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LER-1980-074, /03L-0:on 800427,core Max Fraction of Limiting Power Density Found in Excess of Tech Spec.Cause Not Stated. Average Power Range Monitor Adjusted,Power Reduced & Process Computer Updated,Run & Verified |
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| 3661980074R03 - NRC Website |
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NRC FOPM 366 U.S. NUCLEAR REGULATORY COMMISSION 87 77)
~ LICENSEE EVENT REPORT O
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IO Til 60 61 DOCKET NUMfi(R 68 69 EVENT DATE 74 75 REPORT DATE 80 i
6 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h lo121lAt 1353 CST on 4-26-80, while operating at approximately 63% power, l
io i3i.l CMFLPD was calculated by the process computer to be.678.
The APRMs l
io 141 Iwere adjusted to compensate for CMFLPD being greater than fraction of l
[o # si t rated thermal power.
Later power was reduced to approximately 40% to l
101a 1 l allow repairs on the MSRs.
CMFLPD was no't calculated at the level until l t o l 71 l 0722 CDT.
This is in violation of Tech Specs 3.2.2.
There were no ef- !
l Oia i l fects to public health or safety.
This is not a repetitive occurrence. l 80 7
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CAUSE
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40 di 42 43 44 47 CAUSE DESCRIPTloN AND CORRECTIVE ACTIONS h li lo t l When power was reduced, the process computer periodic _ thermal limit ev-l lilillaluation was suspended.
At 0600 CDT it was discovered that at 0153 CST I g i the twelve hour limit on calculating CMFi.PD had ;;assed.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> l [i: 3rIof discovery, the process computer was updated, run, and CMFLPD was l
g iverified to be below FRCTP.
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% POWER OTHER STATUS S V Y DISCOVERY DESCRIPTION l1 I s l l F l@ l 01 01 Q@l NA l
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LER 4:
50-36'6/1980-074 l
Licensee:
Georgia Power Company Facili ty Name:
Edvin 1.
'i n t e h Docket 1:
50-366*
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. Narrative Report for LER 50-366/1980-074 i
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1 AT 1353 CST, on 4-26-80, while operating a *. noproximately 63 j
percent and increasing power following a saintenance outage, the process computer calculated Core
'faximum Traction of 1
i Limiting Power Density ( C'4 F L P D ) to bc
.673.
At 1419 C9' of j
the same dgy, the APR'is were adjusted to compensate for this as per Tech Specs 3.2.2.
Fo l l otti ng this, power was reduced to app-oxima t el y 40 percent l
to allow repairs to be performed on unrelated plant i
equipment.
During this reduction,-
the process computer
^
periodic thermal limit evaluation program, P1, nas prevented j
t from running.
At 1600 CDT, on 4-27-80, it wes discovered that Ctf ? ton wa s not calculated by 0153 CST as required by "'ech specs for a CurLPn being higher than the Fract ion of Rated Core Thermal power (FRCTP).
This is a violation of Tech Specs 4.2.2.
I Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of discovery an OD-1 (L?RM Calibration and Base Distribution Updatei was performed, the process computer program P1 run, and CMPLPD v'e r i f i e d to be below WRCTP.
FR C'P P uns.401 and CstFLPD was.388 at 0722 COT.
This brought the unit into compliance with Tech Specs.
"ersonnel will be instructed as to correct action to be t sine n in the future.
This is not a repetitive occurrence.
There was no inpact from this incident on fin i t 1.
There were no e Fe c t s upon public health and safety due to this event, i
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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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