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LER-1980-138, /03L-0:on 801027,leakage on Torus Purge Inlet Outboard Isolation Valve 2T48-F324 Found Such That Test Vol Could Not Be Pressurized.Caused by Worn O Rings.Shaft & Housing for O Rings Cleaned.O Rings Replaced |
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| 3661980138R03 - NRC Website |
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LICENSEE EVENT REPORT cor4T Rol BLOCK:
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8 00 til DOCKE T NUMDE H bei 03 EVEN1 DAIE 14 75 HEPQHi DATE 80 EVENT DESCHIPTION AtJD PROBA0LE CONSEQUENCES h 10121 lJln lo-2 3-80aith_the reactor oower at 2278 MWt. an LLRT of the torus 1
to_jm Lpurge inlet outboard isolation valve 2T48-F324 shaft "0"
ring seals was i 1o141lperformed.
On 10-27-80, the leakage was determined to be such that the I
[ test volume could not be pressurized; therefore, it must be assumed that]
o 5 lo Ic i I the.60 La overall allowabli leakage rate of Tech Specs 3.6.1.2.B.1 l
10171 (could have been exceeded.
This is a repetitive occurrence - see LER
[
10181 L50- 366/1980-0 51.
There were no effects on public health and safety.
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13 18 l 'J 20 SE QUE N TI AL OCCURRENCC HEPORT REVISION
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'd 33 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTloN AND CORRECTIVE ACTIONS l3lolIThe leakage was due to worn "0"
rings.
The shaft and housing for the I
l"0" rings were cleaned, and the "0"
rings were replaced.
The torus I
i i l purge inlet outboard isolation valve 2T58-F324 "0"
rings were then re-l i,igj li l3l l tested, and the retest leakage was 0 accm.
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% POWEH OTHE FI ST ATUS DISCO FY DISCOVEHY DESCniPTION LIJO I o I o I 4 l@l NA l
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NAME OF PREPAREn C I Cnggin. Supt. Plt. Fng. Ser.v.
PHONE:
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LER #:
50-366/1980-138 Licensec:
Georgia Power Company Facility Name; Edwin I.
llatch Docket #:
50-366
Narrative
Report for LER 50-366/1980-138 On 10-23-80, with Unit 2 at steady state power operation at 2278 MWL, an LLRT by procedure llNP-2-3952, " primary Contain-ment Periodic Type B and Type C Leakage Tests", was performed on the torus purge inlet outboard isolation valve 2T48-F324 shaft "0"
ring seals.
On 10-27-80, the LLRT coordinator reviewed the results of the LLRT in which the "0"
ring seals were found to be Icaking such that the test volume could not be pressurized; therefore, it was assumed that the
.60 La overall allowable Icakage rate of Tech Specs 3.6.1.2.B.1 would have been exceeded.
Primary containment integrity was not compromised because torus and drywell purge inlet line isolation valves 2T48-F307 (inboard),
F308 (outboard),
F309 (outboard) were already closed; in addition, these valves were pJ subsequently tagged,in the closed position to ensure the valves could not be operated thereby ensuring primary contain-ment integrity per Tech Specs 3.6.1.1 until the torus purge inlet outboard isolation valve 2T48-F324 "0"
ring seals could be repaired.
This is a repetitive-occurrence; refer to LER 50-366/1980-051.
There were no effcets on public health or safety.
The leakage of the torus purge inle inboard isolation valve was caused by worn "0"
ring seals.
addition rust, paint, and burrs were removed from the shaft on hich the "0"
rings are mounted, and the "O"
ring housing was cleaned.
Then the "O"
rings were replaced.
The "as found Icakage" could not be measured due to the fact that the test volume could not be pressurized.
After the indicated corrective maintenance, a
retest was performed, and the Icakage value
("as Icft leakage") was 0 acem.
o O
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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. 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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. 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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. 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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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