|
|
| Line 1: |
Line 1: |
| {{Adams
| | #REDIRECT [[05000266/LER-1980-015-01, /01T-1:on 801210,during Refueling Outage Surveillance Testing,Snubber 1-HS-14 on Power Operated Relief Valve Header Was Determined Inoperable.Caused by Low Level in Snubber Reservoir Due to O-ring Seal Leakage]] |
| | 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 & 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}}
| |