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NRC Form388 U.S. NUCLEAR REGULATORY COMMISSION 11-83)
APPROVED OMB NO. 31~104 EXPIRES: 8/31/86 LICENSEE EVENT REPORT (LERI FACILITY NAME 111 DOCKET NUMBER 121 PAGE 131 Palisades Plant
- 016101010121515 1 I OF 0 I 4 TITLE 141 LICENSE 'EVENT REPORT 92"."031 INADVERTENT ENGINEERED SAFETY FEATURE ACTUATION CAUSED BY INADEQUATE TEST PROCEDURES - SUPPLEMENTAL INFORMATION EVENT DATE 161 LER NUMBER 181 REPORT DA TE 181 OTHER FACILITIES INVOLVED 181
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LICENSEE CONTACT FOR THIS LER 1121 NAME
' TELEPHONE NUMBER Richard w. Smedley, Staff Licensing Engineer AREA CODE I sj1ls 11sl41-lalsl1l3 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC*
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I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR
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ABSTRACT ILJmit ID 1400 _._.. I.*., --rely flftHn tdn(J>>--* ty1>>wri,_ liM*l 1181 ABSTRACT On April 2, 1992, with the primary system solid and pressurized to 250 psig in the cold shutdown condition, the left channel Design Basis Accident (OBA) sequencer was inadvertently activated by technicians preparing to test the left channel Normal Shutdown Sequencer (NSD).
Th~ OBA sequencer operated properly and actuated the equipment it was programmed to actuate including Low Pressure Safety Injection (LPSI) pump P-67B and Containment Air Cooler fan V-4A.
The inadvertent activation of the OBA sequencer was caused by improperly connecting test equipment with a test cable which had been I
incorrectly modified. After verifying that.left channel OBA equipment had been properly actuated, the operators returned the l~ft channel OBA equipment to its pre-event status.
Corrective action in the form of l} Revising test procedures by adding detail to ensure proper connection between plant sequencer test jacks and the Data Acquisition System, 2} Revising the labeling on test cable wires and plugs and installing labels on the sequencer test jacks and 3} correctly modifying the test cables.
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NRC Form 3HA U.S. NUCLEAR REGULATORY COMMISSION APPll0\\1£0 OMB NO. 3160-010*
EXPIRES: 8/31186 11-131 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 131 PAGE 1*1 YEAR SEQUENTIAL NUMBER RE\\llSION NUMBER Palisades Plant 0 I 5 I 0 I 0 I 0. I 2 I 5 I 5 9 I 2 0 I 3 I 1 -
0 I 1 0 I 2 OF 0 I 4 EVENT.DESCRIPTION At 0829 hours0.00959 days <br />0.23 hours <br />0.00137 weeks <br />3.154345e-4 months <br /> on April 2, 1992, with the primary coolant system [AB] solid at 250 psig in the cold shutdown condition,. Instrument Technicians were connecting equipment to test.normal shutdown operation of the left channel sequencer when the Design Basis Accident (OBA) *operati~n of the sequencer was activate~ and actuated Low Pressure Safety Injection (LPSI) pump P-67B [BP;P]
and Containment Air Cooler*fan V-4A [BK;FAN]. *Plant operators, after verifying that the left channel OBA equipment had actuated properly, returned.
that equipment to pre-event status. This event did not involve the failure of any equipment important to safety.
CAUSE OF THE EVENT
The cause of this event was the improper installation of improperly modified test equipment cables [CBLl].
The root cause was the lack of adequately detailed procedures, the lack of adequately labeled test cables and test connectors [CON], and the lack of detailed identification of all the wires in the test cables and their associated termination point~ on the test cable connectors.
ANALYSIS OF THE EVENT
Both the NSD and OBA sequencer operations are tested during refueling outages to verify. the programmed starting times of the appropriate equipment. *Four surveillance procedures perform this verification. They are:
A.
For the Normal Shutdown Sequencer Test, RT-13A is used for the Left Channel; and RT~l3B is used for the Right Channel.
B.
For the Engineered Safeguards System Test (which test the OBA sequencer),
RT-SC is used for Left Channel; and RT-80 is used for the Right Channel.
The test equipment.used to perform the time interval measurement is called a "Data Acquisition System" (OAS).
During each of the above listed surveillances, the OAS measures the actual time interval for individual contact closures as the sequencer is allowed to operate.
For the measurement process, the OAS is electrically connected into the wiring schemes of all of the input and output contacts on the sequencers. This interconnection is done.with two test cables.
Each test cable had a plug [CON] which was labeled Number 1 for one cable and Number 2 for the other cable at the end which connects to the sequencer cable jacks and a barrier terminal strip at the end which connects to the DAS.
The sequencer had a pair I of unlabeled jacks which mate with the plugs on the test cables.
NRC Form 388A U.S. NUC~EAA REGULATORY COMMISSION APPllOVED OMB N0. 3160-010*
EXPIRES: 81311116
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18*831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION FACILITY NAME l1I DOCKET NUMBER 121 LEA NUMBER 131 PAGE 141 Palisades Plant YE.AA SEQUENTIAL NUMBER REVISION NUMBER 0 I 5 I 0 i 0 I 0 I 2 I 5 I 5 9 ' 2 -
0 I 3 I 1 0 I 1 01 3 OF 0 I 4 During the preparation for the tests, the DAS equipment that was previously used could not be made operational. Therefore, a new and different type of DAS was prepared for use.
The old DAS had always been connected to the sequencers and operated by the Consumers Power Company General Office based System Maintenance and Construction Services Department {SMCSD).
The new DAS required connection to the* sequencers and operation by the plant Instrument and Control Department {l&C).
Thus, the need to change the type of DAS equipment resulted in a different work group having to connect the test cables to the sequencers which was a contributing factor to the cause of the plugs on the test cables being incorrectly connected to their matching jacks on the left channel sequencer (plugs Number 1 and the Number 2 were reversed). This error, in combination with a different group performing the test, most probably occurred for one or all of the following reasons:
- 1.
Two plant prints, E-1508 and E-1509, described the connection of the DAS to *the two sequencers. Connection to the left channel sequencer required use of E-1508, while connection to the right channel sequencer required use of E-1509.
These prints were referenced in procedures RT-SC and RT-SD, however they were not adequately referenced in procedures RT-13A and RT-138.
These prints are no longer used since description of the cables, pins, and connectors is included in the revised versions of RT-SC, RT-SD, RT-13A and RT-138.
- 2.
Proper connection of the cable plugs and sequencer jacks was not a straightforward task.
To assure the cable plugs were mated with the proper sequencer jacks, the wires in the cable had to be physically traced from the terminal strip, compared with the drawing, and a determination made as to which plugs and jacks are the proper match.
Existing procedures did not include this information.
- 3. For proper installation, cable test plug Number 1 was required to be connected to the sequencer test jack which was attached to a cable leading to terminal strip TBL-2; and, cable test plug Number 2 was required to be connected to the sequencer test jack attached to a cable leading to terminal* strip TBL-1.
Additionally, a second error was made when the cables were prepared for the test.
When the old DAS was used, it was physically located in the cable spreading room.
For this outage, arrangements were made to locate the new DAS in the Control Room.
To avoid the congestion which would be caused by the long cables which had been required when the DAS was located in the Cable Spreading Room, the test cables were shortened. During the cable shortening process, several conductors in the cable were observed as "extras.* These
- extra* wires caused some confusion because plant drawings did not identify all of the conductors in the cables nor did they identify the corresponding pin connections on the cable pl~gs. Work instructions which were used to control the cable shortening stated, "Any unused wires should be taped out of
- the way.* Although the. person who wrote these instructions intended for the
NRC Form 388A 111*831 U.S. NUCLEAR REGUL.>.TORY COMMISSION APPROVED OMB NO. 3160-0104
- EXPIRES: 8131186 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER 121 YEAR LER NUMBER 131 SEQUENTIAL NUMBER REVISION NUMBER PAGE 141 Palisades Plant o 1 s 1 o 1 o 1 o 1 2 1 s 1 s 9 r 2
_ o 1 3 1.1 o, 1 o, 4 OF o, 4 wires to be individually taped out of the way, they were folded back as a group and taped out of the way.
Thus, the "extra" wires ended up electrically contacting each other and created short circuits across several independent electrical schemes when the cables from the DAS were incorrectly connected to the sequencer test jacks. Those electrical short circuits combined with the incorrect test cable connection to activate the left channel OBA sequencer which caused the actuation-of the LPSI pump P-678 and containment Air Cooler Fan V-4A.
CORRECTIVE ACTION
- 1)
Procedures RT-13A and B and RT-SC and D were revised to ensure a proper connection between the DAS and the *pl ant sequencers by i dent i fyi ng each wire in each test cable, the pin each wire is connected to on the plug end and the terminal the wire is connected to on the Data Acquisition System (OAS) end; and, to require the cables to be identity tested before use.
- 2)
Labels were added to the sequencer test jacks to be consistent with plant procedures identified in action 1 above.
- 3)
The test cables were correctly.modified by taping the "extra" wires in the test cables in a manner which prevents those "extra" wires from contacting each other~
.ADDITIONAL INFORMATION None
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| 05000255/LER-1992-001, :on 911209,observed That Seal Oil Pressure on Air Side of Electrical Generator Had Decreased from Previous Reading.Caused by Malfunction of Electrical Generator Seal Oil Sys Due to Plugged Filter.Filter Cleaned |
- on 911209,observed That Seal Oil Pressure on Air Side of Electrical Generator Had Decreased from Previous Reading.Caused by Malfunction of Electrical Generator Seal Oil Sys Due to Plugged Filter.Filter Cleaned
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000255/LER-1992-002, :on 911216,discovered That Selected Reactor Protective Sys Instrument Surveillance Requirements Not Being Performed,Per Tech Spech.Caused by Procedural Weakness.Ts Surveillance Procedures Reviewed |
- on 911216,discovered That Selected Reactor Protective Sys Instrument Surveillance Requirements Not Being Performed,Per Tech Spech.Caused by Procedural Weakness.Ts Surveillance Procedures Reviewed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000255/LER-1992-003, :on 911215,both Diesel Generators Inadvertently Started Due to Undervoltage Condition.Caused by Failure to Properly Calculate Cable Impedance.Analysis Being Performed of Voltage Transient |
- on 911215,both Diesel Generators Inadvertently Started Due to Undervoltage Condition.Caused by Failure to Properly Calculate Cable Impedance.Analysis Being Performed of Voltage Transient
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000255/LER-1992-004, :on 920107,loss of Containment Integrity Due to Failure of Emergency Escape Airlock Equalizing Valve Occurred.Caused by Lubricant on Valve Stem.Maint Procedure for Airlocks Being Revised |
- on 920107,loss of Containment Integrity Due to Failure of Emergency Escape Airlock Equalizing Valve Occurred.Caused by Lubricant on Valve Stem.Maint Procedure for Airlocks Being Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000255/LER-1992-005, :on 920115,NRC Notified Plant Staff of Apparent Misrouting of Class 1E Pressurizer Level Instrument Loop. Caused by Inadequate Design Control During Equipment Mod. Loop Disconnected |
- on 920115,NRC Notified Plant Staff of Apparent Misrouting of Class 1E Pressurizer Level Instrument Loop. Caused by Inadequate Design Control During Equipment Mod. Loop Disconnected
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000255/LER-1992-006, :on 920120,temp Element Was Not Environmentally Qualified in Accordance W/Regulatory Guide 1.97.Caused by Personnel Error & Inaccurate Documentation.Mod Prepared to Replace TE-0351B Instrument |
- on 920120,temp Element Was Not Environmentally Qualified in Accordance W/Regulatory Guide 1.97.Caused by Personnel Error & Inaccurate Documentation.Mod Prepared to Replace TE-0351B Instrument
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000255/LER-1992-007, :on 920205,determined That MSIV Actuator Solenoid Valves Could Be Rendered Inoperable by Main Steam Line Break Outside Containment.Caused by Installation of Unqualified Electrical Circuit.Valve Relocated |
- on 920205,determined That MSIV Actuator Solenoid Valves Could Be Rendered Inoperable by Main Steam Line Break Outside Containment.Caused by Installation of Unqualified Electrical Circuit.Valve Relocated
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000255/LER-1992-008, :on 920206,both HVAC Trains Inoperable When Air Conditioning Condensing Unit Bypass Line Leaked.Caused by Lack of Clearance Between Hot Gas Bypass Line & Penetration. Condensing Units Will Be Inspected |
- on 920206,both HVAC Trains Inoperable When Air Conditioning Condensing Unit Bypass Line Leaked.Caused by Lack of Clearance Between Hot Gas Bypass Line & Penetration. Condensing Units Will Be Inspected
| | | 05000255/LER-1992-009, :on 920213,control Room Ventilation Sys Inadvertently Switched to Emergency Mode.Caused by Combination of Inadequate Job Planning & Personnel Error. Job Planning Requirements Reviewed |
- on 920213,control Room Ventilation Sys Inadvertently Switched to Emergency Mode.Caused by Combination of Inadequate Job Planning & Personnel Error. Job Planning Requirements Reviewed
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000255/LER-1992-010, :on 920213,SIRWT Liquid Sample Exceeded MPC of Radionuclides.Caused by Inadequate Corrective Action for Prior Event & Defective Review of MPC Limit.Evaluation to Be Performed of PCS Operating Procedures |
- on 920213,SIRWT Liquid Sample Exceeded MPC of Radionuclides.Caused by Inadequate Corrective Action for Prior Event & Defective Review of MPC Limit.Evaluation to Be Performed of PCS Operating Procedures
| | | 05000255/LER-1992-011, :on 920212,discovered Inadequate Electrical Isolation of Class 1E Pressurizer Pressure Indicator Cable. Caused by Inadequate Design Control When Equipment Installed in 1980.Mod Controls Re Changes Revised |
- on 920212,discovered Inadequate Electrical Isolation of Class 1E Pressurizer Pressure Indicator Cable. Caused by Inadequate Design Control When Equipment Installed in 1980.Mod Controls Re Changes Revised
| | | 05000255/LER-1992-012, :on 920214,determined That Main Steam Line Radiation Elements Not Environmentally Qualified.Caused by Personnel Error.Main Steam Line Radiation Elements Will Be Modified or Justification Will Be Provided |
- on 920214,determined That Main Steam Line Radiation Elements Not Environmentally Qualified.Caused by Personnel Error.Main Steam Line Radiation Elements Will Be Modified or Justification Will Be Provided
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000255/LER-1992-013, :on 920217,lack of Enviornmental Qualification for Stack Gas Flow Transmitter FT01818 Noted.Caused by Lack of Appropriate Controls.Temporary Mod Performed on Radioactive Gaseous Effluent Monitor Sys |
- on 920217,lack of Enviornmental Qualification for Stack Gas Flow Transmitter FT01818 Noted.Caused by Lack of Appropriate Controls.Temporary Mod Performed on Radioactive Gaseous Effluent Monitor Sys
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000255/LER-1992-014, :on 920217,unauthorized Individual Granted Unescorted Access to Plant Protected Area.Caused by Personnel Error.Personnel Reminded of Need for Attention to Detail & Log Revised |
- on 920217,unauthorized Individual Granted Unescorted Access to Plant Protected Area.Caused by Personnel Error.Personnel Reminded of Need for Attention to Detail & Log Revised
| | | 05000255/LER-1992-015, :on 900923,heavy Load Moved in Load Path Which Deviated from Established Safe Load Paths & Was Not Approved by Reactor Engineer.Caused by Inappropriate Procedure Rev. Reactor Engineer Will Approve Subj Deviations |
- on 900923,heavy Load Moved in Load Path Which Deviated from Established Safe Load Paths & Was Not Approved by Reactor Engineer.Caused by Inappropriate Procedure Rev. Reactor Engineer Will Approve Subj Deviations
| 10 CFR 50.73(a)(2)(i) | | 05000255/LER-1992-016, :on 920225,determined That Solenoid Valves & Position Switches for Control Valves Controlling Svc Water Flow from CCW HXs Not Environmentally Qualified.Caused by Inadequate Analysis.Schemes Modified |
- on 920225,determined That Solenoid Valves & Position Switches for Control Valves Controlling Svc Water Flow from CCW HXs Not Environmentally Qualified.Caused by Inadequate Analysis.Schemes Modified
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000255/LER-1992-017, :on 920229,unusual Event Declared When Upper Guide Structure Raised for Removal from Reactor Vessel & Fuel Assembly Observed Hanging from Structure.Caused by Bent Fuel Alignment Pins.Pins Straightened |
- on 920229,unusual Event Declared When Upper Guide Structure Raised for Removal from Reactor Vessel & Fuel Assembly Observed Hanging from Structure.Caused by Bent Fuel Alignment Pins.Pins Straightened
| | | 05000255/LER-1992-018-01, :on 920309,discovered That Electrical Connections Not Environmentally Qualified Existed in Electrical Circuits for Position Switches Due to Inadequate Review.Wire Nut Connections Replaced |
- on 920309,discovered That Electrical Connections Not Environmentally Qualified Existed in Electrical Circuits for Position Switches Due to Inadequate Review.Wire Nut Connections Replaced
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000255/LER-1992-018, :on 920305,determined That Containment Electrical Penetration Connectors Were Not Qualified W/ 10CFR50.49.Caused by Lack of Adequate Technical Guidance. Subj Connectors Replaced |
- on 920305,determined That Containment Electrical Penetration Connectors Were Not Qualified W/ 10CFR50.49.Caused by Lack of Adequate Technical Guidance. Subj Connectors Replaced
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000255/LER-1992-020, :on 920303,discovered That Four SI Valves Which Should Have Been Closed Arranged W/Two Closed by One Safety Injection Signal Channel.Caused by Personnel Error. HPCI Sys Modified to Use Existing Piping |
- on 920303,discovered That Four SI Valves Which Should Have Been Closed Arranged W/Two Closed by One Safety Injection Signal Channel.Caused by Personnel Error. HPCI Sys Modified to Use Existing Piping
| | | 05000255/LER-1992-021, :on 920314,determined That Containment Integrity Had Been Breached Due to Simultaneous Opening of Sys Boundaries.Caused by Personnel Error.Reiterated to Staff That Work Should Begin on Proper Work Orders |
- on 920314,determined That Containment Integrity Had Been Breached Due to Simultaneous Opening of Sys Boundaries.Caused by Personnel Error.Reiterated to Staff That Work Should Begin on Proper Work Orders
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000255/LER-1992-023, :on 920327,discovered That Previously Unidentified Junction Boxes in Electrical Circuits Contained Environmentally Unqualified Connections.Caused by Design Failure.Terminal Blocks to Be Replaced |
- on 920327,discovered That Previously Unidentified Junction Boxes in Electrical Circuits Contained Environmentally Unqualified Connections.Caused by Design Failure.Terminal Blocks to Be Replaced
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000255/LER-1992-024, :on 920327,inadvertent Opening of Station Power Breaker Resulting in ESF Actuation & Interruption of Shutdown Cooling.Caused by Supervisor Allowing Work to Proceed on C Bus.Event Discussed W/Maint |
- on 920327,inadvertent Opening of Station Power Breaker Resulting in ESF Actuation & Interruption of Shutdown Cooling.Caused by Supervisor Allowing Work to Proceed on C Bus.Event Discussed W/Maint
| | | 05000255/LER-1992-025, :on 920331,determined That Longitudinal Welds on 36-inch Main Steam Line Piping Not Included in Inservice Insp Program.Caused by Personnel Error.All Welds Inspected Using Volumetric/Surface Methods |
- on 920331,determined That Longitudinal Welds on 36-inch Main Steam Line Piping Not Included in Inservice Insp Program.Caused by Personnel Error.All Welds Inspected Using Volumetric/Surface Methods
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000255/LER-1992-026, :on 920331,discovered That During LOCA, Concurrent W/Loss of Offsite Power,Overcurrent Trip of EDG 1-1 Could Occur.Caused by Oversight in Original Plant Design.Time Delay Relay Installed |
- on 920331,discovered That During LOCA, Concurrent W/Loss of Offsite Power,Overcurrent Trip of EDG 1-1 Could Occur.Caused by Oversight in Original Plant Design.Time Delay Relay Installed
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000255/LER-1992-027, :on 920401,wire Cage Door on 625-ft Elevation in Containment Found Closed But Wire Cut So That Person Could Have Reached Through to Unlock Door.Possibly Caused by Vandalism.Door Secured by Steel Plate |
- on 920401,wire Cage Door on 625-ft Elevation in Containment Found Closed But Wire Cut So That Person Could Have Reached Through to Unlock Door.Possibly Caused by Vandalism.Door Secured by Steel Plate
| 10 CFR 50.73(a)(2)(i) | | 05000255/LER-1992-028, :on 920331,potential Inability to Maintain Diesel Generator Room Temp Qualification Due to non-1E Qualified Cooling Fan Noted.Procedures Revised & Design Will Be Corrected |
- on 920331,potential Inability to Maintain Diesel Generator Room Temp Qualification Due to non-1E Qualified Cooling Fan Noted.Procedures Revised & Design Will Be Corrected
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000255/LER-1992-028-02, Informs of Completion of Mod Re Emergency Diesel Generator Room Cooling Per LER 92-028-02 | Informs of Completion of Mod Re Emergency Diesel Generator Room Cooling Per LER 92-028-02 | | | 05000255/LER-1992-029, :on 920404,inadvertent Actuation of Left Channel Sequencer Occurred.Caused by Failure to Follow Test Procedure.Importance of Incident Was Discussed W/All Shifts on Rotation |
- on 920404,inadvertent Actuation of Left Channel Sequencer Occurred.Caused by Failure to Follow Test Procedure.Importance of Incident Was Discussed W/All Shifts on Rotation
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000255/LER-1992-030, :on 920403,inadvertent Start of Both Diesel Generators Occurred.Caused by Electrical Discontinuity in Contacts.Fuse Panels for Both 2400 Volt Engineered Safeguard Buses Were Inspected |
- on 920403,inadvertent Start of Both Diesel Generators Occurred.Caused by Electrical Discontinuity in Contacts.Fuse Panels for Both 2400 Volt Engineered Safeguard Buses Were Inspected
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) | | 05000255/LER-1992-031, :on 920402,left Channel DBA Sequencer Inadvertently Activated by Technician Preparing to Test Left Normal Shutdown Sequencer Due to Inadequate Test Procedures. Procedures RT-13A & B & RT-8C & D Revised |
- on 920402,left Channel DBA Sequencer Inadvertently Activated by Technician Preparing to Test Left Normal Shutdown Sequencer Due to Inadequate Test Procedures. Procedures RT-13A & B & RT-8C & D Revised
| | | 05000255/LER-1992-031-01, Forwards LER-92-031-01 Re Inadvertent ESF Actuation Caused by Inadequate Test Procedures.Original Corrective Action to Revise Test Connection Drawings No Longer Required Because Plant Procedures Revised in Such Detail to Eli | Forwards LER-92-031-01 Re Inadvertent ESF Actuation Caused by Inadequate Test Procedures.Original Corrective Action to Revise Test Connection Drawings No Longer Required Because Plant Procedures Revised in Such Detail to Eliminate Need | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000255/LER-1992-032, :on 920406,unplanned Actuation of Right Channel of Safety Injection Sys Relays Occurred.Caused by Inadequate Procedure.Instructions & Steps Added to TSs Surveillance Procedures |
- on 920406,unplanned Actuation of Right Channel of Safety Injection Sys Relays Occurred.Caused by Inadequate Procedure.Instructions & Steps Added to TSs Surveillance Procedures
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000255/LER-1992-033, :on 920414,inoperable Control Room Penetration Occurred.Caused by Misapplication of Procedures & Inaccurate Procedures.Plant Administrative Procedure on Control of Equipment Status Will Be Updated |
- on 920414,inoperable Control Room Penetration Occurred.Caused by Misapplication of Procedures & Inaccurate Procedures.Plant Administrative Procedure on Control of Equipment Status Will Be Updated
| | | 05000255/LER-1992-034, :on 920701,reactor Automatically Tripped on Loss of Load Signal,Resulting in Turbine Generator Trip & Loss of Signal.Caused by Momentary Loss of Power to Turbine Sys computers.Post-trip Review Completed |
- on 920701,reactor Automatically Tripped on Loss of Load Signal,Resulting in Turbine Generator Trip & Loss of Signal.Caused by Momentary Loss of Power to Turbine Sys computers.Post-trip Review Completed
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000255/LER-1992-035, :on 920724,reactor Tripped Due to Loss of Turbine Digital Electrohydraulic Control Sys.Caused by Momentary Loss of Power to Electrohydraulic Sys Computers. Power Supply Switching Circuits Replaced |
- on 920724,reactor Tripped Due to Loss of Turbine Digital Electrohydraulic Control Sys.Caused by Momentary Loss of Power to Electrohydraulic Sys Computers. Power Supply Switching Circuits Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000255/LER-1992-036, :on 920802,during Monthly TS Procedure for 1-1 Edg,Noted That Exhaust Temp Indicated Low Reading.Caused by Lack of Adequate Controls in DG Cylinder Latch.Edg Test Procedures Will Be Revised |
- on 920802,during Monthly TS Procedure for 1-1 Edg,Noted That Exhaust Temp Indicated Low Reading.Caused by Lack of Adequate Controls in DG Cylinder Latch.Edg Test Procedures Will Be Revised
| 10 CFR 50.73(a)(2)(i) | | 05000255/LER-1992-037, :on 920814,reactor Tripped Due to Low SG Level Resulting from Broken Air Line on Main Feedwater Regulating Valve.Air Lines to Main Feedwater Regulating Valves CV-0701 & CV-0703 Replaced & Satisfactorily Tested |
- on 920814,reactor Tripped Due to Low SG Level Resulting from Broken Air Line on Main Feedwater Regulating Valve.Air Lines to Main Feedwater Regulating Valves CV-0701 & CV-0703 Replaced & Satisfactorily Tested
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000255/LER-1992-038-01, Forwards LER 92-038-01,providing Final Results of Testing Program Performed on Sola Electric Constant Voltage Transformers & Results of Evaluation of Failure of Charging Pump auto-start Circuit | Forwards LER 92-038-01,providing Final Results of Testing Program Performed on Sola Electric Constant Voltage Transformers & Results of Evaluation of Failure of Charging Pump auto-start Circuit | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000255/LER-1992-038, :on 920825,reactor Tripped,Resulting from Loss of Preferred Ac Bus Y-20,coincident W/Blown Fuse in Second Channel of Rps.Caused by Failure of Inverter ED-07.All Fuses Checked & Plant Drawings/Vendor Manuals Updated |
- on 920825,reactor Tripped,Resulting from Loss of Preferred Ac Bus Y-20,coincident W/Blown Fuse in Second Channel of Rps.Caused by Failure of Inverter ED-07.All Fuses Checked & Plant Drawings/Vendor Manuals Updated
| | | 05000255/LER-1992-039, :on 921030,reactor Automatically Tripped Due to Loss of Load Resulting from Unstable Voltage to Turbine Control Sys Computers.Caused by Failure to Maintain Power Voltage to Ups.New Transformers Installed |
- on 921030,reactor Automatically Tripped Due to Loss of Load Resulting from Unstable Voltage to Turbine Control Sys Computers.Caused by Failure to Maintain Power Voltage to Ups.New Transformers Installed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
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