ML20084B098

Ao:On 730511,during Pressurization,Preparatory to Starting Reactor Coolant Pumps for Performance of Hydrostatic Leak Test of Rcs,Leak Apparently Occured in Valve 204B Located in Loop 21 Charging Line.Caused by Defect in Stud Holes

ML20084B098
Person / Time
Site:	Indian Point
Issue date:	05/14/1973
From:	Caldwell W CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20084B088	List: ML20084B084 ML20084B098
References
NUDOCS 8304060114
Download: ML20084B098 (3)

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.2 frying Place. New York, N Y 10003 May 14, 1973 Jamen P. O'Reilly, Director kegulatory Operations, Region I S.S. Atomic Energy Commission 470 Broad Street Newark, New Jersey 07102 Ret Indian Point Unit No. 2 AEC Docket No. 50-247 Facility Operating License DPR-26

Dear Mr. O'Reilly:

In accordance with the requirements of Technical Specification 6.6.1.B, we wish to inform you of an abnormal occurrenco which was identified on May 11, 1973 at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />. During pressuriza-tion preparatory to starting reactor coolant pumps for the per-formance of a hydrostatic leak test of the Reactor Coolant System, prior to initial criticality, a leak was apparent in Valve Subsequent Number 204B which is located in the charging line to Loop 21.

investigation indicated that the leakage was apparently due to a defect in the area of the stud holes permitting reactor coolant to seep into two of the stud holes and from there into containment atmosphere.

Since the leak was due to an apparent defect, the valve is being replaced. The replacement valve meets all of the requirements of codes and standards applicable to the design and procurement of equipment as outlined in the Indian Point Unit No. 2 FSAR. After replacement of the valve, the required hydrostatic test of the re-actor coolant system will be performed to insure its integrity.

The valve that is being removed from the reactor coolant system boundary will be subjected to a metalurgical examination in order to determine the exact cause of the leakage and the need for any additional action.

In accordance with the requirements of Technical Specification 6.2., appropriate notification of the Station Manager, the Manager of the Nuclear Power Generation Department, and the Chairman of the Nuclear Pacilities Safety Committee has taken place. Mr. A.

Fasano of your office was also notified on May 12, 1973 of the occurrence.

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, o The safety implications of the occurrence were olight sinco, a) o the leakage was minuto and we).1 within the Inakeup capability of the CVCS, b) the plant was in cold shutdown condition, and c) leakage was into the containment. atmosphere and therefore if the leaking fluid had been radioactive, which it was not, it would i

have been detected and conteined with no exposure to the health and saftsty of the public.

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The required written report will be nubmitted within ten days, i i V9ry truly yours,  ;

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\ .fwr u,y . t. (?st*b % 4 4' WilJiam n. Caldwe.1, 1 sir.

Vice President r L

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Licensee: Consolidated Edison Company U H. D. Thornburg, can Docket No.: 50-247 Chief, FS6EB Abnonnal Occurrence: Report dated May 14, 1973

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DR Central Files (1) em The. attached report from the subject licensee is t Rec,ulat ory Standards 3)

Dir. of Licensine (13 i forwarded in accordance with RO Manual Chapter 1000.

T; m.e . .a ,,r .o a nats navians The action taken by the licensee is considered exft appropriate. Followup will be performed during the next inspection a's appropriate. Copfes of a wo u m.... .. a c.,, new.nas the report have been forwarded to the PDR, Local PDR, NSIC, DTIE and State representatives. The E. J. Brunner, RO:I licensce will submit a 10 day written report to PectE tal DATE 5/16/73 Licensing.

W$t 0, Min 5:04 FOR AColfson.L RtuAnKS . GPC : .9110 - 445-469 9

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