LER-1979-030, /03L-0:on 790812,control Rod Drive Pump Removed from Svc Due to Excessive Leakage from Pump Vent Piping. Piping Was Cracked at Bushing.Caused by Use of Vent Line as Operator Foot Support.Bushing & Pipe Nipple Replaced |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2191979030R03 - NRC Website |
|
text
s CONTROL BLOCK: l l
l l
l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
1'] l N l J l 0 l C l P l 1 l@150l0 -l0l0l0l0l0 l-l0 l0l@26l4l1l1l1l1j@l l
l@
o LICENSE NUMBER 25 LICENSE TYPE 20 57 CAT 68 7
8 9 LICENSEE CODE 14 CON'T 011
[',"c' l L l@l5 l 0 l 0 l 0 l 0 2l1l9l@l0l8(1 l217!9l@l019ll121719l@
7 8
60 61 DOCKET NUME E R 68 69 EVENT D ATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h O
2 l
During normal operation, "A" CRD pump was removed from service due to
[
l O t 31 l excess'ive leakage from the pump vent piping.
The piping was found to be l
O 4
I cracked at the bushing where it enters the pump casing.
The safety slo-O s
nificance of this event is considered minimal because of the availability l
0 6
l of a redundant pump.
l l
017 l
1 1O a
1 EO 7
eo DE CO E 5 BCO E COMPONENT CODE SUBC DE 5
E ol9 l R l B l@ l El@ l X l@ l P l l l P l E X l X l@
l A j @ [Zj @
7 6
9 to 11 12 13 16 19 20 SE OUE NTI AL OCCURRENCE REPORT REVI510N LE A' AO EVENT YE AR REPORT NO.
CODE TYPE N O.
O"sgi,a; 17 19 I l-l 1013101 1/l 10 13 I ILl l-l l0 l a
,21 22 23 24 26 27 28 29 30 31 32 TAKEN AC ON ON PL NT ME HOUR $
5ei FOR B.
$UPPLI R MANUF ACTURE R l A lg]34Xl@
l Z l@
lZl@
l 0l 0l 0] 0l lYl@
lY l@
l Z]@ lZl9l9l9l{
33 3b 36 37 40 41 42 43 44 4-CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i
O ]
The cracking appears to be caused by an operator using the vent line as j
i i
[
a foot support.
The affected bushing and a short pipe nipple in the line i
7 l
were replaced and the pump returned to service.
l 11 131 l i
I 1
4 l
7 8 9 B0 STA
% POWE R OTHE R STATUS DISCO R DISCOVERY DESCRIPTION NA l
l A l@l Operator Observation l
[.E j@ l 019 18 l@l 1
5 ACTIVITY CO TENT RELE ASED OF RELE ASE AMOUNT OF ACTIVITY LOC ATION OF RELE ASE NA l
l NA l
[1_} 6.] l Z l @ Wgl PERSONNEL ExPosVAEs oo DESCRIPTION @
0 0
NUMBER TYPE l0 l0 l0 lhlZlhl l
NA y _ _
_Il_
1 7
PERsONNE L iNev' lies NUMBER
DESCRIPTION
]
k l
l l0 l0 l0 l@l
[]
NA i a n
7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY 7
f l Z l@l NA
{
V 9 0919 0 9'9"f ' ;
1 9
7 8 9 to go ISSUE DE RIPTION W [,Y,,,j h l Week 1v oress re l ea c:e September 18. 1979 I
llllllll1ll}l 7
8 9 to 68 69 30 201-455-8784 NAME OF PREPARER PHONE:
Jersey Central Power & Light Company f y )
Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/79-30/3L-0 Report Date September 12, 1979 Occurrence Date August 12, 1979 Identification of Occurrence "A" Control rod drive pump was removed from service for repair of pump vent piping.
This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b.2.
Conditions Prior to Occurrence The plant was operating at steady state power.
Power:
Generator, 645 MWe Reactor, 1970 MWt Flow:
Recirculating, 15.4 x 104 gpm Feedwater, 7.137 x 106 lb/hr 4
Stack Gas Activity:
2.79 x 10 pCI/sec Description of Occurrence On August 12,1979, at 0331 hours0.00383 days <br />0.0919 hours <br />5.472884e-4 weeks <br />1.259455e-4 months <br />, "A" control rod drive pumo was removed from service due to excessive leakage from the pump vent piping.
The piping was found to be cracked at the bushing where it enters the pump casing.
After completion of the corrective maintenance, "A" CRD pump was placed into service at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on the same date.
Apparent Cause of Occurrence Vent piping was found to be cracked at the bushing where it enters the pump casing at the inboard end.
The cracking appears to be caused by an operator using the vent line as a foot support.
O "
i, fj b Analysis of Occurrence
/
I In addition to supplying drive cooling and accumulator charging pressure, the control rod drive hydraulic system can provide high pressure coolant injection Jersey Central Power & Light Company is a Member of the General Pubhc Utaties System
Reportable Occurrence No. 50-219/79-30/3f.-0 Page 2 September 12, 1979 capability.
For break sizes up to 0.002 ft.2, a singic control rod drive pump with a flow of 110 gpm is edequate for maintaining the reactor water level nearly five feet above the core, thus alleviating the necessity for electromatic relief valve actuation.
The safety significance of this event is considered to be minimal, since the redundant CRD pump was operable.
Corrective Action
"A" CRD pump was removed from service and isolated.
The bushing and a short pipe nipple in the inboard casing vent line were replaced.
"A" CRD pump was placed in service after corrective maintenance.
A memorandum will be issued stressing that operators should not use small piping as a foot support.
Failure Data Not appIlcable.
\\
o.i i
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000219/LER-1979-001-03, /03L-0 on 790118:valve V-14-35 Failed to Open Completely During Routine Isolation Condenser Valve Operability Test.Caused by Dirty Torque Limit Switch Contacts,Which Were Subsequently Cleaned & Burnished | /03L-0 on 790118:valve V-14-35 Failed to Open Completely During Routine Isolation Condenser Valve Operability Test.Caused by Dirty Torque Limit Switch Contacts,Which Were Subsequently Cleaned & Burnished | | | 05000219/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000219/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000219/LER-1979-002-03, /03L-0 on 790206:while Performing Isolation Condenser Automatic Actuation Test & calibr,RE-15B Trip Point Was Less Conservative than Tech Spec Std.Caused by RE-15B Switch Not Set at 1068 Psig valve.RE-15B Reset | /03L-0 on 790206:while Performing Isolation Condenser Automatic Actuation Test & calibr,RE-15B Trip Point Was Less Conservative than Tech Spec Std.Caused by RE-15B Switch Not Set at 1068 Psig valve.RE-15B Reset | | | 05000219/LER-1979-010-03, /03L-0 on 790417:leak of Isotopic Concentration Noticed Near Inside Penetration within Pipe Tunnel.Caused by Component Failure.Drywell Equipment Drain Tank Line Rerouted to Prevent Further Leakage | /03L-0 on 790417:leak of Isotopic Concentration Noticed Near Inside Penetration within Pipe Tunnel.Caused by Component Failure.Drywell Equipment Drain Tank Line Rerouted to Prevent Further Leakage | | | 05000219/LER-1979-010, Forwards LER 79-010/03L-0 | Forwards LER 79-010/03L-0 | | | 05000219/LER-1979-011-03, /03L-0 on 790419:core Spray Pump NZO1A in Sys 1 Failed to Start Upon Initiation Signal.Caused by Fuse Failure.Fuse Replaced & Pump Test Successfully Completed | /03L-0 on 790419:core Spray Pump NZO1A in Sys 1 Failed to Start Upon Initiation Signal.Caused by Fuse Failure.Fuse Replaced & Pump Test Successfully Completed | | | 05000219/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000219/LER-1979-012-03, /03L-0 on 790419:oxygen Level in Suppression Chamber Atmosphere Was Greater than 5%.Caused by Sensitivity of Sampling Sys & Position of Sample Flow Control Valve. Oxygen Analyzer Recalibr;Level Now Below 5% | /03L-0 on 790419:oxygen Level in Suppression Chamber Atmosphere Was Greater than 5%.Caused by Sensitivity of Sampling Sys & Position of Sample Flow Control Valve. Oxygen Analyzer Recalibr;Level Now Below 5% | | | 05000219/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000219/LER-1979-016, Forwards LER 79-016/03L-0 | Forwards LER 79-016/03L-0 | | | 05000219/LER-1979-016-03, /03L-0 on 790506:during Surveillance Test, Isolator Condenser Isolation Sensor Setpoint a Measured Two Inches of Excess Water.Caused by Instrument Drift in Excess of Design Accuracy.Switch Was Recalibr & Put Back in Svc | /03L-0 on 790506:during Surveillance Test, Isolator Condenser Isolation Sensor Setpoint a Measured Two Inches of Excess Water.Caused by Instrument Drift in Excess of Design Accuracy.Switch Was Recalibr & Put Back in Svc | | | 05000219/LER-1979-017, Forwards LER 79-017/03L-0 | Forwards LER 79-017/03L-0 | | | 05000219/LER-1979-017-03, /03L-0 on 790517:during Routine Surveillance of Core Spray Sys Ii,Parallel Isolation Valve V-20-21 Failed to Operate.Caused by Circuit Breaker Contacts Making Poor Contact in B Phase,Creating Overcurrent.Part Replaced | /03L-0 on 790517:during Routine Surveillance of Core Spray Sys Ii,Parallel Isolation Valve V-20-21 Failed to Operate.Caused by Circuit Breaker Contacts Making Poor Contact in B Phase,Creating Overcurrent.Part Replaced | | | 05000219/LER-1979-018, Forwards LER 79-018/03L-0 | Forwards LER 79-018/03L-0 | | | 05000219/LER-1979-018-03, /03L-0 on 790517:snubber 51/21,core Spray Sys II, Had Signs of Grease on Alemite Fitting on Accumulator.Cause Unknown But Appears Related to Rigorous Svc Conditions. Snubber Replaced | /03L-0 on 790517:snubber 51/21,core Spray Sys II, Had Signs of Grease on Alemite Fitting on Accumulator.Cause Unknown But Appears Related to Rigorous Svc Conditions. Snubber Replaced | | | 05000219/LER-1979-019-03, /03L-0 on 790526:reactor High Pressure Isolation Condenser Initiation Switch RE-15A Tripped at 3 Psig Greater than Specified.Caused by Instrument repeatability.RE-158 Reset to Trip at 1,068 Psig | /03L-0 on 790526:reactor High Pressure Isolation Condenser Initiation Switch RE-15A Tripped at 3 Psig Greater than Specified.Caused by Instrument repeatability.RE-158 Reset to Trip at 1,068 Psig | | | 05000219/LER-1979-019, Forwards LER 79-019/03L-0 | Forwards LER 79-019/03L-0 | | | 05000219/LER-1979-020, Forwards LER 79-020/01T-0 | Forwards LER 79-020/01T-0 | | | 05000219/LER-1979-020-01, /01T-0 on 790613:secondary Containment Integrity Breached When Reactor Bldg Airlock Doors Were Opened Simultaneously.Caused by Failure of Procedure to State Correct Method for Securing Airlock Doors.Procedure Revised | /01T-0 on 790613:secondary Containment Integrity Breached When Reactor Bldg Airlock Doors Were Opened Simultaneously.Caused by Failure of Procedure to State Correct Method for Securing Airlock Doors.Procedure Revised | | | 05000219/LER-1979-021-03, /03L-0 on 790620:during Surveillance Testing Activities,Instrument 1P15A Was Found to Trip at Valve Higher than Allowed by Tech Specs.Instrument Found to Be within Expected Accuracy Attainable | /03L-0 on 790620:during Surveillance Testing Activities,Instrument 1P15A Was Found to Trip at Valve Higher than Allowed by Tech Specs.Instrument Found to Be within Expected Accuracy Attainable | | | 05000219/LER-1979-021, Forwards LER 79-021/03L-0 | Forwards LER 79-021/03L-0 | | | 05000219/LER-1979-022, Forwards LER 79-022/03L-0 | Forwards LER 79-022/03L-0 | | | 05000219/LER-1979-022-03, /03L-0 on 790627:leak Detected on Emergency Svc Water Side of Containment Spray Heat Exchanger 1-2.Caused by Leaking Nipple Connection Between Water Box & Piping to Valve V-3-83,due to Corrosion.Nipple Replaced | /03L-0 on 790627:leak Detected on Emergency Svc Water Side of Containment Spray Heat Exchanger 1-2.Caused by Leaking Nipple Connection Between Water Box & Piping to Valve V-3-83,due to Corrosion.Nipple Replaced | | | 05000219/LER-1979-023-01, /01T-0 on 790719:reactor Power Was Reduced Above Value for Removal of a Feedwater String.Caused by Removal of Recirculating Pump Reactor for Maint.Inboard & Outboard Collector Rings Resurfaced & Pump Returned to Svc | /01T-0 on 790719:reactor Power Was Reduced Above Value for Removal of a Feedwater String.Caused by Removal of Recirculating Pump Reactor for Maint.Inboard & Outboard Collector Rings Resurfaced & Pump Returned to Svc | | | 05000219/LER-1979-023, Forwards LER 79-023/01T-0 | Forwards LER 79-023/01T-0 | | | 05000219/LER-1979-024, Forwards LER 79-024/03L-0 | Forwards LER 79-024/03L-0 | | | 05000219/LER-1979-024-03, /03L-0:on 790730,control Rod Drive Pump a Discovered Spraying Water Through Seal.Caused by Failure of Mechanical Seal.Inboard Mechanical Seal & Inboard Bearing Replaced | /03L-0:on 790730,control Rod Drive Pump a Discovered Spraying Water Through Seal.Caused by Failure of Mechanical Seal.Inboard Mechanical Seal & Inboard Bearing Replaced | | | 05000219/LER-1979-025, Forwards LER 79-025/03L-0 | Forwards LER 79-025/03L-0 | | | 05000219/LER-1979-025-03, /03L-0:on 790806,10,000 Gallons of Torus Water Drained & Ability of Primary Containment Degraded.Caused by Isolation Valve Left Open After Water Samplings.Change to Sampling Procedure Submitted on Use of Valve | /03L-0:on 790806,10,000 Gallons of Torus Water Drained & Ability of Primary Containment Degraded.Caused by Isolation Valve Left Open After Water Samplings.Change to Sampling Procedure Submitted on Use of Valve | | | 05000219/LER-1979-026-03, /03L-0:on 790807,while Excavating to Repair Equipment Drain Tank Line,Leak in Laundry Tank Discharge Pipe Discovered.Caused by Levels of Mn-54 & Co-60.Line Temporarily Rerouted Until Repairs Made | /03L-0:on 790807,while Excavating to Repair Equipment Drain Tank Line,Leak in Laundry Tank Discharge Pipe Discovered.Caused by Levels of Mn-54 & Co-60.Line Temporarily Rerouted Until Repairs Made | | | 05000219/LER-1979-026, Forwards LER 79-026/03L-0 | Forwards LER 79-026/03L-0 | | | 05000219/LER-1979-027, Forwards LER 79-027/01T-0 | Forwards LER 79-027/01T-0 | | | 05000219/LER-1979-027-01, /01T-0 on 790807:four Seismic restraints,NZ-2-R5 NZ-2R7,NZ-2-R8 & NZ-2-R9,in Positions Other than Required by Original Design.Caused by Improper Installation & Damage Due to Unrestrained Pipe Movement | /01T-0 on 790807:four Seismic restraints,NZ-2-R5 NZ-2R7,NZ-2-R8 & NZ-2-R9,in Positions Other than Required by Original Design.Caused by Improper Installation & Damage Due to Unrestrained Pipe Movement | | | 05000219/LER-1979-028, Forwards LER 79-028/03L-0 | Forwards LER 79-028/03L-0 | | | 05000219/LER-1979-028-03, /03L-0:on 790807,during Routine Surveillance of Core Spray Sys 1,parallel Isolation Valve V-20-15 Became Inoperable in Open Position.Caused by High Motor Current Drawn When Close Signal Inadvertently Initiated | /03L-0:on 790807,during Routine Surveillance of Core Spray Sys 1,parallel Isolation Valve V-20-15 Became Inoperable in Open Position.Caused by High Motor Current Drawn When Close Signal Inadvertently Initiated | | | 05000219/LER-1979-029, Forwards LER 79-029/03L-0 | Forwards LER 79-029/03L-0 | | | 05000219/LER-1979-029-03, /03L-0:on 790822,rod Block Trip Setting Was Below 100 Counts Per Second 26 Times During QA Audit.Caused by Calibr Procedure Setting Rod Trip at Tech Spec Limit.Rod Withdrawal Block Setpoint Increased | /03L-0:on 790822,rod Block Trip Setting Was Below 100 Counts Per Second 26 Times During QA Audit.Caused by Calibr Procedure Setting Rod Trip at Tech Spec Limit.Rod Withdrawal Block Setpoint Increased | | | 05000219/LER-1979-030, Revised Attachment to LER 79-030/03L-0:on 790812,control Rod Drive Pump a Removed from Svc for Repair of Pump Vent Piping.Piping Cracked at Bushing at Entry to Pump Casing. Caused by Operator Carelessness.Bushing Replaced | Revised Attachment to LER 79-030/03L-0:on 790812,control Rod Drive Pump a Removed from Svc for Repair of Pump Vent Piping.Piping Cracked at Bushing at Entry to Pump Casing. Caused by Operator Carelessness.Bushing Replaced | | | 05000219/LER-1979-030-03, /03L-0:on 790812,control Rod Drive Pump Removed from Svc Due to Excessive Leakage from Pump Vent Piping. Piping Was Cracked at Bushing.Caused by Use of Vent Line as Operator Foot Support.Bushing & Pipe Nipple Replaced | /03L-0:on 790812,control Rod Drive Pump Removed from Svc Due to Excessive Leakage from Pump Vent Piping. Piping Was Cracked at Bushing.Caused by Use of Vent Line as Operator Foot Support.Bushing & Pipe Nipple Replaced | | | 05000219/LER-1979-031, Forwards LER 79-031/03L-0 | Forwards LER 79-031/03L-0 | | | 05000219/LER-1979-031-03, /03L-0:on 790829,seal Water Piping Found Cracked on Short Pipe Nipple Section Where Threaded Into Seal Cartridge.Caused by Operator Using half-inch Piping as Foot Support.Pipe Nipple Replaced | /03L-0:on 790829,seal Water Piping Found Cracked on Short Pipe Nipple Section Where Threaded Into Seal Cartridge.Caused by Operator Using half-inch Piping as Foot Support.Pipe Nipple Replaced | | | 05000219/LER-1979-032, Forwards LER 79-032/03L-0 | Forwards LER 79-032/03L-0 | | | 05000219/LER-1979-032-03, /03L-0:on 790914,leaks Discovered in Both Containment Spray Sys.Caused by Corrosion Accelerated by Galvanic Action.Matl Change in Nipple Recommended | /03L-0:on 790914,leaks Discovered in Both Containment Spray Sys.Caused by Corrosion Accelerated by Galvanic Action.Matl Change in Nipple Recommended | | | 05000219/LER-1979-033, Forwards LER 79-033/03L-0 | Forwards LER 79-033/03L-0 | | | 05000219/LER-1979-033-03, /03L-0:on 790917,electromatic Relief Valve Pressure Switch 1A83A Tripped at Pressure in Excess of Limit.Caused by Defective High Pressure Microswitch. Replacement Switch Installed | /03L-0:on 790917,electromatic Relief Valve Pressure Switch 1A83A Tripped at Pressure in Excess of Limit.Caused by Defective High Pressure Microswitch. Replacement Switch Installed | | | 05000219/LER-1979-034, Forwards LER 79-034/01T-0 | Forwards LER 79-034/01T-0 | | | 05000219/LER-1979-034-01, /01T-0:on 791008,both Personnel Access Air Lock 15ors of Reactor Bldg Were Simultaneoulsy Open.Caused by Contractor Personnel Disconnecting Automatic Closing Device on One Door.Device Reconnected | /01T-0:on 791008,both Personnel Access Air Lock 15ors of Reactor Bldg Were Simultaneoulsy Open.Caused by Contractor Personnel Disconnecting Automatic Closing Device on One Door.Device Reconnected | | | 05000219/LER-1979-035, Forwards LER 79-035/03L-0 | Forwards LER 79-035/03L-0 | | | 05000219/LER-1979-035-03, /03L-0:on 790926,during Normal Operation,Reading on Main Steam Line Radiation Monitor Lower than Other Three Monitors.Caused by Drift of Zero Setpoint of Amplifier in Monitor.Setpoint Reset to Zero | /03L-0:on 790926,during Normal Operation,Reading on Main Steam Line Radiation Monitor Lower than Other Three Monitors.Caused by Drift of Zero Setpoint of Amplifier in Monitor.Setpoint Reset to Zero | |
|