ML19248D489
| ML19248D489 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/25/1979 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 7908160324 | |
| Download: ML19248D489 (4) | |
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.h y S gg Docket No.: 50-368 Mr. William Cavanaugh, III Executive Director for Generation & Construction Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203
Dear Mr. Cavanaugh:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING IE SULLETIN 79-063 We have reviewed yuur responses to IE Bulletin 79-063 for the Arkansas Nuclear Plant which were transmitted by letter dated April 24, 1979.
Our review cf your responses has led us to believe that you have a general understanding of our concerns arising from the TMI-2 incident in relation to their implications to the operation of the Arkansas Nuclear Plant.
Nevertheless, we have dis-covered some deficiencies in your responses which must be resolved before we issue cur safety evaluation for the Arkansas Nuclear Plant.
The resciution of these deficiencies is contingent upon receiving ca.plete and acceptaole responses to the questions in Enclosure 1.
As a result of our continuing review of the TMI-2 incident, we may impose other corrective actions in addition to those in IE Sulletin 79-065.
In the interim, if you need any clarification of the enclosed questions, please contact Mr. I. Villalva, the staff's assigned project manager for Sulletins and Orders involving C-E designed reactors.
Mr. Villaiva may be reached on (301) 49?-
7745.
In order to ensure a timely response to the items in the enclosure, we previcusly transmitted to you a facsimile of said enclosure via telephone.
Accordingly, we request that responses to the items in the enclosure be forwarded to this office approximately two weeks after receipt of the enclosure, but no later than August 10, 1979.
Sincerely,
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q Jcon F. Stolz, Chief)
(dght Water Reactors, Branch No. I Division of Project Management
Enclosure:
Request for Additional Ir. formation oJ.n
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- cc w/encisoures: See next page 7908160 329' f
Arkansas Power & Light Company cc:
Phillip K. Lyon, Esq.
House, Holms & Jewell 1550 Tower Building Little Rock, Arkansas 72201 Mr. David C. Trimble Manager, Licensing Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203 Mr. James P. O'Hanlon General Manager Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Mr. William Johnson U. S, Nuclear Regulatory Commission P. O. Box 2090 Russellville, Arkansas 72801 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Troy B. Conner, Jr., Esq.
CJnner, Ibore & Corber 1747 Pennsylvania Avenue, N.W.
Washington, D.C.
20006 Arkansas Polytechnic College Russellville, Arkansas 72801 (3331'.'1.
REQUEST FOR ADDITIONAL INFORMATION REGARDING IE BULLETIN NO.79-06B ARKANSAS NUCLEAR ONE, UNIT NO. 2 DOCKET NO. 50-368 As a result of the review of the ANO-2 responses to Bulletin No.79-063, we find that the folicwing additional information is required.
The item numbers correspond to th' balletin action item and the related licensee response.
2.a Identify the availability and use of parameters required to verify that the natural circulation mode of operation has been established.
3.
Provide a comitme.:t for assuring manual initiation of CI upon actuation of the SIAS until such time as your long term modifications, as stated in your response to this bulletin item, are completed.
Also, provide assurance that you will initiate a manual override for the valves in the component cooling water system to the RC pump cool-ers upon actuation of CI provided this action does not lead to unsafe plant conditions.
6.b Provide assurance that operating procedures will be modified to keep high pressure injection and charging pumps in operation in accordance with the criteria as provided in Item 6.b of the bulletin, and as clarified by the following statement:,
"After 50F subcooling has been achieved, termination of high pressure safety injection (HPI) operation prior to 20 minutes is only per-missible if it has been determined that cont-inued operation would result in an unsafe plant condition, e.g., attaining pressure / tempera-ture conditions that could jeopardize vessel integrity or that could have the potential for opening the PORVs or safety valves so as to discharge water or a two-phase fluid consisting of water and steam."
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. 7.
Provide assurance that all locked safety related valves are positioned and maintained in the appropriate position for all modes of operation.
11.
Revise your procedures, as necessary, to ensure NRC notification within one hour of the time the reactor is not in a controlled or expected condition of operation.
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