LER-1981-031, /03L-0:on 810701,RHR Pump Room Cooler 3-A Developed Water Leak.Caused by Broken Silfos Joint on 1/4-inch Vent Line.Joint Resoldered |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2601981031R03 - NRC Website |
|
text
e U. S. NUCLE AQ REGULATZY COMMISSION iC FOHV 3G6, LICENSEE EVENT REPORT CONTROL BLOCK; l l
l l
l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATtON) a p l A l L l 3 l R l F l 2 l@l 0 l 0 l - l 0 l 0 l 0 l 0 l 0 l-l 0 l 0 l@l 4 ] 1 l 1 l 1 l 1 l@l l
l@
i
- S 26 LICENSE Tvet JG 57 CATSe LICENSE NuM8tR i4 19 4 i LaCENSEE CODg 5 l 0 l 0 l 0 l 2 l 6 l 0 Ql 0 l 7 l 0 l 1 l 8 l 1 }@]0 l 7 l21218 l1 l@
JN'T l L Ql 0 t I1}
3c nCE 74 75 R EPORT ;; ATE 80 6d 69 EVENT OATE 00 61 DOCKET NUM8ER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h d
the 3-A RHR pump room coolcr developed a l
l During normal operation at steady state,
,l2l The U-l l
,q gater leak and was isolated for repair, making 3-A RHR pump inoperable.
3 l3 and D pumps were already inoperable because the U-l torus was drained, thus three l
3 ja.
2 cross connection became inoperable.
(Cre T.S. 3.5.3-l 3 j, J i RHR pumps located on the unit There was no danger to the health or safety of the public, no redundant systems, j 3 i., j l 12)
[
3iij t and no previous similar events.
l1*
l s
80 J l al !I l
e COMP.
VALv!
SYSTEM
CAUSE
CAUSE CODE COCE SI'acOca!
COMPCNENT CODE SUSCCOE SU SCCO E aial I c l F l@ Lx_J@ I z i s) I ZI zl 21 zi zl zlO 1 z i@ I z l @
d 3
10 11 12 fJ Id 19 20 REVISICN SEQUENTI AL OCCUR R ENCE
- REPORT, EVENT vE AR REPORT NO.
CCOE TYPE N C,
@.agg; 18111 1-1 1 01 31 11 L/._j l 01 31 i Ll l-l I 01 gg a.no
,, 21 22 23 24 26 27 2 12 29 30 Ji J2 A TTACNM E N T NPRO4 PRIME COMP.
COMPONENT ACTION FUTURE EFFECT SMUTOOWN~
woVRS SU8MITTED FORM bWS.
$U PPLIE R M ANUF ACTURER I 3 l@[J.j@
l2l@
l2l@
l Ol Of 0l 0l lY l@
l Nl@
l Ll@
lZl9l9l9l@
TAKEN ACTICN CN PLANT VETHCO IJ 34 ab J6 31 40 41 42 43 44 47 CAUSE 'ESCAIPTION AND CORRECTIVE ACTIONS on a one huarter inch vent 'line broke. causing a water leak. The I
41 ;oilThe Sil' fos 4cint I
l i i i i I icine was resoldered with Sil' fos. the leak reraired and the system returned to
! i i 21 I service within 2/4 hours. This is considered a random failure, and no further i
l 12 111I recurrence control is reaufred.
I Iii4 Ii 80 4
%7owSA oTHER$TATU$
015 RY DISCOVERY CESCRIPTION NA l
lA[gl Operator observed l
- j ' i' ! l E '@ l 0i 9 ! 9 lhl Ac'n vi r v
~
'8
~
.mcuNT Os ACTiviTv @ l cuNrENT LOCATION CF RELEASE NA l
NA l
~FLE Ano 05 aELEn l1 lGl
@ l))hl so o 9
- o it u
46
- E D'.O N N E i., C * #O*.U A E *,
ER tvPt O EScriisticaa l
U'40 *? U @l zl@l l
NA i > iil i l
i
,EmscNNa' mo2 Es 4
NLutlER CE S CR:P Y'CN l
lijjlOlO!0l@l NA go 4
t 11 12 Los3 0F GR OAVALE TO F AcitiTV vv E uEccR. rinN l
ll l 9 l dhl NA go 4
'l ni
" * 'o "
8107310393 U10722 NRC USE CNLY IIIIIIIIIIIIII c.,u f ot sa n e r'""
PDR ADOCK 05000260 l-I"I l Nl l
S PDR
- -l 68 69 80 %
Gene Holder R~CNE NAME OF PAEPAPER
c Form BF 17
'5cnnest,ce Vallev Authority BF 15.2 P,rowns Ferry N'nclear Plant G/04/81
~
LMit SUI'PLEMENTAI, INFORMATION Technical Specification In co!ved 3.5.3.12 R! itf > 50 2g. / 31031.
- cate duc NBC:_.713Jf.81. _
!tcparted Under Technical Specification 6. 7 2.b,(2),
j Darc of Occurrenec 7/1/81 Time of Occurrence 0500 Unit 2_.
Identification and Description of Occurrence:
The 3-A RHR pump room cooler developed a water leak and was isolated for repair, The Unit 1 B and D pumps were already inoperable making 3-A RHR pump inoperable.
because the unit 1 torus was drained, thus three RHR pumps located on the unit 2 cross connection became inoperable.
t *otolif ion:. I'rior to Ucrurrence:
Unit 1 in refueling outage.
Unit 2 at 99%.
Unit 3 at 96%.
l Action specified in the Technical Specification Surveillance Requirements met Describe.
- 49. to. inoperable equigment.
t Met surveillance requirements of T.S. 4.5.3.12.
Apparent Cause of Occurrence:
The soldered joint on a one quarter inch vent line broke, causing a water leak.
Anpl,vsis, of fjecurrence There was no danger to the health or safety of the public, no release of activity, no damage to the plant or equipment, and no resulting significant chain of events.
Currective Action.
The joint was resoldered, 'the leak repaired and the system returned to service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This is considered a random failure, and no further recurrence control is required; l':ninre Data:
H et en t ion :
l'ery ni - 1.ifetime; Responsibility - Document Control Supervisor None
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000260/LER-1981-001, Forwards LER 81-001/01T-0 | Forwards LER 81-001/01T-0 | | | 05000260/LER-1981-001-01, /01T-0:on 810102,scram Discharge Vol Level Switch 2-LS-85-45A Found Inoperable & -C & -D Found Offscale.Caused by One Robert Shaw Switch Model SL-305-EI-X Sticking & Setpoint Drift.Stuck Switches Float Chamber Back Flushed | /01T-0:on 810102,scram Discharge Vol Level Switch 2-LS-85-45A Found Inoperable & -C & -D Found Offscale.Caused by One Robert Shaw Switch Model SL-305-EI-X Sticking & Setpoint Drift.Stuck Switches Float Chamber Back Flushed | | | 05000259/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000296/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000296/LER-1981-001-03, /03L-0:on 810106,both Smoke Detectors in Reactor Bldg Fixed Spray Zone Were Inoperable.Caused by Loose Screw in Terminal Block.Screw Replaced | /03L-0:on 810106,both Smoke Detectors in Reactor Bldg Fixed Spray Zone Were Inoperable.Caused by Loose Screw in Terminal Block.Screw Replaced | | | 05000259/LER-1981-001-03, /03L-0:on 810105,core Spray Sparger to Reactor Pressure Vessel D/P Switch 1-PDIS-75-28 Found Set Above Tech Spec Limit.Caused by Barton Model 288 Setpoint Drift.Switch Replaced W/New Switch on 810115 | /03L-0:on 810105,core Spray Sparger to Reactor Pressure Vessel D/P Switch 1-PDIS-75-28 Found Set Above Tech Spec Limit.Caused by Barton Model 288 Setpoint Drift.Switch Replaced W/New Switch on 810115 | | | 05000260/LER-1981-002-03, /03L-0:on 810102,scram Discharge Instrument Vol Rod Block Level Switch 2-LS-85-45E Found Set at 27 Gallons. Alarm Switch 2-LS-85-45F Found Inoperable.Caused by Drift of Robertshaw Model SL-305-EI-X.Switch Recalibr | /03L-0:on 810102,scram Discharge Instrument Vol Rod Block Level Switch 2-LS-85-45E Found Set at 27 Gallons. Alarm Switch 2-LS-85-45F Found Inoperable.Caused by Drift of Robertshaw Model SL-305-EI-X.Switch Recalibr | | | 05000296/LER-1981-002-03, /03L-0:on 810104,excess Flow Check Valves in B3 & B7 Instrument Lines to Panel 25-7 Would Not Restrict Flow Properly.Cause Not Stated.Internals Changed & SI 4.7.D.1.d Successfully Completed | /03L-0:on 810104,excess Flow Check Valves in B3 & B7 Instrument Lines to Panel 25-7 Would Not Restrict Flow Properly.Cause Not Stated.Internals Changed & SI 4.7.D.1.d Successfully Completed | | | 05000259/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000259/LER-1981-002-03, /03L-0:on 810114,smoke Detector in Relay Room Alarmed & Would Not Clear.Caused by Detector Sensitivity Increasing Due to Normal,Natural Aging.Detector Replaced & Tested | /03L-0:on 810114,smoke Detector in Relay Room Alarmed & Would Not Clear.Caused by Detector Sensitivity Increasing Due to Normal,Natural Aging.Detector Replaced & Tested | | | 05000296/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000260/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000260/LER-1981-003-03, /03L-0:on 810112,core Spray Pump Discharge Pressure Switch 2-PS-75-16 Found Outside Tech Spec Limits. Caused by Setpoint Drift.Switch Recalibr & Replaced | /03L-0:on 810112,core Spray Pump Discharge Pressure Switch 2-PS-75-16 Found Outside Tech Spec Limits. Caused by Setpoint Drift.Switch Recalibr & Replaced | | | 05000259/LER-1981-003-01, /01T-0:on 810124,Div of Engineering Notified That 1-inch Vent Line on Unit 1 Scram Discharge Vol Not Seismically Qualified.Caused by Piping Configuration Not Conforming to Design Requirements | /01T-0:on 810124,Div of Engineering Notified That 1-inch Vent Line on Unit 1 Scram Discharge Vol Not Seismically Qualified.Caused by Piping Configuration Not Conforming to Design Requirements | | | 05000259/LER-1981-003, Forwards LER 81-003/01T-0 | Forwards LER 81-003/01T-0 | | | 05000260/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000296/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000296/LER-1981-003-03, /03L-0:on 810107,during Refueling Outage,Fuel Pool Cooling Sys Auto Isolated When Power Was Removed.Fuel Pool Sampling Not Performed on 8-h Schedule.Caused by Personnel Error.Personnel Reinstructed | /03L-0:on 810107,during Refueling Outage,Fuel Pool Cooling Sys Auto Isolated When Power Was Removed.Fuel Pool Sampling Not Performed on 8-h Schedule.Caused by Personnel Error.Personnel Reinstructed | | | 05000260/LER-1981-004-01, /01T-0:on 810119,reactor Water Level Switches LIS-3-203A Switch 1 & LIS-3-A,B,C,D Switch 2 Found Outside Tech Specs.Caused by Drift Due to Air Impact Drilling Next to Switch Panel.Switches Recalibr | /01T-0:on 810119,reactor Water Level Switches LIS-3-203A Switch 1 & LIS-3-A,B,C,D Switch 2 Found Outside Tech Specs.Caused by Drift Due to Air Impact Drilling Next to Switch Panel.Switches Recalibr | | | 05000296/LER-1981-004-03, Diesel Generator 3A & Breaker 1836 Tripped from Generator Overspeed During Testing.Caused by Vs Relay on Speed Sensing Panel Energizing at Less than 870 Rpm,Closing Breaker 1836 | Diesel Generator 3A & Breaker 1836 Tripped from Generator Overspeed During Testing.Caused by Vs Relay on Speed Sensing Panel Energizing at Less than 870 Rpm,Closing Breaker 1836 | | | 05000296/LER-1981-004, Forwards Updated LER 81-004/03X-1 | Forwards Updated LER 81-004/03X-1 | | | 05000259/LER-1981-004, Forwards Updated LER 81-004/03L-1 | Forwards Updated LER 81-004/03L-1 | | | 05000259/LER-1981-004-03, Standby Gas Treatment Sys Train C Relative Humidity Heaters Declared Inoperable.Caused by Dwyer Photohelic Pressure Switch/Gage Circuit Hh & Ite Imperial Relay Contact Block Malfunction | Standby Gas Treatment Sys Train C Relative Humidity Heaters Declared Inoperable.Caused by Dwyer Photohelic Pressure Switch/Gage Circuit Hh & Ite Imperial Relay Contact Block Malfunction | | | 05000260/LER-1981-005-03, /03L-0:on 810119,core Max Fraction of Limiting Power Density Exceeded Limit for One Node in Core.Caused by Operation Close to Limit in Conjunction W/Minor (Normal) Perturbation in Monitored Parameters.Power Reduced Slightly | /03L-0:on 810119,core Max Fraction of Limiting Power Density Exceeded Limit for One Node in Core.Caused by Operation Close to Limit in Conjunction W/Minor (Normal) Perturbation in Monitored Parameters.Power Reduced Slightly | | | 05000259/LER-1981-005-04, /04T-0:on 810131,hydrogen Ion Concentration of Reservoir Near Plant Found in Excess of Allowable Discharge Limit.Probably Caused by Upstream Source.Discharge of Spent Regenerants Stopped & Monitoring Program Established | /04T-0:on 810131,hydrogen Ion Concentration of Reservoir Near Plant Found in Excess of Allowable Discharge Limit.Probably Caused by Upstream Source.Discharge of Spent Regenerants Stopped & Monitoring Program Established | | | 05000296/LER-1981-005-03, /03L-0:on 810127,containment Atmosphere Hydrogen analyzer,3-H2M-76-94,removed from Svc.Caused by Maint on Sensing Line at 3-FIC-76-94,Model 1350,due to Water Collection.Water Removed & Lines Returned to Svc | /03L-0:on 810127,containment Atmosphere Hydrogen analyzer,3-H2M-76-94,removed from Svc.Caused by Maint on Sensing Line at 3-FIC-76-94,Model 1350,due to Water Collection.Water Removed & Lines Returned to Svc | | | 05000296/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000260/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000259/LER-1981-005, Forwards LER 81-005/04T-0 | Forwards LER 81-005/04T-0 | | | 05000259/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000259/LER-1981-006-03, /03L-0:on 810211,while Performing SI 4.2.B-57,RHR Area Cooling Fan Temp Switch 1-TS-64-68 Failed to Operate. Caused by Switch T675A1540 Failure.Switch Replaced,Calibr & 4.2.B-57 Completed | /03L-0:on 810211,while Performing SI 4.2.B-57,RHR Area Cooling Fan Temp Switch 1-TS-64-68 Failed to Operate. Caused by Switch T675A1540 Failure.Switch Replaced,Calibr & 4.2.B-57 Completed | | | 05000296/LER-1981-006-03, /03L-0:on 810128,containment Atmosphere Hydrogen Analyzer Removed from Svc.Caused by Maint on Sensing Lines Due to Effect of Water Accumulation on Model 76-01A625 Timer.Water Removed & Monitor Returned to Svc | /03L-0:on 810128,containment Atmosphere Hydrogen Analyzer Removed from Svc.Caused by Maint on Sensing Lines Due to Effect of Water Accumulation on Model 76-01A625 Timer.Water Removed & Monitor Returned to Svc | | | 05000296/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000260/LER-1981-006-03, /03L-0:on 810121,core Max Fraction of Limiting Power Density Exceeded Limit.Caused by Power Increase in Conjunction W/Inoperable Process Computer.Power Reduced & Control Rod Pattern Adjustment Made on 810123 | /03L-0:on 810121,core Max Fraction of Limiting Power Density Exceeded Limit.Caused by Power Increase in Conjunction W/Inoperable Process Computer.Power Reduced & Control Rod Pattern Adjustment Made on 810123 | | | 05000260/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000260/LER-1981-007-03, /03L-0:on 810129,during Power Increases,Tech Spec Limit of 13.33 Kw/Ft for Linear Heat Generation Rate Exceeded in One Node.Node Reached 13.77 Kw/Ft.Caused by Xenon Transient Resulting from Increased Core Power | /03L-0:on 810129,during Power Increases,Tech Spec Limit of 13.33 Kw/Ft for Linear Heat Generation Rate Exceeded in One Node.Node Reached 13.77 Kw/Ft.Caused by Xenon Transient Resulting from Increased Core Power | | | 05000260/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000259/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000259/LER-1981-007-03, /03L-0:on 810210,during Fire Door Insp,Fire Door Damper (Door 472) Not Closed.Caused by Paint Buildup in Operating Mechanism.Damper Closed & Other Dampers Inspected. Procedure for Insp & Preventive Maint Will Be Written | /03L-0:on 810210,during Fire Door Insp,Fire Door Damper (Door 472) Not Closed.Caused by Paint Buildup in Operating Mechanism.Damper Closed & Other Dampers Inspected. Procedure for Insp & Preventive Maint Will Be Written | | | 05000296/LER-1981-007-03, /03L-0:on 810202,setpoint for 3-PS-1-76 Below Tech Specs Limit.Caused by B2TA12SS Setpoint Drift.Switch Recalibr & Verified.Switch to Be Replaced W/Analog Trip Sys by DCR 1398 | /03L-0:on 810202,setpoint for 3-PS-1-76 Below Tech Specs Limit.Caused by B2TA12SS Setpoint Drift.Switch Recalibr & Verified.Switch to Be Replaced W/Analog Trip Sys by DCR 1398 | | | 05000296/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000260/LER-1981-008-03, /03L-0:on 810220,reactor Core Isolation Cooler Turbine Trip & Throttle Valve Closed & Would Not Reopen. Caused by Overload Heater Relay.Relay Replaced | /03L-0:on 810220,reactor Core Isolation Cooler Turbine Trip & Throttle Valve Closed & Would Not Reopen. Caused by Overload Heater Relay.Relay Replaced | | | 05000259/LER-1981-008-01, /01T-0:on 810226,secondary Containment Integrity Lost When Exterior Equipment Access Door 229 & Interior Personnel Door 228 Opened Simultaneously.Caused by Lack of Interlocks Between Doors.Interlocks to Be Installed | /01T-0:on 810226,secondary Containment Integrity Lost When Exterior Equipment Access Door 229 & Interior Personnel Door 228 Opened Simultaneously.Caused by Lack of Interlocks Between Doors.Interlocks to Be Installed | | | 05000296/LER-1981-008-03, /03L-0:on 810202,RHR Pump Found Inoperable.Caused by Loose Pump 3D Breaker Trip Adjustment Nut & Adjustment Change,Causing Breaker to Trip Free on Attempting to Close. Breaker Replaced.Adjustment Locknut Tightness Checks Add | /03L-0:on 810202,RHR Pump Found Inoperable.Caused by Loose Pump 3D Breaker Trip Adjustment Nut & Adjustment Change,Causing Breaker to Trip Free on Attempting to Close. Breaker Replaced.Adjustment Locknut Tightness Checks Added | | | 05000296/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000259/LER-1981-008, Forwards LER 81-008/01T-0 | Forwards LER 81-008/01T-0 | | | 05000260/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000296/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000259/LER-1981-009, Forwards LER 81-009/01T-0 | Forwards LER 81-009/01T-0 | | | 05000260/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | |
|