ML17252A851
| ML17252A851 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 02/01/1974 |
| From: | Cobean W Consolidated Edison Co of New York |
| To: | O'Leary J US Atomic Energy Commission (AEC) |
| References | |
| Download: ML17252A851 (2) | |
Text
iRegU1ato'fy Docket Fife,,..
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Consolidated Edison Company of New York, Inc.
~~
I, 4 Irving Phi'ce, New York, NY 10003 Re:
Mr. John F. O'Leary, Director Directorate of.Licensing U. S. Atomic Energy Commis*sion Off ice of Regulations Washington, D. c.
20545
Dear Mr. O'Leary,
February 1, 1974 Indian Point Unit No. 2 Facility Operating License DPR-26 A.0.-4-2-3 The following report is provided pursuant to the requirements of Section 6~12.2(a) of the Technical Specifications to Facil-ity Operating License No. DPR£26.
Following the completion of repairs associated with the November 13,* 1973 feedwater line break incident, an inspection of all
- Bergen-Paters.on hydraulic shock and sway arrestors (snubbers) located in the vapor containment was performed.
This inspection was completed on January 18, 1974 and of the approximately 350 snubbers located in the containment, two (2) did not meet the established criterion for operability; that
. i~, the accumulator oil level plunger was more than one inch below the "EXT" mark.
- one of the above two snubbers (SR-1040) is located on the com-ponent cooling water return line (Line No. 14) from upper bear-ing cooler of No. 23 reactor coolant pump and the other (SR SR3) is located on the secondary blowdown line (Line No. 48).
from No. 24 steam generator.
( I I.-
The two defective snubbers* which have been replaced with spares are being disassembled for inspection in an effort to determine the cause of the problem.
Presently, we plan to periodically inspect all of the snubbers inside of the containment building.
We further intend to replace all the existing millable gum
- so~
- .. ~,..
~~
Mr. John F. O '-Leary 2 -
February l~ 1974 Re:
Indian Point Unit No. 2 Facility Operating License DPR-26 A.0.-4-2-3 polyurethane seals on these snubbers with seals recommended by the manufacturer based on the temperature environment that the seals will experience.
The replacement will be conducted on a progressive schedule that is presently being discussed with the A.E.C. Regulatory Staff.
We believe our program for inspections of the snubbers and replacement of their seals together with a further investi-gation into the two instances of low oil level will signif i-cantly reduce or eliminate such maintenance actions required for the snubbers and remove any resultant concern that such problems with snubbers might affect the performance of their required safety function.
Very truly yours,
~~o~J~ber Nuclear Power Generation cc:
Mr. James P. O'Reilly