ML19210E857

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Provides Supplemental Response to IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping. Program Initiated to Assure That All 2.5 Inch & Larger Pipes Meet Design Requirements
ML19210E857
Person / Time
Site: Yankee Rowe
Issue date: 11/14/1979
From: Groce R
YANKEE ATOMIC ELECTRIC CO.
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
IEB-79-14, NUDOCS 7912130096
Download: ML19210E857 (2)


Text

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g Teleph6ne bl7 3t a-90\\l 710-390-O*39 YA. L't2 ATOMIC El.ECTRIC 00iAPANY y.);%,

20 Turnpike Road Westborough, Massachusetts 01581 Y

9~ amass November 14, 1979 United States Nuclear Regulatory Ccmmission Office of Inspection and Ehforcemnt Region I 631 Park. Avenue King of Prussia, PA 19406 Attention:

Mr. Boyce H. Grier Director

References:

(a)

License No. DPR-3 (Docket 50-29)

(b)

USNRC Ietter to YAEC dated July 2,1979 I&E Bulletin 79-14 (c)

YAEC Ietter to USNRC dated July 18, 1979 Gentlemen:

Subject:

Sumlemntal Response to I&E Bulletin 79-14 Since our original response, Reference (c), to Bulletin 79-14 we have initiated a program to assure that all piping 21/2 inches in diamter and larger, including supports for safety class systems in Yankee Nuclear Power Station met design requirefrents.

We schedule, preriously discussed with unbers of your staff, will be coupleted as follows:

Complete as-built verification in accessible areas prior to Mcenber 1,1979.

Complete as-built verification in inaccessible areas prior to canpletion of the next scheduled refueling outage.

21s schedule was satisfactory to your staff contingent on completion of a preliminary review of piping inside the vapor container during the recent repair autage. No major differences were found upon completion of the preliminary review of all piping in the vapor containment. A nunter of mincr differences between the original plant design drawings and existing hardware were found.

All of these were additional to those required in the original design, and were found to be acceptable to Yankee Nuclear Services Division engineering.

1543 238 7012i o 076

.yy, United States Nuclear Regulatory Comission November 1979 Attention:

Mr. Boyce H. Grier, Director Page 2 The final verification survey will include the following features of piping and supports:

Pip size and geonetry Hanger location Hanger details, including function clearances and attachments Valve type and orientation Discrepancies found in this process will be documented and reviewed by Yankee engineering for disposition. Minor deviations will be dispositioned to use as-is without drawing change. Major deviations from design requiremnts will require drawing modification. These will also be reviewed for structural adequacy within 30 days of their identification. Disposition of any deviation frcm design requirements identified to affect operability of a safety system will be executed in complete compliance with applicable technical spcification requirements.

We are confident this plan as chveloped, will meet the intent and concerns expressed in I&E Bulletin 79-14.

If, however, you desire additional information, please contact us at your convenience.

Very truly yours, k

IAAh Robert H. Groce I

Senior Engineer - Licensing r

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