ML20004E074

Proposed Changes to Tech Specs 4.2.4 & 4.2.5 Re Cumulative Reactor Utilization Factor

ML20004E074
Person / Time
Site:	Three Mile Island
Issue date:	06/05/1981
From:	METROPOLITAN EDISON CO.
To:
Shared Package
ML20004E070	List: ML20004E069 ML20004E071 ML20004E074
References
NUDOCS 8106110108
Download: ML20004E074 (1)

Text

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4.2.4 Th2 lictnssa shall cubnit a r port or application for licanae amendment to the NRC wichin 90 days af ter any time that Crystal River Unit 3 fails to maintain a cumulative reactor utilization factor of at least 65%.

The report shall provide justification for continued operation of TMI-l with the reactor vessel surveillance program conducted at Crystal River Unit No. 3, or the application for license amendment shall propose an alternate program for conduct of the TMI-l reactor vessel surveillance program.

For the purpose of this technical specification, the definition of commercial operation is that given in Regulatory Guide 1.16, Revision

4. The definition of cumulative reactor utilization factor is:

Cumulative reactor utilization factor - (Cumulative megawatt l hours (thermal) since the beginning of Cycle 3 (9/10/80) x (100) divided by (licensed power.(HWt) x (Cumulative hours since the beginning of Cycle 3 (9/10/80)). l 4.2.5 In addition to the reports required by Specification 4.2.4, a report shall be submitted to the NRC prior to September 1, 1982, which summarizes the first five years of operating experience with the TMI-1 integrated surveillance program performed at a host reactor. If, at the time of submission of this report, it is desired to continue the surveillance program at a host reactor, such continuation shall be justified on the basis of the attained operating experience.

Bases ,

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a. Specifications 4.2.1 & 2 ensure that inservice inspection of ASMI Code Class 1, 2 and 3 components will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a(g).

Relief from any of the above requirements has been provided in writing by the NRC and is not a part of these technical specifications.

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, 8106110/07-

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