ML20054C460

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Submits Special Rept 82-04 Re Results of Two Reactor Bldg Insps Performed Mar & Sept 1981.Insps Performed in Accordance W/Util Surveillance Procedure Sp 205.4
ML20054C460
Person / Time
Site: Rancho Seco
Issue date: 03/24/1982
From: Mattimoe J
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20054C461 List:
References
NUDOCS 8204210121
Download: ML20054C460 (2)


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)SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, Box 15830, Sacramento, California 95813; (916) 452-3211 March 24, 1982 "M3 /

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R H ENCELKEi', REGIONAL ADPINISTRATOR p

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REGION V 0FFICE OF INSPECTION & ENFORCEMENT

%d 1450 MARIA LANE SUITE 210 WALNUT CREEK CA 94596 V

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LICENSE t'O. DPR-54 SPECIAL REPORT NO. 82-04 In accordance with Rancho Seco Nuclear Generating Station Technical Specifications Section 6.9.5.B.1 and 10 CFR 50 rpnendix K, the Sacramento Punicipal litility District hereby submits a report of the Reactor building Inspections performed during March and September of 1981.

There were two inspections perforned in 1981, both of which were accomplished in accordance with Surveillance Procedure SP 205.4.

The first inspection on March 5,1981 was to satisfy the periodic inspection requirement.

The second was conducted on Seotember 8, 1981 to :issess structural integrity after severe vibration was encountered when the turbine rotor failed.

A summary of discren-l ancies and corrective actions is listed belc'v.

Inspection on March 5, 1981 1.

Some penetrations were found leaking arease.

Palfunctioning grease fittings will be repaired during the next refueling outage.

2.

Mincr cracks were noted in the exterior surface of the wall.

These were exanined and determined to be normal and expected due l

to aging of the concrete. They will be narked or mapped to ensure that they can be monitored for future crowth.

3.

Some corrosion was noted on interior surfaces of the containment wall liner.

This will be removed during the forthcoming; refueling outage.

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o R. H. Engelken March 24, 1982 Inspection on September 8, 1981 1.

A wood wedge was noted between some piping and the structure.

The wedge was removed.

2.

Some corrosion was noted around the emergency hatch. This will be removed during the forthcoming refueling outage.

3.

Corrosion was noted around a penetration. This will be removed during the forthcoming refueling outage.

A copy of the surveillance procedure and test results is attached.

The results verify that the structural integrity of the Reactor Building is satisfactory.

If there are any questions regarding this report, please contact R. W. Colombo of my Rancho Seco staff.

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John J('Mattimoe

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Assistant General Manager and Chief Engineer cc:

Director NRR 9

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