ML17250A451
| ML17250A451 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/08/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | White L ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| NUDOCS 8007280142 | |
| Download: ML17250A451 (6) | |
Text
Docket No. 50-244 JUL 5 580 Hr, Leon D. White. Jr.
Vice President Electric 8 Steam Generation Rochester Gas and Electt ie Corp.
89 East Avenue Rochester, New York 14649
Dear Hr. White:
DISTRIBUTION'ocket NRC PDR Local PDR 2 TERA NSIC NRR Reading ORB ¹5 Reading DEisenhut RPurple RTedesco TNovak GLainas JOlshinski DCrutchfield SNowicki HSmith OELD OIaE (3)
ACRS (16)
Gray File Xtra Cy (6)
Enclosed for your information is the staff's evaluation of the results of your April 1980 steam generator inspection at the R.E. Ginna Nuclear Power Plant.
We agree with your evaluation and conclusions that the R. E. Ginna plant mould return to power after the inspection,and we concur with your proposed mid-cycle inspection.
We request that you submit your inspection program for our information and comments 40 days prior to the scheduled mid-cycle shutdown for steam generator inspection.
Should you have any questions regarding our evaluation, please contact usi
, Sincerely, prigiml signe1i bV
Enclosure:
Steam Generator Inspection Evaluation Report cc:
See page 2
Dennis'M: 'Crutchfield, Chief Operating Reactors Branch ¹5 Division of Licensing
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Docket No. 50-244 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 July 8, 1980 Mr. Leon D. White, Jr.
Vice President Electr ic 8 Steam Generation Rochester Gas and Electric Corp.
89 East Avenue Rochester, New York 14649
Dear Mr. White:
Enclosed for your information is the staff's evaluation of the results of your April 1980 steam generator inspection at the R.E. Ginna Nuclear Power Plant.
We agree with your evaluation and conclusions that the R.E.
Ginna plant could return to power after the inspection and we concur with your proposed mid-cycle inspection.
We request that you submit your inspection program for our information and comments 40 days prior to the scheduled mid-cycle shutdown for steam generator inspection.
Should you have any questions regarding our evaluation, please contact us.
Si
- erely,
Enclosure:
Steam Generator Inspection Evaluation Report cc:
See page 2
Dennis M. Crutchfield, ief Operating Reactors Branch 85 Division of Licensing
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Mr. Leon D. White, Jr.
July 8, 1980 cc w/enclosure:
Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby & MacRae 1757 N Street, N.
W.
Washington, D. C.
20036 Mr. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Rochester Comnittee for Scientific Information Robert E. Lee, Ph.D.
P. 0.
Box 5236 River Campus Station Rochester, New York 14627 Jeffrey Cohen New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza
- Albany, New York 12223 Director, Technical Development State of New York Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontari o 107 Ridge Road West
- Ontario, New York 14519 Director, Technical Assessment Division Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall g2 Arlington, Virginia 20460 U. S. Environmental P rotect i on Agency Region II Office ATTN:
EIS COORDINATOR 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,
Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Coomission Washington, D. C.
20555 Dr. Richard F. Cole Atomic Safety and Licensing Board Programs U. S. Nuclear Regulatory Comnission Washington, D. C.
20555 Dr. Emneth A. Luebke Atomi c Safety and Licens ing Board U. S. Nuclear Regulatory Comnission Washington, D. C.
20555 Mr. Thomas B. Cochran Natural Resources Defense Council, Inc.
1725 I Street, N.
W.
Suite 600 Washington, D. C.
20006
R.
E.
GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 APRIL 1980 STEAM GENERATOR INSPECTION EVALUATION REPORT In response to our request,.Rochester Gas
& Electric Corporation (RGE) submitted a report and an evaluation, dated April 29.
- 1980, on the steam generator inspection.
The inspection was conducted on both steam generators, designated S/G A and S/G B, during the April 1980 scheduled refueling and maintenance
- outage, using multifrequency eddy current techniques (ECT) to quantify tube defects.
This is the third year multifrequency eddy current examinations were used at Ginna.
The results of these examinations are summarized in Table I:
TABLE I - R. E.
GINNA UNIT NO.
1 1980 EDDY CURRENT INSPECTION RESULTS Steam Generator Area 8 of Tubes
-Y E
C Location S/G A
Hot Leg (100%)
1 tube
- ~50%
2" above top of tubesheet S/G B
Cold Leg Hot Leg (25%)
(100%)
None 1 tube
- <20%
w/in thickness of tubesheet 1 tube 1 tube 1 tube 5 tubes 2 tubes 1 tube 1 tube 18 tubes 39% 49%o 59% 69%o 79/o 80 89%o 90 1 00%
- Under Crevice Attack Cold Leg (25%)
1 tube
- 41%
1 tube
- 46/
1 tube 36%
None 2" above tubesheet 24" above, tubesheet 24" above tubesheet
These crevice indications can be divided into two categories:
the first 13 indications were identified at frequencies of 400 KHZ differential, 200 KHZ differential, 100 KHZ differential, and 100 KHZ absolute.
The remaining 18 indiciations were detected at a frequency of 100 KHZ absolute only.
These later indications appeared as abnormal vertical channel signals on the brush strip chart recorded that resembled the signals at 100 KHZ absolute of the 13 tubes found at the other frequencies.
Therefore, these 18.tubes are con-sidered to be under Intergranular Attack (IGA) inside the crevices.
As shown in Table I, the crevice indications were identified only in the hot leg side of the "B" steam generator and not in the "A" steam generator.
As shown in Table 1,
31 ECT indications. were found within.the tubesheet (within the thickness of the tubesheet).
Host, of the crevice indications were located 15" and 18" above the tube bottom.
In addition, one tube in the hot leg side of the "A" steam generator and three tubes. in the hot leg side of the "B" steam generator were found with defects above the tubesheet.
Although the Ginna Unit No.
1 technical specification require tube plugging if the indication is 405 or greater, all.31 tubes with crevice indications in Table I and the four defective tubes above the tubesheet were plugged.
The licensee believes that the four defects located above the tubesheets of both "A" and "B" steam geoerators are small volume defects.
Eddy current tapes for these tubes from previous inspections are being re-evaluated to establish the rate of through=wall penetration.
We do not attach any safety significance to these small volume defects, particularly in view of the small number of affected tubes suggesting a minimal level of tube degradation above the tubesheet.
In view of the fact that all the crevice indications within the tubesheet were located in the "B" steam generator, the licensee removed two tubes in the hot leg side and one tube in the cold leg side of the "B" steam generator for further laboratory examination.
The examination is being conducted in coopera-tion with the Steam Generators Owners Group.
The final report on the results of these tube examinations will be provided in about two months.
This report should contain valuable information concerning the damage mechanism.
Based on the review of licensee's inservice inspection, remedial action, preventive tube plugging, flushing, water chemistry control and leakage rate limit, we concur with the licensee that there is reasonable assurance that R. E. Ginna is safe to return to power operation.
We concur with the proposed mid-cycle inspection and request that the licensee submit their inspection program for comments 40 days prior to the scheduled shutdown for steam generator inspection.