B10737, Submits Results of Leakage Measurements Completed on 830407, Per Amend 83 to License DPR-65 Re Deferred Inservice Insp Requirements.Steam Generator Leakage Rates Acceptable

Submits Results of Leakage Measurements Completed on 830407, Per Amend 83 to License DPR-65 Re Deferred Inservice Insp Requirements.Steam Generator Leakage Rates Acceptable

ML20073Q025
Person / Time
Site:	Millstone
Issue date:	04/19/1983
From:	Counsil W NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	Clark R Office of Nuclear Reactor Regulation
References
B10737, TAC-49905, NUDOCS 8304280090
Download: ML20073Q025 (2)

Text

, .o' General Offices e Seldon Street, Berlin, Connecticut C""**"'"'""

P.O. BOX 270 q

.". "w,, ,o. co., A HARTFORD. CONNECTICUT 06141-0270 L t  ;  %'O Z",",%%"", (203) 666-69M April 19,1983 Dccket No. 50-336 B10737 Director of Nuclear Reactor Regulation Attn: Mr. Robert A. Clark, Chief Operating Reactors Branch //3 U. S. Nuclear Regulatory Commission Washington, D. C. 20555

References:

(1) R. A. Clark letter to W. G. Counsil dated, March 16,1983, transmitting Amendment No. 83 to DPR-63.

(2) W. G. Counsil letter to R. A. Clark dated, March 14,1983.

(3) W. G. Counsil letter to R. A. Clark dated, February 10,1983.

Gentlemen:

Millstone Nuclear Power Station, Unit No. 2 License Amendment No. 83 By Reference (1), the NRC Staff issued Amendment No. 83 to Operating License No. DPR-65 for Millstone Unit No. 2. This amendment deferred steam generator inservice inspection requirements of Technical Specification 4.4.5.1.3.c.1 to the 1983 refueling outage. The purpose of this letter is to inform the Staff of the results of the leakage measurements conducted following startup from the March 1,1983 outage.

Leakage measurements completed at steady state operating conditions on April 7,1983 indicate total reactor coolant system (RCS) leakage of 0.1 gpm.

Primary-to-secondary leakage rate measurements for both steam generators have been obtained using the secondary side gross activity determination method. It has been determined that the primary-to-secondary leakage in Steam Generator No. I has been reduced significantly. Revised base line primary-to-secondary leakage rates for each steam generator are:

Steam Generator No. I less than .005 gpm j[

Steam Generator No. 2 No detectable leakage 8304280090 830419 PDR ADOCK 05000336 P PDR

,. m This informati$n provided 'in fulfillment of the reporting requirements of .

O-f Technical Specification 3/4.7.1.4, Table 4.7-2.

. Current secondary side' activity measurements are thought to: be residual long 7.'

lived radioisotopes released from the sludge pile. Secondary side gross activity measurements in Steam Generator No. 2 are at mdetectable levels. - The g t' discrepency between the new baseline value reported herein for Steam Generator l<," . No. 2 and the reported baseline value of .031 gpm in Reference (3) is believed to be due to activity carry over from the leak in Steam Generator No. I_via the

. main feedwater system. NNECO is also evaluating data obtained from the steam

. jet air ejector which will be used to confirm the leakage measurements obtained by the secondary side gross activity method.

An inspection of RCS valves 2-51-247 and 2-RC-405 at HOT STANDBY revealed no leakage. Both of these valves were known sources of leakage prior to _the March 1,1983, outage and maintenance was performed during the shutdown to mitigate the leakage. In addition two reactor coolant pump seals were' replaced during the outage.

The prompt response of the Staff to expedite this matter is appreciated.

Significant savings to the company and its rate payers were realized due to the efforts of the Staff in their review and disposition of the license amendment request.

Very truly yours,

. NORTHEAST NUCLEAR ENERGY COMPANY

. /[(/)1& '

. W. G. Counsil

( Senior Vice President i

r 1

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