IR 05000313/1971005
| ML19326B568 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/28/1972 |
| From: | Jennifer Davis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8004160350 | |
| Download: ML19326B568 (3) | |
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UNITED STATES
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ATOMIC ENERGY COMMISSION Division OF COMPLIANCE Me
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REGIO N 18 - Su s T E 818
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230 PE ACHT REE ST REET, NORT HWEST g
AT t. ANT A GECRGI A 30303 In Reply Refer To:
January 28, 1972
'CO:II:VLB 150-313/71 '5 50-368/T1-6
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Arkansas Power and Light Company Attn: Mr. J. D. Phillips Vice President and Chief Engineer Sixth and Pine Streets Pine Bluff, Arkansas 71601 Gentlemen:
This refers to the inspection conditeted by Messrs. Brownlee, Crossman, and Cochran of this office on November 3-5, 1971, of activities authori::ed by S
AEC Construction Permit No. CPPR-57 for the Arkansas Nuclear One, Unit 1
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facility and of your quality assursnee program for work to be performed under an exemption from the requirements of 10 7.3 50.10 for the Arkansas Nuclear One, Unit 2 facility. Our findings ve'.e discussed by Mr. Brownlee with Messrs. Moore, Bland, and Bean ef yot.r staff and Messrs. Curtis, Loth, and Zampieri of Bechtel Engineering Corporation (Bechtel) at the conclusion of the inspection.
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Areas examined during the inspection included installation of electrical and instrumentation.omponents and cable, the program for primary loop erection,
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transport and setting of primary loop ma,jor mechanical components for Unit 1, cud construction activities authorized by the construction permit exemption for Unit 2.
Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with site personnel, and observations by the inspectors.
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During the inspection, it was found that certain of your activities appeared
l to be in noncompliance with AEC requirements. The item and reference to the l
pertinent requirements are included in the enclosure to this letter.
Since
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corrective sction was taken prior to completion of the inspection, you need (
not reply concerning this item.
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As discussed with representatives of your staff, certain items were unre-solved at the conclusion of the inspection. With regard to separation of safety channel equipment, the inspectors observed that power supplies for
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two safety channels were contained in the same cable tray and utilized the (L
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v Arkansas Power and-2-January 28, 1972 Light Compt ny same color coding. Tbis item has been referred co Regulatory Headquarters for further evaluatica. We vill advise you of the results of this evalua--
tion when it is completed.
With regard to failure of the hydrostatic seal and journal.of the main coolant pump and subsequent modifications by the supplier, it is our under-standing that the pump will be retested to assure adequacy of the modified design. This item vill be examined during subsequent inspections.
With regard to the unscheduled descent of the pressurizer vessel during handling, it is our understanding that ultrasonic examination of the top end area vill be performed during the in-service baseline testing. This
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item will be examined during subsequent inspections.
A reply to_this letter is not necessary; however, should you have any ques-tions concerning this letter, you may comnunicate directly with this office.
Very truly yours, O
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Jo G. Davis Director Enclosure:
Description of Item of Ncncompliance
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Q ENCLOSURE DOCKET NOS. 50-313 50-368
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Certain items appear to be in noncompliance with 10 CFR 50, Appendix B,
" Quality Assurance Criteria for Nuclear Power Plants," as indicated below:
Criterion IX, " Control of Special Processes," states, " Measures shall be established to assure that special processes, including velding, heat treating, and nondestructive testing, are controlled and accomplished by qualified personnel using qualified procedures in accordance with applicable codes, standards, specifications, criteria, and other special requirements."
Contrary to the above, the inspector observed that field veld No.
FW CCA-6-5 in the core f1 coding system of Unit 1 was undergoing repair although the required veld traveler, Form WR-5, " Welding Check List," was not available at the veld.
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