ML17332A907
| ML17332A907 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/01/1995 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | Fitzpatrick E AMERICAN ELECTRIC POWER SERVICE CORP., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| References | |
| TAC-M93238, NUDOCS 9509080251 | |
| Download: ML17332A907 (4) | |
Text
fir. E.
E. Fitzpatrick, Vice President Indiana Michigan Power Company September 1995 p
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c/o Amer>can Electric Power Serv>ce Corporat>on 1 Riverside Plaza
- Columbus, OH 43215
SUBJECT:
RE(UEST FOR ADDITIONAL INFORMATION, DONALD C.
COOK NUCLEAR UNIT 1, REPAIR BOUNDARY FOR PARENT TUBE'NDICATIONS IN HEJ TUBES (TAC NO. M93238)
Dear Mr. Fitzpatrick:
PLANT SLEEVED a
By letter dated August 4,
- 1995, you requested an amendment to license DPR-58 modifying the technical specifications to allow use of alternate repai'r criteria for parent tube indications in hybrid expansion joint (HEJ) sleeved steam generator tubes.
The enclosed request for additional information addresses the ability of circumferentially cracked HEJ sleeved steam generator tubes to perform their fission product containment function under severe accident conditions.
Degraded tube severe accident performance was previously addressed in the safety evaluation approving interim plugging criteria.
However, the degradation now under consideration requires that the issue be revisited.
This requirement affects nine or fewer respondents and, therefore, is not subject to the Office of Management and Budget review under P.L.96-511.
If you have any questions on these items please contact me at (301) 415-3017.
Sincerely, Original signed by Docket No. 50-315 cc:
See next page
Enclosure:
As stated John B. Hickman, Project Manager Project Directorate III-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation 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 1995
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REVEST FOR ADDITIONAL INFORMATION DONALD C.
COOK UNIT 1 TECHNICAL SPECIFICATIONS CHANGE (TAC NO. M93238)
In its safety evaluation granting approval of steam generator tube interim plugging criteria (IPC), Amendment 178 dated March 15, 1994, the staff addressed the expected impact of a voltage-based repair criterion on tube performance under severe accident conditions.
The staff concluded that the repair criterion would not sufficiently impact tube performance as to alter high pressur e severe accident analyses.
The staff judged that the effect of the IPC on plant response to high pressure severe accident challenges was within the uncertainties associated with severe accident analysis capabilities.
The proposed redefinition of repair boundary limits for hybrid expansion joint (HEJ) sleeved tubes would allow continued operation of the steam generators with circumferentially cracked tubes.
Current repair criteria dictate that tubes with circumferential cracks be repaired.
The application addresses the consequences of an overpressurization (i.e., main steamline break) challenge of a circumferentially cracked HEJ sleeved
- tube, suggesting that tube/sleeve joint strength is sufficient to maintain leak resistance.
A defense-in-depth argument is also presented, which asserts that even if the joint lacked adequate
- strength, geometric considerations would prevent gross failure of sleeved tubes.
The application did not address the ability of affected tubes to perform their fission product containment function under conditions that could result from severe accidents.
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Address the impact of plant operation with circumferentially cracked HEJ sleeved steam generator
- tubes, concentrating on the ability of the steam generators to perform their fission product containment function under high temperature and pressure conditions that could result from severe accidents.