ML19256E684
| ML19256E684 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/02/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 7911150015 | |
| Download: ML19256E684 (3) | |
Text
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[e wo, UNITED STATES E'
'i NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
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November 2,1979
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g Docket No. 50-313 Mr. William Cavanaugh, III Vice President, Generation and Construction Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203
Dear Mr. Cavanaugh:
We have reviewed your letters dated December 29, 1978, January 30, 1979, April 2,1979 and August 22, 1979, concerning the containment purge and vent system at Arkansas Nuclear One, Unit No. 1.
In order to complete the mechanical review of this issue, we need additional information identified in the enclosure.
You are requested to provide the information within 45 days.
Sincerely, Q s/J Ui 2 J Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
Request for Additional Information 1333 155 cc w/ enclosure:
See next page 7911150 C /
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Arkansas Power & Light Conpany cc:
Phillip K. Lyon Esq.
l House, Holms & Jewell 1550 Tower Building Little Rock, Arkansas 72201 Mr. David C. Trimble j
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 Comission P. O. Box 2090 Russellville, Arkansas 72801 Mr. Robert B. Borsum Babcock & W',1cox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Troy B. Conner, Jr., Esq.
Conner, Moore & Corber 1747 Pennsylvania Avenue, N.W.
Washington, D.C.
20006 Arkansas Polytechnic College Russellville, Arkansas 72801 1333 156
i Enclosure
[
.2 REQUEST FOR ADDITIONAL INFORMATION FOR CONTAINMENT PURGE SYSTEM AND CONTAINMENT VENTING SYSTEM FOR ARXANSAS NUCLEAR ONE, UNIT 1 I
i DOCKET NO. 50-313 1.
With regard to the containment purge and venting system, provide the following information:
a.
Discuss the provisions made to ensure that isolation valve closure will not be prevented by debris which could poten-tially become entrained in the escaping air and steam.
b.
Discuss the provisions made for testing the availability of the isolation function and the leakage rate of the isolation valves, individually, during reactor operation.
Provide an analysis to demonstrate the acceptability of the c.
provisions made to protect structures and safety-related equipment; e.g., fans, fil ters, and ductwork, located beyond the purge system isolation valve against loss of function from the environment created by the escaping air and steam, d.
For the containment purge isolation valves, specify the differential pressure across the valve for which the maximum leak rate occure.
Further, provide test results (e.g., from vendor tests of leakage rate versus valve differential pressure) which support the above data, e.
Provide an analysis of the reduction in the containment pressure resulting from the partial loss of containment atmosphere during the accident for ECCS backpressure deter-mination.
2.
Provide a schematic drawing of your purge and vent system.
1333 157 l
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