ML20010B665

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Forwards Automation Industries,Inc Re Pipe Breaks Outside Containment,In Response to NRC Request Concerning SEP Topic III.5.B
ML20010B665
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 08/05/1981
From: Linder F
DAIRYLAND POWER COOPERATIVE
To: Eisenhut D
Office of Nuclear Reactor Regulation
Shared Package
ML20010B666 List:
References
TASK-03-05.B, TASK-3-5.B, TASK-RR LAC-7733, NUDOCS 8108170385
Download: ML20010B665 (2)


Text

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DlDA/RYLAND h!

1 COOPERA T/VE

  • P O BOX 817 2615 E AST AV SOUTH. t A CROSSE WISCONSIN 9601 (608) 788 4 000 August 5, 1981 In reply, please refer to LAC-7733 DOCKET NO. 50-409 U.

S. Nuclear Regulatory Commission ATTN:

Mr. Darrell G. Eisenhut, Director c>g Division of Licensing

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Office of Nuclear Reactor Regulation lh-Division of Operating Reactors k

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a Washington, D. C.

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SUBJECT:

DAIRYLAND POWER COOPERATIVE s$"CU 12 LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 4

SEP TOPIC III.S.B - PIPE BREAK j

f OUTSIDE CONTAINMENT Q%

Reference:

(1)

DPC Letter, LAC-7635, Linder to Eisenhut, dated June 29, 1981.

Gentlemen:

As requested by Mr.

enclosing 3 copies of NES letter, P-5101-77, Ralph Caruso, LACBWR Project Officer to R. E. Shimshak (DPC),

dated December 4, 1974.

This letter is referenced in the enclosure to Reference (1) above.

If you have any further questions, please contact us.

Very truly yours, DAIRYLAND POWER COOPERATIVE s

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Frank Linder, General Manager FL:IUiT:af cc:

J. G. Keppler, Reg. Dir., NRC-DRO III NRC Resident Inspectors DB$p s.

8108170385 810805 PDR ADOCK 05000409 p

PDR

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{} AUTOMATION INDUSTFUES,-INC.

gjj NUCLEAR ENERGY SERVICES DIVISION.

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December 4, 1974 Reference No. P-5101-77 Mr. R. E. Shimshak Lacrosse Boiling Water Reactor DAIRYLAND POWER COOPERATIVE P. O. Box 135 Genoa, WI 54632

Subject:

Additional Information Requested by USAEC on Pipe Breaks Outside Containment, NES BIA00'3, Rev. I

Dear Dick:

Enclosed is the subject Report, Rev. I which now Indicates the ?oca-tion of the two alternate core spray valves as outside containment.

An evaluation of potential pipe failures near the alternate core spray valves showed that the valves will be adequately protected from pipe whip by the restraints that are to be Installed on the main steam and 3

bypass lines. There are no potential break locations in high energy lines greater than 1-inch diameter in the valve area that can result in Jet Impingement on the valves.

Since the actuator motors are totally enclosed and non-ventilated, there will be no adverse environ-mental ef fects.

l l

The draf t submi ttal letter forwarded wi th our letter P-5101-38 (August l

2, 1974) does not require revision, and may be used to summarize the l

conclusions and recommendations of the report.

l Sincerely, AUTOMATION INDUSTRIES, INC.

NUCLEAR ENERGY SERVICES DIVISION W

~ William J. Manion Vice President and General Manager

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Enclosure i-

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