LER-1980-091, /01T-0:on 801220,Channel B Instruments Indicated Low Refueling Water Tank Level.Caused by Frozen Level Transmitters.Replaced Fuse |
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- F,OM f DaTE 80 EVENT OESCRIPTION AND PROB ABLE CONSEOUENCES h 1o12i IDuring Mode 1 operation, while performing routine Refueling Water Tank i
to i31 l(RWT) level indication checks, it was observed that Channels A, C, & D 1
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Previous checks indicated I
t c i s t iaoproximatelv 94%
All ESFAS RWT Instrumentation channels beino declared I ie is i linoperable, the L.C.0. of Action Statement #9 per T.S. 3.3-3 Item 6b, i
10171 'T.5. 3.3.2.1 could not be satisfied.
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40 el di e3 se as CAUSE DESCR.PTION AND CORREC flVE ACTIONS m 1 The instrurent indication discrecancy was diagnosed as frozen RWT level I
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The system heat tracing i
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I lii si i The fuse was replaced and RWT level indication returned to operable status.
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LER 80-091/01T-0 (Continued) 10 initiated per T.S. 3.0.3; however, to meet the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> " time-clock" a manual Reactor trip was required at 30% power. Similar to LER's 50-368/79-001,79-002, 79-008,79-101.
Reportable per T.S. 6.9.1.8.b.
l 27 Investigation revealed fusible disconnect did not confom to design drawings.
Ramifications and long term corrective actions are being evaluated.
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1.
Reportable Occurrence Report No. 50-368/80-091 2,
Report Date:
12/26/80 3.
Occurrence Date: 12/20/80 a.
Facility: Arkansas Nuclear One - Unit Two Russellville, Arkansas 5.
Identification of Occurrence:
Operation of the unit with Engineered Safety Features Actuation System instrumentation subject to a Limiting Condition for Operation (LCO) per T.S. 3.3.2.1, T. S. Table 3.3-3 Item 6b (Refueling Water Tank level instrumentation) in a less conservative than the least conservative aspect of the LCO as established by Action Statement #9 (allowing one inoperablechannel).
Reportable per T.S. 6.9.1.8.b.
6.
Conditions Prior to Occurrence:
Steady-State Power X
Reactor Power 2168 MWth Ilot Standby Net Output 685 MWe Cold Shutdown Percent of Full Power 77 %
Refueling Shutdcwn Load Changes During Routine Power Operation Routine Startup Operation Mode 1 Routine Shutdown Operation Cther (specify) 7.
Description of Occurrence:
While perfoming' routine Refueling Water Tank (RWT) level indication checks, as required by T.S. 4.3.2.1.1, T.S. Table 4.3-2 Item 6b, it was observed that Channels A, C, & D were indicating a level of >100% and~ Channel B was indicating 82%.
The previous channel check readings ranged from 93 to 95% on all RWT level indications.
All EFSAS RWT instrumentation being declared inoperable, the LC0 and associated action statement could not be satisfied; therefore, a Reactor shutdown to Mode 3 operation was initiated per the requirements of T. S. 3.0.3.
To meet the I hour time clock, a manual Reactor trip was required at 30% power.
Reportable occurrence neport No. 50-368/80-091 8.
Designation of Apparent Cause of Occurrence:
Desi m Procedure X
t bbnufacture Unusual Service Condition Including Environnental Installation /
X Const ruction Component Failure X
(See Failure Data)
Operator Personnel Error X
Other (specif,c)
The instrument indication discrepancy was diagnosed as frozen RWT level transmitters due to 150F ambient temperature.
The system heat tracing (added per corrective action to previous occurrences) was found de-energized because of a missing power fuse in a fusible disconnect located in terminal box, 2TB-608.
9.
Analysis of Occurrence:
Investigation revealed that the installation of a fusible disconnect in the heat tracing circuit did not conform to the original design configuration.
The power fuse was apparently removed when an unrelated plant design change required that the RWT level sensing lines be re-rcuted due to space utilization requi rements.
The post design modification check out failed to reverify the operablility of the heat tracing circuitry.
t
i-
able Occurrence Report do.
50-368/80-091 10.
Corrective Action
The short tenm corrective action was to replace the missing power fuse,. thaw the RWT level transmitter, and return the ESFAS Refueling Water Tank instrumentation to an operable status.
Luig term corrective actions are being evaluated.
II.
Failure Data:
Refueling Water Tank, frozen level transmitter, occurrences were reported in LER's 50-368/79-001,79-002, 79-008, and 79-101.
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| 05000368/LER-1980-001-03, /03L-0:on 800107,during Mode 1 Operation, Containment Isolation Valve 25V-5876-2 Failed to Close After Taking Samples from Safety Injection Tanks for Boron Analysis.Caused by Faulty Valve Position Indication | /03L-0:on 800107,during Mode 1 Operation, Containment Isolation Valve 25V-5876-2 Failed to Close After Taking Samples from Safety Injection Tanks for Boron Analysis.Caused by Faulty Valve Position Indication | | | 05000313/LER-1980-001-03, /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7444 Failed to Close.Caused by Oxidation on Torque Switch Contacts, Resulting in High Resistance to Closure.Contacts Cleaned | /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7444 Failed to Close.Caused by Oxidation on Torque Switch Contacts, Resulting in High Resistance to Closure.Contacts Cleaned | | | 05000368/LER-1980-002-03, /03L-0:on 800110,during Mode 1 Operation,Core Protection Calculator C Failed,Resulting in DNBR & Linear Power Density Trips in Channel C Primary Power Sys.Cause Undetermined.Sys Restarted During Failure Analysis | /03L-0:on 800110,during Mode 1 Operation,Core Protection Calculator C Failed,Resulting in DNBR & Linear Power Density Trips in Channel C Primary Power Sys.Cause Undetermined.Sys Restarted During Failure Analysis | | | 05000313/LER-1980-002-03, /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7448 Failed to Close.Caused by Oxidation on Torque Switch Contacts.Contacts Cleaned | /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7448 Failed to Close.Caused by Oxidation on Torque Switch Contacts.Contacts Cleaned | | | 05000313/LER-1980-003-01, /01T-0:on 800121,while at Cold Shutdown,Boron Buildups Identified on Loop B of Reactor Bldg Spray & Piping.Buildups Verified to Be Cracks in heat-affected Zone of Schedule 10 Pipe to Fitting Welds | /01T-0:on 800121,while at Cold Shutdown,Boron Buildups Identified on Loop B of Reactor Bldg Spray & Piping.Buildups Verified to Be Cracks in heat-affected Zone of Schedule 10 Pipe to Fitting Welds | | | 05000313/LER-1980-003, Forwards LER 80-003/01T-0 | Forwards LER 80-003/01T-0 | | | 05000368/LER-1980-003-03, /03L-0:on 800120,during Mode 3 Operation, Emergency Feedwater Flow Control Valve Failed to Close on Demand.Caused by Lack of Hydraulic Pressure | /03L-0:on 800120,during Mode 3 Operation, Emergency Feedwater Flow Control Valve Failed to Close on Demand.Caused by Lack of Hydraulic Pressure | | | 05000368/LER-1980-004-03, /03L-0:on 800107,during Mode 1 Operation,Core Protection Calculator B Failed.Channel B DNBR & Linear Power Density Trips Were Bypassed Placing Reactor Trip Logic in two-out-of-three Trip Sequence.Cause Unknown | /03L-0:on 800107,during Mode 1 Operation,Core Protection Calculator B Failed.Channel B DNBR & Linear Power Density Trips Were Bypassed Placing Reactor Trip Logic in two-out-of-three Trip Sequence.Cause Unknown | | | 05000313/LER-1980-004-03, /03L-0:on 800205,during Operational Test for Leak Rates,Reactor Bldg Ventilation Penetrations V1 & V2 Found Leaking in Excess of Tech Specs.Caused by Maladjusted Valve Seats.Valves Readjusted & Retested | /03L-0:on 800205,during Operational Test for Leak Rates,Reactor Bldg Ventilation Penetrations V1 & V2 Found Leaking in Excess of Tech Specs.Caused by Maladjusted Valve Seats.Valves Readjusted & Retested | | | 05000313/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000368/LER-1980-005, Forwards Revised LER 80-005/03X-1 | Forwards Revised LER 80-005/03X-1 | | | 05000368/LER-1980-005-03, /03L-0:on 800123,during Steady State Mode 1 Operation,Reactor Coolant Leakage Calculation Indicated Approx 3.6 Gpm Unidentified Leakage.Caused by Packing on Pressurized Spray Valves Leaking Excessively | /03L-0:on 800123,during Steady State Mode 1 Operation,Reactor Coolant Leakage Calculation Indicated Approx 3.6 Gpm Unidentified Leakage.Caused by Packing on Pressurized Spray Valves Leaking Excessively | | | 05000313/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000313/LER-1980-005-03, /03L-0:on 800306,during Scheduled Surveillance Test of P7-A,CV-2617 Valve Failed to Close Remote Electrically.Caused by Valve Binding in Closed Position. Valve Stem Repacked & Proper Operation Verified | /03L-0:on 800306,during Scheduled Surveillance Test of P7-A,CV-2617 Valve Failed to Close Remote Electrically.Caused by Valve Binding in Closed Position. Valve Stem Repacked & Proper Operation Verified | | | 05000313/LER-1980-006, Forwards LER 80-006/04L-0 | Forwards LER 80-006/04L-0 | | | 05000368/LER-1980-006-03, /03L-0:on 800123,during Mode 1 Operation,Core Protection Calculator B Failed,Generating DNBR & Linear Power Density Trips in Primary Power Sys.Cause Undetermined. Channel Restarted & Declared Operable | /03L-0:on 800123,during Mode 1 Operation,Core Protection Calculator B Failed,Generating DNBR & Linear Power Density Trips in Primary Power Sys.Cause Undetermined. Channel Restarted & Declared Operable | | | 05000313/LER-1980-006-04, /04L-0:on 800318,average Gross Release Rate for Jan-Mar 1980 Found to Be 4.3% of Max Permissible Concentration,Exceeding Tech Specs.Major Portion Caused by Reactor Bldg Purge in Jan | /04L-0:on 800318,average Gross Release Rate for Jan-Mar 1980 Found to Be 4.3% of Max Permissible Concentration,Exceeding Tech Specs.Major Portion Caused by Reactor Bldg Purge in Jan | | | 05000313/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000313/LER-1980-007-99, Vendor Notified of Discrepancy Between Decay Heat Pump Specs & Parts Supplied. Potential Failure Feared.Tests & Performance History Indicate No Reliability Problems | Vendor Notified of Discrepancy Between Decay Heat Pump Specs & Parts Supplied. Potential Failure Feared.Tests & Performance History Indicate No Reliability Problems | | | 05000313/LER-1980-007-01, /01T-0:on 800314,B&W Advised That Mating Wear Rings on Double Suction Pump Could Cause Pump Failure During Accident Conditions.Caused by Failure to Document Design Revision on Pump Design Drawings | /01T-0:on 800314,B&W Advised That Mating Wear Rings on Double Suction Pump Could Cause Pump Failure During Accident Conditions.Caused by Failure to Document Design Revision on Pump Design Drawings | | | 05000368/LER-1980-007-03, /03L-0:on 800124,during Mode 1 Operation,Sodium Hydroxide Tank Level Found to Be 93% of Indicated Level. Following Calibr,Level Found to Be Below Tech Spec Limits. Cause Not Stated.Tank Levels Returned to Operable Limits | /03L-0:on 800124,during Mode 1 Operation,Sodium Hydroxide Tank Level Found to Be 93% of Indicated Level. Following Calibr,Level Found to Be Below Tech Spec Limits. Cause Not Stated.Tank Levels Returned to Operable Limits | | | 05000313/LER-1980-008-03, /03L-0:on 800324,while Performing Surveillance Test,Bypass Flow Was Observed to Be Zero Due to Failure of CV-2126 in Closed Position.Caused by Blown Control Fuse.Fuse Replaced & Valve Proved Operable | /03L-0:on 800324,while Performing Surveillance Test,Bypass Flow Was Observed to Be Zero Due to Failure of CV-2126 in Closed Position.Caused by Blown Control Fuse.Fuse Replaced & Valve Proved Operable | | | 05000368/LER-1980-008-03, /03L-0:on 800128,during Mode 1 Operation,Core Protection Calculator B Failed.Cause Not Determined.Core Protection Calculator B Restored & Functionally Tested | /03L-0:on 800128,during Mode 1 Operation,Core Protection Calculator B Failed.Cause Not Determined.Core Protection Calculator B Restored & Functionally Tested | | | 05000313/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000313/LER-1980-009-03, /03L-0:on 800328,while Performing Surveillance Test,Lead Hydrogen Purge Supply fan,VSF-30A Tripped on Overload.Caused by Check Valve HPA-5 Being Stuck,Due to Corrosion from Seal Water Leaking Onto Valve | /03L-0:on 800328,while Performing Surveillance Test,Lead Hydrogen Purge Supply fan,VSF-30A Tripped on Overload.Caused by Check Valve HPA-5 Being Stuck,Due to Corrosion from Seal Water Leaking Onto Valve | | | 05000313/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000368/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000368/LER-1980-009-03, /03L-0:on 800129,during Mode 3 Operation Following Reactor Trip from 100% power,I-131 Value of 1.67 Uci Was Observed.Caused by Expected Spike Following Reactor Trip.No Corrective Actions Necessary | /03L-0:on 800129,during Mode 3 Operation Following Reactor Trip from 100% power,I-131 Value of 1.67 Uci Was Observed.Caused by Expected Spike Following Reactor Trip.No Corrective Actions Necessary | | | 05000368/LER-1980-010-03, /03L-0:on 800212,during Mode 5 Operation, Discovered That Tech Spec 24-month Local Leak Rate Surveillance Requirements Had Not Been Performed.Caused by Confusion Over 24-month Surveillance Interval | /03L-0:on 800212,during Mode 5 Operation, Discovered That Tech Spec 24-month Local Leak Rate Surveillance Requirements Had Not Been Performed.Caused by Confusion Over 24-month Surveillance Interval | | | 05000313/LER-1980-010-03, /03L-0:on 800307,sys Reviews Per IE Bulletin 79-14 Found Hangers Inoperable.Cause Not Stated.Hangers Repaired & Mods Made by Revision to DCP 80-D-1207.List of Hangers Encl | /03L-0:on 800307,sys Reviews Per IE Bulletin 79-14 Found Hangers Inoperable.Cause Not Stated.Hangers Repaired & Mods Made by Revision to DCP 80-D-1207.List of Hangers Encl | | | 05000313/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000313/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000313/LER-1980-011-03, /03L-0:on 800401,based on Sys Review Per IE Bulletin 79-14,certain Hangers Declared Inoperable.Cause Not Stated.Hangers Repaired or Modified within Required Time Limit on Affected Svc Water & Main Steam Sys | /03L-0:on 800401,based on Sys Review Per IE Bulletin 79-14,certain Hangers Declared Inoperable.Cause Not Stated.Hangers Repaired or Modified within Required Time Limit on Affected Svc Water & Main Steam Sys | | | 05000368/LER-1980-011-03, /03L-0:on 800214,during Mode 5 Operation,While Performing Local Leak Rate Test,Five Containment Penetration Leak Rates Exceeded Tech Specs.Caused by Corrosion Buildup on Seating Surface or Valves Needing Adjustment | /03L-0:on 800214,during Mode 5 Operation,While Performing Local Leak Rate Test,Five Containment Penetration Leak Rates Exceeded Tech Specs.Caused by Corrosion Buildup on Seating Surface or Valves Needing Adjustment | | | 05000368/LER-1980-012, Forwards Updated LER 80-012/03X-2 | Forwards Updated LER 80-012/03X-2 | | | 05000313/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000313/LER-1980-012-03, /03L:on 800406,while Performing Monthly Inservice Valve Stroke Test,Emergency Feedwater Supply valves,CV2667 & CV2617,failed to Fully Open.Caused by Binding Due to Loose Bolts Securing Actuator | /03L:on 800406,while Performing Monthly Inservice Valve Stroke Test,Emergency Feedwater Supply valves,CV2667 & CV2617,failed to Fully Open.Caused by Binding Due to Loose Bolts Securing Actuator | | | 05000368/LER-1980-012-03, /03L-0:on 800222,during Mode 5 Operation,While Performing Surveillance Tests on Diesel Generator 1,unit Became Inoperable.Caused by Broken Generator Rotor Shaft in Area of Motor End Bearing Housing.Analyzing Exact Cause | /03L-0:on 800222,during Mode 5 Operation,While Performing Surveillance Tests on Diesel Generator 1,unit Became Inoperable.Caused by Broken Generator Rotor Shaft in Area of Motor End Bearing Housing.Analyzing Exact Cause | | | 05000313/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000368/LER-1980-013-03, /03L-0:on 800229,during Mode 5 Operation,Reactor Cooling Sys Chloride Concentration Found to Be Approx 0.5 Ppm,Violating Tech Specs.Probably Caused by Batch Contaminated During Maint on Safety Injection Check Valve | /03L-0:on 800229,during Mode 5 Operation,Reactor Cooling Sys Chloride Concentration Found to Be Approx 0.5 Ppm,Violating Tech Specs.Probably Caused by Batch Contaminated During Maint on Safety Injection Check Valve | | | 05000368/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000313/LER-1980-013-03, /03L-0:on 800407,during Reactor Trip of Offsite Power,High Pressure Injection Was Manually Initiated & CV-1227 High Pressure Injection Valve,Loop B Failed to Open on Demand.Caused by Stuck Engaging Lever | /03L-0:on 800407,during Reactor Trip of Offsite Power,High Pressure Injection Was Manually Initiated & CV-1227 High Pressure Injection Valve,Loop B Failed to Open on Demand.Caused by Stuck Engaging Lever | | | 05000368/LER-1980-014-03, /03L-0:on 800313,during Mode 5 Operation,Local Leak Rate Testing at Containment Penetration 2V2 Revealed Excessive Leak Rate Between Valve Actuation & Heatup Processes.Caused by Partially Open Inside Isolation Valve | /03L-0:on 800313,during Mode 5 Operation,Local Leak Rate Testing at Containment Penetration 2V2 Revealed Excessive Leak Rate Between Valve Actuation & Heatup Processes.Caused by Partially Open Inside Isolation Valve | | | 05000368/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000313/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000313/LER-1980-014-03, /03X-1:on 800415,fire & Smoke Detector Testing Not Completed within Surveillance Interval Due to High Radiation Level.Detectors Tested at Cold Shutdown.Tech Spec 4.19 Revised | /03X-1:on 800415,fire & Smoke Detector Testing Not Completed within Surveillance Interval Due to High Radiation Level.Detectors Tested at Cold Shutdown.Tech Spec 4.19 Revised | | | 05000368/LER-1980-015, Forward LER 80-015/99X-0 | Forward LER 80-015/99X-0 | | | 05000368/LER-1980-015-99, /99X-0:on 800129,during Recovery from Planned Transient,Rcs Depressurized to Min of 1,350 Psia.Caused by Pressurizer Spray Valve 2CV-4651 & Steam Dump & Bypass Valve 2CV-0301 Not Fully Closing on Demand.Valves Modified | /99X-0:on 800129,during Recovery from Planned Transient,Rcs Depressurized to Min of 1,350 Psia.Caused by Pressurizer Spray Valve 2CV-4651 & Steam Dump & Bypass Valve 2CV-0301 Not Fully Closing on Demand.Valves Modified | | | 05000313/LER-1980-015, Forwards LER 80-015/01T-0 | Forwards LER 80-015/01T-0 | | | 05000313/LER-1980-015-01, /01T-0:on 800510,changes in Seal Pressure & Makeup Tank Level Occurred During Steady State Power Operation. Caused by Rx Coolant Pump Seal C.Seal Cartridge Rebuilt & Seal Failure Being Investigated | /01T-0:on 800510,changes in Seal Pressure & Makeup Tank Level Occurred During Steady State Power Operation. Caused by Rx Coolant Pump Seal C.Seal Cartridge Rebuilt & Seal Failure Being Investigated | |
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