ML20056G110
| ML20056G110 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/16/1993 |
| From: | Olshan L Office of Nuclear Reactor Regulation |
| To: | Donnelly P CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| GL-87-02, GL-87-2, TAC-M69429, NUDOCS 9309020066 | |
| Download: ML20056G110 (3) | |
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NUCLEAR REGULATORY COMMISSION g.. 4 y W ASHINGTON, D.C. 20555-0001 August 16, 1993 Docket No. 50-155 Mr. Patrick M. Donnelly, Plant Manager Big Rock Point Plant Consumers Power Company 10269 U.S. 31 North Charlevoix, Michigan 49720
Dear Mr. Donnelly:
SUBJECT:
BIG ROCK POINT PLANT - RESPONSE TO SUPPLEMENT NO. 1 TO GENERIC LETTER 87-02 (TAC NO. M69429)
By letter dated November 27, 1992, we provided our Safety Evaluation (SE) of your September 21, 1992, response to Generic Letter (GL) 87-02. Our SE noted several deficiencies which you addressed in letters dated February 18 and April 16, 1993.
We were not certain that you were comitting to the entire Generic Implementation Procerture, Revision 2 (GIP-2); however, your April 16, 1993 submittal satisfactorily clarified your commitment.
You also proposed two deviations from GIP-2. The first deviation involved the plant's inability to meet the single failure criterion because it has only one automatically started emergency diesel generator.
In your February 18, 1993, letter this deviation was withdrawn by verifying the seismic adequacy of the standby diesel generator, referencing the Station Blackout Supplemental SE and requiring availability of the standby diesel generator within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> under accident conditions.
The second deviation involved using a probabilistic risk approach for resolving outliers. This deviation was also withdrawn in your February 18 letter and the plan described in this letter for resolving outliers is acceptable.
Our SE also asked for additional information concerning the licensing-basis spectra.
Your February 18 response stated that you would use the in-structure i
response spectra generated from design spectra of either Regulatory Guide 1.60 anchored at 0.12 g or the NRC site-specific design spectra anchored at 0.104g, which are both contained in section 2.5 of the Big Rock Point Updated Final Hazards Summary Report. We agree that the in-structure response spectra generated by either of the two acceptable ground response spectra is acceptable.
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f Mr. Patrick M. Donnelly August. 16, 1993 Thus, we conclude thet you have satisfactorily resolved all the concerns addressed in our November 27, 1992 SE.
Sincerely, ORIGINAL SIGNED BY Leonard N. Olshan, Project Manager Project Directorate 111-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation cc: See next page i
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s Mr. Patrick M. Donnelly, Plant Manager Big Rock Point Nuclear Plant cc:
Mr. Thomas A. McNish, Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Jane E. Brannon, County Clerk County Building Annex 203 Antrim Street Charlevoix, Michigan 49720 Office of the Coverr.or Room 1 - Capitol Building Lansing, Michigan 48913 Regional. Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3423 N. Logan Street P. O. Box 30195 Lansing, Michigan 48909 U.S. Nuclear Regulatory Commission Resident Inspector Office Big Rock Point Plant 10253 U.S. 31 North Charlevoix, Michigan 49720 Mr. David P. Hoffman, Vice President Nuclear Operations Big Rock Point Plant Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 m+ ws