ML20010A555

LER 81-010/01T-0:on 810716,check Valves 1-853C & D Were Opened Up & Found Stuck in Full Open Position During Testing.Caused by Interference Between Disc Wire & Valve Body.Disc Wires Replaced W/Cotter Pins

ML20010A555
Person / Time
Site:	Point Beach
Issue date:	07/31/1981
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20010A545	List: ML20010A544 ML20010A555
References
LER-81-010-01T, LER-81-10-1T, NUDOCS 8108110540
Download: ML20010A555 (3)

Text

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EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l During the performance of high and low head safety injection check valvel o 3 l leakage test, TS-30, on 7-14-81, leakage in excess of the acceptance l o 4 l criteria for 1-853C&D was noted. Check valves 1-85 3C&D are the first l 0 s l off check valves from the reactor coolant system for the low head safety l p;Tg] l injection core deluge lines. On 7-16-81, valves 1-85 3C&D were opened upl gij l and found stuck in the full open position. This occurrence is l i o p j l reportable in accordance with T.S. 15.6.9.2.A.9. l 7 8 9 80 DE CODE S BC DE COMPONENT CODE SUSC DE S E I

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, 42 43 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h y lOn 7-16-81, valves 1-853C&D were found stuck in the full open position I i i ldue to interference between the disc wire and the valve body. Simila r I

, 7 l valves were inspected with no abnormalities noted. Disc wires on valves l

, 3 l 1-85 3A, B, C and D were replaced with cotter pins to orevent further I i 4 l valve hanger bindinr7. Inspections of valves of similar design are .

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ATTACHMENT TO LICENSEE EVENT REPORT NO. 81-010/0lT-0 Wisconsin Electric Power Company Point Beach Nuclear Plant, Unit 1 Docket No. 50-266 During the performance of high and low head safety injection check valve leakage test TS-30 during a. unit shut-down on July 14, 1981, leakage in excess of six gallons per minute past 1-853 C&D was noted. The acceptance criteria for the leak test is leakage less than or equal to five gallons per minute. Check valves 1-853 C&D are the first off check valves from the reactor coolant system for the low head safety injection core deluge lines.

On July 16, 1981, valves 1-853 C&D were opened up and found to be stuck in the full open position. Further investi-gation revealed that the valve operating arm hanger for both valves was stuck in the full open position due to interference between the disc unit lock wire (disc wire) and the valve body.

Two other valves of similar design, 1-853 A&B, were inspected with no abnormalities noted.

The manufacturer's nameplate data for the affected valves are as follows:

Manufacturer: Velan Type: Swing Check Pressure Rating: 1500 #ASA Size: 6" Drawing: 78704, Rev. B The disc wires on check valves 1-853 A, B, C, and D were replaced with cotter pins to prevent further valve hanger binding on July 16, 1981. Following repairs to the check valves disc wires, satisfactory leak check 9 were completed on July 17, 1981.

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An investigation is presently underway to determine

' existence of other valves of similar design and construction in Units 1 and 2 for further evaluation.

At no tLme during this occurrence was there any danger to the public's health and safety, Backup isolation for 1-853 C&D was provided by a check valve and a motor-operated gate valve

} in series downstream of 1-853 C&D. It is impossible to determine when the valves initially became open. Shortly after the leak test on July 14, 1981 full flow was passed through 1-853 C&D in an effort to reduce back leakage. Full flow through valves 1-853 C&D could have jammed the valves in the open position.

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2-This occurrence is reportable in accordance with Technical Specification 15.6.9.2.A.9, " performance of structures, systems, or components that require remedial action or corrective measures to prevent operation in a manner less conservative than that assumed in the accident analysis report or Technical Speci-fication basis."

After review of this occurrence by the Manager's Super-visory Staff and the Nuclear Engineering Section Safety Review Committee, it was determined that the cause af the valve jamming was reportable in accordance with 10 CFR 21. Notification of the defect was reported on July 16,.1981 via 24-hour written notification for Licensee Event Report No. 81-010/0lT-0.

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