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LER-1980-002, /01T-0:on 800128,during Cold Shutdown,Ae Notified Util That Single Mode Failure Existed for Torus Gravity Fill Isolation Valve 2G51-F013.Caused by Design Deficiency. Standing Order Issued |
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| 3661980002R01 - NRC Website |
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EVEN'T DESCH APTION AND PROOABLC CCNSECUENCES h 10n 1-28-80, at,1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> CST Unit 2 was in cold shutdown in order to perform modific-I 3
2 gtions per TMI requirements (f;UREG-0578).
Architect-engineer notified utility that a j 3
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Georgia Power Company Plant E. I. Hatch Baxley, Georgia 31513 Event Description and Probable Consequences.
would be greater than water head pressure from CST.
Actual event date cannot be determined as this condition has existed since plant was constructed.
Un-it I was not affected by occurrence as Torus Water Cleanup system has not been installed to date.
There were no effects upon public health and safety due'to this event.
All redundant systems were available and capable of performing their intended functions.
This is a non-repetitive event for this system.
Cause Description and Corrective Actions.
Architect-engineer has issued a proposed design change which will install a second valve in the affected piping system.
Bechtel PDCR #B2M-041 was rec-
. cived on site on 1-23-80, and is being reviewed.
Upon comoletion of review of preliminary engineering package, engineering services personnel will issue necessary design change request for modification.
Terus Water Cleanup system is not currently installed on Unit 1 so event had no affect upon that particul-ar unit.
Torus water cleanup system will remain isolated until such time as a second isolation valve can be installed.
Resolution of this potential problem is expected by 5-1-80.
I
s' LER #:
50-366/1980-002 Licensee:
Georgia Pcwer Company Facility flame: Edwin I. Hatch f
Docket #:
50-366 g
t'arrative Report for LER 50-356/1980-002 On January 28,1980, at 1300 CST, Hatch Unit 2 was in a cold shutdoun condition to perform modifications per TM1 requirements (l1UREG-0578). The plant l
was contacted by the architect-engineer, Bechtel Power Corporation, and was
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notified that a single mode of failure existed for valve 2G51-F013 (u us Gravity Fill Isolation valve). They contend that folicwing a postulatcc LOCA and a single failure of valve 2G51-F013, that a flow path is provided via the "B" core spray suction piping and the condensate storage tank (CST) to core spray suction isolation valve bypass (2G51-F013) from the torus to the CST. This water transfer to the CST could occur post LOCA because the tor-us pressure would be greater than the water head pressure from the CST.
The actual event cannot be readily determined as this condition has existed since the plant was constructed Hatch. Unit 1 was not affc:ted by this occurrence as a torus water cleanup system has not been installed to date.
This was a first tif,e occurrence for Unit 2 for the condition described.
There were no effects upon public health and safety as a result of this ev-ent. All redundant systems were available for use and capable of performing their intended functions.
The cause of this event can be attributed to design deficiency.
The archi t-ect-engineer possibly failed to consider post LCCA consequences on this par-ticular section of the system during the design stages of the plant.
Immed-iate corrective actions taken by plant personnel was the writing and implem-entation of a standing order (50 #80-5).
This particular standing order req-uires the closing of certain valves associated with the Torus ' dater Cleanup system and visually inspecting the valves daily to assure the valves are in a closed position.
Bechtel has issued a proposed design change which will install a second valve in the affected bypass line upstream of valve 2G51-F013. The proposed deqign change, Bechtel PDCR r!B2M-041, was received on site on 1-28-80, and is in the process of review.
Upon. completion of rev-iew of the preliminary engineering package, site engineering services person-nel will issue the necessary design change request for the modification.
This event did not affect Unit 1 as the torus water cleanup system is not pre-sently installed on that particular unit.
However, a design change is being The des-currently worked on to add the torus water cleanup system to Unit 1.
ign change for Unit I has been revised to add the second valve in the bypass Resolution of this potential problem as a result of the Unit 2 occurrence.
is expected by 5-1-80.
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| 05000321/LER-1980-001-01, /01T-0:on 800103,while Performing Maint on RHR LPCI Injection Valve,Clevis Pin Found Missing from Strut on Drywell Penetration Restraint.Caused by Improper Installation.New Clevis Pin Installed | /01T-0:on 800103,while Performing Maint on RHR LPCI Injection Valve,Clevis Pin Found Missing from Strut on Drywell Penetration Restraint.Caused by Improper Installation.New Clevis Pin Installed | | | 05000366/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000366/LER-1980-001-03, /03L-0:on 800102,while Performing Narrow Range Torus Water Level Functional Test & Calibr,Level Transmitter 2T48-N021B Found Out of Tolerance.Caused by Range Drift. Transmitter Recalibr & Returned to Svc | /03L-0:on 800102,while Performing Narrow Range Torus Water Level Functional Test & Calibr,Level Transmitter 2T48-N021B Found Out of Tolerance.Caused by Range Drift. Transmitter Recalibr & Returned to Svc | | | 05000321/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000321/LER-1980-002-03, /03L-0:on 800112,while Performing HNP-1-3655,fan lT46-C001B Would Not Meet Flow Requirements Per Tech Specs. Ten Days Later,While Venting Drywell Per HNP-1-1500,flow Did Not Meet Tech Specs.Equipment Recalibr | /03L-0:on 800112,while Performing HNP-1-3655,fan lT46-C001B Would Not Meet Flow Requirements Per Tech Specs. Ten Days Later,While Venting Drywell Per HNP-1-1500,flow Did Not Meet Tech Specs.Equipment Recalibr | | | 05000321/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000366/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000366/LER-1980-002-01, /01T-0:on 800128,during Cold Shutdown,Ae Notified Util That Single Mode Failure Existed for Torus Gravity Fill Isolation Valve 2G51-F013.Caused by Design Deficiency. Standing Order Issued | /01T-0:on 800128,during Cold Shutdown,Ae Notified Util That Single Mode Failure Existed for Torus Gravity Fill Isolation Valve 2G51-F013.Caused by Design Deficiency. Standing Order Issued | | | 05000366/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000366/LER-1980-003-03, /03L-0:on 800117,while Applying Equalizing Charge to 125/250-volt Dc Station Svc Batteries,Hpci Automatic Flow Control Power Inverter Tripped.Caused by Instrument Drift. Instrument Recalibr Satisfactorily | /03L-0:on 800117,while Applying Equalizing Charge to 125/250-volt Dc Station Svc Batteries,Hpci Automatic Flow Control Power Inverter Tripped.Caused by Instrument Drift. Instrument Recalibr Satisfactorily | | | 05000321/LER-1980-003-03, While Performing RHR Valve Operability Procedure,Outboard Shutdown Cooling Isolation Valve F008 Opened in 25.8-S.Caused by Normal Wear & Human Reaction Time.Valve Operator Adjusted | While Performing RHR Valve Operability Procedure,Outboard Shutdown Cooling Isolation Valve F008 Opened in 25.8-S.Caused by Normal Wear & Human Reaction Time.Valve Operator Adjusted | | | 05000321/LER-1980-003, Forwards Revised LER 80-003/03X-1 | Forwards Revised LER 80-003/03X-1 | | | 05000321/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000321/LER-1980-004-03, /03L-0:on 800106,during Startup Mode,Main Steam Line Inboard Isolation Drain Valve Failed in mid-position. Caused by Failure of Valve Motor Winding.Motor Replaced & Valve Returned to Operable Status | /03L-0:on 800106,during Startup Mode,Main Steam Line Inboard Isolation Drain Valve Failed in mid-position. Caused by Failure of Valve Motor Winding.Motor Replaced & Valve Returned to Operable Status | | | 05000366/LER-1980-004-03, /03L-0:on 800118,during Steady State Power Operation Hydrogen Recombiner Inlet Valve 2T49-F003A Did Not Open.Caused by a Failed Torque Switch.Sys Returned to Operation After Switch Was Replaced | /03L-0:on 800118,during Steady State Power Operation Hydrogen Recombiner Inlet Valve 2T49-F003A Did Not Open.Caused by a Failed Torque Switch.Sys Returned to Operation After Switch Was Replaced | | | 05000366/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000321/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000321/LER-1980-005-03, /03L-0:on 800109,w/reactor Mode Switch in Run Mode,Discovered That Surveillance Procedure HNP-1-3007, Turbine Control Valve Fast Closure,Was Not Performed in Grace Period.Caused by Personnel Error | /03L-0:on 800109,w/reactor Mode Switch in Run Mode,Discovered That Surveillance Procedure HNP-1-3007, Turbine Control Valve Fast Closure,Was Not Performed in Grace Period.Caused by Personnel Error | | | 05000366/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000366/LER-1980-005-03, /03L-0:on 800119,during Power Operation,Tech Specs 4.8.1.1.1.a & 4.8.1.1.2a4 for Electrical Power Sources Were Not Performed within 1-h.Caused by Personnel Misinterpretation of Tech Spec Requirements | /03L-0:on 800119,during Power Operation,Tech Specs 4.8.1.1.1.a & 4.8.1.1.2a4 for Electrical Power Sources Were Not Performed within 1-h.Caused by Personnel Misinterpretation of Tech Spec Requirements | | | 05000321/LER-1980-006-03, /03L-0:on 800113,one Standby Gas Treatment Sys Rendered Inoperable W/Both Units in Power Operation.Unit Not Proven Operable within Required 4-h.Caused by Inability to Prove Filter Train Operable within 4-h | /03L-0:on 800113,one Standby Gas Treatment Sys Rendered Inoperable W/Both Units in Power Operation.Unit Not Proven Operable within Required 4-h.Caused by Inability to Prove Filter Train Operable within 4-h | | | 05000321/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000321/LER-1980-007-03, /03L-0:on 800114,while Testing Standby Svc Water Pump,Pump Would Not Meet Criteria.Caused by Disengagement of Pump First Stage Impeller Lock Collet.Lock Collet Replaced & Pump Reinstalled | /03L-0:on 800114,while Testing Standby Svc Water Pump,Pump Would Not Meet Criteria.Caused by Disengagement of Pump First Stage Impeller Lock Collet.Lock Collet Replaced & Pump Reinstalled | | | 05000321/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000366/LER-1980-007-01, /01T-0:on 800130,while Performing High Drywell Pressure Instrument (Reactor Protection Sys) Functional Test & Calibr,Instruments 2C71-N002A,B & D Exceeded Tech Specs.Caused by Instrument Drift | /01T-0:on 800130,while Performing High Drywell Pressure Instrument (Reactor Protection Sys) Functional Test & Calibr,Instruments 2C71-N002A,B & D Exceeded Tech Specs.Caused by Instrument Drift | | | 05000366/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000366/LER-1980-008-03, While Increasing Reactor Power by Rod Withdrawal,Operator Noticed Rod Select Matrix Backlighted & Rod Sequence Control Sys Not Initiating Rod Blocks Properly.Caused by Design Change | While Increasing Reactor Power by Rod Withdrawal,Operator Noticed Rod Select Matrix Backlighted & Rod Sequence Control Sys Not Initiating Rod Blocks Properly.Caused by Design Change | | | 05000366/LER-1980-008, Forwards LER 80-008/03L-1 | Forwards LER 80-008/03L-1 | | | 05000321/LER-1980-008-03, /03L-0:on 800115,during Steady State Power Operation,Secondary Containment Integrity Violated When Personnel Opened 164-ft Elevation Reactor Bldg & Turbine Bldg Airlock Doors Simultaneously.Procedure Revised | /03L-0:on 800115,during Steady State Power Operation,Secondary Containment Integrity Violated When Personnel Opened 164-ft Elevation Reactor Bldg & Turbine Bldg Airlock Doors Simultaneously.Procedure Revised | | | 05000321/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000366/LER-1980-009-03, /03L-0:on 800130,while Performing Procedure HNP-2-33-3,HPCI Min Flow Valve 2E41-F012 Failed to Close. Caused by Sticking Switch Contacts on Flow Switch 2E41-N006. Switch Contacts Cleaned & Procedure HNP-2-3303 Performed | /03L-0:on 800130,while Performing Procedure HNP-2-33-3,HPCI Min Flow Valve 2E41-F012 Failed to Close. Caused by Sticking Switch Contacts on Flow Switch 2E41-N006. Switch Contacts Cleaned & Procedure HNP-2-3303 Performed | | | 05000321/LER-1980-009-03, /03L-0:on 800118,during Normal Operation,Drywell/ Torus Temp Recorder 1T47-R611 Found Stamping Erratically, Making Drywall & Torus Air Temps & Water Temp Difficult to Ascertain.Caused by Failure of Microswitch.Switch Replace | /03L-0:on 800118,during Normal Operation,Drywell/ Torus Temp Recorder 1T47-R611 Found Stamping Erratically, Making Drywall & Torus Air Temps & Water Temp Difficult to Ascertain.Caused by Failure of Microswitch.Switch Replaced | | | 05000366/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000321/LER-1980-010-03, /03L-0:on 800118,during Normal Operation While Performing Standby Liquid Control Pump Operability Test & Relief Valve Test,Pump a Discharge Relief Valve 1C41-F029A Operated at 1,225 Psig.Caused by Setpoint Drift.Valve Reset | /03L-0:on 800118,during Normal Operation While Performing Standby Liquid Control Pump Operability Test & Relief Valve Test,Pump a Discharge Relief Valve 1C41-F029A Operated at 1,225 Psig.Caused by Setpoint Drift.Valve Reset | | | 05000321/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000366/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000366/LER-1980-010-03, /03L-0:on 800131,during Reactor Startup,At 58% Power,Max Total Peaking Factor Was Calculated at 3.0 Compared to Design Value of 2.38.Caused by Lower than Normal Xenon Distribution During Startup | /03L-0:on 800131,during Reactor Startup,At 58% Power,Max Total Peaking Factor Was Calculated at 3.0 Compared to Design Value of 2.38.Caused by Lower than Normal Xenon Distribution During Startup | | | 05000321/LER-1980-011-03, /03L-0:on 800120,while at Steady State Power, torus-to-drywell Differential Pressure recorder,LT48-R631B Had Low Reading.Cause Not Stated | /03L-0:on 800120,while at Steady State Power, torus-to-drywell Differential Pressure recorder,LT48-R631B Had Low Reading.Cause Not Stated | | | 05000366/LER-1980-011-03, /03L-0:on 800202,while Performing Reactor Core Isolation Cooling Shutdown Flow Test,Power Inverter for Remote Flow Control Loop Found to Be Tripped.Caused by Defective Input Filter Capacitors | /03L-0:on 800202,while Performing Reactor Core Isolation Cooling Shutdown Flow Test,Power Inverter for Remote Flow Control Loop Found to Be Tripped.Caused by Defective Input Filter Capacitors | | | 05000321/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000366/LER-1980-012-03, /03L-0:on 800214,while at Full Power,Rhr & Plant Svc Water Min Flow Line Found to Be Inadequately Supported. Caused by Design Deficiency.Design Change Request & Maint Request Implemented to Add Supports | /03L-0:on 800214,while at Full Power,Rhr & Plant Svc Water Min Flow Line Found to Be Inadequately Supported. Caused by Design Deficiency.Design Change Request & Maint Request Implemented to Add Supports | | | 05000321/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000366/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000321/LER-1980-012-03, /03L-0:on 800122,while Reactor Core Isolation Cooling Sys Was Tagged Out for Maint,Hpci Was Found Inoperable,Requiring Orderly Shutdown.Caused by Leak in Line to HPCI Booster Pump Discharged Pressure Gauge | /03L-0:on 800122,while Reactor Core Isolation Cooling Sys Was Tagged Out for Maint,Hpci Was Found Inoperable,Requiring Orderly Shutdown.Caused by Leak in Line to HPCI Booster Pump Discharged Pressure Gauge | | | 05000321/LER-1980-013, Forwards Updated LER 80-013/03X-1 | Forwards Updated LER 80-013/03X-1 | | | 05000321/LER-1980-013-03, Reactor Recirculation Pump a Tripped Causing Power Reduction.Caused by Electrical Short Circuit Due to Steam Leak in Drywell.Terminal Board Replaced & Tested | Reactor Recirculation Pump a Tripped Causing Power Reduction.Caused by Electrical Short Circuit Due to Steam Leak in Drywell.Terminal Board Replaced & Tested | | | 05000366/LER-1980-013-03, /03L-0:on 800203,while Maint Was Performed on 2082-K002 Static Inverter,Emergency Control Transfer Switch Was Placed in Emergency Position.Reactor Core Isolation Cooling Was Rendered Inoperable.Caused by Personnel Error | /03L-0:on 800203,while Maint Was Performed on 2082-K002 Static Inverter,Emergency Control Transfer Switch Was Placed in Emergency Position.Reactor Core Isolation Cooling Was Rendered Inoperable.Caused by Personnel Error | | | 05000366/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000366/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000366/LER-1980-014-03, /03L-0:on 800204,while Performing HNP-2-3054, Average Power Range Monitor C Failed.Caused by Instrument Drift.Instrument Adjusted Per Procedure & Returned to Svc | /03L-0:on 800204,while Performing HNP-2-3054, Average Power Range Monitor C Failed.Caused by Instrument Drift.Instrument Adjusted Per Procedure & Returned to Svc | |
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