ML19353A260
| ML19353A260 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 12/15/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TASK-04-02, TASK-4-2, TASK-RR LSO5-80-12-017, LSO5-80-12-17, NUDOCS 8101070618 | |
| Download: ML19353A260 (3) | |
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NUCLEAR REGULATORY COMMISSION E
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a, DEC 151980 Docket No. 50-155 LS05-80-12-017 Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Power Company 212 West Michigan Avenue J u son, Michigan 49201
Dear Mr. Hoffrran:
RE:
BIG ROCK P0 INT - SEP TOPIC IV-2, REACTIVITY CONTROL SYSTEMS DESIGN AND PROTECTION AGAINST SINGLE FAILURES The enclosed request for information has been prepared by the staff as a part of our review of SEP Topic IV-2.
Please provide the requested information within 90 days of receipt of this letter.
Sincerely,
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Dennis M. Crutchfield, khief Operating Reactors Branch #5 Division of Licensing
Enclosure:
Request for Information on SEP Topic IV-2 cc w/ enclosure:
See next page
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O Mr. David P. Hoffman BIG ROCK POINT DOCKET NO. 50-155 CC Mr. Paul A. Perry, Secretary U. S. Environmental Protection V
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4 Consumers Power Coupany Agency 212 West Michigan Avenue Federal Activities Branch i
Jackson, Michigan 49201 Region V Office l
ATTN: EIS COORDINATOR Judd L. Bacon, Esquire 230 South Dearoorn Street Consumers Power Company Chicago, Illinois 60604 212 West Michigan Avenue l
Jackson, Michigan 49201 Herbert Grossman, Esq., Chairman Atomic Safety and Licensing Board Joseph Gallo, Esquire U. S. Nuclear Regulatory Comission Isham, Lincoln & Beale Washington, D. C.
20555 1120 Connecticut Avenue Room 325 Dr. Oscar H. Paris Washington, D. C.
20036 Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comission Peter W. Steketee, Esquire Washington, D. C.
20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atemic Safety and Licensing Board Alan S. Rosenthal, Esq., Chairman U. S. Nuclear Regulatory Comission Atomic Safety & Licensing Appeal Board Washington, D. C.
20555 U. S. Nuclear Regulatory Comission Washington, D. C.
20555 Big Rock Point Nuclear Power Plant ATTN: Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent Route 2, Box 44 Charlevoix, Michigan 49720 Maple City, Michigan 49664 Chri s ta-Mari a Charlevoix Public Library Route 2, Box 108C 107 Clinton Street Charlevoix, Michigan 49720 Charlevoix, Michigan William J. Scanlon, Esquire Chai rman 2034 Pauline Boulevard County Board of Supervisors Ann Arbor, Michigan 48103 Charlevoix County Charlevoix, Michigan 49720 Resident Inspector Big Rock Point Plant Office of the Governor (2) c/o U.S. NRC Room 1 - Capitol Building RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720 Director, Technical Assessment Mr. Jim E. Mills Division Route 2, Box 108C
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Office of Radiation Programs Charlevoix, Michigan 49720 (AW-459)
U. 5. Environmental Protection Thomas S. Moore Agency Atomic Eafety & Licensing Appeal Board Crystal Mall #2 U. S. Nuclear Regulatory Comission Arlington, Virginia 20460 Washington, D. C.
20555 l
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i ENCLOSURE REQUEST FOR INFORPATION SEP TOPIC IV-2 General Design Criterion 25 requires that the reactor protection system be designed to assure that specified acceptable fuel damage limits are not exceeded in the event of any single failure of the reactivity control systems, such as accidential rod withdrawals.
1.
Describe the single failures within systems used for reactivity control which can:
a) Cause an inadvertent reactivity insertion.
b) Cause a single or combination of rods to be positioned in other than the design sequence.
For PWRs this should include consideration of single rod withdrawal / insertions which can result from a single equipment component failure.
2.
Delineate those design features which limit reactivity insertion rates and rod malpositions resulting from a single failure.
Provide the appropriate circuit schematics showing these design features.
3.
Provide or reference appropriate analyses to demonstrate that specified acceptable fuel damage limits are not exceeded in the event of any of the single failures identified in Item 1 above.
4.
Identify the operating procedures, alarms, interlocks, or protection system actions which must be used in limiting the consequences following a single failure within systems used for reactivity control. 'ihere equipment actions are required, indicate whether the equipment meets the~
criteria of (EEE-279.
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