ML17256A835
| ML17256A835 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/14/1982 |
| From: | Lyons J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17256A836 | List: |
| References | |
| LSO5-82-04-042, LSO5-82-4-42, NUDOCS 8204260125 | |
| Download: ML17256A835 (6) | |
Text
rpo LS05-82-04-042 April 14, 1982 S
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'~4'>>e FACILITY:
R. E. Ginna Plant LICENSEE:
ROCHESTER GAS S ELECTRIC CORPORATION
SUBJECT:
SUMMARY
OF MARCH 23, 1982 MEETING WITH RG&E TO DISCUSS THE
,THE RECOVERY'CTIVITIES AT THE R. E.
GINNA PLANT On Tuesday, March 23, 1982, members of the NRC staff met with representatives of Rochester Gas and Electric Corporation (RGSE) and Westinghouse to discuss the status of repair activities proposed for the Ginna Plant.
The purpose of this meeting was to obtain the NRC's approval for the removal of 24 structurally degraded tubes in the RB" steam generator.
A copy of the slides used by RGSE and Westinghouse during the presentation and the atItendence list are enclosed.
To obtain metallurgical data needed for evaluation of'he failure mechanism, RGSE proposed the removal of selected tube samples through two access ports drilled in the side of the steam generator.
Following a meeting with the licensee and Westinghouse, NRR approved this proposal on March 1, 1982.
Seven tube samples, including the ruptured tube, have been removed and sent to Westinghouse for metallurgical examination.
Results of the examinations indicate that the two tubes immediately outboard of the ruptured tube, which were severed gust above the tube sheet, and the ruptured tube all show signs of metal to metal wear.
The ruptured ociorriid ak~ona".'qP'-tht"Led r areas.
The licensee indicated that photomicrography of the rupture showed that the failure was a ductile tear occurring after the loss of approximately 901 of the tube wall thickness.
The staff is obtaining a number of samples of the tubes for independent laboratory examination.
Westinghouse has developed a failure mechanism evaluation program that will include investigation of various influences such as mechanical loads.
gross fluid loads, axial loads and local fluid loads.
The program also includes a historical information review, initial perimeter tube investigation, laboratory examination of removed tube sections, model testing, laboratory callapse and fatigue. testing, and field testing and examination.
The investigation program is designed to provide information regarding other possible failure mechanisms and is not restricted to a single postulated cause.
OFFICE/
SURNAME/
OATE II 8>04260
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a April 14, 1982 The remainder of the repair plan calls for the restoration of the three tubes ad)acent to the ruptured tube that were pr eventatively plugged following the January 25, 1982 incident and for flushing and removal of all foreign objects and tubing fragments from the "B" steam generator.
Upon completion of the repairs, eddy current examinations of tubes adjacent to the repairs and a secondary side video inspection will be performed.
An acoustic monitoring system for both steam generators will be installed to detect any further loose parts during operation.
Following a caucus among the NRC staff present RGSE received permission to remove from the "B" steam generator another 17 tubes that showed signs of external damage.
This would bring to 24 the total number of tubes removed from the "B" generator since January 25, 1982.
This number includes the tubes already removed for metallurgical eamples and the three tubes that were severed gust above the tube sheet and gust below the first support plate.
Only the sections of the tubes between the tube sheet and the first support plate wi'Il be removed.
Ilestinghouse evaluation shows that there will be no adverse effects on the steam generator or remaining tubes caused by the removal of this number of tubes..
The licensee's schedule calls for completion of work in the steam generator related to the rupture in early April, the submittal of a report on the event by April 16, 1982, and pro)ected restart in early May.
The staff will provide a comprehensive Safety Evaluation prior to restart.
Original signed by
Enclosures:
As stated cc w/enclosures:
See next page James E. Lyons, Prospect Manager Operating Reactors Branch 85 Division of LicensiItg OFFICEI SURNAME/
DATE0 NRC FORM 318 {10.80) NRCM 0240 DL:
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Mr. John E. Maier CC Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby and MacRae 1333 Net Hampshire
- Avenue, N.
W.
Suite 1100 Washington, D.
C.
20036 Mr. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 U. S. Environmental Protection Agency Region II Office ATTN:
Regional Radiation Representative 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,
Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Ronald C. Haynes, Regional Administrator Nuclear Regulatory Commission, Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Resident Inspector R.
E. Ginna Plant c/o U. S.
NRC 1503 Lake Road
- Ontario, New York 14519 Director, Bureau of Nuclear Operations State of New York Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Supervisor of the Town of Ontario 107 Ridge Road West
- Ontario, New York 14519 Dr. Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. Richard F. C".le Atomic Safety and Licensing Board U.
S. Nuclear Regulatory Commission Washington, D. C.
20555
ATTENDENCE LIST Meeting of March 23, 1982 JLyons HKister GLainas TIppolito DEisenhut CMcCracken JRajan DFischer Nohnston WHazelton JHutton ACurtis RMecredy JMaier DCrutchfield JRoberts RSmith PCronin JHoon FSchwoerer DWhite MKumada MWert
'Kamimura GFar ber WSpezial etti Leyse
'Vantesiaar NRC'RC HRC NRC NRC NRC NRC ACRS HRC HRC RG&E RG&E RG&E RG&E NRC HYS-PSC'G&E Nixon, Hargrave (RG&E)
RG&E SHUPPS (RG&E-NSARB)
Westinghouse Kansas Electric Power Co., Inc.
RG&E ANRE, MITI GRS/Germany Westinghouse NSAC Westinghouse