ML19262A976

Interim Deficiency Rept Re Broken Anchor Bolt in Reactor Vessel Support Skirt Flange.Anchor Stud Purchased from Ms Valley Structural Steel Co,Who Procured Matl from Southern Bolt & Fastner Corp

ML19262A976
Person / Time
Site:	Midland
Issue date:	12/05/1979
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML19262A968	List: ML19262A967 ML19262A976
References
NUDOCS 7912110373
Download: ML19262A976 (2)

Text

Date: 12/5/79

SUBJECT:

3ROIEN REACTOR VESSEL ANCHOR STUD IN UNIT 1 STATUS REPORT Introduction This report summarizes the additicnal action taken to date to determine the failure mechanism of the subject anchor stud and corrects the identity of the procurement source for the stud that failed.

History of Fsiled Stud The anchor stud that failed was identified as stud number 35, and was in-correctly located en Figure 1 of the previous status report. More ccrrectly, the stud has no specific ncnerical identifier, the cited nunber 35 being only the Babecck and W11ccx tensicning sequence identifier. The revised Figure 1 attached clarifies the identified position of the stud.

This stud var purchased frem Mississippi Valley Structural Steel Ccmpany who procured the material frem Southern Bolt and Fastener Corpcration. The material originated frca 3ethlehe: Steel, was heat treated by J W Rex Cc=pany of Lansdale, Pennsylvania, for Southern Bolt and Fastener Corpcration, and ec=pleted and shipped by Southern Bolt and Fastener Corporatien directly to Bechtel.

Investigation plan Bechtel, as agents for Censumers Power Cc=pany, has entered into a Technical Services Agreement with Teledyne Engineering Services of Waltha=,

Massachusetts, for testing and censultant services to determine the cause of the failure. The prcgram fcr planned testing remains as described in the previous statas report.

The testing commenced on November 15, 1979 with non-Destructive Exsninatien.

The expected completion date for the planned series of tests is mid-January, 1980, with results available by mid-February,1980. After the results are received frem Teledyne and reviewed, a ecurse of action to correct this deficiency vill be deter =ined.

Safety Imolicatiens Based on preliminary analysis, it is judged that the failure of a single anchor stud does not represent an impediment to the safety-related support requirements for the reacter vessel. Overall safety implications vill be further evaluated upon receipt of test data.

_ Recortability This ccndition . remains in the potentially reportable category pending the results of the currently in progress testing program.

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