ML17325B740
| ML17325B740 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/28/1985 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Dolan J AMERICAN ELECTRIC POWER SERVICE CORP., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| Shared Package | |
| ML17325B741 | List: |
| References | |
| NUDOCS 8507110602 | |
| Download: ML17325B740 (5) | |
Text
Docket No. 50-315 June 28, 1985 DISTRIBUTION 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:
LPDR GrayFile OELD BGrimes DWigginton ACRS 10 NRC PDR ORB¹l Rdg HThompson EJordan JPartlow CParrish By letter dated May 17, 1985, the Indiana 5 Michigan Electric Company requested relief from the pressure test inspection requirements of the ASME BIIPV Code Section XI, subsections IWB-5000 and IWC-5000.
This relief was required for sections of four groups of pipe in which code specified pressure 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 systems for which relief has been requested will be tested at 2280 psig at. a temperature of 100'F during Mode 3 while the reactor coolant system pressure is at 2280 psig and temperature greater than or equal to 500'F.
These piping systems are detailed in the enclosure and include the accumulator discharge piping, reactor letdown and charging piping, and safety injection system piping.
The relief is granted.
Sincerely,
/s/SVarga Steven A. Varga, Chief Operating Reactors Branch ¹1 Division of Licensing
Enclosure:
As stated cc w/enclosure:
See next page 8507110502 850528 PDR ADDCK 05000815 PDR iJ
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Docket No. 50-315 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:
DISTRIBUTION oce re LPDR GrayFil e OELD BGrimes DWigginton ACRS 10 NRC PD ORB¹+R)g HThymppon EJordan Jkyrtlow Parr ish By letter dated May 17, 1985, the Indiana 5 Michigan Elpgtric Company requested relief from the pressure test inspection reqbjkements of the ASME B&PV Code Section XI, subsections IWB-5000 and JAB'-5000.
This relief was required for sections of four groups of pipe ig/qhich code specified pressure tests were determined to be impractical sn hout extensive modification of valves and substantial radiationfe posure to plant personnel.
We have completed our review and t 0 afety Evaluation is enclosed.
In accordance with Technical Specification
.,0.5, written relief may be granted by the Comnission pursuant to 10 F)~50.55a(g)(6)(i).
Our review has determined that the code requirement for the specified systems are impractical and the granting of the rel'eg is authorized by law and will not endanger life or property or the c
mmon defense and security and is otherwise in the public interest.
Th afore, the systems for which relief has been requested will be tested atj2280 psig at a temperature of 100'F during Mode 3 while the reactor co an't system pressure is at 2280 psig and temperature greater than or equal o 500'F.
These piping system are detailed in the enclosure and in tide the accumulator discharge
- piping, reactor letdown and charging pi ng, and.safety injection system piping.
The relief is granted.
Sincerely,
/
Enclosure:
As stated
/
cc w/enclosure:,
~'ee next page V'teven A. Varga, Chief Operating Reactors Branch ¹1 Division of Licensing
- See previous white ncurre ORB¹l: DL*
CPar rish 6/20/85 ORB¹1:DL 0 B¹1:DL DWigginton;ps ga 6/gQ85 6
/85
Docket No. 50-315 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:
DISTRIBUTION oc et i e LPDR GrayFil e OELD BGrimes DWigginton ACRS 10 NRC PDR ORB¹l Rdg HThompson EJordan JPartlow C
rrish By letter dated May 17, 1985, the Indiana 8 Michigan lectric Company requested relief from the pressure test inspection n requirements of the ASME BSPV Code Section XI, subsections IWB-5000 a d IWC-5000.
This relief was required for sections of four groups of pip in which code specified pressure tests were determined to be impractic without extensive modification of valves and substantial radia on exposure to plant personnel.
We have completed our review an the Safety Evaluation is enclosed.
In accordance with Technical Specifica on 4.0.5, written relief may be granted by the Coomission pursuant to 0
CFR 50.55a(g)(6)(i).
Our review has determined that the code require ents for the specified systems are impractical and the granting of the relief is authorized by law and will not endanger life or property or t e common defense and security and is otherwise in the public interest.
Therefore, the systems for which relief has been requested will be test at 2280 psig at a temperature of 100'F during Mode 3'while the reacto coolant system pressure is at 2280 psig and temperature greater than or e ual to 500'F.
These piping system are detailed in the enclosure an include the accumulator discharge
- piping, reactor letdown and chargin piping, and safety injection system piping.
The relief is granted.
Sincerely,
Enclosure:
As stated Steven A. Varga, Chief Operating Reactors Branch ¹1 Division of Licensing cc w/enclosu e:
See next pa e
ORB¹1:DL CParrish 6/g,f85 ORB¹1: DL BC-ORB¹1: DL QELD DWi ginton;ps SVarga 6/
85 6/
/85 6/ /85
Mr. John Dolan Indiana and Michigan Electric Company Donald C.
Cook Nuclear Plant CC:
Mr. M. P. Alexich Yice 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 Super visor 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 Commission 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 Post Office Box 30035 Lansing, Michigan 48909 The Honorable John E. Grotberg United States House of Representatives Washington, DC 20515 James G. Keppler Regional Administrator - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 J. Feinstein American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216