AO 50-219/74/2:main Steam Line High Flow sensors,RE22C & RE22E Actuated at Differential Pressure of 100 Psi Greater than Tech Specs.Cause of Setpoint Change Being Investigated| ML20151C142 |
| Person / Time |
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| Site: |
Oyster Creek |
|---|
| Issue date: |
01/17/1974 |
|---|
| From: |
JERSEY CENTRAL POWER & LIGHT CO. |
|---|
| To: |
|
|---|
| References |
|---|
| AO-50-219-74-2, NUDOCS 8103040582 |
| Download: ML20151C142 (2) |
|
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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML19343C2181975-12-23023 December 1975
AO 50-219/75-33:on 751212,during 6-month Load Test on Station a batteries,125 Volt Dc Distribution Ctr de-energized.Caused by Personnel Error in Following Procedure.Distribution Ctr re-energized
ML20090C9991975-12-12012 December 1975
AO 75-33:on 751212,125-volt Dc Distribution Ctr of Station a Battery Inadvertently de-energized.Caused by Failure to Establish Proper Breaker Lineup Preparation for Conducting Battery Load Test.Procedure changed.W/751219 Memo
ML19343C2191975-12-11011 December 1975
AO 50-219/75-32:on 751203,during Testing,Emergency Diesel Generator 1 Failed to Start When Simulated Loss of Power Condition Applied to Fast Start Logic Circuit.Caused by Failure of Relay to Operate Due to Varnish on Armature
ML20126E8281975-12-0303 December 1975
AO 50-219/75-31:on 751124,during Operability Test of Torus to Drywell Vacuum Breakers,Alarm Sys 2 Failed to Annunciate in Control Room When V-26-4 Opened.Caused by Failure of Relay Due to Contacts Being Detective.Relay Replaced
ML20090D0071975-11-25025 November 1975
AO 75-31:on 751124,drywell Vacuum Breaker Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-4 Opened. Caused by Component Failure.Corrective Action Under Investigation
ML20090D0161975-11-0707 November 1975
AO 75-30:on 751106,low Reactor Pressure Core Spray Valve Permissive Pressure Switches Re 17 a & C Tripped at Pressure Less than Min Required Value.Caused by Switch Repeatability.Pressure Switches Recalibr
ML20090D0601975-11-0606 November 1975
AO 75-29:on 751027,torus Drywell Vacuum Breakers Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-8 Opened. Caused by Sticking Microswitch
ML20090D0761975-10-28028 October 1975
AO 75-29:on 751027,torus to Drywell Vacuum Breaker Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-8 Opened.Caused by Component Failure.Corrective Action Under Investigation
ML20090D0941975-10-24024 October 1975
AO 75-28:on 751015,standby Gas Treatment Sys 1 Inoperable. Caused by Air Solenoid Valve Coil Failure.Defective Solenoid Coil Replaced
ML20090D1141975-10-17017 October 1975
AO 75-27:on 751008,low Reactor Pressure Core Spray Valve Permissive Pressure Switches RE17B & D Tripped at Pressure Less than Min Required Value.Caused by Switch Repeatability. Pressure Switches Recalibr
ML20090D1041975-10-16016 October 1975
AO 75-28:on 751015,standby Gas Treatment Sys 1 Inoperable. Caused by Air Solenoid Valve Coil Failure.Defective Solenoid Coil replaced.W/751016
ML20090D1341975-10-0808 October 1975
AO 75-27:on 751008,low Reactor Pressure Core Spray Valve Permissive Pressure Switches RE17B & D Tripped at Pressures Less than Min Required Value.Caused by Switch Repeatability. Pressure Switches Recalibr
ML20090D1501975-09-23023 September 1975
AO 75-26:on 750923,emergency Svc Water Pump 52C Failed to Start Automatically During Routine Surveillance Test of Containment Spray Sys Ii.Caused by Failure of Contact Switch in Time Delay Relay 16 K4B.Relay Replaced
ML20090D2071975-09-0808 September 1975
AO 75-24:on 750829,electromatic Relief Valve Pressure Switches 1A83C & 1A83D Tripped at Pressures in Excess of Max Allowable Value.Caused by Instrument Setpoint Repeatability. Switches Reset
ML19291C2641975-09-0808 September 1975
AO 73-19:when Closing Signal Was Applied to Breaker S1A,loss of Power Occurred at 4160-volt Ac Bus 1A Causing Trip of Various Pumps.Caused by Incorrect Setting of Current Transformer Ratio Matching Taps.Taps Set Properly
ML20090D1941975-09-0808 September 1975
AO 75-25:on 750829,stack Gas Sample Sys Failed to Monitor Stack Releases Continuously While Reactor Was in Unisolated Condition.Caused by Malfunctioning Pump Lubricator.Thermal Overload Protection Reset
ML20090D2151975-09-0202 September 1975
AO 75-24:on 750829,electromatic Relief Valve Pressure Switches 1A83C & 1A83D Tripped at Pressures in Excess of Max Allowable Value.Caused by Instrument Setpoint Repeatability. Switches Reset
ML20090D2011975-09-0202 September 1975
AO 75-25:on 750829,stack Gas Sample Sys Failed to Monitor Stack Releases Continuously While Reactor Was in Unisolated Condition.Caused by Malfunctioning Pump Lubricator.Thermal Overload Protection Reset
ML20090D2241975-08-21021 August 1975
AO 75-23:on 750817-20,stack Effluent for Iodine & Particulates Not Monitored.Caused by Personnel Error.Filter Installed in Operating Stack Gas Sampling Train
ML20090D2261975-08-11011 August 1975
Preliminary AO-50-219/75-22:on 750810,stack Gas Sample Line Low Flow Alarm Received.Caused by Stack Gas Sample Pump a Not Running.Thermal Overload Protection Reset
ML20090D2471975-08-0404 August 1975
Preliminary AO-50-219/75-21:on 750801,during Routine Surveillance on B Isolation Condensor Sys,Steam Line Valve V-14-32 Failed to Close on Simulation of Steam Line High Flow.Caused by Low Torque Switch Setting.Torque Increased
ML20090D2521975-07-17017 July 1975
AO 50-219/75-19:on 750708,during Monthly Surveillance Test on Reactor High Pressure Scram Sensors,Re 03A,B,C & D, A,B & D Tripped Above Normal Trip Points.Caused by Switch Repeatability.Sensors Recalibr
ML20090D2561975-07-0909 July 1975
Preliminary AO 50-219/75-19:on 750708,during Monthly Surveillance Test on Reactor High Pressure Scram Sensors,Re 03A,B,C & D,A,B & D Tripped Above Normal Trip Points.Caused by Switch Repeatability.Sensors Recalibr
ML20084E1151975-07-0101 July 1975
RO 50-219/75-18:on 750623,two 8-1/2 Inch Handhole Covers in Standby Gas Treatment Filter Train Not in Place.Cause Unknown.Handhole Covers Repositioned & Secured
ML20090D2741975-06-27027 June 1975
AO 50-219/75-17:on 750619,during Surveillance Test,Core Spray Sys Parallel Isolation Valve V-20-15 Failed to Demonstrate Operability.Caused by Broken Tab on B Phase of Valve Motor Breaker Stab.Stab Replaced
ML20090D2661975-06-24024 June 1975
Preliminary AO 50-219/75-18:on 750623,handhole Covers in Standby Gas Treatment Filter Train 1-1 Not in Place.Cause Under Investigation.Covers Repositioned & Secured
ML20090D2781975-06-24024 June 1975
AO 50-219/75-16:on 750614,electromatic Relief Valve Pressure Switches 1A83P & E Tripped at Pressures Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Switches Reset
ML20090D2731975-06-19019 June 1975
Preliminary AO 50-219/75-17:on 750619,during Surveillance Test,Core Spray Sys Parallel Isolation Valve V-20-15 Failed to Demonstrate Operability.Caused by Broken Tab on B Phase of Valve Motor Breaker Stab.Stab Replaced
ML20090D2901975-06-16016 June 1975
Preliminary AO 50-219/75-16:on 750614,electromatic Relief Valve Pressure Switches 1A83B & E Tripped at Pressure Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Switches Reset
ML20090D6561975-06-0606 June 1975
AO-50-219/75-14:on 750529,during Surveillance Test of Containment Spray Pump Operability,Essential Svc Water Pump 1-2 Failed to Develop Sufficient Discharge Pressure.Caused by Dirt in Check Valve V-3-68.Valve Cleaned & Repaired
ML20090D2971975-06-0606 June 1975
AO 50-219/75-15:on 750530,calculations of TIP Traces Indicated Total Peaking Factor in One Core Location in Excess of Value of Pf Given in Tech Specs.Caused by Lack of Operating Experience W/New Core Loading
ML20090D2981975-06-0202 June 1975
Preliminary AO 50-219/75-15:on 750530,calculations of TIP Traces Indicated Total Peaking Factor in One Core Location in Excess of Value of Pf Given in Tech Specs.Caused by Lack of Operating Experience W/New Core Loading
ML20090D6581975-05-30030 May 1975
Preliminary AO-50-219/75-14:on 750529,during Surveillance Test of Containment Spray Pump Operability,Essential Svc Water Pump 1-2 Failed to Develop Sufficient Discharge Pressure.Caused by Dirt in Check Valve V-3-68.Valve Cleaned
ML20090D6611975-05-14014 May 1975
AO-50-219/75-13:on 750507,during Surveillance Test,Time Delay Relay 6Kll Failed to de-energize within 15 After Pressure Sensor RE-15C Tripped.Caused by Component Failure.Relay 6Kll Replaced
ML20090D6641975-05-0707 May 1975
Preliminary AO-50-219/75-13:on 750507,during Surveillance Test,Time Delay Relay 6Kll Failed to de-energize within 15 After Pressure Sensor RE-15C Tripped.Caused by Component Failure.Relay 6Kll Replaced
ML20090D6531975-05-0606 May 1975
AO-50-219/75-12:on 750426,low Reactor Pressure Core Spray Valve Permissive Pressure Switches Re 17B & C Found to Trip at Pressure Less than Tech Spec Value.Caused by Switch Repeatablilty.Switches Recalibr
ML20090D6701975-04-28028 April 1975
Preliminary AO-50-219/75-12:on 750426,low Reactor Pressure Core Spray Valve Permissive Pressure Switches Re 178 & C Found to Trip at Pressure Less than Tech Spec Value.Caused by Switch Repeatability.Switches Recalibr
ML20090D6751975-04-18018 April 1975
AO-50-219/75-11:on 750410,leakage of Main Line Drain & Bypass Line Exceeded Tech Spec Rate.Caused by Failure of Packing on Valve V-1-110.Valve to Be Repacked
ML20090D7001975-04-14014 April 1975
AO-50-219/75-10:on 750404,reactor Bldg to Torus Vacuum Breaker Valves V-26-16 & 18 Leak Rates Exceeded Tech Spec Limits.Caused by Component Failure.Valves Adjusted &/Or Repaired
ML20090D6811975-04-11011 April 1975
Preliminary AO-50-219/75-11:on 750410,leakage of Main Line Drain & Bypass Line Exceeded Tech Spec Rate.Caused by Failure of Packing on Valve V-1-110.Valve to Be Repacked
ML20090D7131975-04-0808 April 1975
AO-50-219/75-09:on 750329,breaker 1C Tripped Resulting in Fault on Bus 1C.Caused by Fault on Cable 86-25.Cables Replaced
ML20090D7061975-04-0707 April 1975
Preliminary AO-50-219/75-10:on 750404,reactor Bldg to Torus Vacuum Breaker Valves V-26-16 & 18 Leak Rates Exceeded Tech Spec Limits.Caused by Component Failure. Valves Adjusted &/Or Repaired
ML20090D7271975-04-0303 April 1975
AO-50-219/75-08:on 750325,power Operation Continued W/ Average Linear Heat Generation Rate of Fuel Assemblies in Excess of Max Linear Heat Generation Rate.Caused by Failure to Properly Monitor Reactor Core.Rate Reduced
ML20090D7211975-03-31031 March 1975
Preliminary AO-50-219/75-09:on 750329,breaker 1C Tripped Due to Fault on Bus 1C.Caused by Fault on Cable 86-25.Cables Replaced
ML20090D7651975-03-27027 March 1975
AO-50-219/75-07:on 750319,during Standby Gas Treatment Sys (SGTS) Test,Dehumidifying Heater EHC-1-5 in SGTS 1 Failed to Energize.Caused by Plugged Orifice in Air Supply to Controller.New Type of Differential Relay Installed
ML20090D7361975-03-26026 March 1975
Preliminary AO-50-219/75-08:on 750325,power Operation Continued W/Average Linear Heat Generation Rate of Fuel Assemblies in Excess of Max Linear Heat Generation Rate. Caused by Improper Reactor Core Monitoring.Rate Reduced
ML20090D7761975-03-20020 March 1975
Preliminary AO-50-219/75-07:on 750319,during Stanby Gas Treatment Sys (SGTS) Test,Dehumidifying Heater EHC-1-5 in SGTS 1 Failed to Energize.Caused by Plugged Orifice in Air Supply to Controller.New Type of Relay Installed
ML20090D7801975-03-19019 March 1975
AO-50-219/75-06:on 750310,stack Gas Sample Sys Failed to Continuously Monitor Stack Releases While Reactor in Unisolated Condition.Caused by Circuit Design.Request to Modify Circuit for Stack Gas Sample Pumps Submitted
ML20090D7901975-03-13013 March 1975
AO-50-219/75-05:on 750306,during Monthly Surveillance Test, Containment Spray Pump 51A Failed to Start When Subjected to Simulated Signals.Caused by Breaker Trip Bar Failing to Reset After Previous Breaker Trip.Trip Bar Bushings Cleaned
ML20090D7811975-03-11011 March 1975
Preliminary AO-50-219/75-06:on 750310,stack Gas Sample Sys Failed to Monitor Stack Releases While Reactor in Unisolated Condition.Caused by faulty-circuit Design
1975-09-08
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4451999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Oyster Creek Nuclear Generating Station.With
ML20211P6731999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Oyster Creek Nuclear Generating Station.With
ML20211A7051999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Oyster Creek Nuclear Station.With
ML20209G0631999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Oyster Creek Nuclear Generating Station.With
ML20212H5491999-06-18018 June 1999
Non-proprietary Rev 4 to HI-981983, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool
ML20195E7961999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Oyster Creek Nuclear Generating Station.With
ML20206N7431999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Oyster Creek Nuclear Generating Station.With
ML20205P5401999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Oyster Creek Nuclear Generating Station.With
ML20204C8201999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Oyster Creek Nuclear Generating Station.With
ML20199E4671998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Oyster Creek Nuclear Generating Station.With
ML20195E8321998-12-31031 December 1998
10CFR50.59(b) Rept of Changes to Oyster Creek Sys & Procedures, for Period of June 1997 to Dec 1998.With
ML20198D2091998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Oyster Creek Nuclear Generating Station.With
ML20195J8591998-11-12012 November 1998
Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan
ML20195C4271998-11-0606 November 1998
Safety Evaluation Supporting Proposed Ocnpp Mod to Install Core Support Plate Wedges to Structurally Replace Lateral Resistance Provided by Rim Hold Down Bolts for One Operating Cycle
ML20155J3021998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Oyster Creek Nuclear Generating Station.With
ML20154R4981998-10-20020 October 1998
Core Spray Sys Insp Program - 17R
ML20154L3051998-10-14014 October 1998
Safety Evaluation Accepting Licensee Request to Defer Insp of 79 Welds from One Fuel Cycle at 17R Outage
ML20154Q3371998-09-30030 September 1998
Rev 8 to Oyster Creek Cycle 17,COLR
ML20154L5571998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Oyster Creek Nuclear Generating Station.With
ML20151V6311998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Oyster Creek Nuclear Generating Station.With
ML20237D5691998-08-31031 August 1998
Rev 0 to MPR-1957, Design Submittal for Oyster Creek Core Plate Wedge Modification
ML20237D5711998-08-18018 August 1998
Rev 0 to SE-000222-002, Core Plate Wedge Installation
ML20237B0131998-07-31031 July 1998
Monthly Operating Rept for July 1998 for Oyster Creek Nuclear Generating Station
ML20236R0511998-06-30030 June 1998
Monthly Operating Rept for June 1998 for Oyster Creek Nuclear Generating Station
ML20249B2981998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Oyster Creek Nuclear Station
ML20248F3531998-05-21021 May 1998
Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted
ML20247F1891998-05-0505 May 1998
Risk Evaluation of Post-LOCA Containment Overpressure Request
ML20247G0581998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for Oyster Creek Nuclear Generating Station
ML20216K0341998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for Oyster Creek Nuclear Generating Station
ML20151Y4651998-03-31031 March 1998
Non-proprietary Version of Rev 1 to GENE-E21-00143, ECCS Suction Strainer Hydraulic Sizing Rept
ML20217A4631998-03-23023 March 1998
Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively
ML20212E2291998-03-0404 March 1998
Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected
ML20216J0841998-02-28028 February 1998
Monthly Operating Rept for Feb 1998 for Oyster Creek Nuclear Generating Station
ML20203B2781998-02-16016 February 1998
10CFR50.59(b) Rept of Changes to Oyster Creek Systems & Procedures
ML20203A3801998-01-31031 January 1998
Monthly Operating Rept for Jan 1998 for Oyster Creek Nuclear Generation Station
ML20198P1791997-12-31031 December 1997
Monthly Operating Rept for Dec 1997 for Oyster Creek Nuclear Station
ML20217C7591997-12-31031 December 1997
1997 Annual Environmental Operating Rept for Oyster Creek Nuclear Generating Station
ML20197E9131997-11-30030 November 1997
Monthly Operating Rept for Nov 1997 for Oyster Creek Nuclear Station
ML20199E4561997-11-13013 November 1997
Safety Evaluation Accepting Ampacity Derating Analysis in Response to NRC RAI Re GL-92-08, Thermo-Lag 330-1 Fire Barriers, for Plant
ML20199D4381997-10-31031 October 1997
Monthly Operating Rept for Oct 1997 for Oyster Creek Nuclear Station
ML20202E8511997-10-21021 October 1997
Rev 0 to Scenario 47, Gpu Nuclear Oyster Creek Nuclear Generating Station Emergency Preparedness (Nrc/Fema Evaluated) 1997 Biennial Exercise. Pages 49 & 59 of Incoming Submittal Were Not Included
ML20211M9481997-10-0303 October 1997
Supplemental Part 21 Rept Re Condition Effected Emergency Svc Water Pumps Supplied by Bw/Ip Intl Inc to Gpu Nuclear, Oyster Creek Nuclear Generation Station.No Other Nuclear Generating Stations Effected by Notification
ML20198J7361997-09-30030 September 1997
Monthly Operating Rept for Sept 1997 for Oyster Creek Nuclear Generating Station
ML20211B7461997-09-24024 September 1997
Part 21 Rept Re Failure of Emergency Service Water Pump Due to Threaded Flange Attaching Column to Top Series Case Failure.Caused by Dissimilar Metals.Pumps in High Ion Svc Will Be Upgraded to 316 Stainless Steel Matl
ML20210V0181997-08-31031 August 1997
Monthly Operating Rept for Aug 1997 for Oyster Creek Nuclear Generating Station
ML20210L2961997-07-31031 July 1997
Monthly Operating Rept for Jul 1997 for Oyster Creek Nuclear Station
ML20149F9961997-07-18018 July 1997
Safety Evaluation Re Gpu Nuclear Operational Quality Assurance Plan,Rev 10 for Three Mile Island Nuclear Generating Station,Unit 1 & Oyster Creek Nuclear Generating Station
ML20196H0111997-07-11011 July 1997
Special Rept 97-001:on 970620,removed High Range Radioactive Noble Gas Effluent Monitor (Stack Ragems) from Service to Allow Secondary Calibr IAW Master Surveillance Schedule. Completed Calibr on 970628 & Returned Stack Ragems to Svc
ML20210L3081997-06-30030 June 1997
Corrected Page to MOR for June 1997 for Oyster Creek Nuclear Generating Station
ML20141H2051997-06-30030 June 1997
Monthly Operating Rept for June 1997 for Oyster Creek Nuclear Station
1999-09-30
[Table view] |
Text
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fh. h Report Dateg _
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' Occurrence:
'gb ' . Y{. 1100 F -
OYSTER CREEK NUCLEAR CD1ERATING STATION . .,
FORKED RIVER, NEW JERSEY 08731
. . ~ '
Abnormal Occurrence port No. 50-219/74/4, . . .
IDENTIFICATION - Violation of the Technical Specifications, Table 3..171.B.} and .1,
.0F OCCURRD;CE: which specifies that the RE22 Main Steam Line high flow sensors hctuate at a differential pressure corresponding to line flows l<~ 120% of rated. .
. h.'eg /, ' . Q A,. , ..d ,. . .
i 1his event is considered to be an abnorcal occurrence as de-fined in the Technical Specif1. cations; paragraph 1.15A - '
CONDITIONS PRIOR . ,
TO OCCURRENCE: X _ Steady State Power __.Routino Shutdown Hot Standby Operation .
. Cold Shutdown -
Load Changes During
.. Refueling Shutdown ~ Routine Power Operation Routine Startup , _
Other (Specify)
Operation ,
~
llin reactor was operating 'at approximately 1827 MWt wit
recirculation flow of 61X10 . 8/hr when the surveillance test was conducted. .
$ESCRIPTION During the routine monthly surveillance testing of the RE22 0F OCCURRENCE: Main. Steam Line high flow sensors, it was observed that the RB22C and RE225 sensors actuated at a differential pressure
~o f 100 psi, one in cach of the two safety systems. This is
~
- gren'ter than the maximum allowable level of 97.5 psid which -
corresponds to a Main Steam Line flow 120% of rated.. .
.n . ... .J :
ms.40CUMENT 00NTAINS
. 1. ,
P0hRAUAUTY PAGES
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. ~ . ._.
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k Abnorr.a1Occdirence .
Page 2,.
Rapprf. No. 50-219/74/2 ,
i' . - ,
. i. - . . . . .
APPARENT CAUSE Design _
Procedure OF OCCURRENCE: Hanufacture _
Unusual'Scrvice Condition
~
Installation / Inc. Environmental >
' Component Failure Construction' -
Operator -
, 0ther (Specify) . .
i .
The cause of the failure is under investigation.
~
s .. . . .: o . .
- ~ .
ANALYSIS OF The safety significance of this event is in the loss of -
OCCURRENCE: system redundancy. Had a high flow event developed, the L'edundant sensors RE22A, B, D, F, G, and H would have . .
performed the isolation funct.'.on. ,
i c . . .
t CORRECTIVE Each of the two sensors were recal.ibrated and returned -
ACTION: . . to service as the failures were discovered. .
~
FAILURE DATA: Manufacturer: B'arton Type: Indicating Differential Pressuro Switch
- - Range: 0-200 psid -
Series: RB22C - 224-19938 '
RB228,- 278-770
~
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