ML19208A760
| ML19208A760 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 09/13/1979 |
| From: | Bixel D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| TASK-04-01.A, TASK-05-10.A, TASK-05-12.A, TASK-RR NUDOCS 7909170427 | |
| Download: ML19208A760 (2) | |
Text
_
y 1 CORSum8IS l PcWEr
/ Compa'Jy
,ap General OHeces: 212 West Michigan Avenue, Jackson, Michigan 49201 e Area Code 517788-0550 September 13, 1979 Director, Nuclear Reactor Regulation Att Mr Dennis L Zie= ann, Chief Operating Reactors Branch No 2 US Nuclear Regulatory Connission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - COMMENTS ON SAFETY EVALUATIONS FOR SEP TOPICS IV-1.A, V-10.A, V-12.A NRC letter dated July 12, 1979 forwarded a Safety Evaluation Report (SER) on SEP Topic V-10.A, " Residual Heat Removal System Heat Exchanger Tube Failures" for Big Rock Point. NRC letters dated August 9, 1979 forwarded SERs on Topics IV-1.A, " Operation With Less Than All Loops in Service," and V-12.A, " Water Pur".ty of BWR Coolant." Censumers Power was requested to review these reports and identify any errors therein. Consumers Power Company's con =ents are provided below:
1.
Topic IV-1.A Page 6, Paragraph 1 - The sentence reading, "The same reduction in set point would relate to the overpressure trip" should be deleted and replaced with a sentence reading, " Reactor operating pressure would be the same for single-pump operation as for two-pump operation (1350 psia); therefore, the prox-imity to the high-pressure trip (1450 psia) would be the same in both cases."
2.
Topic V-10.A Page 3, Paragraph 2 - The second sentence should be revised to read, "Because the service water pressure at these heat exchangers varies from approximately 20 to h5 psig, the possibility exists...."
Dbss2).3 c 9 0917 0 C7
2 3.
Topic V-12.A a.
The third paragraph on Page 3 states that Big Rock Point Technical Specifications will be revised to conform to the Standard Technical Specifications' format and content. This project is currently being reevaluated. Accordingly, we request the.?. reference to this modifi-cation be deleted.
b.
Page 8, Paragraph 2 - The term " river coolant" in the first sentence should be replaced with " Lake Michigan coolant."
David A Bixel (Signed)
David A Bixel Nuclear Licensing Administrator CC JGKeppler, USNRU 3.'iii' 34 2