ML19351F391

LER 80-015/01T-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

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: ML19351F370 ML19351F391
References
LER-80-015-01T, LER-80-15-1T, NUDOCS 8101120367
Download: ML19351F391 (2)

Text

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

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EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 10121lDurina refueline outace surveillance testino of safetv-related shock l tol2l lsuppressors of Unit 1, according to Technical Specification 15.4.13.2 I 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. I to161IThis event is reportable accordino to Technical Specification i 10171Il5.6.9.2.A.9 and similar to LER 78-015/OlT-0, 77-Oll/01T-0. I l o !s t I l

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3J 34 Jb 36 31 40 el 43 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

, 2 Ivoir, resulting from piston rod 0-ring seal leakage. The snubber was l g l repaired on 12/10/80, and tested and returned to service on 12/11/80. I g lSimilar snubbers were checked in accordance with TS 15. 4.13. 2 on 12/11/80. l 7 8 9 80 ST S  % POWER OTHER STATUS S RY DISCOVERY DESCRIPTION l'IsI{,,H_j@ l010l0l@l NA l lBI@l Surveillance test l

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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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