ML17332B017
| ML17332B017 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/20/1995 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| References | |
| GL-95-03, GL-95-3, TAC-M92235, TAC-M92236, NUDOCS 9511270146 | |
| Download: ML17332B017 (4) | |
Text
s' November 20,
~,-95t' Hr.
E.
E. Fitzpatrick, Vi'ce President Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, OH 43215 n
SUBJECT:
REQUEST FOR ADDITIONAL'INFORMATION',DONALD G.
COOK NUCLEAR PLANT UNITS 1
AND 2, CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES, GENERIC LETTER 95-03 (TAC NOS.
H92235 AND H92236)
Dear Hr. Fitzpatri ck:
On April 28,
- 1995, the U.S. Nuclear Regulatory Commission, issued Generic Letter (GL) 95-03, "Circumferential Cracking of Steam Generator Tubes," which requested addressees to evaluate recent operating experience related to circumferential cracking, justify continued operation until the next scheduled steam generator tube inspections, and to develop plans for the next steam generator tube inspections.
The staff has reviewed your response for D.C.
Cook Units 1 and 2 dated June 27, 1995.
As a result of the review of your
- response, the staff has identified areas for which additional information and/or clarification is needed.
The enclosure to this letter contains the information needed for the staff to complete its review of your response to GL 95-03.
Please provide your response within 30 days from the receipt of this request for additional information.
This request is within the original reporting burden for information collection of 350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> covered by the Office of Management and Budget clearance number 3150-0011, which expires July 31, 1997.
If you have any questions on these items please contact me at (301) 415-3017.
Sincerely, Docket No. 50-315 and 50-316 cc:
See next page Original signed by John B. Hickman, Project Manager Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information DISTRIBUTION:
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Mr. E.
E. Fitzpatrick Indiana Michigan Power Company CC:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall P.O.
Box 818 Bridgman, Michigan 49106 Al Blind, Plant Manager Donald C.
Cook Nuclear Plant 1 Cook Place Bridgman, Michigan 49106 U.S. Nuclear Regulatory. Commission Resident Inspector's Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.
W.
Washington, DC 20037 Mayor, City of Bridgman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3423 N. Logan Street P. 0. Box 30195
- Lansing, Michigan 48909 Donald C.
Cook Nuclear Plant Mr. S.
Brewer American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43215 April 199$
RE(VEST FOR ADDITIONAL INFORMATION DONALD C.
COOK UNITS I AND 2 CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES 1.
During the Maine Yankee outage in July/August
- 1994, several weaknesses were identified in their eddy current program as detailed in NRC Information Notice 94-88, Inservice Inspection Deficiencies Result in Severely Degraded Steam Generator Tubes".
In Information Notice 94-88, the staff observed that several circumferential indications could be traced back to earlier inspections when the data was reanalyzed using terrain plots.
These terrain plots had not been generated as part of the original field analysis for these tubes.
For the rotating pancake coil (RPC) examinations performed at your plant at locations susceptible to circumferential cracking during the previous inspection (i.e., previous inspection per your Generic Letter 95-03 response),
discuss the extent to which terrain plots were used to analyze the eddy current data.
If terrain plots were not routinely used at locations susceptible to circumferential cracking, discuss wh'ether or not the RPC eddy current data has been reanalyzed using terrain mapping of the data.
If terrain plots were not routinely used during the outage and your data has not been reanalyzed with terrain mapping of the data, discuss your basis for not reanalyzing your previous RPC data in light of the findings at Maine Yankee.
Discuss whether terrain plots will be used to analyze the RPC eddy current data at locations susceptible to circumferential cracking during your next steam generator tube inspection (i.e., the next inspection per your Generic Letter 95-03 response).
ENCLOSURE