05000266/LER-1980-015-01, /01T-0:on 801210,during Refueling Outage Surveillance Testing of safety-related Shock Suppressors, Snubber 1-HS-14 Found to Be Inoperable.Caused by Low Level in Reservoir,Resulting from Piston Rod O-ring Seal Leakage

/01T-0:on 801210,during Refueling Outage Surveillance Testing of safety-related Shock Suppressors, Snubber 1-HS-14 Found to Be Inoperable.Caused by Low Level in Reservoir,Resulting from Piston Rod O-ring Seal Leakage

ML19351F391
Person / Time
Site:	Point Beach
Issue date:	12/23/1980
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19351F371	List: 05000266/LER-1980-015, Forwards LER 80-015/01T-0 05000266/LER-1980-015-01, /01T-0:on 801210,during Refueling Outage Surveillance Testing of safety-related Shock Suppressors, Snubber 1-HS-14 Found to Be Inoperable.Caused by Low Level in Reservoir,Resulting from Piston Rod O-ring Seal Leakage
References
LER-80-015-01T, LER-80-15-1T, NUDOCS 8101120367
Download: ML19351F391 (2)

LER-1980-015, /01T-0:on 801210,during Refueling Outage Surveillance Testing of safety-related Shock Suppressors, Snubber 1-HS-14 Found to Be Inoperable.Caused by Low Level in Reservoir,Resulting from Piston Rod O-ring Seal Leakage

Event date:
Report date:
2661980015R01 - NRC Website

text

NEC FORM 366 U. S. NUCLE A3 CERULATOCY COMMISSION (747)

LICENSEE EV~ ' REPORT CONTROL BLOCK: l l

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10141 lon 12/10/80, snubber 1-HS-14 (utility identification), located on the I

l o I s l lpower-operated relief valve header, was determined to be inoperable.

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3J 34 Jb 36 31 40 el 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h litolIThe Grinnel I.D. No. 3146, Figure 200/llK, 2-1/2" x 5" (bore and stroke) l g isnubber was determined to be inoperable due to a low level in its reser-i Ivoir, resulting from piston rod 0-ring seal leakage.

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ATTACHMENT TO LICENSEE EVENT REPORT NO. 80-015/01T-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 1 Docket No. 50-266 During refueling outage s rveillance testing of safety-related shock suppressors of Unit 1, in accordance with Technical Specification 15.4.13.2 on December 10, 1980, snubber 1-HS-14 (utility identification), located on the power-operated relief valve header, was found with a low fluid level in its reservoir.

The Grinnel I.D. No. 3146, Figure 200/11k, 2-1/2" x 5" (bore and stroke) snubber was determined to be inoperable due to leakage past the piston rod 0-ring seals.

Snubber 1-HS-14 was repaired on December 10, 1980 and retested satisfactorily on December 11, 1980.

In accordance with Technical Specification 15.4.13.2, an additional 10%

of all snubbers of the same type as 1-HS-14 (one snubber) were inspected.

Snubber 1-HS-18 was inspected with satisfactory results on December 11, 1980.

This event is reportable in accordance with Technical Specification 15.6.9.2.A.9 since remedial action was required to prevent operation in a less conservative manner than that assumed in the safety analysis report.

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