ML19211C456
| ML19211C456 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/07/1980 |
| From: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| 1510, NUDOCS 8001110427 | |
| Download: ML19211C456 (2) | |
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3 ARKANSAS POWER & LIGHT COMPANY POST OFFICE box 551 LITTLE ROCK, ARKANSAS 72203 (501) 371-4422 WILLIAM CAVANAUGH lli January 7,1980 Vice Presidene Generation & Constnacton 1-010-05 2-010-05 Director of Nuclear Reactor Regulation ATTN:
Mr. Darrell G. Eisenhut, Acting Director, Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
Arkansas Nuclear One-Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Fuel Clad Swelling (File:
1510, 2-1510)
Gentlemen:
The following is provided in response to your November 9,1979, and November 27, 1979, letters.
AN0-1 As is outlined in the November 2,1979, letter from B&W (James Taylor) to your Mr. Darrell G. Eisenhut all B&W plants meet the requirements of Appendix K and 10 CFR 50.46.
We have confimed through telecons and correspondence that the information submitted by B&W to the NRC in their November 2,1979, and November 20, 1979, letters is correct and appli-cable to AN0-1.
In that the infonaation submitted by B&W previously shows their ECCS model to be conservative when taken as a whole, we are not proposing additional analysis at this time.
Af ter NUREG-0636 is released we will evaluate the need for analysis to show conformance to Appendix K.
ANO-2 The November 2,1979, and Novenber 16, 1979, letters from Combustion Engineering (A.E. Scherer) to your Mr. Darrell G. Eisenhut confims that all CE operating plants meet Appendix K and the 2200 F peak cladding temperature criterion. We have confirmed that the representations made by Combustion Engineering in our behalf are correct and applicable to ANO-2.
1735 138 a _ mesom1or,m1,eee f u0111e Y
1-010-05 2-010-05 Mr. Darrell G. Eisenhut January 7,1980 We are funding a generic analysis of the impact of the new NRC fuel cladding strain and assembly flow blockage models on our ECCS analysis at this time. We will provide you with results of this analysis no later than March 1,1980.
Very truly yours,
/
p William Cavdnaug( III WC/M0W/ew 1735 139
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