ML20003D712

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Concurs W/Nrc 801215 Evaluation of SEP Topic III-8.C Re Irradiation Damage,Use of Sensitized Stainless Steel & Fatigue Resistance
ML20003D712
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 03/03/1981
From: Linder F
DAIRYLAND POWER COOPERATIVE
To: Crutchfield D
Office of Nuclear Reactor Regulation
References
TASK-03-08.C, TASK-3-8.C, TASK-RR LAC-7397, NUDOCS 8103310255
Download: ML20003D712 (1)


Text

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D DA/RYLAND COOPERA T/VE eo BOX 817 2615 EAST AV SOUTH LA CROSSE. WISCONSIN 51601 a

<cos) 7884000 March 3, 1981 In reply, please refer to LAC-7397 DOCKET NO. 50-409 Director of Nuclear Reactor Regulation l

[. \\ ^f ATTN:

Mr. Dennis M. Crutchfield, Chief

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Operating Reactors Branch No. 5

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Division of Operating Reactors U.

S. Nuclear Regulatory Commission 6

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Washington, D.

C.

20555

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SUBJECT:

DAIRYLAND POWFR COOPERATIVE k

A S LA CROSSE BOILING WATER REACTOR (LACBWR) 7,

%s h PROVISIONAL OPERATING LICENSE NO. DP R-4 5 N

IRRADIATION DAMAGE, USE OF SENSITIZED STAINLE f gg gg Y STEEL AND FATIGUE RESISTANCE (SEP TOPIC III-8.C

Reference:

(1)

NRC Letter, Crutchfield to Linder, dated December 15, 1980.

Gentlemen:

Reference 1 enclosed a copy of your evaluation of Systematic Evaluation Program Topic III-8.C - Irradiation Damage, Use of Sensitized Stainless Steel'and Fatigue Resistance.

This assess-ment compared the La Crosse Boiling Water Reactor (LACBWR) facility as described in Docket No. 50-409, with the criteria currently used by the regulatory staff for licensing new facilities.

We concur in your evaluation, and no changes are needed to reflect the as-built conditions of the LACBNR.

If you have any further questions, please call.

Very truly yours, DAIRYLAUD POWER COOPERATIVE

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.[ @ w Frank Linder, General Manager FL: HAT:af cc:

J.

Keppler, Reg. Dir., NRC-DFO III 8108310#55

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