ML19317F847

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Forwards RO-76-03.Provides Details
ML19317F847
Person / Time
Site: Rancho Seco
Issue date: 04/16/1976
From: Mattimoe J
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML19317F848 List:
References
NUDOCS 8002210590
Download: ML19317F847 (1)


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SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, Box 15830, Sacramento, California 95B13; (916) 452 3211 ee e, ei

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i April 16, 1976 I

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Mr. R. H. Engelken 9j e

Director of Regulatory Operations e\\

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Region V, NRC Operations Office

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V-Mi 1990 N. California Boulevard Walnut Creek Plaza, Suite 202 fg bb C

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Walnut Creek, California 94596 2

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Re: Operating License DPR-54 v.5 ",Th,,,eawar p' (9

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Docket No. 50-312 cf Reportable Occurrence 76-3 j

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Dear Mr. Engelken:

  • l As defined by Technical Specifications for Rancho Seco Nucl, ear Generating Station, Section 6.9.1, and Regulatory Guide 1.16, Revisicn 4,.

Section C.2.b.4, the Sacramento Municipal Utility District is hereby reporting the following Reportable Occurrence as RO 76-3.

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79 A report on March 18, 1976, stated that during a routine check of l

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plant equipment leakage was noted from the bypass line to the suction

d isolation valve (SIM-001) of the makeup pump. The reactor was operating in steady state operation at 81.5% power. A temporary repair to prevent further leakage was made by peening the weld area and making a single weld pass. This fix stopped leakage until the plant could be shut down f'

on April 4.

During the shutdown a Work Request was written to have the weld

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ground out completely, revelded in accordance with the Rancho Seco procedure M.113-8 (velding austenitic stainless steel to austenitic steel). The Work Request requires testing of the new weld to meet the requirements of Quality Assurance Procedure QCI-101 for liquid penetrant testing on the initial and final weld passes and a hydrostatic test of the piping following completion of the weld.

The original weld was made by the Architect-Engineer (Bechtel Co.)

,4 during the construction period at Rancho Seco and was liquid penetrant tested at that time. Vibration levels were measured on the line while the makeup pump was operating and indicated only 1.0 mil.

It was determined that vibration was not the cause of the failure.

It was determined that the weld was probably defective, due to the appearance of the weld and the absence of any indication of other possible causes.

2, There was no transient associated with this occurrence.

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/G, Respectfully submitted, g'

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Mattimoe Assistant General Manager JJM:RWC: sal and Chief Engineer j

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