View source for 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

{{Adams
| number = ML19351F391
| issue date = 12/23/1980
| title = /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
| author name = Fay C
| author affiliation = WISCONSIN ELECTRIC POWER CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION III)
| docket = 05000266
| license number = 
| contact person = 
| document report number = LER-80-015-01T, LER-80-15-1T, NUDOCS 8101120367
| package number = ML19351F371
| document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| page count = 2
}}
{{LER
| Title = /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
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000266
| LER year = 1980
| LER number = 15
| LER revision = 1
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

=text=
{{#Wiki_filter:*
NEC FORM 366 U. S. NUCLE A3 CERULATOCY COMMISSION (747)
LICENSEE EV~ ' REPORT CONTROL BLOCK: l l
l l
l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI k
l W l I l P l B l H l 1 l@150 l 01 -l 0 l 0 l 0 l 0 l 0 l-1010 l@l 4 l 1 l1 l 1l 1 l@l l
l@
F 8 9 LICENSEE CODE 14 LICENSE NuveER 2$
26 LICENSE TYPE Jo
$7 CAT $8 CCYT HI]
1 L l@l 0l 510 l 0 l 0 l 2 l 6 l 6 @l 1l 2 l 110 l 8 l 0 l@l 1l 2l 2 l3 l 810 l@
5 uaC 7
6 60 61 DOCK ET NUVS E R 68 69 EVENT DATE 74 75 REPORT O ATE 80 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
$O0E C00E SysCODE COMPONENT CODE SusCODE SU E
10191
, S I H l @ [_E_j@ W @ I S l U l P I O I R l T lh ( D_J@ l_z_j @
7 8
9 10 11 12 13 18 19 20 SEQUENTie OCCURRENCE REPORT REVISION v
L EVENTYEAR REPORT NO.
CODE TYPE NO.
O
'E n AO 18101
( _j l0l115l M
l011l lTl l,---J 101 Nu' g,,
_ 21 22 23 24 26 27 28 29 JO 31 32 TAK N A T ON ON PLANT YET HOURS S e eT POR h 8.
SUPPL MANUPACTURER IAl@lzl@
[ z_j@
12l@
10 1010 10 I [J_J@
l Yl@
lNl@
l G l 2 l 5 l 5 l@
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.
The snubber was l
, 2 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
'8 88 CO0 TENT ACTIVITY RELE ASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OP RELEASE L'_LJ 1 z J @ l_z_l@l NA l
l NA I
7 8 9 10 ft 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE

==DESCRIPTION==
[TTT1 I o 101 Ol@l Z l@l l
NA PERSONNE L INJURIES DESCRIPTION @
NUveER L'_LJ 1010101@l NA l
7 8 9 11 12 80 P,'E ESC !, TION ''''''" @
' " ^"
L' L9J Lz_J@l NA I
l 7
8 9 10 80 l,y_j,.o_j NSUE @S'SCaiPTiON @
8101120 NRC uSe ONov l NA 3b1 l
lllllllllllll$
iS 7
8 9 10 68 69 80 414/277-2811
{
C. W. Fay pgoug:
NAME OF PREPARER

e A
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.
l l
l l
I l
l
}}

{{LER-Nav}}