ML20010D811
| ML20010D811 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/14/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Caranaugh W ARKANSAS POWER & LIGHT CO. |
| Shared Package | |
| ML20010D812 | List: |
| References | |
| NUDOCS 8108310565 | |
| Download: ML20010D811 (2) | |
Text
h AUGUST 14b81 AUGUST 4 881 DISTRIBUT_I_0ft:
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, L PDR GVissing TERA RIngram Docket flo. 50-313 flSIC H0rnstein ORB #4 Rdg EBlackwood
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Itr. llilliam Cavanaugh, III IE-3 c
E C-a I h-f6 Senior Vice President, Energy ACRS-10
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Supply Gray File Arkansas Power & Light Company CNelson 4 Q M OF L2 P. O. Box 551
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Little Rock, Arkansas 72203 pj
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Ibar Mr. Cavanaugh:
lie have completed our review of your letter dated December u 7, sup-plemented by letter dated February 19, 1980 in response to our letter dated September 15, 1977, conceming the potential for and consequences of boron dilution accidents at Arkansas fluclear One, Unit !!o.1 (AfiO-1).
The results of this review am contained in the enclosed Technical Evaluation Report by the Franklin Research Institute.
Based on this review we have concluded the following:
As a result of modifications of certain operating procedures by Arkansas Power & Light Company (AP&L), there is no testing which can result in advertent moderator dilution because of misposition of a single fla0ll tank isolat.on valve.
The nodification of operating procedures to further isolate the fla0!!
tank during refueling canal fill using LPI punps significantly reduces the potential for inadvertent boron dilution and does not adversely affect other engineered safety feature systems.
APat's review of boron dilution incidents at Afl0-1 did not reveal potential incidents rare limiting than that analyzed in the FSAR.
Based on the above conclusions we have detemined your responses to our letter dated September 15, 1977, to be acceptable.
If you have any questi6ns on this subject, please contact your ilRC Project !!anager.
Sincerely,
'0RIGINAL SICTE'D BY JC:C" ~ ZT 8108310565 010814 John F. Stolz, Chief PDR ADOCK 05000 Operating Reactors Branch #4 P
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. Mr. William Cavanaugh. III
Enclosure:
Technical Evaluation Report Re: PWR lbderator Dilution By Franklin Research Center cc w/ enclosure:
See next page
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