ML17325A290
| ML17325A290 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/11/1987 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | Dolan J AMERICAN ELECTRIC POWER SERVICE CORP., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| References | |
| NUDOCS 8709180208 | |
| Download: ML17325A290 (5) | |
Text
Q,p i1 198'1 Docket Nos.:
50-315 and 50-316 Distribution:
NRC-8 Local PDRs PD III-3 r/f DWigginton PKr cuter OGC Bethesda ordan
Dear Nr. Dolan:
Mr. John Dolan, Vice President EJ Indiana and Michigan Electric Company c/o American Electric Power Service Corporation 1 Riverside Plaza
In the Indiana and Michigan Electric Company letter dated March 23, 1987 and Nay 13,
- 1987, IMEC requested an interpretation of Technical Specification regarding the use of residual heat removal (RHR) and safety injection (SI) crossties.
In both letters, INEC noted the critical need for the interpre-tation to prevent unnecessary shutdowns or delays in startup should problems develop in surveillance or maintenance.
We have had several discussions with your staff and are awaiting additional information concerning the SI crossties as it would affect the small break loss of coolant analysis. We believe we have sufficient information on the RHR crossties and their affects on accident analyses.
On September, 11, 1987, your office notified the NRC of a leak in one RHR system which would require an RHR heat exchange be drained to accomplish the repair.
The repair was characterized as one that was not critical but in the best interest of controlling'ontamination and as a good plant
- practice, the leak should be repaired as soon as" practical.
By letter dated the same day,INEC requested that the interpretation be granted to allow the RHR crossties to be closed while in Mode 3 to allow the repair under the action statement which allows one train of RHR to be inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Based on our review to date and as we have requested from IMEC, additional information is needed regarding the SI crossties and the small-break loss of coolant analysis.
We feel certain that the RHR crosstie will not affect the accident analyse's beyond that which"we have seen from the material we have received.
Furthermore, the plant,has been down for a period of time which minimizes the decay heat and urgency associated with having all RHR systems operable.
Node 3 will,not significantly increase the heat load and will not result in a decay heat increase which might ultimately challenge the RHR system during th'is repair effort.
Therefore, for the particular 8709180209 9709k 1 t oa aaac~<
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circumstances at D. C.
Cook Unit 1 we find that IMEC has established an analysis of record and there are no significant safety issues with closing the RHR crosstie in Mode 3 to complete the repair.
If there is any further questions on this matter, please let me know.
Sincerely,s' cc:
See next page David L. Migginton, Project Manager Project Directorate III-3 Division of Reactor Projects Office:
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PKreutzer Date:
09 yl /87 PD/
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Mr. John Dolan Indiana and Michigan Electric Company Donald C.
Cook Nucle'ar 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 Supervisor Lake Township Hall Post Office Box 818 Bridgeman, Michigan 49106 W.
G. Smith, Jr., Plant Manager Donald C.
Cook Nuclear Plant Post Office Box 458
- Bridgman, Michi gan 49106 U.S.. Nuclear Regulatory Commission Resident Inspectors 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 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, Ohi o 43216