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w APPROVE 3 oms leo.3190 4 104 LICENSEE EVENT REPORT (LER)
PACILITY NAast (11 DOCKET NUGAeER (2)
PA8BE (3 EDWIN I. HATCH, UNIT I O I5101010 l3 l2 l 1 1 lOFl 0l 2 flTLE lol Reactor Water Cleanup System Isolations IVENT DATE 151 LER NuesSER ten REPORT DATE 171 OTHER PACILITIES INVOLVED 108 MONTH DAY vtAR YEAR Mogyn OAy YEAR P ACILiTV NAMt3 DOCKET NUMSER(s) 88O
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488TR ACT (Limte se 7400 apsres. J.e., esereennetery arreen senere sesce tyneerrrfee hess# 1191 On 01/05/85, and on 01/10/85, the Reactor Water Cleanup (RWCU) system automatically leolated due to a high differential flow trip signal.
The outboard isolation valve (G31-F004) closed, and the running RWCU pump (G31-C001B) tripped.
The inboard icolation valve (G31-F001) did not shut as required by Tech. Specs section 3.7.D.1 and Tcble 3.7.1.
It was determined that the trips were caused by air trapped in the sensing lines of the system inlet flow transmitter (G31-NO36) and a leaking relief valve on the regenerative hrat exchanger (G31-B001).
The relief valve was replaced and the transmitter was vented.
The transmitter's proper operation was verified by observing its indicator, G31-R615, and it was returned to s::rvice.
An engineering evaluation was conducted, and it was determined that the RWCU system icolation logic would not allow a high differential flow trip to isolate both G31-F001 cnd G31-F004 unless both RWCU pumps were running.
There are, however, other signals which would have isolated both RWCU isolation valves regardless of pump status.
They l
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low reactor vessel water level
- scram, high RWCU equipment room ambient l
temperature, and high differential temperature across the RWCU equipment room l
v:ntilation ducts.
l A DCR has been implemented which changed the isolation logic circuitry to allow a high I
differential flow trip to isolate both G31-F001 and G31-F004 with elther, both or n31ther RWCU pump running.
The changes were satisfactorily tested per the DCR functional test, and the system was returned to service on 01/12/85.
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UCENSEE EVENT REPORT (LER) TEXT CONTINUATION Areaovso ous eso. asso-eio4 EXPIRES. S/31/86 PActLITY esaast (1)
DOCKET peutGBER (2)
LER soutaBER tel PAGE (30 "R',T?
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EDWIN I. HATCH, UNIT 1 0 l5 l 0 l 0 l 0 l3 l2 l 11815 O p l1
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ace asuwim This 30 day LER is required by 10CFR50.73(a)(2)(iv) because these events were tutomatic actuations of an ESF.
It is also required by 10CFR50.73(a)(2)(i) because sysluation of these events has shown that the unit has been operating contrary to the pesvisions of Tech. Specs. section 3.7.D.1, and Table 3.7.1.
On 01/05/85, at approximately 1824 CST with the reactor mode switch in the shutdown p sition and the unit shutdown, operations personnel were attempting to put the Ricctor Water Cleanup (RWCU) demineralizers in service with RWCU pump G31-C001B running and G31-C001A secured.
At this time, the Cleanup System Leak alarm ennunciaLed, the RWCU outboard isolation valve (G31-F004) closed and the "B" RWCU pump l
(G31-C001B) tripped. The inboard isolation valve (C31-F001) failed to close.
On 01/10/85, at approximately 1340 CST with the reactor mode switch in the startup and hat standby position and the unit at less than 1% thermal power, with G31-C001B running and G31-C001A secured, the Cleanup System Leak alarm again annunciated, G31-F004 closed and the "B" RWCU pump tripped.
The inboard isolation valve (G31-F001) failed to close.
C31-F001 was declared inoperable.
The RWCU system was removed from service, and G31-F001 and G31-F004 were closed as required by Tech. Specs. Table 3.2.1, reference no. 8, note C.
Eo actual or potential safety consequences resulted from these events nor was the hsolth and safety of the public affected.
Thsse are repetitive events as previously reported in LER 50-321/1984-29.
Investigation of the event on 01/10/85 revealed that a relief valve on the esgenerative heat exchanger (G31-B001) was leaking, and that the cleanup system inlet flow transmitter (G31-NO36) had air trapped in its sensing lines which was causing an seroneous signal to be sent to the differential flow network.
Tha relief valve was replaced and the transmitter was vented.
The transmitter's pecper operation was verified by observing its indicator, G31-R615, and it was esturned to service.
An engineering investigation was conducted to determine why G31-F001 had not shut when tha system isolated.
It was determined that the RWCU system isolation logic was such th:t it would not allow a high differential flow trip to isolate both G31-F001 and G31-F004 unless both RWCU pumps were running.
With G31-C001A running, G31-F001 would chut, G31-F004 would remain open.
With G31-C001B running, G31-F004 would shut, G31-F001 would remain open.
With no pumps running, neither valve would shut.
There cro, however, other signals which would have isolated both RWCU isolation valves regardless of pump status.
They are: low reactor vessel water level scram, high RWCU equipment room ambient temperature, and high differential temperature across the RWCU equipment room ventilation ducts.
A DCR has been implemented which changed the isolation logic circuitry to allow a high differential flow trip to isolate both G31-F001 and G31-F004 with either, both or noither RWCU pump running.
The changes were satisfactorily tested per the DCR functional test, and the system was returned to service on 01/12/85.
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Post Office Box 439
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' Bexley, Georgia 31513 Telephone 912 367-7781
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GeorgiaPbwer
. Edwin 1. Hatch Nuclear Plant January 27, 1985 i
GM-84-041 i
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PLANT-E.
I.. HATCH Licensee Event Report
. Docket No. 50-321 1.
United States Nuclear Regulatory Commission Documer.t Control Desk l
Washington, D. C.
20555 Attached is Licensee Event Report No. 50-321/1985-001.
This report is required by 10CFR 50.73(a)(2)(1), and 10CFR 50.73(a)(2)(iv).
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K. M. Gillespie Superintendent of Regulatory Compliance R. D.
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| 05000366/LER-1985-001-01, :on 850119,reactor Scrammed.Caused by Failure of Inboard Msiv.Procedure HNP-2-3111 Revised to Allow 2-minute Wait Between Operating MSIV Cycle to Prevent Isolation of Drywell Pneumatic Sys |
- on 850119,reactor Scrammed.Caused by Failure of Inboard Msiv.Procedure HNP-2-3111 Revised to Allow 2-minute Wait Between Operating MSIV Cycle to Prevent Isolation of Drywell Pneumatic Sys
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000321/LER-1985-001, :on 850105,reactor Water Cleanup Sys Automatically Isolated Due to High Differential Flow Trip Signal.Caused by Air Trapped in Sensing Lines of Sys Inlet Flow Transmitter G31-N036 |
- on 850105,reactor Water Cleanup Sys Automatically Isolated Due to High Differential Flow Trip Signal.Caused by Air Trapped in Sensing Lines of Sys Inlet Flow Transmitter G31-N036
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | | 05000366/LER-1985-002-01, :on 850429,spurious Reactor Protection Sys (RPS) Logic Actuation Occurred Twice.Caused by Spurious Electrical Noise in intermediate-range Monitor Channel.Rps Trips Reset |
- on 850429,spurious Reactor Protection Sys (RPS) Logic Actuation Occurred Twice.Caused by Spurious Electrical Noise in intermediate-range Monitor Channel.Rps Trips Reset
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000321/LER-1985-002, :on 850113,safety Relief Valve B Failed to Open.Caused by Open Links.Links Closed |
- on 850113,safety Relief Valve B Failed to Open.Caused by Open Links.Links Closed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000321/LER-1985-003-01, :on 850106,reactor Protection Sys Logic Actuation Occurred During Completion of Maint Activities on Reactor Low Water Level Instrument 1B21-N080A,due to Backfilling 1B21-N080A Before Return to Svc |
- on 850106,reactor Protection Sys Logic Actuation Occurred During Completion of Maint Activities on Reactor Low Water Level Instrument 1B21-N080A,due to Backfilling 1B21-N080A Before Return to Svc
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000366/LER-1985-003, :on 850107,Group 5 Isolation Occurred from Reactor Water Cleanup High Differential Temp.Cause Attributed to Short Circuit During Corrective Maint on Resistance Temp Detector |
- on 850107,Group 5 Isolation Occurred from Reactor Water Cleanup High Differential Temp.Cause Attributed to Short Circuit During Corrective Maint on Resistance Temp Detector
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000366/LER-1985-004, :on 850121 & 23,ESF Actuation Occurred.Caused by Reactor Protection Sys B Motor Generator Set Tripping Due to Failed Voltage Regulator.Regulator Replaced & Adjusted. Motor Generator Tested & Returned to Svc |
- on 850121 & 23,ESF Actuation Occurred.Caused by Reactor Protection Sys B Motor Generator Set Tripping Due to Failed Voltage Regulator.Regulator Replaced & Adjusted. Motor Generator Tested & Returned to Svc
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000321/LER-1985-004-01, :on 850130,reactor Bldg & Refueling Floor Standby Gas Treatment Sys Supply Dampers Control Logic Determined to Fail Closed on Loss of Electrical Power.Design Change Requested |
- on 850130,reactor Bldg & Refueling Floor Standby Gas Treatment Sys Supply Dampers Control Logic Determined to Fail Closed on Loss of Electrical Power.Design Change Requested
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000321/LER-1985-005, :on 850123,plant Shut Down.Caused by Exhaust Diaphragm of HPCI Rupturing Due to Defective Seal on Exhaust Line.Diaphragm Replaced.Leak Rate Test Performed Satisfactorily |
- on 850123,plant Shut Down.Caused by Exhaust Diaphragm of HPCI Rupturing Due to Defective Seal on Exhaust Line.Diaphragm Replaced.Leak Rate Test Performed Satisfactorily
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(1) | | 05000366/LER-1985-005-01, :on 850329,determined That Battery Surveillance Procedure Contained Acceptance Criteria That Did Not Satisfy Tech Specs.Caused by Procedural Inadequacy.Procedure Being Revised |
- on 850329,determined That Battery Surveillance Procedure Contained Acceptance Criteria That Did Not Satisfy Tech Specs.Caused by Procedural Inadequacy.Procedure Being Revised
| 10 CFR 50.73(a)(2)(1) | | 05000321/LER-1985-006-01, :on 850130 & 0202,reactor Tripped When Main Transformer 3 Phase Main Generator Output Line Fell.Caused by Incorrect Tensile Strength of Insulators Holding Power Line.New Insulators Installed |
- on 850130 & 0202,reactor Tripped When Main Transformer 3 Phase Main Generator Output Line Fell.Caused by Incorrect Tensile Strength of Insulators Holding Power Line.New Insulators Installed
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000366/LER-1985-006, :on 850124,calibr Head Correction Data for RCIC Steam Line Differential Pressure Transmitters 2E51-N057A & 2E51-N057B Determined Incorrect.Caused by Error in Procedure.Rcic Declared Inoperable |
- on 850124,calibr Head Correction Data for RCIC Steam Line Differential Pressure Transmitters 2E51-N057A & 2E51-N057B Determined Incorrect.Caused by Error in Procedure.Rcic Declared Inoperable
| 10 CFR 50.73(a)(2)(i) | | 05000366/LER-1985-007-01, :on 850210,reactor Water Cleanup Inboard Isolation Valve 2G31-F001 Isolated Due to False Trip Signal from Inlet Temp Instrument 2G31-N661A.Caused by Poor Connection Between Trip Card & Edge Connector |
- on 850210,reactor Water Cleanup Inboard Isolation Valve 2G31-F001 Isolated Due to False Trip Signal from Inlet Temp Instrument 2G31-N661A.Caused by Poor Connection Between Trip Card & Edge Connector
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000321/LER-1985-007, :on 850109,Tech Spec Requirements for New Setpoint for HPCI Low Steam Line Pressure Instrument Not Met.Caused by Loss of Administrative Controls.Instrument Recalibr |
- on 850109,Tech Spec Requirements for New Setpoint for HPCI Low Steam Line Pressure Instrument Not Met.Caused by Loss of Administrative Controls.Instrument Recalibr
| 10 CFR 50.73(a)(2)(1) | | 05000366/LER-1985-007, :on 850210 & 24,reactor Water Cleanup Inboard Isolation Valve 2G31-F001 Isolated as Result of False Trip Signal.Caused by Bad Connection Where Trip Card 2G31-N661A Plugged Into Connector |
- on 850210 & 24,reactor Water Cleanup Inboard Isolation Valve 2G31-F001 Isolated as Result of False Trip Signal.Caused by Bad Connection Where Trip Card 2G31-N661A Plugged Into Connector
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000321/LER-1985-008, :on 850109,electrical Overspeed Trip Did Not Actuate within Specified Limits of Tech Specs.Electrical Overspeed Repaired.On 850111,RCIC Isolated.Caused by High Exhaust Diaphragm Pressure.Diaphragm Replaced |
- on 850109,electrical Overspeed Trip Did Not Actuate within Specified Limits of Tech Specs.Electrical Overspeed Repaired.On 850111,RCIC Isolated.Caused by High Exhaust Diaphragm Pressure.Diaphragm Replaced
| 10 CFR 50.73(a)(2)(1) | | 05000366/LER-1985-008-01, :on 850420,reactor Water Cleanup Outboard Isolation Valve 2G31-F004 Isolated on High Differential Flow.Caused by Flow Fluctuation During Valving in of Filter Demineralizer 2A.Valve Opened |
- on 850420,reactor Water Cleanup Outboard Isolation Valve 2G31-F004 Isolated on High Differential Flow.Caused by Flow Fluctuation During Valving in of Filter Demineralizer 2A.Valve Opened
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000366/LER-1985-009-01, :on 850319,RCIC Steam Supply Primary Containment Inboard Isolation Valve 2E51-F007 Inadvertently Closed.Caused by Personnel Error.Isolation Logic Reset & Valve Returned to Open Position |
- on 850319,RCIC Steam Supply Primary Containment Inboard Isolation Valve 2E51-F007 Inadvertently Closed.Caused by Personnel Error.Isolation Logic Reset & Valve Returned to Open Position
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(s)(2)(iv) | | 05000321/LER-1985-009, :on 850123,clearance Hold Tags Placed on Wrong Switches,Resulting in Inability of Ball Valves to Close. Caused by Personnel Error.Responsible Personnel Counseled. Tags Placed on Correct Switches |
- on 850123,clearance Hold Tags Placed on Wrong Switches,Resulting in Inability of Ball Valves to Close. Caused by Personnel Error.Responsible Personnel Counseled. Tags Placed on Correct Switches
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | | 05000366/LER-1985-010-01, :on 850409,certain Valves Discovered Leaking in Excess of Limits Specified in Tech Spec Sections 3.6.1.2.b & C.Valves Will Be Repaired & Tested |
- on 850409,certain Valves Discovered Leaking in Excess of Limits Specified in Tech Spec Sections 3.6.1.2.b & C.Valves Will Be Repaired & Tested
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000321/LER-1985-010, :on 850116,reactor Scrammed on Reactor Vessel Low Water Level Signal.Caused by Vital Ac Power Supply Trip. Personnel Restored Reactor Level to Normal |
- on 850116,reactor Scrammed on Reactor Vessel Low Water Level Signal.Caused by Vital Ac Power Supply Trip. Personnel Restored Reactor Level to Normal
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000321/LER-1985-010-01, :on 850116,reactor Scram on Low Level Water Signal Received.Caused by Ac Power Supply Trip & Runback of Feedpumps a & B.Personnel Restored Level to Normal Via Feedpump a & Booster Pumps |
- on 850116,reactor Scram on Low Level Water Signal Received.Caused by Ac Power Supply Trip & Runback of Feedpumps a & B.Personnel Restored Level to Normal Via Feedpump a & Booster Pumps
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000366/LER-1985-011, :on 850401,main Steam Line Monitor B High Trip Setpoint Set at 3.2 Times Full Power Background.Caused by Personnel Communication Error.Setpoint Data Will Be Retrieved in Person Rather than Via Telephone |
- on 850401,main Steam Line Monitor B High Trip Setpoint Set at 3.2 Times Full Power Background.Caused by Personnel Communication Error.Setpoint Data Will Be Retrieved in Person Rather than Via Telephone
| 10 CFR 50.73(a)(2)(vi) | | 05000321/LER-1985-011-01, :on 850424,Train a of Standby Gas Treatment Sys Started.Caused by Inadequate Special Instructions Which Failed to Give Detailed Instructions for Returning Battery Charger to Svc.Train a Returned to Normal |
- on 850424,Train a of Standby Gas Treatment Sys Started.Caused by Inadequate Special Instructions Which Failed to Give Detailed Instructions for Returning Battery Charger to Svc.Train a Returned to Normal
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000366/LER-1985-012-01, :on 850409,unplanned Actuation of Reactor Protection Sys Occurred.Caused by Failure of Main Steam Line Radiation Detectors Due to Loose & Saturated Power Cables. Cables Replaced |
- on 850409,unplanned Actuation of Reactor Protection Sys Occurred.Caused by Failure of Main Steam Line Radiation Detectors Due to Loose & Saturated Power Cables. Cables Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000321/LER-1985-012, :on 850324,reactor Water Cleanup Primary Containment Isolation Valves Closed Due to Leak Detection Isolation Signal.Manual Isolation Valves Replaced |
- on 850324,reactor Water Cleanup Primary Containment Isolation Valves Closed Due to Leak Detection Isolation Signal.Manual Isolation Valves Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000366/LER-1985-013-01, :on 850411,while in Refueling Mode,Full Reactor Scram Indicated.Investigation Determined That Full Reactor Protection Sys Logic Actuation Occurred.Caused by hi-hi Signal from Source Range Monitors |
- on 850411,while in Refueling Mode,Full Reactor Scram Indicated.Investigation Determined That Full Reactor Protection Sys Logic Actuation Occurred.Caused by hi-hi Signal from Source Range Monitors
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000321/LER-1985-013, :on 850216,drywell Floor Drain Total Leakage Exceeded Max Limit.Caused by Shaft Seal 1 on Reactor Recirculation Pump B Leaking Excessively.Shaft Seal Cartridge Replaced |
- on 850216,drywell Floor Drain Total Leakage Exceeded Max Limit.Caused by Shaft Seal 1 on Reactor Recirculation Pump B Leaking Excessively.Shaft Seal Cartridge Replaced
| 10 CFR 50.73(a)(2)(1) | | 05000321/LER-1985-014, :on 850128,instrumentation & Controls Personnel Discovered That RCIC Pump Suction Pressure Instrument Procedure Not Performed Until 850204.Caused by Personnel Error.Personnel Reinstructed |
- on 850128,instrumentation & Controls Personnel Discovered That RCIC Pump Suction Pressure Instrument Procedure Not Performed Until 850204.Caused by Personnel Error.Personnel Reinstructed
| 10 CFR 50.73(a)(2)(i) | | 05000366/LER-1985-014, :on 850510,seven Safety Relief Valves Serving Automatic Depressurization Sys Function Opened,Constituting ESF Actuation.Caused by Procedural Rev Deficiency.Personnel Counseled on Need for Accurate Revs |
- on 850510,seven Safety Relief Valves Serving Automatic Depressurization Sys Function Opened,Constituting ESF Actuation.Caused by Procedural Rev Deficiency.Personnel Counseled on Need for Accurate Revs
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000366/LER-1985-015-01, :on 850415,reactor Protection Sys Logic Actuation Occurred Due to Spurious Actuation in Other Sys Channel.Caused by Intermediate Range Monitor Spurious Electrical Noise.Preventing Noise Unachievable |
- on 850415,reactor Protection Sys Logic Actuation Occurred Due to Spurious Actuation in Other Sys Channel.Caused by Intermediate Range Monitor Spurious Electrical Noise.Preventing Noise Unachievable
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000321/LER-1985-016-01, :on 850519,RCIC Pump Failed to Meet Rated Flow Requirement of 400 Gpm at Normal Reactor Vessel Operating Pressure.Caused by Failure of RCIC Sys Automatic Control Amplified Circuit Board.Circuit Board Replaced |
- on 850519,RCIC Pump Failed to Meet Rated Flow Requirement of 400 Gpm at Normal Reactor Vessel Operating Pressure.Caused by Failure of RCIC Sys Automatic Control Amplified Circuit Board.Circuit Board Replaced
| 10 CFR 50.73(a)(2)(1) | | 05000366/LER-1985-016, :on 850425,during Testing of Main Steam Safety Relief Valves,Four Valves Failed to Lift within Range Required by Tech Spec 3.4.2.1.Caused by Valve Pilot Setpoint Drift.Pilot Assemblies Refurbished & Retested |
- on 850425,during Testing of Main Steam Safety Relief Valves,Four Valves Failed to Lift within Range Required by Tech Spec 3.4.2.1.Caused by Valve Pilot Setpoint Drift.Pilot Assemblies Refurbished & Retested
| 10 CFR 50.73(a)(2)(1) | | 05000321/LER-1985-017, :on 850515,determined Cable Tray Support 33 Located in Cable Spreading Room Could Experience Overloading During OBE or Sse.Caused by A/E Design Error.Cable Support Modified.Part 21 Related |
- on 850515,determined Cable Tray Support 33 Located in Cable Spreading Room Could Experience Overloading During OBE or Sse.Caused by A/E Design Error.Cable Support Modified.Part 21 Related
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000366/LER-1985-017-01, :on 850430 & 0501,molded Case Circuit Breakers Trip Setpoints &/Or Breaker Locations Contrary to Specified Setpoints or Locations of Tech Spec Table 3.8.2.6-1.Caused by Inadequate Instructions.Tech Specs Amended |
- on 850430 & 0501,molded Case Circuit Breakers Trip Setpoints &/Or Breaker Locations Contrary to Specified Setpoints or Locations of Tech Spec Table 3.8.2.6-1.Caused by Inadequate Instructions.Tech Specs Amended
| 10 CFR 50.73(a)(2)(1) | | 05000366/LER-1985-017, :on 850430 & 0501,molded Case Circuit Breakers Discovered W/Trip Setpoints &/Or Breaker Locations Contrary to Tech Spec Table 3.8.2.6-1.Caused by Inadequate Instructions for Implementing Design Change |
- on 850430 & 0501,molded Case Circuit Breakers Discovered W/Trip Setpoints &/Or Breaker Locations Contrary to Tech Spec Table 3.8.2.6-1.Caused by Inadequate Instructions for Implementing Design Change
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | | 05000321/LER-1985-018, :on 850515,safety Relief Valve a Activated & Remained Open & Reactor Manually Scrammed.Caused by Falling Water from Control HVAC Creating Excessive Moisture in Panel 1H11-P926.HVAC Filter Train Maint Done |
- on 850515,safety Relief Valve a Activated & Remained Open & Reactor Manually Scrammed.Caused by Falling Water from Control HVAC Creating Excessive Moisture in Panel 1H11-P926.HVAC Filter Train Maint Done
| 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) | | 05000366/LER-1985-018-01, :on 850603,during Load Reduction to Take Div of Plant Svc Water Out of Svc,Turbine Trip & Subsequent Reactor Scram Received on High Moisture Separator Reheater Level Signal.Caused by High Level Trip Signal |
- on 850603,during Load Reduction to Take Div of Plant Svc Water Out of Svc,Turbine Trip & Subsequent Reactor Scram Received on High Moisture Separator Reheater Level Signal.Caused by High Level Trip Signal
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000321/LER-1985-019, :on 850403 & 05,reactor Water Cleanup (RWCU) Sys Pump Suction Primary Containment Valves 1G31-F001 & 1G31-F004 Isolated Three Times.Caused by High Ambient Temp in RWCU Pump Rooms 1A & 1B |
- on 850403 & 05,reactor Water Cleanup (RWCU) Sys Pump Suction Primary Containment Valves 1G31-F001 & 1G31-F004 Isolated Three Times.Caused by High Ambient Temp in RWCU Pump Rooms 1A & 1B
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000366/LER-1985-019-01, :on 850429,during Cold Shutdown,Reactor Water Cleanup Primary Containment Inboard Isolation Valve 2G31-F001 Isolated.Caused by Personnel Error.Resistance Temp Detectors Relabeled |
- on 850429,during Cold Shutdown,Reactor Water Cleanup Primary Containment Inboard Isolation Valve 2G31-F001 Isolated.Caused by Personnel Error.Resistance Temp Detectors Relabeled
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000366/LER-1985-020, :on 850726,RWCU Pump Inboard & Outboard Suction Isolation Valves Isolated on High Sys Differential Flow. Caused by Leakage Past RWCU Loop a Resin Strainer Drain Valves.Investigation Continuing |
- on 850726,RWCU Pump Inboard & Outboard Suction Isolation Valves Isolated on High Sys Differential Flow. Caused by Leakage Past RWCU Loop a Resin Strainer Drain Valves.Investigation Continuing
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000366/LER-1985-020-01, :on 850726,reactor Water Cleanup Pump Inboard & Outboard Suction Isolation Valves 2G31-F001 & 2G31-F004, Isolated on High Sys Differential Flow.Caused by Filter Demineralizer Not Being Completely Filled |
- on 850726,reactor Water Cleanup Pump Inboard & Outboard Suction Isolation Valves 2G31-F001 & 2G31-F004, Isolated on High Sys Differential Flow.Caused by Filter Demineralizer Not Being Completely Filled
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000321/LER-1985-020, :on 850415,special Purpose Procedure Directing Implementation of Direct Conversion Reactor on Plant Standby Gas Treatment Sys in Violation of Tech Specs.Caused by Inadequate Technical Review of Procedures |
- on 850415,special Purpose Procedure Directing Implementation of Direct Conversion Reactor on Plant Standby Gas Treatment Sys in Violation of Tech Specs.Caused by Inadequate Technical Review of Procedures
| 10 CFR 50.73(a)(2)(vi) | | 05000366/LER-1985-021-01, :on 850707,during Reactor Water Cleanup Sys Procedure,Inboard & Outboard Suction Isolation Valves Isolated.Caused by Misaligned Position Indicators.Repairs in Progress |
- on 850707,during Reactor Water Cleanup Sys Procedure,Inboard & Outboard Suction Isolation Valves Isolated.Caused by Misaligned Position Indicators.Repairs in Progress
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000366/LER-1985-021, :on 850707,reactor Water Cleanup Pump Inboard & Outboard Suction Isolation Valves Isolated on High Sys Differential Flow.Caused by Incompletely Closed Valves Due to Misaligned Indicators.Valves Closed |
- on 850707,reactor Water Cleanup Pump Inboard & Outboard Suction Isolation Valves Isolated on High Sys Differential Flow.Caused by Incompletely Closed Valves Due to Misaligned Indicators.Valves Closed
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000321/LER-1985-021, :on 850612,plant Personnel Determined That Fire Protection Valve Cycling Procedures Could Make Valves Inaccessible During Operations to Be Cycled Once Every 18 Months Rather than Every 12 Months |
- on 850612,plant Personnel Determined That Fire Protection Valve Cycling Procedures Could Make Valves Inaccessible During Operations to Be Cycled Once Every 18 Months Rather than Every 12 Months
| 10 CFR 50.73(a)(2)(vi) | | 05000321/LER-1985-022, :on 850527,operations Personnel Determined That Reactor Water Cleanup Pump Suction Inboard Primary Containment Isolation Valve Isolated on High Ambient Temp in Reactor Water Cleanup Pump Room 1A |
- on 850527,operations Personnel Determined That Reactor Water Cleanup Pump Suction Inboard Primary Containment Isolation Valve Isolated on High Ambient Temp in Reactor Water Cleanup Pump Room 1A
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000366/LER-1985-022-01, :on 850814,personnel Determined That Monthly Channel Check for Drywell High Range Pressure & Radiation Instrumentation Not Performed Per Tech Specs. Caused by Personnel Error |
- on 850814,personnel Determined That Monthly Channel Check for Drywell High Range Pressure & Radiation Instrumentation Not Performed Per Tech Specs. Caused by Personnel Error
| 10 CFR 50.73(a)(2)(1) | | 05000366/LER-1985-023, :on 850515,performance of Channel Logic Response Time Procedure Actuated LPCI Sys Signal.Caused by Error in Procedure Instructions.Personnel Reviewed & Corrected Procedure |
- on 850515,performance of Channel Logic Response Time Procedure Actuated LPCI Sys Signal.Caused by Error in Procedure Instructions.Personnel Reviewed & Corrected Procedure
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000321/LER-1985-023-01, :on 850616,reactor Water Conductivity Monitoring Inoperable Due to Conductivity Cell.Caused by Broken Gauge Which Had Been Removed on 850614.Reactor Water Conductivity Cell Reestablished |
- on 850616,reactor Water Conductivity Monitoring Inoperable Due to Conductivity Cell.Caused by Broken Gauge Which Had Been Removed on 850614.Reactor Water Conductivity Cell Reestablished
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(1) |
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