ML17332A912
| ML17332A912 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/07/1995 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | Fitzpatrick E AMERICAN ELECTRIC POWER SERVICE CORP. |
| References | |
| TAC-M92235, TAC-M92236, NUDOCS 9509120264 | |
| Download: ML17332A912 (4) | |
Text
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September 7,
1995 Hr.
E.
E. Fitzpatrick, Vice President Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, OH 43215
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION, DONALD C.
COOK NUCLEAR PLANT UNITS 1
AND 2, CIRCUMFERENTIAL CRACKING OF STEAN GENERATOR TUBES, GENERIC LETTER 95-03 (TAC NOS.
H92235 AND H92236)
Dear Hr. Fitzpatrick:
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.
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I/Kropp, RIII KKart/oski DHcDonald DOCUMENT NAME:
G: iWPDOCSiDCCOOKiC092235. RAI To receive m copy of tNe document. Irdcete In the box: 'C'e Copy without attachment/enctoetme E'
Copy with ttec ent/endoetme 'N'o copy John B. Hickman, Project Manager Project Directorate III-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation If you have any questions on these items please contact me at (301) 415-3017.
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Mr. E.
E. Fitzpatrick Indiana Hichigan 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, Hichigan 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 Hayor, City of Bridgman Post Office Box 366 Bridgman, Hichigan 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 hpril 199S
REQUEST FOR ADDITIONAL INFORMATION DONALD C.
COOK UNITS 1
AND 2 CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES
- l. It was indicated that one tube circumferentially separated during a tube pull at Unit 1 in 1992.
It was further indicated that the remaining three tubes which were pulled had burst pressures in excess of 5500 psi.
Discuss the assessments performed, if any, on the structural integrity of the tube that circumferentially separated during the tube pull in 1992.
2.
Clarify the scope of the inspections to be performed in the U-bend portion of the tubes with small radius U-bends (i.e.,
Row 1 and 2) in Unit 1
during the next steam generator tube inspections.
Provide the expansion criteria to be used if indications are detected during these inspections.
3.
Operating temperature was one factor cited for having less pronounced tube degradation at sleeve joints, if any degradation is present at all.
Please compare the operating temperature at Cook Unit 1 to the operating temperatures at the other plants cited.
4.
The following areas have been identified as being susceptible to circumferential cracking:
a 0 b.
c d.
Expansion transition circumferential cracking Small radius U-bend circumferential cracking Dented location (including dented TSP [tube support plate])
circumferential cracking Sleeve joint circumferential cracking In your response for Unit 2, area d was not specifically addressed.
Please provide the requested information for this area (and any other areas susceptible to circumferential cracking) per Generic Letter 95-03.
The staff realizes that some of these areas may not have been addressed since they may not be applicable to your plant; however, this should be clearly stated with the basis for the statement (e.g.,
no sleeves are installed; therefore, the plant is not susceptible to sleeve joint circumferential cracking).
5.
Please provide the expansion criteria to be used if circumferential indications are detected at the expansion transition during the Cook Unit 2 steam generator inspections.