ML20076G303

Ro:On 830729,review of Log Sheets Determined Isolation Valve Seal Water Sys Violated Tech Specs.Corrective Action Taken to Assure Locally Indicated Pressure on Tank Maintained Per Tech Specs

ML20076G303
Person / Time
Site:	Indian Point
Issue date:	08/01/1983
From:	Christopher Jackson CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8308310095
Download: ML20076G303 (2)

Text

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b s Chcrfes C. Jackson Vce Prescent I

t Cons & dated Ed: son Company ci New v ork. Inc Indian Point Station

, Broadway & Bieakley Ave.,

Buchanan, NY 10511 Tetephor'e (914) 737-8116 Date: August 1, 1983

) Re: Indian Point Unit No. 2 Docket No. 50-247 1

Dr. Thmas E. Murley, Regional Administrator

! Region I U.S. Nuclear Regulatory Cmmission

! 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Dr. Murley:

i In accordance with the Tu:hnical Specifications of Facility Operating License No. DPR-26, the following confirms notification on July 29, 1983 to Mr. Thcmas Kenny of your office, by Mr. John Basile and Mr. Michael Blatt

, of Consolidated Edison of a potential Reportable Occurrence. 'Ihis event is the type defined in Technical Specification, Section 6.9.1.7.

, Con Edison has been conducting a program to review and upgrade its l operating procedures and checkoff lists. On July 29, 1983 as a result of plant staff review of non-licensed operator log sheets we determined that i the identification of the operating status of the Isolation Valve Seal Water System tank did not adequately correspond to the requirements of Technical Specification 3.3C.l.b. Our review back through 1982, however, indicates that when the unit was in power operation, the equivalent pressure, including the effective elevation head, assured that the j Technical Specification 52 psig was available at the delivery point to the isolation valves.

Tm wdiate corrective action was taken to assure that the locally indicated pressure on the tank is maintained consistent with the Technical Specification without taking credit for the elevation head. In addition, i

t the schedule for the ongoing procedure review program was revised to expedite review, and revise as necessary, the non-licensed operator log i

sheets. 'Ihis revised review schedule was inplemented July 29, 1983 and is expected to be cmpleted approximately August 5,1983.

i

! Additional information associated with this review of non-licensed t

operator logs will be provided in a supplemental report.

l Con Edison believes that this report also satisfies the requirements of 10 CFR Part 21.

Very trul Ys, CMI:ah 4 cc: List Attached Y

8308310095 830801 gDRADOCK 05000247 (Fl 1 d PDR

c ,.

.C .~ $

cc: Mr. William Mcdonald, Director (2 copies)

Office of Management Information and Program Control c/o Distribution Services Branch, DDC, AD4 U. S. Nuclear Regulatory Ca mission Washington, D. C. 20555 Mr. T. Foley, Senior Resident Inspector U. S. Nuclear Regulatory Ca mission P. O. Box 38 Buchanan, New York 10511 Mr. T. Kenny, Senior Resident Inspectcr U. S. Nuclear Regulatory Cm mission P. O. Box 66 BuchaInn, New York 10511

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