ML19326B534

Interim Deficiency Rept:On 730601,valve Wall Thickness Verification Program Revealed Six Nuclear Class I Check Valves Failed to Meet Requirements of Draft ASME Code for Pumps & Valves.Valves Will Be Repaired

ML19326B534
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/02/1973
From:	Phillips J ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19326B531	List: ML19326B534
References
NUDOCS 8004160325
Download: ML19326B534 (2)

Text

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FS&E3 ACTION COTT20L FORM JUL 171973 .

A. Action Code 131 Name of Licensee and Facility Arkansas Power & Light (Arkansas Nuclear

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Docket No. or License No. 50-313 Title CDR Evaluation and Followup Origin CDR Date Rec'd 7/10/73 B. FS&EB Branch Coordinator: , ,

Bryan Dreher Ellis Paulus X Complet),on Requested by C. Action Requested of:

ADREMP M&PPOB EPB RPB ADC0 OB CB TAB 00E Region II Date Requested 7/12/73 Completion Requested by Reference Let.ter dated July 2, 1973 from J. D. Phillips to D. F. Knuth s . '.

i D. Action Requested - -

In cecordance with PI 0600/6, " Construction Deficiency Reporting"';

I the Arkansas Power & Light Company (Arkansas Nuclear One - Unit 1) deficiency report of 7/2/73 covering thin walled valves is being

, assigned to Region II for evaluation of the technical adequacy of the corrective action and the final resolution of the deficiency.

E. Date Action Completed Close-out (Date & Method)

Comments: If completion date is not consistent with your work schedule, please let us know. =

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G. Davis #, Deputy Director for Field Operations Directorate of Regulatory Operations s0041"' .l l

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ARKANS AS POWER & LIGHT COMPANY STM Avenue AN. PINE STREET

• PIN. BLUFF, AAKANSAS 71601,(5 13534-1330 July 2, 1973 Mr. D. F. Knuth Director of Regulatory Operations United States Atomic Energy Commission

SUBJECT:

ARKANSAS POWER & LIGHT COMPANY ARKANSAS NUCLEAR ONE - UNIT 1 DOCKET No. 50-313 SIGNIFICANT DEFICIENCY REPORT

Dear Mr. Knuth:

The following is a report submitted as required by 10 CFR 50.55(e) concerning a deficiency identified to the Principal Reactor Inspector assigned to Arkansas Nuclear One, Unit 1, by telephone on June 1,1973, relating to nine (9) twelve inch and fourteen inch check and gate valves procured from Velan Engineering Company.

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\s/ During the conduct of AP&L's valve wall thickness verification program of primary pressure boundary valves, six (6) nuclear Class I check valves were found that did not meet the requirements of Table 452.1 of "Draf t ASME Code for Pumps and Valves for Nuclear Power" and three (3) Class II gate valves were found that do not meet minimum wall requirements of ANSI B16.5.

Subsequent investigation indicates that the three (3) Class II gate valves have acceptable wall thickness because for these valves MSS-SP-66 and ASNE Code Case 1329 are applicable.

We anticipate that repair work for the six (6) Class I check valves will be performed at the nuclear plant site by the valve manufacturer.

The manufacturer (Velan) is presently obtaining ASME Code authorization for these repairs. Velan's welding procedure has been received and approved and an additional repair procedure is under review. This work will not affect the scheduled completion of the preoperational testing program. ,

Very truly yours,

'J. D. PHILLIPS Senior Vice President .-

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Mr. D. F. Knuth 2- July 2, 1973 -,

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!. cc: Mr. Norman C. Moseley, Director '

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Region II I 230 Peachtree Street, N.W., Suite 818 l

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