05000287/LER-1978-005-03, /03L-0:on 780207,valve BS-2 Failed in Intermediate Position During Operability Test.Caused by Valve Stem Failure & Partly by Faulty Torgue Switch.Stem & Switch Replaced.Stems Made by Walworth

/03L-0:on 780207,valve BS-2 Failed in Intermediate Position During Operability Test.Caused by Valve Stem Failure & Partly by Faulty Torgue Switch.Stem & Switch Replaced.Stems Made by Walworth

ML19308B521
Person / Time
Site:	Oconee
Issue date:	03/09/1978
From:	Ken Wilson DUKE POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19308B511	List: 05000287/LER-1978-005, Forwards LER 78-005/03L-0 05000287/LER-1978-005-03, /03L-0:on 780207,valve BS-2 Failed in Intermediate Position During Operability Test.Caused by Valve Stem Failure & Partly by Faulty Torgue Switch.Stem & Switch Replaced.Stems Made by Walworth
References
LER-78-005-03L, LER-78-5-3L, NUDOCS 8001090527
Download: ML19308B521 (2)

LER-1978-005, /03L-0:on 780207,valve BS-2 Failed in Intermediate Position During Operability Test.Caused by Valve Stem Failure & Partly by Faulty Torgue Switch.Stem & Switch Replaced.Stems Made by Walworth

Event date:
Report date:
2871978005R03 - NRC Website

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The failure caused one of two buildine sorav trains Iolei i to be inonerable.

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DUKE B]WER COMPANY OCONEE UNIT 3 Report Number:

RO-287/78-5 Report Date:

March 9, 1978

- Occurrence Date:

February 7, 1978 Facility: Oconee Unit 3, Seneca, South garolina t

Identification of Occurrence:

3BS-2 ES Discharge Valve Failure Conditions Prior to Occurrence:

100 Percent Full Power Description of Occurrence:

On February 7 at 0950 during the performance of PT/3/A/0130/15A (valve opera-bility), valve 3BS-2 Reactor Building Spray System Discharge Valve, failed in an intermediate position.

It was determined that the valve stem was damaged and would have to be replaced. A replacement valve stem was fabricated on-site but failed when it was operated.

A reactor shutdown was commenced at 1849 as required by Technical Specification 3.3.5.

The shutdown was halted when the station was notified that a Technical Specification change had been approved ex-tending the time allowed for repair to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

At 0345 on February 1.0, the stem was replaced and the valve functioned properly.

Apparent Cause of Occurrence:

The apparent cause of the valve failure was the fat.ty stem which was either caused or aggravated by a faulty torqua switch.

Analysis of Occurrence:

The failure of 3BS-2 caused the B train of the Reactor Building Spray System to be inoperable.

However, the A train was availaole at all times to miti-gate the consequences of any potential accidents.

The analysis of the poten--

tial hazard associated with one spray train being inoperable is presented in FSAR Supplement 13 and indicates that the system is fully capable of handling any postulated incident.

The Technical Specifications for the Oconee Nuclear Station allow for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> repair time but Standard Technical Specifications allow a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, period.- Upon request by Duke, the NRC extended the allowed repair time to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

The health and safety of the public were not affected by this incident.

Corrective Action

The corrective action ~taken vac the replacement of the valve stem, stem key and torque switch.

The valve functioned properly af ter the repair parts were ins talled.

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