ML20052G978
| ML20052G978 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 05/18/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Vandewalle D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TASK-07-02, TASK-7-2, TASK-RR LSO5-82-05-038, LSO5-82-5-38, NUDOCS 8205190208 | |
| Download: ML20052G978 (4) | |
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May 18,1982 Docket No. 50-155 LS05-82 038 Mr. David J. VandeWalle Nuclear Licensing Administrator Comumers Power Company 1945 W Parnall Road Jackson, Michigan 49201
Dear Mr. VandeWalle:
SUBJECT:
SEP TOPIC VII-2, ENGINEERED SAFETY FEATURES SYSTEM C0fRROL LOGIC AND DESIGN, SAFETY EVALUATION REPORT FOR BIG ROCK POINT The enclosed page is a replacement for page 7 of Enclosure 1 to D. M.
Crutchfield's February 1,1982 letter on this subject. This change corrects the description of LT 3184. The staff's safety evaluation remains unchanged.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page DSa USS Sh l
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.Mr. David J. VandeWalle
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cc Mr. Paul A. Pe'rry, Secretary U. S. Environmental Protection Consumers Power Company Agency 212 West Michigan Avenue Federal Activities Branch
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Jackson, Michigan 49201 Region V Office ATTN:
Regional Radiation Representative Judd L. Bacon, Esquire 230 South Dearborn Street
- Consumers Power Company Chicago, Illinois 60604 212 West Michigan Avenue Jackson, Michigan 49201 Peter B. Bloch, Chairman Atomic Safety and Licensing Board Joseph Gallo, Esquire U. S. Nuclear Regulatory Commission 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 Commission Peter W. Steketee, Esquire Washington, D. C.
20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board Alan S. Rosenthal, Esq., Chairman U. S. Nuclear Regulatory Commission Atomic Safety & Licensing Appeal Board Washington, D. C.
20555 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Big Rock Point Nuclear Power Plant ATTH:
Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent Route 2, Box 44 Charlevoix, Michigan 49720 Maple City, Michigan 49664 Christa-Maria Mr. Jim E. Mills Route 2, Box 108C Route 2, uox 108C Charlevoix, Michigan 49720 Charlevoix, Michigan 49720 William J. Scanlon, Esquire Chairman 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 Herbert Semmel Counsel for Christa Maria, et al.
Urban Law Institute Antioch School of Law 2633 16th Street, NW Washington, D. C.
20460 5
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Mr. David J. VandeWalle cc Dr. John H. Buck Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Ms. JoAnn Bier 204 Clinton Street Charlevoix, Michigan 49720 Thomas S. Moore Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 James G. Keppler, Regional Administrator Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 4
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and the main steam line motor operated valves, is f rom the instrument panels lY and 2Y.
The mainsteam line valves and the ventilation system receive power fran the 125V DC bus and the 125V DC distribution panel No.1 respectively.
The distribution panel No.1 is fed from the 125V DC plant bus.
Isolation from other loads on the same buses is by thermal circuit breakers.I4 Evaluation The containment isolction system consists of redundant channels and is isolated from control and non-safety systems by relay con-tacts, switch contacts and thermal circuit breakers.
3.6 Reactor Depressurization System.15 The Reactor Depressurization System (RDS) is comprised of four parallel blowdown paths with an air actu-ated depressurization valve and a solenoid actuated isolation valve in each path. Actuation of the RDS is from four separate and redundant logic chan-nels arranged in a 2 out of 4 configuration. All four channels are identi-cal so only channel A is described here.
Four sensors, LT3184 monitoring low steam drum level, LT3180 monitoring low reactor coolant water and pressure switches PS789 and PS793 monitoring discharge pressure fran the fire pumps, provide RDS initiation.
A low steam drum pressure signal from LT3184 energizes three bistables (SDL-FPS, SDL-H and SDL-L).
Bistable SDL-FPS has two outputs, one to each of two 2 out of 4 logic modules for starting the fire pumps (see ECCS Section 3.2 for pump start detail).
Bistable SDL-H provides annunciator indication of the steam drum level.
Bistable SDL-L starts a time delay relay, TD00. The output of the TD00 relay upon time out feeds a three input AND gate.
LT3180, upon detecting low reactor water level, energizes bistable RWL-L. The output signal of RWL-L also goes to the three input AND gate.
Pressure switches PS789 and PS793 both have an output to an OR gate.
When either pressure switch senses adequate fire pump discharge pressure the OR gate transmits a signal to the three input AND gate. The three input sig-nals then initiate an AND gate output.
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