ML20004F725

Application for Amend to License DPR-50,consisting of Tech Spec Change Request 101 Re Refueling Interval Surveillance Extensions

ML20004F725
Person / Time
Site:	Three Mile Island
Issue date:	06/15/1981
From:	Hukill H METROPOLITAN EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20004F726	List: ML20004F725 ML20004F730
References
L1L-162, NUDOCS 8106220234
Download: ML20004F725 (2)

Text

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Metropolitan Edison Company Post Office Box 480 II L Middletown, Pennsylvania 17057 Writer's Cinct Dial Number Jun 15, 1981 LlL 162 e to Office of Nuclear Reactor Regulation O O'

Attn: John F. Stolz, Chief {f ,

Operating Reactors Branch No. 4 3./ -

U. S. Nuclear Regulatory Commission j JUti 2 g ;gg;,

u,s, %, ,,N B-Wasnington, D.C. 20555 -

Dear Sir:

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Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 e .

Docket No. 50-289 Technical Specification Change Request No. 101 Revision Attached please find revised pages 4-7, 4-39, 4-41, 4-44, 4-55, and 4-55b of TSCR No. 101 which requested extensions of refueling interval surveillances

• of various specifications. These changes were required because the surveill-ances could not be performed in our present mode, and would exceed the surveillance period prior to the start of Cycle 5.

Based on discussions between members of my staff and the TMI-l Project Manager, Mr. D. Dilanni, several modifications to TSCR No. 101 were discussed. Additionally, Met-Ed proposed deleting the requirement to perform the Emergency Loading Sequence test prior to testing the Reactor Building Cooling System test. The safety analysis and justification for this request is as follows:

Reason for Change -

The requested change provides needed scheduling flexibility in ECCS, reactor building cooling system and emergency powcr surveillar.ce testing without changing the surveillance requirements or operability requirements.

Safety Evaluation Justifying Change The existing surveillance requirements specify that the Emergency Loading Sequence and Automatic Power Transfer Test be performed successfully as a prerequisite to any system test of the emergency core cooling system or reactor building cooling system. These tests are scheduled to be performed on a re-fueling interval frequency. The order of testing is of no consequence as long as all required components are demonstrated to be operable during the appropriate time period.

Since demonstration of operability is required regardless of the order of testing, this change does not constitute an unreviewed safety question.

Metropolitan Ed: son Company is a Memoer of me General Pubhc Utikties System 56 .

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4 ' ' John F. Stolz,: Chief L1L 162 j The attached pages reflect the revised TSCR No.-101 pages as agreed to with Mr. D. DiIanni.

Sincerely, Director, MI-1 HDH:DCM:1ma Attachments cc: B.-H. Grier B. J. Snyder D. Dilanni

' H. Silver L'. Barrett k

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