ML20058L171

Ro:On 740318,excessive Leakages Past Inboard MSIV 2-80A & LPCI a Loop Check Valve AO 10-46A Reported.On 740321, During LLRT on B Core Spray Sys Pci Valves,Testable Check Valve AO 14-13B Found to Be Leaking Excessively

ML20058L171
Person / Time
Site:	Monticello
Issue date:	03/22/1974
From:	Larson C NORTHERN STATES POWER CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 9105090395
Download: ML20058L171 (2)

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NORTHERN STATES' POWER COMPANY

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,. Monticello, Minnesota 5536Z' Mamh 22,1974

/' 73 +N er, Regional Director Mr. J. G~.

Directorate o Regulator /* Opersticris j62 9.gygA-A -g Region.III o n-United States Atzmic Energy em=rission @\$ $ chyl

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799 Roosevelt Road

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Glen Ellyn, Illinois 61073 N' , ,

Dear Mr. Keppler:

ENTICEllD NJCEAR GENERATING PIAhT Docket No. 50-263 License No. DPR-22 - -

In discussions with Regulatory Operations personnel on March 21, 1974, it was agreed that during the present refueling outage, penetration and isol-ation valve leakage rates waich maai the acceptance criteria outlined in section 4.7.A.2.f. of the Technical Specifications will be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph to the Director of the Regional Regulatory Operations Office with a carbon copy to the Director of Licensing. These notification reports shal], to the extet possible, provide the infomation normally contained in the 10 day abnomal occurrence reports, as outlined in Technical Specification 6.7.B.1. Followp infomation, including corrective actions, will oe included in the primary containment leak rate test report.

This agroirent recognites the inpossibility of providing emplete infomation within 10 days during a refueling outage, and eWintes duplicative reporting.

In accordance with the above agrement, notification is hereby made that the total allowable testable penetration and isolation valve leakage rate specified by Technical 4ecification 4.7.A.2.f (2)(a) was exceeded when the total leakage through Inboard Main Steam Line Drain Isolation Valve, 10 2373, was found to be 502 SCFH (refer to letter fr a C E Larson to J G Keppler, dated March 18,1974). A detemination of the leakage past the redundant (outboard) isolation w Lve on the main steam drain line will be made following repair of the inboard u olation valve. -

On March 18, 1974, excessive leakages past Inboard Main Steam Isolation Valve 2-80A and LPCI "A" loop Check Valve 10 10-46A were s pud ed. The lealage rates measured for these two valves weit 70 SCFH and 28.6 SCFH respectively. On March 21, 1974, while perfoming a local leak rate test on the "B"' Core Spray System primary containment isolaticn valves, testable check valve, A014-13B, was found to be lealmg 397 SCFH. The redundant isolation valve in each of these three lines was found to have leakage within the carian allovable leakage for a single penetration or isolation valve as specified in Technical Specifications 4.7.A.2.f. (2)(b) and (c) .

9105090395 740322 CF ADOCK 05000263 2d(9 CF

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Corrective actims to be taken on the above idatified valves will be detemiral following an im+estigation into the cause of the excess leakages.

Yours very ,

GE w C. E, lars Plant Manager CELhnm cc: J F O' Leary, Directorate of Licmsing G Charnoff Mi=mta Pollution Control Agency Attn: E A Pryzina File . . _ .

Copies set by telecopier to Keppler and O'Imary

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