ML20054B029

Significant Deficiency Rept 50-413/82-07 Re Anchors Overtorqued Beyond Specified Limits,Initially Reported 820303.Investigation in Progress to Determine Corrective Actions.Final Rept Will Be Completed by 820701

ML20054B029
Person / Time
Site:	Catawba
Issue date:	04/02/1982
From:	Parker W DUKE POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8204160287
Download: ML20054B029 (2)

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e DUKE POWER COMPANY Pown.a Buitmixo 422 Sourn Cnuacu STazer, CiuunnTTE, N. C. 202.s2 wiwau o. pAnnen,an. ., .

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> r ec Mr. James P. O'Reilly, Regional Administrator ..

U. S. Nuclear Regulatory Comission .r -

Region 11 rc 101 Marietta Street, Suite 3100 ~

Atlanta, Georgia 30303 Re: Catawba Nuclear Station Unit 1 Docket No. 50-413

Dear Mr. O'Reilly:

Pursuant to 10 CFR 50.55e, please find attached Significant Deficiency Report SD 413/82-07.

(D t 9 Very truly yours,

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William 0. Parker, Jr

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-l EA ta _I RWO/php Q#'$ncQ$$jiris, Attachment 'e ig/,a }

I l cc: Director Mr. Robert Guild, 4 Office of Inspection and Enforcement Attorney-at-Law U. S. Nuclear Regulatory Commission 314 Pall Mall Washington, D. C. 20555 Columbia, South Carolina 29201 t

Mr. P. K. Van Doorn Palmetto Alliance

! NRC Resident Inspector 2135h Devine Street Catawba Nuclear Station Columbia, South Carolina 29205 l

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i gl'iCI AL COI'Y w-8204160287 820402 gDRADOCK05000 s{

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CATAWBA NUCLEAR STATION

1. Report Number: SD 413/82-07

2. Report Date: April 2,1982

3. Facility: Catawba Nuclear Station, Unit 1

4. Identification of Deficiency: Overtorquing of concrete expansion anchors identified on February 10, 1982.

5. Initial Report: Mr. H. Dance of NRC Region II was notified on March 3,1982, by W. O. Henry, Duke Power Company, 422 S. Church Street, Charlotte, NC 28242.

6. Supplier: Concrete expansion anchors are supplied to Catawba by ITT-Phillips.

7. Description of Deficiency: QC inspections of pipe support installations revealed l a number of anchors which had been overtorqued beyond specified limits. A sampling program was undertaken to determine the extent of the problem. This resulted in the identification of additional overtorqued anchors.

8. Analysis of Safety Implications: By overtorquing, an anchor may be overstressed such that its ability to carry design loads is diminished. This may lead to failure of pipe supports which may, in turn, impair safe operation of the plant.

Testing to determine the effects of overtorquing on bolt stress is incomplete at this time.

9. Corrective Action: Investigations to determine what, if any, corrective actions may be required are incomplete and inconclusive at this time. These investigations will be complete by July 1,1982. A final report will be filed by that date.

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