ML19210D484
| ML19210D484 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 10/29/1979 |
| From: | William Cahill CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | Brunner E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML19210D474 | List: |
| References | |
| NUDOCS 7911270150 | |
| Download: ML19210D484 (2) | |
Text
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William J. Cahill, Jr.
Vice Pres cent Censolidated Edison Company of New York. Inc.
4 lrving Place. New York, N Y 10003 Telephone (212) 460-3819 October 29, 1979 Indian Point Station Docket No. 50-247 Mr. Eldon J. Brunner, Chief Reactor Operations and Nuclear Support Branch Office of Inspection and Enforcement U.
S. Nuclear Regulatory Commission, Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Dear Mr. Brunner This refers to Inspection 50-247/79-09 conducted by Mr. T. Rebelowski, Resident Inspector, on April 29 -
August 18, 1979, of activities authorized by NRC License No. DPR-26 at IndianPoint Station.
Your October 4, 1979, letter stated that it appeared that certain of our activities were not conducted in full compliance with NRC requirements, as set forth in the Notice of Violation enclosed therewith as Appendix A.
Our response to these items of noncompliance is pre-sented in the following paragraphs.
Item I
Response
This item resulted from a misinterpre-tation that the administrative order only required the looging of jumper installation on safety related equip-ment.
The turbine bearing lift pump control circuit is required for main turbine startup and is clearly not safety related.
To preclude future items of a similar nature, responsible personnel have been reinstructed in the requirements of the Station Administrative Order for use of jumpers.
1396 059 7911270
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- *.e ITEM II
Response
The subject valve is one of the three valves in series providing isolation of the containment building pressure relief line.
The valve on either side of the subject valve had been leak rate tested at the required frequency.
Due to an improper interpretation of the testing requirements, the valve in question, although pressurized during the test sequence, was not checked for leak rate.
The subject valve was satisfactorily tested for leak rate on August 21, 1979.
In order to prevent recurrence, the procedures for leak rate testing of these valves have been revised to include leak rate testing of the subject valve.
Very truly yours
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CC:
Mr. T. Rebelowski, Resident Inspector U.
S. Nuclear Regulatory Commission P.
O.
Box 38 Buchanan, New York 10511 l396 UhD