ML19318B900

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Responds to IE Bulletin 80-02, Inadequate QA for Nuclear Supplied Equipment. Improved Interference Fit Spargers & Thermal Sleeves Mfg for Facility,But Not Yet Installed. No Performance History Available
ML19318B900
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 05/29/1980
From: Novarro J
LONG ISLAND LIGHTING CO.
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
IEB-80-02, IEB-80-2, NUDOCS 8006300267
Download: ML19318B900 (2)


Text

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1 LONG ISLAND LIGHTING COM PANY l

(O i SHOREHAM NUCLEAR POWER STATION g

- w P.O. BOX 618. NORTH COUNTRY ROAD + WADING RIVER. N.Y.11792 SNRC-476 May 29, 1980 Mr. Boyce Grier Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa 19406 IE BULLETIN 80-02 SHOREHAM NUCLEAR POWER STATION - UNIT 1 DOCKET NO. 50-332

Dear Mr. Grier:

IE Bulletin 80-02 describes deficiencies in the implementation of the Marvin Engineering Company (MEC) quality assurance program relative to the manufacture of feedwater spargers and thermal sleeves.

General Electric has advised us that MEC did manufacture a set of improved interference fit spargers end thermal sleeves for Shoreham under their Purchase Order Numbers 205-XC173 dated 9/8/78 and 205-G5Fil dated 8/16/77.

G.E. applied Quality Assurance Requirements - II to this order and MEC applied their Q.A. Manual Number 7, Revision O.

This hardware has not yet been installed at Shoreham.

Therefore, no performance history is available as requested by Item 2 of IE Bulletin 80-02.

A detailed description of this equipment and its design function is contained in General Electric's ' NEDE-21821-A" which was accepted by the NRC on January 14, 1980.

In accordance with G.E. design require-ments, this equipment is not classified as a safety essential component.

As such, the integrity of this equipment should not effect plant operation.

Our review has concluded that the G.E. equipment classifi-l cation has been appropriately e.pplied with respect to the design function of these components.

Further, the Q.A./Q.C. programs imple-mented during fabrication were sufficient with respect to the design function of this equipment.

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May 29, 1980-Mr. B. Grier - SNRC-476 Page two Should you have further questions concerning this matter, please contact us.

Very truly yours, j

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,t"2~JsAc J. P. Novarro

'# Project Manager Shoreham Nuclear Power Station CKS:me cc:

Mr. Victor Stello, Direct"or NRC Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D.C.

20555 Mr. J. Higgins Site NRC Trailer s

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