Re Licensee Application for Amend to OL to Permit Rev of Tech Specs to Recognize Steam Generator Tube Repair Techniques

ML20126B585
Person / Time
Site:	Three Mile Island
Issue date:	11/06/1984
From:	Cunningham G NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20126B295	List: 05000289/LER-1981-013, Forwards LER 81-013/01T-0 Re Leaking Found in Steam Generators.Event Reportable Per Tech Spec 6.9.2.A(3). Supporting Documentation Encl IA-84-897, Forwards Safety Evaluation Re Increase in once-through Steam Generator Primary to Secondary Leakage Rate,Per NUREG-1019 & Suppl 1.Rate Acceptable ML20126B293 ML20126B302 ML20126B316 ML20126B321 ML20126B337 ML20126B342 ML20126B358 ML20126B376 ML20126B390 ML20126B412 ML20126B435 ML20126B467 ML20126B475 ML20126B493 ML20126B504 ML20126B513 ML20126B520 ML20126B560 ML20126B563 ML20126B585 ML20126B592 ML20126B610 ML20126B618 ML20126B623 ML20126B635 ML20126B639 ML20126B648 ML20126B650 ML20126B656 ML20126B658 ML20126B667 ML20126B670 ML20126B684 ML20126B688 ML20126B701 ML20126B708 ML20126B716 ML20126B719 ML20126B739 ML20126B751 ML20126B758 ML20126B766 ML20126B784 ML20126B797 ML20126B806 ML20126B825 ML20126B831 ML20126B879 ... further results
References
FOIA-84-897 NUDOCS 8506140143
Download: ML20126B585 (2)

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. Note to: Harold R. Denton, Director ,wpo Office of Nuclear Reactor Regulation ,

Guy H. Cunningham, III Y AAA 8.

From:

Executive Legal Director },y g

SUBJECT:

TMI-1: INITIAL DECISION ON STEAM GENERATOR REPAIR On October 31, 1984 the Atomic Safety and Licensing Board issued an initial Il decision on GPU's application for an amendment to its operating license for

-TMI-1 to permit revision of its technical specifications to recognize steam generator tube repair techniques, other than plugging, and to pennit operation using the repaired steam generators. The Board concluded that the license conditions proposed by the Staff, two additional conditions imposed by the Board, and Licensee's post repair and plant performance testing and analysis provide reasonable assurance that the leak tight integrity of the repaired steam generator _ tube joints will be maintained, that the uncertainties leading to the Board's request to hear evidence on

, specific issues have been resolved, and that reasonable assurance exists that the repair process has not increased'the probability of simultaneous tube ruptures.

The Staff had proposed several license conditions in its SER. In addition to those conditions, the Board imposed two other conditions, one requiring shutdown for eddy current testing (ECT) in the event of prolonged operation I at less than 50% power (0 pinion, pp. 8-9), and the other requiring a redund-l ancy to the RM-A5 (monitor of radioactive gas) or, alternatively, a technical l specification requiring that the RM-A5 system be operable at all times during reactor operation (0 pinion, pp. 6-7).

The provision relating to special shutdown for ECT in the event of extended plant operation at less than 50% power was not contained in the Staff's proposed license condition on ECT because, the Staff testified, the possi-bility of such extended operation had not been anticipated. However, the Staff's witness stated at the hearing that, if such extended operation were to occur, he would be inclined to request of licensee that the plant be shut down for ECT after a specified period of time, such as 180-200 days.

l The time specified by the Board is 180 days.

As for the condition requiring redundancy of the RM-A5 system, the Staff ,had

, considered, but rejected, a possible license condition that would require operability of the RM-A5 system at all times. The Board's condition only imposes such a restriction if Licensee does not wish to install a redundant system. If such a system is installed, the technical specifications would B506140143 850125 PDR FOIA DETJEN94-697 PDR 20/

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. NOV 6 E84 be modified to permit plant operation for a maximum of 28 days with one of the systems inoperable. The current t2chnical specifications permit plant operation for 28 days with the RM-A5 inoperable, provided grab samples are-being taken.

OELD staff has consulted with your staff on the Licensing Board's' decision, t but has identified no need_ or basis for an NRC Staff appeal of the decision.

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uy II. Cunninghamr111 Executive Legal Director cc: W. Dircks T. Murley 4