ML17325A525
| ML17325A525 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/11/1987 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | Dolan J INDIANA MICHIGAN POWER CO. |
| Shared Package | |
| ML17325A526 | List: |
| References | |
| NUDOCS 8712160131 | |
| Download: ML17325A525 (5) | |
Text
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December ll,', 1987 Docket Nos.
50-315 and 50-316 Mr. John Dolan, Vice President Indiana and Michigan Power Company c/o American Electric Power Service Corporation
- j. Riverside Plaza
- Columbus, Ohio 43216 DISTRIBUTION: -.
. Docket Fi 1 es PKreutzer NRC PDR DWigginton Local PDR OGC-Bethesda PDIII-3 r/f EJordan KPerkins JPartl ow GHo1 ahan ACRS(10)
PDIII-3 Gray File
Dear Mr. Dolan:
SUBJECT:
SAFETY EVALUATION RELATED TO REQUEST FOR CODE RELIEF EXTENSION FOR RHR SYSTEM VALVES By letter dated October 31, 1986, the Indiana & Michigan Electric Company (IMEC) requested a permanent relief to test Residual Heat Removal (RHR) valves IM0-330,
-331, -340 and -350 quarterly.
The request was made because the present test configuration would place the plant in an unanalyzed condition if these valves are tested during power operations.
The NRC responded to the above request by letter dated December 19, 1986 which transmitted a Safety Evaluation (SE).
In that SE, the staff concluded that permanent relief from quarterly testing for these valves should not be granted and instead that an interim relief from quarterly testing should be granted until the next refueling outage for each unit.
The interim relief was to allow IMEC additional time to reevaluate the Emergency Core Cooling System (ECCS) analysis for the unanalyzed condition and/or develop acceptable alternative testing methods.
Since the issuance of the December 19, 1986 letter, IMEC has completed part of the ECCS reanalysis, but still needs more time to complete the last portion of this analysis pertaining to containment long-term pressure.
By letter dated November 20,
- 1987, IMEC requested an extension of the interim relief until the analysis is completed.
The additional time is needed because the interim relief for Unit 1 expired with the last refueling outage which occurred in October
- 1987, and the relief for Unit 2 will expire during the next refueling outage s
scheduled for May 1988.
No further relief is needed for Unit 2 at this tim ince the May outage will last for about a year to replace all four steam gene-is ime rators.
We have reviewed the IMEC request for extension of the interim relief for Unit l.
Based on the previous staff evaluation of the original request for relief and additional discussion on alternative testing methods, we conclude that the interim. relief should be extended to June 1988, to provide time to complete the required analysis.
- However, IMEC shou)d complete and submit the analysis results for staff review at least three months before the extension expires to allow sufficient time for the NRC review and appropriate action for future testing of the RHR valves.
6 87i2i60131 87i&2 1
, I
J.
Dolan In accordance with Technical Specifications 4.0.5, 'written relief must be obtained from the Commission pu'rsuant to 10 CFR 50.55a(g)(6)(i).
Our review has determined that the code requirements for the specified systems are imprac-tical 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 RHR valves designated IM0-330, IM0-331, IM0-340, and IMO-350 for Unit 1 need not be tested during power operation until June 1988, provided that they will be tested at any intervening outage of sufficient duration when the plant is in a condition for tests to be performed.
These valves are detailed in the November 20, 1987 IMEC letter and the enclosure.
The temporary relief is granted for Unit 1 until June 1988.
Sincerely, priginal Signed By:
Enclosure:
As stated David L. Wigginton, Acting Director Project Directorate III-3 Division of Reactor Projects cc:
See next page
~See previous concurrence Office:
LA/P III-3 Surname:
P.
er" Date:
12.y /87 PM/PDIII-3 DWig inton/tg" 12/J /87 PD/PDIII-3 DWigginton" 12/
/87 OGC Vc 12/'87
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Mr. John Dolan Indiana and Michigan Power Company 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 Bridgeman, Michigan 49106 W.
G. Smith, Jr., Plant Manager Donald C ~
Cook Nucl ear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensvi1 le, Michigan 49127 Gerald Charnoff, Esquire
- Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.
Washington, DC 20037 Mayor, City of Bridgeman Post Office Box 366 Bridgeman, 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 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. J. Feinstein American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216