05000361/LER-1992-009-01, Forwards LER 92-009-01 Re Misalignment of Salt Water Cooling Pump Emergency Seal Water Supply Isolation Valve

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Forwards LER 92-009-01 Re Misalignment of Salt Water Cooling Pump Emergency Seal Water Supply Isolation Valve
Person / Time
ML20127L362
Site:	San Onofre
Issue date:	11/19/1992
From:	Krieger R SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20127L366	List: 05000361/LER-1992-009, :on 920614,discovered That Salt Water Cooling Pump P112 Emergency Seal Water Isolation Valve MU019 Closed. Caused by Valve Misalignment on 920528.Water Supply Restored & Event Reviewed by Engineering Personnel 05000361/LER-1992-009-01, Forwards LER 92-009-01 Re Misalignment of Salt Water Cooling Pump Emergency Seal Water Supply Isolation Valve
References
NUDOCS 9211240051
Download: ML20127L362 (1)
v • d • e

LER-1992-009, Forwards LER 92-009-01 Re Misalignment of Salt Water Cooling Pump Emergency Seal Water Supply Isolation Valve

Event date:
Report date:
3611992009R01 - NRC Website
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Southern C'alifomia Edison Company 6.AN Of '3F F4E NUCLE AR OENLFiATING ST ATioN P O. DOX 128 S AN CLEut-WTE. CALIFORNI A92674 0126 T EL E PtK:WE R. W. KRIEGER Nove,iber 19, 199.9

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er,a,m moo, U. S. Nuclear Regulatory Commission Document Centrol Desk Washington, D.C.

20555

Subject:

Docket Nos. 50-361 and 50-362 30-Day Report Licensee Event Report No. 92 009, Revision 1 San Onofre Nuclear Generating Station, Units 2 and 3

Reference:

Letter, R. W.

Krieger (SCE) to USNRC Document Control Desk, dated July 14, 1992 The referenced letter provideo Licensee Event Report (LER) No.92-009, Revisicn 0, for an occurrence involving the mis-alignment of a salt w' iter cooling pump emergency seal water supply isolation valve.

Since this occurrence involves similar bystems, cause, and corrective actions applicable to Units 2 and 3, a sing)e report for Unit 2 la being submitted in accordance with NUREG-1022.

Neither the health nor the safoty of plant. personnel er the public was affected by this occurrence.

If you require any additional infomation, please so advise.

Sincerely, I

t, i

j\\,AAN/A Enclosure: LER No.92-009, Rev. 1 cc:

C.

W.

Caldwell (USNRC Senior esident Inspector, Units 1, 2 and 3)

J. B. Martin (Regional Admi istrator, USNRC Region VI Institute of Nuclear Power Operations (7NPO)

/.90003 9211240051 9'21119 PDR ADOCK 05000361 y/ /n S

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Licensee Event Report

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		Reporting criterion
05000362/LER-1992-001-01, :on 920225,containment Purge Isolation Sys Actuated.Caused by Personnel Error.Signs Installed Near Monitors Reminding Personnel of Responsibility for Control Room Notification	on 920225,containment Purge Isolation Sys Actuated.Caused by Personnel Error.Signs Installed Near Monitors Reminding Personnel of Responsibility for Control Room Notification	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(viii)(A)
05000361/LER-1992-002, :on 920209,CR Isolation Sys Actuation,Automatic Start of EDG 3G002 Occurred Due to de-energization of ESFs Actuation Sys Power Supply.Esfas Dc Power Supply Breaker Reclosed	on 920209,CR Isolation Sys Actuation,Automatic Start of EDG 3G002 Occurred Due to de-energization of ESFs Actuation Sys Power Supply.Esfas Dc Power Supply Breaker Reclosed	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000362/LER-1992-002-01, :on 920219,determined That Source Range Neutron Flux Monitor Was Not Providing Audible Indication,Per TS 3.9.2.Caused by Audible Count Rate Booster Amplifer Being in Off Position.Subj Amplifer re-energized	on 920219,determined That Source Range Neutron Flux Monitor Was Not Providing Audible Indication,Per TS 3.9.2.Caused by Audible Count Rate Booster Amplifer Being in Off Position.Subj Amplifer re-energized	10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000206/LER-1992-003-02, :on 921219,sample Incorrectly Taken from out-of-svc Wgdt Due to Personnel Error.Technicians Involved Received Appropriate Disciplinary Action	on 921219,sample Incorrectly Taken from out-of-svc Wgdt Due to Personnel Error.Technicians Involved Received Appropriate Disciplinary Action	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000361/LER-1992-003, :on 920211,control Room Isolation Actuation & Automatic Start of Emergency Diesel Generator 3G002 Occurred.Caused by Deenergization of ESF Actuation Sys Power Supply.Event Was Reviewed W/Personnel	on 920211,control Room Isolation Actuation & Automatic Start of Emergency Diesel Generator 3G002 Occurred.Caused by Deenergization of ESF Actuation Sys Power Supply.Event Was Reviewed W/Personnel	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B)
05000362/LER-1992-003-01, :on 920515,reactor Coolant Pump Tripped.Caused by Phase C Differential Relay Operation on RCP Supply Breaker.Rcp Motor Preventive Maint Program Modified to Include Periodic Replacement of Capacitors	on 920515,reactor Coolant Pump Tripped.Caused by Phase C Differential Relay Operation on RCP Supply Breaker.Rcp Motor Preventive Maint Program Modified to Include Periodic Replacement of Capacitors	10 CFR 50.73(a)(2)
05000362/LER-1992-004, :on 920720,manual Initiation of Emergency FW Actuation Sys Occurred in Response to Trip of Mfpt.Caused by Low Bearing Lube Oil Pressure Condition of Associated MFP 3P062.PRV 3PCV-4270 Adjusted	on 920720,manual Initiation of Emergency FW Actuation Sys Occurred in Response to Trip of Mfpt.Caused by Low Bearing Lube Oil Pressure Condition of Associated MFP 3P062.PRV 3PCV-4270 Adjusted
05000361/LER-1992-004, :on 920218,dye-penetrant Exam of Pressurizer Vapor Space Level Instrument Nozzle Revealed Presence of Crack.Caused by Primary Water Stress Corrosion Cracking. Vapor Nozzles Will Be Replaced W/Inconel 600	on 920218,dye-penetrant Exam of Pressurizer Vapor Space Level Instrument Nozzle Revealed Presence of Crack.Caused by Primary Water Stress Corrosion Cracking. Vapor Nozzles Will Be Replaced W/Inconel 600	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000361/LER-1992-007, :on 920226,TDAFWP P-140 Tripped on Overspeed During Startup for Inservice Test Surveillance.Caused by Introduction of Accumulated Condensed Steam Into Pump Turbine.Replaced Clogged Steam Trap Strainer	on 920226,TDAFWP P-140 Tripped on Overspeed During Startup for Inservice Test Surveillance.Caused by Introduction of Accumulated Condensed Steam Into Pump Turbine.Replaced Clogged Steam Trap Strainer	10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1)
05000361/LER-1992-008-01, :on 920424,automatic Turbine Trip/Reactor Trip Occurred.Caused by Failure of Transformer 2B13X.Transformer Was Replaced	on 920424,automatic Turbine Trip/Reactor Trip Occurred.Caused by Failure of Transformer 2B13X.Transformer Was Replaced	10 CFR 50.73(a)(2)
05000361/LER-1992-008, :on 920218,primary Water Stress Corrosion Cracking of Pressurizer Instrument Nozzles.Noted.Caused by Rust & Boric Acid Crystals.Nozzle Replaced & Interim Repair Will Be Implemented	on 920218,primary Water Stress Corrosion Cracking of Pressurizer Instrument Nozzles.Noted.Caused by Rust & Boric Acid Crystals.Nozzle Replaced & Interim Repair Will Be Implemented	10 CFR 50.73(a)(2)
05000361/LER-1992-009-01, Forwards LER 92-009-01 Re Misalignment of Salt Water Cooling Pump Emergency Seal Water Supply Isolation Valve	Forwards LER 92-009-01 Re Misalignment of Salt Water Cooling Pump Emergency Seal Water Supply Isolation Valve
05000361/LER-1992-009, :on 920614,discovered That Salt Water Cooling Pump P112 Emergency Seal Water Isolation Valve MU019 Closed. Caused by Valve Misalignment on 920528.Water Supply Restored & Event Reviewed by Engineering Personnel	on 920614,discovered That Salt Water Cooling Pump P112 Emergency Seal Water Isolation Valve MU019 Closed. Caused by Valve Misalignment on 920528.Water Supply Restored & Event Reviewed by Engineering Personnel	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000361/LER-1992-010, :on 920506,spurious Train a Toxic Gas Isolation Sys Actuation Occurred Due to Momentary High Ammonia Concentration Signal.Caused by Intermittent Electronic Problem or Noise Spike.Train Returned to Svc	on 920506,spurious Train a Toxic Gas Isolation Sys Actuation Occurred Due to Momentary High Ammonia Concentration Signal.Caused by Intermittent Electronic Problem or Noise Spike.Train Returned to Svc	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000361/LER-1992-011, :on 921005,discovered That Fire Sys Impairment Compensatory Actions Not Performed Per TS 3.7.8.3,due to Cognitive Personnel Error.Officers Involved in Event Received Counseling	on 921005,discovered That Fire Sys Impairment Compensatory Actions Not Performed Per TS 3.7.8.3,due to Cognitive Personnel Error.Officers Involved in Event Received Counseling	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000362/LER-1992-011, :on 900722,AFW Bypass Control Valve 3HV-4763 Failed to Close Upon Demand.Caused by Failed Actuator Solenoid Valve Which Prevented Closure.Valve 3HV-4763 Manually Isolated	on 900722,AFW Bypass Control Valve 3HV-4763 Failed to Close Upon Demand.Caused by Failed Actuator Solenoid Valve Which Prevented Closure.Valve 3HV-4763 Manually Isolated	10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000361/LER-1992-012, :on 920731,automatic Reactor Trip Occurred When Potential Transformer Drawer Opened for Thermographic Insps, Resulting in Trip of Reactor Coolant Pumps.Caused by Inadequate Warning Sign.Guidelines Enhanced	on 920731,automatic Reactor Trip Occurred When Potential Transformer Drawer Opened for Thermographic Insps, Resulting in Trip of Reactor Coolant Pumps.Caused by Inadequate Warning Sign.Guidelines Enhanced	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)
05000361/LER-1992-013, :on 921209,identified Deficiency Involving Check Valve Test Methodology.Applicable Check Valve Procedure Modified.Applicable SONGS Units 2 & 3 IST Implementing Procedures Will Be Evaluated	on 921209,identified Deficiency Involving Check Valve Test Methodology.Applicable Check Valve Procedure Modified.Applicable SONGS Units 2 & 3 IST Implementing Procedures Will Be Evaluated	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)

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