ML18085A397
| ML18085A397 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/19/1980 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8012230259 | |
| Download: ML18085A397 (2) | |
Text
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- Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 December 19, 1980 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. Frank J. Miraglia, Chief Licensing Branch 3 Division of Licensing Gentlemen:
CONTAINMENT BOUNDARY FRACTURE TOUGHNESS NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 r--.
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PSE&G hereby submits additional information in response to your letter dated November 17, 1980 requesting fracture toughness data for the Al06 grade C piping used in the Steam Generator Feedwater System from the connection to the proc-ess pipe at the feedwater penetrations to the stop check isolation valves.
The information that had been available on the reference c..-,:_:
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subject has already been addressed in our letter-of December 1, 1980.
In continuing our effort to obtain the information re-quested, we visited U.S. Steel Corp. in Lorain, Ohio on December 15, 1980.
They confirmed that no fracture tough-ness data existed for 3 out of 4 feedwater lines in ques-tion.
On December 16~ 1980 we visited Phoenix Steel Corp.
in Phoenixville, Pennsylvania, the manufacturer of the bal-ance of pipe for the portion of the feedwater system in question.
They also confirmed that no fracture toughness data existed for this material.
However, we reviewed proprietary information at both mills that indicated that their procedures called for a finishing process in the range of normalizing temperatures.
PSE&G believes that the information provided in our December 1, 1980 submittal and subsequent visits to the steel mills sup-ports our contention that the integrity of the containment boundary with respect to brittle fracture and rapidly propa-gating fracture will be maintained for the normal operating, maintenance, testing and postulated accident conditions, and is therefore in compliance with GDC-51.
The Energy People 95-0942
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"_,bi rector of Nuclear 12/19/80 Reactor Regulation Shouid you have any questions in this regard, do not hesi-tate to contact us.
CC:
Mr. Leif Norrholm Salem Resident Inspector BJ05 1/2 Very truly yours,
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R. L. Mittl General Manager -
Licensing and Environment