ML102530249
| ML102530249 | |
| Person / Time | |
|---|---|
| Site: | Indian Point |
| Issue date: | 05/08/1991 |
| From: | Bram S Consolidated Edison Co of New York |
| To: | NRC/IRM |
| References | |
| IEB-89-001, IEB-89-1, NUDOCS 9105170117 | |
| Download: ML102530249 (2) | |
Text
Stephen B. Brain Vice President Consolidated Edison Company of New York, Inc.
Indian Point Station Broadway & Bleakley Avenue Buchanan, NY 10511 Telephone (914) 737-8116 Document Control Desk US Nuclear Regulatory Mail Station P1-137 Washington, DC 20555 May 8, 1991 Re:
Indian Point Unit No. 2 Docket No. 50-247 Commission
SUBJECT:
NRC Bulletin No. 89-01:
Failure -of Westinghouse Steam Generator Tube Mechanical Plugs
REFERENCE:
Consolidated Edison letter dated June 15, 1989, same subject.
The reference letter contained our response to the subject NRC Bulletin in which we identified that corrective actions would be implemented in 1991 for steam generator tube plugs of material heats acknowledged by Westinghouse to be suspect.
We had intended to install a leakage limiting device similar to those provided by Westinghouse for all suspect plugs.
- However, in one instance, this concept was not feasible.- In
- 1986, at the time of original plug installation into tube R45C47 in steam generator 24, the plug expander (mandrel) was wedged into the plug and broke during retrieval efforts. The mandrel has remained in the steam generator since then.
Since the tube is located in the outer periphery of the tube
- sheet, it is not presently feasible to remove the mandrel by robotic means. Manual removal would be man-rem intensive.
Due to similarities in configuration between the wedged mandrel and the Westinghouse plug -
in -
plug design (PIP) a study was performed to determine whether the mandrel would function similar to a PIP.
This study culminated in a safety evaluation concluding that the mandrel is functionally equivalent to a PIP as a leakage limiting device and poses no additional safety concerns.
'10.5 1701 17 9P1 C:)5)
PDR FR
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Should you have any questions concerning this matter, please contact Mr. Charles W. Jackson,' Manager, Nuclear Safety and Licensing.
Very truly yours, cc:
Mr. Thomas T. Martin Regional Administrator -Reg ion I US Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Francis J. Williams, Jr., Project Manager Project Directorate I-1 Division of Reactor Projects I/II US Nuclear Regulatory Commission Mail Stop 14B-2 Washington, DC 20555 Senior Resident Inspector US Nuclear Regulatory Commission P0 Box 38 Buchanan, NY 10511