IR 05000313/1972002
| ML19326B685 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/23/1972 |
| From: | Jennifer Davis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8004170525 | |
| Download: ML19326B685 (2) | |
Text
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L G DJI REGION 84 - Sua f E 013 { 230 P E A C HT R E E 31*R E ET. *40R T H W EST g ,
v AT t.A NT A, GEORGI A 30303 44tg 44 DIRECTORATE OF REGULATORY OPERATIONS MAY 231972 . In Reply Refer To: ) , RO:II:VLB . 50-313/72-2 50-368/72-2 . Arkansas Power and Light Comp =r/ Attn: Mr. J. D. Phillips ' Vice President and Chief Engineer Sixth and Pine Streets Pine Bluff, Arkansas T1601 , b Gentlemen: This refers to the inspection conducted by Messrs. Brownlee, Crossman, 28-30, 1972, of activities authorized by AEC Con-Swan and Jape on March struction Permit No. CPPR-57 for the Arkansas Nuclear One, Unit 1 facility ' and of your quality assurance pregram for verk to be perfomed under an exemption from the requirements of 10 CFR 50.10 for the Arkansas Nuclear Our findings were discussed by Mr. Brownlee with One, Unit 2 facility.
Messrs. Moore, Bland, and Bean of your staff, and Messrs. Zampieri and Sly of Bechtel Engineering Corporation at the conclusion of the inspection.
Areas examined during the inspection included the installation of electrical and instrumentation components and cable, piping systems, major pri=ary , ' pressure boundary valves, and the post-tensioning system; containment liner erection for Unit 2, control of drawings, and control of measuring and test ' equipment onsite.. . Within the scope of this inspection, there were no items of noncompliance identified.
, We have examined the actions you have taken with regard to uniformity of veld transitions between piping and valves or fittings identified in our . ' letter of January 24, 1972, and ultrasonic testing of the top end of the ,) pressurizer vessel identified in our letter of January 28, 1972.
In addi-i l;p)_ tion, the inspectors examined the actions you have taken with regard to our letter of December 9,1971, concerning a' scram breaker failure at , V nnether facility. We have no further questions concerning these items.
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' ' i f} h0 g 'Q-2 . i ht Comp y . . From discussions with,a member of your staff, it is our understanding that you will determine the applicability to your facility and conduct an eval-untion of the failure of a reactor in-core. instrument gui,C' tube which We vill examine this' item further on a:sub. occurred at another facility.
sequent inspection.
As discussed with members of your staff, our records indicate that two items remained unresolved and vill require additional review by our inspectors.
The items were the main steam relief valve manifold stress evaluation iden - tified in our letter of December 10, 1971, and the tendon wire stressing washer, identified in our letter of January 24, 1972.
A reply to this letter is not necessary; however, should you have any questions concerning this letter, you may communicate directly with this office.
cry truly yours, e ' . . John G. Dav'is Director , _,.
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