ML17324A761
| ML17324A761 | |
| Person / Time | |
|---|---|
| Site: | Cook |
| Issue date: | 03/31/1986 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | Dolan J AMERICAN ELECTRIC POWER SERVICE CORP., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| Shared Package | |
| ML17324A763 | List: |
| References | |
| NUDOCS 8604080461 | |
| Download: ML17324A761 (4) | |
Text
Docket No.:
50-316 Mr. John Dolan, Vice President Indiana and Michigan Electric Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
Dear Mr. Dolan:
By letter dated February 3, 1986, the Indiana 5 Michigan Electric Company requested relief from the pressure test inspection requirements of the ASME BSPV Code Section XI, Subsections IWB-5000 and IWC-5000.
This relief was required for sections of five groups of pipe in which code specified pres-sure tests were determined to be impractical without extensive modification of valves and substantial radiation exposure to plant personnel.
We have completed our review and the Safety Evaluation is enclosed.
In accordance with Technical Specification 4.0.5, written relief may be granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i).
Our review has determined that the code requirements for the specified systems are impractical and the granting of the relief is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Therefore, the accumulator discharge piping, reactor charging piping, and safety injection system piping will be tested at 2280 psig at a temperature greater than 100'F during Mode 3 while the reactor coolant system pressure is at 2280 psig and temperature is greater than or equal to 500'F.
The reactor coolant letdown piping will be tested at 2280 psig at temperature above 100'F during Mode 3 using reactor coolant system pres-sure and the auxiliary spray line to the pressurizer will be tested at 2800 psig.
These piping systems are detailed in the enclosure.
The relief is granted.
Sincerely, Qxigfnal s1gned bgt Zl~ Hood B. J.
Youngblood, Director PWR Project Directorate ¹4 Division of PWR Licensing-A, NRR
Enclosure:
As stated cc:
See next page
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MAR 3.1 1986 Donald C.
Cook Nuclear Plant CC:
Mr. M. P. Alexich Vice President Nuclear Operations American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43215 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Bridgman, Michigan 49106 W.
G. Smith, Jr., Plant Manager Donald C.
Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commi,ssion Resident Inspectors Office 7700 Red Arrow Highway Stevensville, Michigan 49127.
Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, DC 20036 Mayor, City of Bridgeman 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 3500 N. Logan Street
'ost Office Box 30035 Lansing, Michigan 48909 The Konorab1 e John E.
Gr otberg United States House of Representatives Washington, DC 20515 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen El lyn, Illinois 60137 J. Feinstein American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
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