LER-1979-033, /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 |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2191979033R03 - NRC Website |
|
text
uc CONTROL BLOCK: I l
l l
l l
l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6 lN lJ l0 lC lP l 1 l@l 0 l0 l - l 0 l 0 l 0 l 0 l 0 l - l 0 l 0 @l4 l 1 l 1 l 1 ] 1 ]@]
l l@
0 1
7 8 9 LICENSEE CODE 14 16 LICENSE NUMBER 25 26 LICENSE TYPE 30 67 CAT 68 CON'T
@l51l 011l 017 l 9 l@
5f$[ l L j@] 0 l 5 l 010 l0 l 2l 1 l 9 l@l 0 l 9 l 1 l7 l 719 }
Io 1
7 REPORT DATE 80 7
8 60 61 DOCKET NUMB ER 68 59 EVENT DATE 74 EVENT OEsCRIPTION AND PROBABLE CONSEQUENCES h I
10171 While performino surveillance on five electromatic reifef valva nracenra F6 TT1 I switches, it was found that IA83A tripped at a value in excess of the i
O 4
I maximum allowable point of 1059 psig. The initial "As Found" trio point 1
0 s_
I was 1175 psig.
Successive tests found various readings between 1050 l
O 6
I and 1175 psig.
It was then determined that the high pressure micro-l o
7 I
switch was defective and the occurrence could not be attributed to l
0 a
1 instrument drift.
I 80 7
8 D 0 E CO E
$ BC DE COMPONENT CODE St,BC DE S
E l Sl Hlh ((_jh lG lh lI lN lS lT lR l U lh [jLjh d h O
9 7
8 9
10 11 12 13 16 19 20 SEQUENTI AL OCCURRENCE REPORT REVISION LER EVENT YE AR REPOqT NO.
CODE TYPE N O.
O"sge/RO 1719l l-l 01313l Ld 10131 It I l-1 LO_J a
g 21 22 23 24 26 27 28 M
30 31 32 KEN AC ON ON PL NT M
HOURS SB i FOR 8.
SUPPL 1 MANUFACTURER lAl@!Zl@
lZl@
lZ l@
l0l0 010 l lY l@
lYl@
lNl@
l B l0 l7 l0 l 33 34 35 36 3?
40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 1
O l Pressure switch IA83A was replaced with a new Bourdon Tube Pressure l
1 i
l Switch Assembly, Model No. B25-H-1255 by Barksdale.
I i
7 l i
a l
i l
1 4
l 7
8 9 80 SA
% POWER OTHER STATUS Dis O RY DISCOVERY DESCRIPTION lGl@ l0l0l0l@l Hot Standby l
lBl@l Surveillance Testino l
i s
A TIVITY CO TENT RELE ASED OF RELEASE AMMUNT OF ACTIVITY LOC ATION OF RELE ASE NA l
l NA l
Z l @ l Z lgl 1
6 PERSONNEL EXPOS ES NUMBER TYPE
DESCRIPTION
l 0 l 0 l 0 l@l Zl@l NA 1
7 8"
PERSONNEL N3u' dies t
7 i
f h,
NUMBER
DESCRIPTION
NA l
l0l0l0l@l 1 s 7
8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE D ESCRIPTION NA 1910180 l
[ij 9 j W @l 7
8 9 10 30 g l YEf@DE CRIPTION Weekly news release - October 16, 1979 l
lllll;;;;;;;l ISS l
68 69 so 7
8 9 to onald A. Ross 201-455-8785 NAME OF PREPARER PHONE:
.)
v - '.
Jersey Central Power & Light Company D(,
LM7
'(f g )j Madison Avenue at Punch Bowl Road b
Morristown, New Jersey 07360 (201)455-8200 OYSTER CREEK NUCLEAR GENEP.ATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/79-33/3L-0 Report Date October 10, 1979 Occurrence Date September 17, 1979 Identification of Occurrence Violation of the Technical Specifications, paragraph 2.3.4 when electromatic relief valve pressure switch 1A83A was found to trip at a pressure in excess of the maximum allowable value. This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b.1.
Conditions Prior to Occurrence The plant was in hot standby condition.
Temperature - 460*F.
Pressure - 460 psig Water level - 70" yarway SRM counts were between 45 and 70 Description of Occurrence On Honday, Septen.ber 17, 1979, while performing surveillance on five electro-matic relief valve pressure switches, it was found that IA83A tripped at a value in excess of the maximum allowable trip point of 1059 psig. The trip point is derived by adding an appropriate head correction factor to the Technical Specification limit. The initial "As Found" trip point was 1175 psig.
Successive testing found various readings between 1050 and 1175 psig.
It was then determined that the :;tgh pressure micro-switch was defective and the discrepancies could not te attributed to instrument drift.
Apparent Cause of Occurrence The cause of this occurrence is attributed to component failure.
1176 151 Jersey Central Power & Light Company is a Member of the General Pubhc Utilities System
Reportable Occurrence.No. 50-219/79-33/3L-0 Page 2 October 10, 1979 Analysis of Occurrence The reIIef valves are provided to remove sufficient energy from the primary system to prevent the safety valves from lifting during a transient. The limiting pressure transient is a turbine trip from rated design power with a failure of the bypass to function. Under these conditions, the five relief valves are required to operate in order to prevent reaching the lowest set point of the primary system safety valves.
It should be noted that a 25 psig margin exists between the resulting peak pressure and the lowest safety valve set point as added assurance that the safety valves will not Ilft during this transient.
Now with valve NR108A actuating at over 100 psig above the maximum allowable trip point and assuming the most Ilmiting pressure transient has occurred, the lowest set point safety valve may have been required to actuate in order to Ilmit the pressure transient.
Corrective Action
Pressure switch IA83A has been replaced with a new Bourdon Tube Pressure Switch Assembly, Model No. B25-H-1255, manufactured by Barksdale.
Failure Data Manufacturer:
Barksdale Model: B25-H-1255 1176 152
|
|---|
|
|
| | | 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 | |
|