ML20031C936

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Forwards Request for Addl Info for SEP Topics VII-1.A & VII-2 Re Isolation of Reactor Protection & ESF
ML20031C936
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 10/06/1981
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Linder F
DAIRYLAND POWER COOPERATIVE
References
TASK-07-01.A, TASK-07-02, TASK-7-1.A, TASK-7-2, TASK-RR LSO5-81-10-004, LSO5-81-10-4, NUDOCS 8110090142
Download: ML20031C936 (3)


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October 6,198i Docket No. 50-409 LS05 10-004 t-t.I l?/%

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Mr. Frank Linder 9

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Dear Mr. Lindtr:

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StBJECT: REQUEST FOR ADDITIONAL.INFORMATION ON LA CROSSE BOILING WATER REACTOR FOR SEP TOPICS VII-1.A AND VII-2. ISOLATION OF REACTOR PROTECTION AND ENGINEERED SAFETY FEATURES The enclosed request for additional information has been prepared by our support contractor. Responses within 30 days of receipt is requested so that we may maintain the present SEP schedule.

Sincerely.

Dennis M. Crutchfiel<i, Chief Operating Reactors Branch No. 5 Division of Licensing

Enclosure:

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Mr. Frank Linder NM.

cc Fritz Schubert, Esquire U. S. Environmental Protection Staff Attorney Agency Dairyland Power Cooperative Federal Activities Branch 2615 East Avenue South Region V Office La Crosse, Wisconsin 54601 ATTN: Regional Radiation Representative 230 Sc. th DearboYn Street

0. S. Heistand, Jr., Esquire Chicago, Illinois 60604 Morgan, Lewis & Bockius 1800 M Street, N. W.

Mr. John H. Buck Washington, D. C.

20036 Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Mr. R. E. Shimshak Washington, D. C.

20555 La Crosse Boiling Water Reactor Dairyland Power Cooperative Dr. Lawrence R. Quarles P. O. Box 135 Kendal at Longwood, Apt. 51 Genoa, Wisconsin 54632 Kenneth Square, Pennsylvania 19348 Ms. Anne K. Morse Charles Bechhoefer, Esq., Chairman Coulee Region Energy Coalition Atomic Safety and Licensing Board P. O. Box 1583 U. S. Nuclear Regulatory Commission

.La Crosse, Wisconsin 54601 Washington, D. C.

20555 La Crosse Public Library Dr. George C. Anderson

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800 Main Street Department of Oceanography La Crosse, Wisconsin 54601 University of Washington Seattle, Washington 98195 U. S. Nuclear Regulatory Commission Resident Inspectors Office Mr. Ralph S. Decker Rural Route #1, Box 276 Route 4, Box 190D Genoa, Wisconsin 54632 Cambridge, Maryland 21613 Town Chairman Thomas S. Moore Town of Genoa Atomic Safety and Licensing Appeal Board Route 1 U. S. Nuclear Regulatory Commission Genoa, Wisconsin 54632 Washington, D. C.

20555 Chairman, Public Service Commission of Wisconsin Hill Farms State Office Building Madison, Wisconsin 53702

/ Man S. Rosenthal, Esq., Chairman Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Mr. Frederick Milton Olsen, III 609 North lith Street Lacrosse, Wisconsin 54601

3-i GP REQUEST FOR ADDITIONAL INFORMATION ON LACROSSE B0ILING WATER REACTOR FOR SEP TOPICS VII-1.A AND VII-2 ISOLATION OF REACTOR PROTECTION AND ENGINEERED SAFETY FEATURES The Safeguards Report for Operating License and the available drawings do not contain sufficient information to review the degree of isolation of the Reactor Safety System and the Engineered Safety Features between redundant channels and from control and non-safety systems (GDC 22). Therefore, please

- provide the following drawings and information:

1.

Current schematic or elementary diagram of the Reactor Trip Systens and the ESF systems and their interface with shared control systems.

2.

P& ids of the ESF systems.

3.

One-line diagrams of the power buses, AC and DC, that supply power to the reactor trip and ESF systems.

Identify types of " protective breakers used on the buses.

4.

Schemacic or elementary diagrams of the control system for the 120 AC no. interruptable rotary inverter.

5.

Identify locations and describe, by make and mcdel, all isolation buffer devices used in the reactor trip and ESF systems to isolate these systems from computers, recorders, remote indicating meters, controls,.nd non-safety systems. Describe how they meet the requirements of IEEE 279-1971 Section 4.7.2 and GDC 24.

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