05000369/LER-1981-192, Forwards Updated LER 81-192/03X-1.Detailed Event Analysis Encl

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Forwards Updated LER 81-192/03X-1.Detailed Event Analysis Encl
ML20041D662
Person / Time
Site: McGuire Duke Energy icon.png
Issue date: 02/22/1982
From: Parker W
DUKE POWER CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20041D663 List:
References
NUDOCS 8203080589
Download: ML20041D662 (2)


LER-1981-192, Forwards Updated LER 81-192/03X-1.Detailed Event Analysis Encl
Event date:
Report date:
3691981192R00 - NRC Website

text

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Re: McGuire Nuclear Station Unit 1 Docket No. 50-369

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Dear Mr. O'Reilly:

Please find attached Revision 1 to Reportable Occurrence Report R0-369/81-192.

The original report was submitted by my letter dated January 21, 1982. This report concerns T.S.6,9.1.13(c), " Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems".

This incident was considered to be of no significance with respect to the health and safety of the public.

Note that this occurrence also involves Unit 2, which was reported via 50.55(e)

Report No. SD-370/81-12.

Very truly yours, j :[.

William O. Parker, Jr.

PBN/jfw Attachment cc: Director Records Center Office of Management and Program Analysis Institute of Nuclear Power Operations U. S. Nuclear Regulatory Commission 1820 Water Place Washington, D. C.

20555 Atlanta, Georgia 30339

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Mr. P. R. Bemis Senior Resident Inspector McGuire Nuclear Station OFFICI A1. co! y u.-

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DUKE POWER COMPANY McCUIRE NUCLEAR STATION j

REPORTABLE OCCURRENCE REPORT 81-192 (Update)

REPORT DATE: February 22, 1982 j

FACILITY: McGuire Unit 1 Cornelius, NC IDENTIFICATION OF DEFICIENCY: Circumferential butt welds on ASME Class 1 piping previously identified as " flush" may not meet the stringent require-ments of the ASME Code criteria as defined in Table NB-3683.2-1, footnote (2)(a). Specifically, the requirement that the finished contour of the weld shall not exceed a 70 slope had not been satisfied at the weld I.D.

This

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deficiency was first identified December 16, 1981.

J DESCRIPTION OF DEFICIENCY: The initial deficiency was first identified by 4

a Catawba Nuclear Station NCI which reported that certain butt welds do not meet the ASME Code criteria for being flush as defined in Table NB-3683.2-1.

J This NCI specifically pointed out that the I.D. of the weld did not meet the 70 contour as stipulated in footnote (2)(a) of that table. Furthermore, a review determined that the Catawba Construction procedure for flush welds may not provide adequate assurance that the weld contour on the I.D. is <70 a review of the corresponding McGuire Nuclear Station procedure indicates that similar conditions exist for McGuire flush welds.

ANALYSIS OF SAFETY IMPLICATIONS: The existing welding and Non-destructive Examination procedures for flush welds were reviewed to determine the " worst case" weld profile associated with the weld I.D.

This " worst case" weld profile was then analyzed by Duke Power Company to determine the stress indices associated with it.

This was accomplished by employing the analy-tical procedures outlined in the ASME Code.

The results of this analysis

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verify that the stress indices associated with the Duke Power flush weld are equivalent to those associated with ASME Code flush welds.

Therefore, the existing piping analysis calculations remain valid, and there is no impact on plant safety, i

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CORRECTIVE ACTION

Construction procedures will be revised as required to correctly define the profile for the Duke Power flush weld. The defined profile will be the " worst case" profile used in the previously described e

analysis. All future flush welds will be compared to this defined profile.

I The affected Construction procedures will be revised by April 1, 1982.

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