LER-1980-033, /03L-0:on 800806,24-h After Reactor Mode Switch Was Placed in Run,Torus Oxygen Concentration Found in Excess of 5%.Caused by Torus Oxygen Analyzer Out of Calibr & Reduced Flow Capability of Nitrogen Purge Sys |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2191980033R03 - NRC Website |
|
text
.
- (7 77) k LICENSEE EVENT REPORT 1
m.
y V
CONTOOL BLOCK: l l
l l
I l
l@
(PLEASE PRINT CR TYPE ALL REQUIRED INFor,.MATION) i 1
8 fo-[Il l N l J l 0 l C l P l 1 l@15 0 l 0l --l 0 l 0 l 0 l 0 l 0 l - l 0 l O l@284lIl1l1l1l@l l
l@
7 8 9 UCENSEE CCOE 14 uCENst NUMBER 25 uCENSE TYPE JO S7 CAT 58
'{
CON"T loIti QuYC l L j@l0 l 5 l0 l0 l0 l2 l1 19 )@l 0 l 8 l 0 l 6l 8 l 0 @l 018 l 2 l 8 l 81 O l@
T 7
8 80 81 DOCICET NuuSER 88 89 EVENT DATE 74 75 REPORT QATE 80 EVENT DESCRIPTION AND PRO 8A8tE CONSEQUENCES h 7
+
FITI l On Wednesday, August 6,1980, at approximately 0939 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.572895e-4 months <br /> (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l
ITTTl I after the reactor mode switch was placed in RUN), the torus oxygen con-1: -
I o i A l 1 centration was found to be in excess of 5% in violation of T.S. 3.5. A.6.
I I
io #s: 1 Containment inerting at reduced capability was in progress at the time.
I lo is i l A reactor shutdown was commenced while the inerting orocess continued.
l l o l 71 l At 1003 the shutdown was terminater' when the torus oxygen concentration l
i ois ; l was reduced,-and remained below, 5%.
I" 7
8 9 CE Co SL C E COMPCNENT CCCE SU8 OCE SU E
ioisi ls lE l@ ]@ l Z l@ l Z l Z l Z l Z l Z l Z l@ l Zl@ l Zl @
7 8
9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPCRT REVISION LER EVENT YE AR REPoAT NO.
CODE TYPE NO.
O ag/RO l8l0l l_j l0l3l3l y
l0 l3 l l Ll l_l l
l l
s
,, 21 22 23 24 26 27 28 29 30 31 32 EN A C
P T
METH MouRS 22 S8 i FOR 8.
Su Li VA F
RER j XlgW@
l B l@
lZl@
l0l0l0l1l l Y l@ ' l Nl@
lZl@
l Zl 9l 9l 9l@'
33 34 35 38 37 40 el 42 43 44 47 CAusE DESCRIPTICN AND CORRECTIVE ACTIONS h li l a l l The cause of this occurrence is attributed to the torus oxycen analvrer l
L' L2_J l being out of calibration and to the reduced flow caeabilitv of the l
I: 121 i nitrogen purge system.
A reactor shutdown was commenced.
The nitrocen I
Ld.3J Lourge system was made to operate at a creater flew rate. and after about I
y 1 1/2 hour, the torus oxygen was less than St.
The shutdown was terminated.
I 7
3 3 80 A
4 POWER OTHER STATLS Disco Y
DISCOVERY QESCRIPTICN 11 15 l l El@ l 0 ] 8 l 0 l@l NA l
lAl@l Operator observation l
ACTIVITY C TENT RELEASE AMCUNT CF ACTIVITY LOCATION CF RELEASE l 8 l d @D OF RELEASE lZl@l NA l
l NA l
j
'l 1 7
8 9-10 11 44 48 80 s
- ERSCNNEL EXPC$uRES NUVSER TYPE
DESCRIPTION
l1 l 7 l l 0l 0l Ol@l Zl@l NA l
,ER$chNE N u L S oESCRiPficN@
Nuo8ER l1 la l l 0l 0l -0l@l NA l
7 3 3 11 12 80 1
LOSS 08 OR OAMAGE TO FACILtTv Q l
.Tv'E DESCRIPTfCN v
l 1 l 9 l l Zl@l NA l
1 7-4 9 10 80
$3y g 08 CRIPTION
[,,2j,o_j l Yfhl ll1l1IIllIlT,li Weekiv News Release l
ll t$ U 0 9 0 9 0 3Sl Donald ' A.
t i s so Ross 201-455-878h PHONE:
NAME OF PREPARER
-- cr m _.._
I' Jersey Central Power & Ught Company 2)
Madison Avenue at Punch Bowl Road Monistown, New Jersey 07960 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 2'
Licensee Event Report Reportable Occurrence No. 50-219/80-33/3L Report Date August 28, 1980 Occurrence Date r
August 6, 1980 Identification of Occurrence The primary containment atmosphere was not reduced to less than 5.0% oxygen concentration within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the reactor mode selector switch was placed in the RUN mode as required by Technical Specifications paragraph 3.5. A.6.
This event is considered to be a reportable occurrence as defined in the Tech-nical Speci fications, paragraph 6.9.2.b(2).
Conditions Prior to Occurrence The plant was operating at steady state power.
Plant parameters at the time of occurrence were:
Power:
Reactor, 1544 Wt Electrical, 463 We Flow:
Recirculation 11.6 x 104 gpm Feedwater 5.35 x 10' lb/hr Stack Gas Activity:
1.6 x 103 pCi/sec Descriotion of Occurrence On Wednesday, August 6,1980, at approximately 0939 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.572895e-4 months <br /> (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter plac-
~ j ing the reactor mode switch in RUN) the torus oxygen concentration was greater than 5.0%.
Containmen: Inerting was in progress at the time and had been since about 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on August 5, 1980.
The Nitrogen Purge System, however, was discovered to be operating in a reduced status due to a faulty high temperature cutout switch in the nitrogen purge vaporizer.
This rendered one set of the vaporizer beaters inoperable making it
_ Jersey Cen:ral P:wer & Uger Comcany :s a Verncer cf :re General Pucic Utttes Sys:em l-
~
~r
- - Reporttblo-Occurrsnca No. 50-219/80-33/3L Pcga 2 t1 August 28,.1980-i necessary to reduce the nitrogen purge rate.
Two other sets of heaters were also operating' in a reduced status. At 0050 on August 6, the torus oxygen con-
~
centration indicated 5.0% at which' time a nitrogen purge of the drywell was s ta'rted. At about 0830 on August 6, a calibration of the drywell and torus oxy-4 gen analyzers was performed. After the calibration, -the indicated oxygen con-centrations in the drywell and torus were 3.6% and 7.3%, respectively. The purge was shifted back -to the torus but the oxygen concentration could not be reduced to less than 5.0% by 0939 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.572895e-4 months <br />.
The indicated torus oxygen concentra-
.tlon at 0939 was about 6.2%.
At that time a reactor shutdown was commenced while the inerting process continued. At 1003 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.816415e-4 months <br /> the shutdown was termi-nated when the torus oxygen concentration was reduced to, and remained below, 5.0%.
Apparent Cause of Occurrence The cause of the occurrence was attributed to the indicated torus oxygen concen-tration increasing following instrument calibration compounded by the nitrogen purge system operating in a reduced status.
Another contributing factor in the event was that the drywell oxygen analyzer was operating without a sample pump. This requires the operators to estimate when the drywell oxygen concen-tration is less than 5%. The drywell must then be pressurized in order to obtain sample flow to the analyzer.
in this Instance the drywell indicated 3.6% oxygen after calibration.
Had the operators had continuous indication of drywell oxygen they could have shifted the nitrogen purge back to the torus early enough.to reduce the torus oxygen to less than 5.0% within the required time.
Analysis of Occurrence The containnent atmosphere control system is designed to maintain an inert atmos-phere within the primary containment to preclude energy releases from a possible hydrogen-oxygen reaction following a postulated loss of coolant accident which could jeopardize the Integrity of the containment.
Conservative estimates of the hydrogen produced following the postulated loss of coolant accident with the operation of either core. spray system show that the hydrogen produced from the metal-water reaction would result in a hydrogen concentration of 0.4% in the primary containment. This concentration is significantly below the concen-tration at which hydrogen can be ignited in air.
However, inerting of the pri-mary containment was included in the proposed design and operation to preclude the possibility of an energy release within the primary containment from a hydrogen-oxygen reaction under more severe conditions than could be foreseen.
in iaddition, considering the drywell oxygen concentration was reduced to less than 5.0% ar.d the torus oxygen concentration was above 5% (6.2%) for only a short length of time, the safety significance of this event is considered minimal.
Corrective Action
A reactor shutdown was commenced'while N2 purging operations continued.
The high temperature cutout switch in the nitrogen purge vaporizer was jumpered out allowing the system to operate at a greater flow rate.
At 1003 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.816415e-4 months <br />, the torus 02 concentration was reduced to less than 5% and the shutdown was terminated.
8
^
x.
~.
I i,
. Reportable.0ccurrence No. 50-219/80-33/3L Page i,
- August 28, 1980-J!
L' i. -
Failure Data.
1 1ki CEXI Electric Vaporizer I'
' Cryogenic Experts,- Inc..
Serial #100E-36
'7 d
i e
a j
- - l I
i i
a k
4 s
i ',
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000219/LER-1980-001-01, /01T-o:on 800105,while Performing Electromatic Relief Valve Operability Test,Emergency Releie Valve D Failed to Open.Caused by Component Failure Due to Retainer Ring Being Backed Off Approx Six Threads | /01T-o:on 800105,while Performing Electromatic Relief Valve Operability Test,Emergency Releie Valve D Failed to Open.Caused by Component Failure Due to Retainer Ring Being Backed Off Approx Six Threads | | | 05000219/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000219/LER-1980-002-03, /03L-0:on 800116,during Fuel Bundle Clip Insp,Fuel Bundle UD-3-023 Was Misoriented & Was Not Properly Seated in Core Cell Location.Caused by Personnel Error & Inadequate Procedural Controls.Procedure 205 Revised | /03L-0:on 800116,during Fuel Bundle Clip Insp,Fuel Bundle UD-3-023 Was Misoriented & Was Not Properly Seated in Core Cell Location.Caused by Personnel Error & Inadequate Procedural Controls.Procedure 205 Revised | | | 05000219/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000219/LER-1980-003-01, /01T-0:on 800116,during Inservice Insp on Core Spray Sparger Piping for Sys Ii,Two Indications of Cracks Discovered.Ultrasonic Test Revealed through-wall Cracks. Possibly Caused by Sparger Installation Method | /01T-0:on 800116,during Inservice Insp on Core Spray Sparger Piping for Sys Ii,Two Indications of Cracks Discovered.Ultrasonic Test Revealed through-wall Cracks. Possibly Caused by Sparger Installation Method | | | 05000219/LER-1980-003, Forwards LER 80-003/01T-0 | Forwards LER 80-003/01T-0 | | | 05000219/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000219/LER-1980-004-03, /03L-0:on 800125,on 800125,29 & 0213,radioactive Water Discovered Leaking from Severely Pitted Aluminum Piping of Condensate Transfer Sys.Caused by Galvanic Corrosion.Leaks Temporarily Repaired & Piping to Be Replaced | /03L-0:on 800125,on 800125,29 & 0213,radioactive Water Discovered Leaking from Severely Pitted Aluminum Piping of Condensate Transfer Sys.Caused by Galvanic Corrosion.Leaks Temporarily Repaired & Piping to Be Replaced | | | 05000219/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000219/LER-1980-005-03, /03L-0:on 800205,during Weekly Surveillance of Standby Gas Treatment Sys,Setpoints for Radiation Monitors RNO4A-1 & RNO4A-2 Found to Read Less Conservatively than Tech Spec.Caused by Personnel Error & Instrument Drift | /03L-0:on 800205,during Weekly Surveillance of Standby Gas Treatment Sys,Setpoints for Radiation Monitors RNO4A-1 & RNO4A-2 Found to Read Less Conservatively than Tech Spec.Caused by Personnel Error & Instrument Drift | | | 05000219/LER-1980-006-03, /03L-0:on 800131,during Reactor Recirculation Flow Calibr surveillance,as-found Values of Recirculation Flow Sensors at Zero Percent Simulated Flow Were Out of Tolerance.Caused by Instrument Drift | /03L-0:on 800131,during Reactor Recirculation Flow Calibr surveillance,as-found Values of Recirculation Flow Sensors at Zero Percent Simulated Flow Were Out of Tolerance.Caused by Instrument Drift | | | 05000219/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000219/LER-1980-007-03, /03L-0:on 800213,while Performing 10-h Test on Standby Gas Treatment Sys 1,flow Was Less than Tech Spec Limit.Caused by Slipping Drive Belts on Exhaust Fan EF1-8. Drive Belts Replaced | /03L-0:on 800213,while Performing 10-h Test on Standby Gas Treatment Sys 1,flow Was Less than Tech Spec Limit.Caused by Slipping Drive Belts on Exhaust Fan EF1-8. Drive Belts Replaced | | | 05000219/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000219/LER-1980-008-01, /01T-0:on 800215,during Insp for IE Bulletin 79-14,discovered Nine Pipe Clamps Installed W/O Restraining Welded Lugs.Caused by Oversight During Const.Welded Lugs to Be Installed | /01T-0:on 800215,during Insp for IE Bulletin 79-14,discovered Nine Pipe Clamps Installed W/O Restraining Welded Lugs.Caused by Oversight During Const.Welded Lugs to Be Installed | | | 05000219/LER-1980-008, Forwards LER 80-008/01T-0 | Forwards LER 80-008/01T-0 | | | 05000219/LER-1980-009-03, During Annual Insp of Containment Spray Heat Exchanges,Leaks Discovered in Four Heat Exchangers.Caused by Component Failure & Design.Heat Exchangers to Be Retubed W/Titanium | During Annual Insp of Containment Spray Heat Exchanges,Leaks Discovered in Four Heat Exchangers.Caused by Component Failure & Design.Heat Exchangers to Be Retubed W/Titanium | | | 05000219/LER-1980-009, Forwards Revised LER 80-009/03L-1 | Forwards Revised LER 80-009/03L-1 | | | 05000219/LER-1980-010, Forwards LER 80-010/01T-0 | Forwards LER 80-010/01T-0 | | | 05000219/LER-1980-010-01, /01T-0:on 800220,during IE Bulletin 79-14 Insp, Pipe hangers,NP-2-R8A & NP-2-R8B Found Improperly Installed. Cleanup Sys Restraint Mod & Nonrigid Restraint Added | /01T-0:on 800220,during IE Bulletin 79-14 Insp, Pipe hangers,NP-2-R8A & NP-2-R8B Found Improperly Installed. Cleanup Sys Restraint Mod & Nonrigid Restraint Added | | | 05000219/LER-1980-010-03, /03L-1:on 790417,excavation Was Started to Repair Leak Near Inside Penetration within Pipe Tunnel.Activity Was Detected in Soil Near Dedt Line.Dedt Line Rerouted on 800316.Line Will Be Repaired | /03L-1:on 790417,excavation Was Started to Repair Leak Near Inside Penetration within Pipe Tunnel.Activity Was Detected in Soil Near Dedt Line.Dedt Line Rerouted on 800316.Line Will Be Repaired | | | 05000219/LER-1980-011-03, /03L-0:on 800219,during Surveillance Test,Trip Occurred on Standby Gas Treatment Sys 1.Caused by Cracked Flow Sensing Line Which Was Probably Stepped On.Line Replaced | /03L-0:on 800219,during Surveillance Test,Trip Occurred on Standby Gas Treatment Sys 1.Caused by Cracked Flow Sensing Line Which Was Probably Stepped On.Line Replaced | | | 05000219/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000219/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000219/LER-1980-012-03, /03L-0:on 800228,discovered That Weekly Surveillance Tests for Main Station & Diesel Generator Batteries Not Performed During Seventh Wk.Caused by Error in Personnel.Evaluation Will Be Made to Determine Improvements | /03L-0:on 800228,discovered That Weekly Surveillance Tests for Main Station & Diesel Generator Batteries Not Performed During Seventh Wk.Caused by Error in Personnel.Evaluation Will Be Made to Determine Improvements | | | 05000219/LER-1980-013, Forwards LER 80-013/01T-0 | Forwards LER 80-013/01T-0 | | | 05000219/LER-1980-013-01, /01T-0:on 800309,fire Suppression Water Sys Removed from Svc to Replace Cracked Valve,Contrary to Tech Specs.Fire Truck Pumper Used as Water Supply Backup. Cause of Valve Body Crack Under Investigation | /01T-0:on 800309,fire Suppression Water Sys Removed from Svc to Replace Cracked Valve,Contrary to Tech Specs.Fire Truck Pumper Used as Water Supply Backup. Cause of Valve Body Crack Under Investigation | | | 05000219/LER-1980-014-01, /01T-0:on 800302,emergency Diesel Generator 1 Failed to Synchronize & Tripped When Generator 2 Was Tagged for Mod.Caused by Component Failure.Fuse F7,found Loose in Holder.Fuseholder Repaired | /01T-0:on 800302,emergency Diesel Generator 1 Failed to Synchronize & Tripped When Generator 2 Was Tagged for Mod.Caused by Component Failure.Fuse F7,found Loose in Holder.Fuseholder Repaired | | | 05000219/LER-1980-014, Forwards LER 80-014/01T-0 | Forwards LER 80-014/01T-0 | | | 05000219/LER-1980-015, Forwards LER 80-015/03L-0 | Forwards LER 80-015/03L-0 | | | 05000219/LER-1980-015-03, /03L-0:on 800403,piston Rod on Closure Mechanism for Reactor Bldg Ventilation Automatic Isolation Valve Was Found Broken,Making Valve Inoperable.Caused by Component Failure.New Piston Rod Eye Stud Was Fabricated & Installed | /03L-0:on 800403,piston Rod on Closure Mechanism for Reactor Bldg Ventilation Automatic Isolation Valve Was Found Broken,Making Valve Inoperable.Caused by Component Failure.New Piston Rod Eye Stud Was Fabricated & Installed | | | 05000219/LER-1980-016, Forwards LER 80-016/01T-0 | Forwards LER 80-016/01T-0 | | | 05000219/LER-1980-016-01, /01T-0:on 800512,util Recognized That 800420 Discovery of Defective Pressure Switch,Psl D,Constituted Immediate Rept.Caused by Cocked Teflon Actuator.Switch Removed & Will Be Replaced | /01T-0:on 800512,util Recognized That 800420 Discovery of Defective Pressure Switch,Psl D,Constituted Immediate Rept.Caused by Cocked Teflon Actuator.Switch Removed & Will Be Replaced | | | 05000219/LER-1980-017-01, /01T-0:on 800516,while Performing Control Rod Interference checks,green-green Rod Position Indication Remained Illuminated While Withdrawing Rod 10-23.Caused by Operator & Procedure in Bypass & Component Failure | /01T-0:on 800516,while Performing Control Rod Interference checks,green-green Rod Position Indication Remained Illuminated While Withdrawing Rod 10-23.Caused by Operator & Procedure in Bypass & Component Failure | | | 05000219/LER-1980-017, /03L-0:on 800520,during Investigation of LER 80-17/1T, One Rod Free Travel Interlock Surveillance Requirements Not Performed as Required.Causec by Failure to Perform Procedure & Schedule Surveillance | /03L-0:on 800520,during Investigation of LER 80-17/1T, One Rod Free Travel Interlock Surveillance Requirements Not Performed as Required.Causec by Failure to Perform Procedure & Schedule Surveillance | | | 05000219/LER-1980-018-03, /03L-0:on 800507,during Monthly Surveillance Testing of Reactor High Pressure Scram sensors,RE03D Found to Be Less Conservative than Specified.Caused by Sensor Repeatability.Sensor Reset | /03L-0:on 800507,during Monthly Surveillance Testing of Reactor High Pressure Scram sensors,RE03D Found to Be Less Conservative than Specified.Caused by Sensor Repeatability.Sensor Reset | | | 05000219/LER-1980-018, Forwards LER 80-018/03L-0 | Forwards LER 80-018/03L-0 | | | 05000219/LER-1980-020, Forwards LER 80-020/01T-0 | Forwards LER 80-020/01T-0 | | | 05000219/LER-1980-020-01, /01T-0:on 800605,following Insp of Fire Barriers Protecting safety-related Areas,Several Penetrations Found in Degraded Condition.Caused by Deficiencies in Installation Specs & Personnel Error Re Delay in Establishing Watche | /01T-0:on 800605,following Insp of Fire Barriers Protecting safety-related Areas,Several Penetrations Found in Degraded Condition.Caused by Deficiencies in Installation Specs & Personnel Error Re Delay in Establishing Watches | | | 05000219/LER-1980-021, Has Been Cancelled | Has Been Cancelled | | | 05000219/LER-1980-022-03, /03L-0:on 800603,reactor High Pressure Isolation Condenser Initiation Switch Trip Points Found Less Conservative than Specified.Caused by Unusual Svc Condition. Pressure Switches Reset & Exercised to Ensure Operation | /03L-0:on 800603,reactor High Pressure Isolation Condenser Initiation Switch Trip Points Found Less Conservative than Specified.Caused by Unusual Svc Condition. Pressure Switches Reset & Exercised to Ensure Operation | | | 05000219/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000219/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000219/LER-1980-023-03, /03L-0:on 800523,prior to Inservice Insp Reactor Vessel Hydro,Testing Revealed That Electromatic Relief Valve High Pressure Sensor IA83B Exceeded Tech Spec Setpoint. on 800531,sensor IA83F Found to Exceed Setpoint | /03L-0:on 800523,prior to Inservice Insp Reactor Vessel Hydro,Testing Revealed That Electromatic Relief Valve High Pressure Sensor IA83B Exceeded Tech Spec Setpoint. on 800531,sensor IA83F Found to Exceed Setpoint | | | 05000219/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000219/LER-1980-025, Forwards LER 80-025/01T-0 | Forwards LER 80-025/01T-0 | | | 05000219/LER-1980-025-01, /01T-0:on 800618,during Surveillance Test, Nonfunctioning Operator Discovered in Valves V-9-12 & V-9-8 Found Leaking.Caused by Component Failure.Defective Valves Replaced & Will Be Inspected.Revised Rept Will Follow | /01T-0:on 800618,during Surveillance Test, Nonfunctioning Operator Discovered in Valves V-9-12 & V-9-8 Found Leaking.Caused by Component Failure.Defective Valves Replaced & Will Be Inspected.Revised Rept Will Follow | | | 05000219/LER-1980-026, Forwards LER 80-026/03L-0 | Forwards LER 80-026/03L-0 | | | 05000219/LER-1980-026-03, /03L-0:on 800709,during Routine Testing Insp of Hydraulic Snubbers Installed in safety-related Sys,Snubber 75/5 Failed to Lock Up in Compression Direction.Caused by Foreign Matl in Snubber Fluid.Snubber Flushed & Refilled | /03L-0:on 800709,during Routine Testing Insp of Hydraulic Snubbers Installed in safety-related Sys,Snubber 75/5 Failed to Lock Up in Compression Direction.Caused by Foreign Matl in Snubber Fluid.Snubber Flushed & Refilled | | | 05000219/LER-1980-027, Forwards LER 80-027/01T-0 | Forwards LER 80-027/01T-0 | |
|