ML19339C943

Final Deficiency Rept Re Post Weld Heat Treatment Penetration Pieces,Initially Reported on 800924.Technical Review Proved Subassemblies Were Fabricated in Compliance W/Asme Code.Deficiency Is Not Reportable Under 10CFR50.55e

ML19339C943
Person / Time
Site:	Millstone
Issue date:	10/24/1980
From:	Counsil W NORTHEAST NUCLEAR ENERGY CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19339C942	List: ML19339C943
References
10CFR-050.55E, 10CFR-50.55E, 10CFRR-50.55E, AEC-MP3-223, B101113, B10113, NUDOCS 8102120488
Download: ML19339C943 (2)

Text

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October 24, 1980 Docket No. 50-423 AEC-MP3-223 B10ll3 Mr. Boyce H. Grier, Director Region I Office of Inspection and Enforcement.

U.S. Nuclear Regulatory Coc=iission 631 Park Avenue King of Prussia, Pennsylvania 19406 J Gentlemen:

Millstone Nuclear Power Station, Unit No. 3 Reporting of Deficiencies in Desien and Construction As required by Title 20, Code of Federal Regulations Part 50, Paragraph 55(e), we reported on Septe=ber 24, 1980 a Potential Significent Deficiency in the design of

.1 stone Unit No. 3 to your representative Mr. McGat.ghy.

Our report of a Potential Significant Deficiency was based on a letter from Graver Tank, Inc. describing possible code interpretations which might question the fabri-cation of the Millstone Unit No. 3 Containment Liner. A technical review was per-

for=ed by NUSCO and Stone & Vebster Engineering Corporation with the results as l follows

1) n e Millstone Unit No. 3 Liner was fabricated in accordance with the ASME Section III Code 1971 Edition and all addenda through Su==er 1973.

In aedition, the requirements of Safety Guide 19 were included in the ,

design and construction of

• he Containment Liner.

2) The ASME Section III c.ae, 1971 Edition through Su=mer 1973 addenda, did not classify penetrations as nozzles or similar welded construction.

Therefore, the Containment Liner penetration subassemblies were post-l weld heat treated in accordance with the applicable requirements of Par. NE-4621.1.

l Baed on the above, it is concluded that there was no deviation from the requirements of the PSAR and procurement documents in the fabrication of the containment penetration l subass e='alies . Therefore, the condition reported in the Graver letter of August 15, l 1980 to Northeast Utilities and further reported to the NRC as a Potential Significant 1

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810 212018D

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Deficiency is not reportable under 10CFR50.55(e) requirements.

We trust that this thirty (30) day report closes out this issue.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

/rA :

W. d. Counsil '

Senior Vice President cc: Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555

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