ML19326B737
| ML19326B737 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/28/1972 |
| From: | Meek J ARKANSAS POWER & LIGHT CO. |
| To: | Jennifer Davis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19326B720 | List: |
| References | |
| NUDOCS 8004170569 | |
| Download: ML19326B737 (2) | |
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ARK ANS AS POWER G LIGHT CCMPA NY GTH G LOUISTANA GTAEETS
- LITTLE HOCK, ARK ANCAD 7D203. [301) 373-4311 July 28, 1972 Mr. John G. Davis, Director Region II Directorate of Regulatory Operations Region II - Suite 818 230 Peachtree Street, Northwest Atlanta, Georgia 30303
Subject:
Arkansas Power & Light Company ex Arkansas Kuclear One-Unit 1
(
)
Docket No. 50-313 Verification of Records of Valves Innortant to Nuclear Safety
Dear Mr. Davis:
In response to your letter of June 30, 1972, regarding the verification that valves c'rer one inch nominal pipe size important to nuclear safety within the roe.ctor coolant pressure boundary vill meet the minints *vall thiclmess requirements, the following information is submitted.
The purchase of Arkansas nuclear One-Unit 1 valves was generally based on the proposed ASME Nuclear Pump and Valve Code. This code did not require documented verification of vall thiclmess on valves. For this reason, vc believe that the request for compliance with documentation of valve vall thickness verification is the imposition of new standards which are not applicable to Arkansas nuclear One-Unit 1.
Reasonable compliance with your request vill be proposed in the following manner:
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Valves important to Nuclear Safety within the reactor coolant pressure boundary greater than 2 " vill be ultrasonically tested to verify vall thickness and dccumented with records which will be available at the plant site. Acceptable documentatien vill 7
be supplied on these valves within the allotted time of three (3) years from the date of your letter (June 30,1972).
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Mr. &an C; Davic July 28, 1972 Valves important to rn'eler safety vithin the ren: tor ecclant pressure boundary C/' and smaller have b;;ea r.uufuetured from forced material.
Since the valvec are ninufactured from forged material and have vall thicknesses specially designed in excess l
of code requirements it is believed thc.t verification of vall l
l thicknesses should not be required. Ultrasonic testing of valvec 2h" and cmaller is difficult and produces inconclusive re:, ult c.
i Decumentation of vall thickness verification is presently available at the plant site for six (6) valvec important to nuclear safety and greater than 2\\".
Thase records are available for your examination at any time of your preference.
t Very truly yours, Q'y a...- l;,,a -
V John Meek Vice President JM:lt i
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