ML20054C168

Ro:On 820323,during Reactor Trip from Full Power Operating Conditions,Baseline primary-to-secondary Leakage Rates Increased.Caused by Increased Steam Generator Activity Due to Trip.Equilibrium Operation in Mode 1 Achieved on 820326

ML20054C168
Person / Time
Site:	Millstone
Issue date:	04/07/1982
From:	Counsil W NORTHEAST NUCLEAR ENERGY CO.
To:	Clark R Office of Nuclear Reactor Regulation
References
A02357, A2357, TAC-48062, NUDOCS 8204200169
Download: ML20054C168 (2)

Text

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April 7, 1982 g Docket No. 50-336 p D A02357 RECEIVED 9 g, ~~

APR19 m Director of Nuclear Reactor Regulation Attn: Mr. Robert A. Clark, Chief

( saem las Operating Reactors Branch #3 g //

U. S. Nuclear Regulatory Commission _ 4 Washington, D.C. 20555

Reference:

(1) R. A. Clark letter to W. G. Counsil, dated March 5, 1982, transmitting Amendment No. 73 to Facility Operating License No. DPR-65.

Centlemen:

Millstone Nuclear Power Station, Unit No. 2 Baseline Primary-to-Secondary Leakage Rates In accordance with the reporting requirements of Technical Specification 3/4.7.1.4, Table 4.7-2, as issued in Reference (1) for Cycle 5 operation of Millstone Unit No. 2, Northeast Nuclear Energy Company (NNECO) hereby provides the following information.

The primary-to-secondary leakage rate in each steam generator has been determined to be:

0.012 gpm Steam Generator No. 1

<0.005 gpm Steam Generator No. 2 These leakage rate measurements were complete 3 in Mode 1 during steady state operating conditions at a power level of approximately 2700 MW(th).

The plant achieved equilibrium operation in Mode 1 on March 26, 1982.

Millstone Unit No. 2 tripped from full power operating conditions on March 23, 1982. As a result of this trip, the activity measured in the steam generators increased resulting in a change in the in-dicated leakage rate. NNECO performed additional measurements of the primary-to-secondary leakage rates following this Plant trip in an effort to trend these variations.

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The results._f the additional leak rate measurements confirm that an increase in the indicated leak rate will occur after a Plant trip wi subsequent decrease to a lower value upon return to steady sto.e operation. These additional leak rate determinations clearly demonstrate the effects of a Plant trip on the indicated primary-to-secondary leakage rate as well as the need to conduct leak rate measure-ments during periods of steady state, equilibrium operating conditions.

We trust you find this information satisfactory.

Very truly yours, NORTilEAST NUCLEAR ENERGY COMPANY A4Ld4 W. t. Counsil Senior Vice President

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