ML17309A268
| ML17309A268 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/25/1982 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17256A978 | List: |
| References | |
| NUDOCS 8206010610 | |
| Download: ML17309A268 (4) | |
Text
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ROCHESTER GAS AND ELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 YORK JOHN Ei MAIER Vice President TELEPHONE AREA cooE'Tie 546.2700 May 25, 1982 Director of Nuclear Reactor Regulation Attention:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Supplemental Information Steam Generator Evaluation Steam Generator Tube Rupture Incident R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
Our Steam Generator Evaluation, submitted on April 26,
- 1982, provided an evaluation of the Ginna steam generator including the results of inspections, a description of analysis and tests used to establish the tube failure mechanism, and a
summary of the repairs.
As discussed i'n the report, additional confirmatory test-ing was still in progress at the time the report was prepared.
Some results were presented to the NRC Staff during an April 30, 1982 meeting.
The additional testing has been completed and enclosed reports present the results.
The reports are:
Addendum 1, Laboratory Collapse Tests These tests were discussed in Sections 4.7.1 and 7.2.1 of our April 26, 1982 submitted.
2.
Addendum 2, Laboratory Fatigue Testing These tests were discussed in Sections 4.7.2 and 7.2.1.
of our April 26, 1982 submittal.
3.
Addendum 3, Phase II Metallurgical Examinations These tests were discussed in Section 4.4 of our April 26, 1982 submittal.
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Addendum 4, External Tube Loading Test This test was discussed in Section 7.2.2 and in Appendix C of our April 26, 1982 submittal.
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ROCHESTER GAS AND ELECTRIC CORP.
DATE May 25, 1982 Mr. Dennis M. Crutchfield SHEET NO.
The results of the testing do not alter the conclusions presented in our April 26, 1982 report and, therefore, should not alter the conclusions presented in NUREG-0916.
Ten copies of this letter and the enclosed reports are pro-vided.
Very truly yours, Jo n E. Maier Enclosures