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On 1-7-86 at 1230 Operations personnel noticed the double door leading from the Turbine Building into the Electrical Switchgear Room had been propped open to facilitate the bringing in of scaffolding materials for a plant mbdification project. No fire watch was posted so the door was immediately closed.
Subsequent investigation showed that the door had been open for approximately 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
On 1-12-86 at 0245 Security personnel discovered tape covering the latching mechanism on the door leading from the Primary Auxiliary Building to the Waste Drumming Room. The tape was immediately removed and the door was properly latched. Subsequent investigation showed that the door had been in this inoperable condition for approximately I day.
Both events are considered separate incidents, however since both involve contractor personnel errors a single report is being issued. These incidents are reportable under 10CFR50.73(a)(2)(1) since both involved inoperable periods of time in excess of that specified in Technical Specification 3.22-F.
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asac Form 3e4A U S NUCLEf.!3 KEIULATORY COMurassoas
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LICENSEE EVENT REPORT (LER) TEXT CENTINUATl3N
.uwoveo oMe ho siso-oios E OtI E S 8 '31 '85 F ACILITY hAME (18 DOCEET souMcER (2)
LER huMSER (St PAGE13)
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<nx w -. -. m m c r.- a u,n m Switchgear Room Door On 1-7-86 at 1230 Operations personnel during a routine plant tour discovered the double door leading from the Turbine Building into the Electrical Switchgear Room propped open by contractor laborers to facilitate the transport of scaffolding materials into the room. This work was being performed in support of the NUREG 0737 modification for the Inadequate Core Cooling Instrumentation System. Security personnel were guarding the door opening, since it is a normally closed and alarmed security door in addition to being a Technical Specification fire door. A fire watch trained person however was not posted at the door. The Operations personnel discovering this situation immediately closed the door and notified the Control Room.
Work on bringing the scaffolding materials into the Switchgear Room had begun at approximately 0730 on the same day.
It was subsequently determined that the contractor personnel supervision involved were unfamiliar with the fire door restrictions and as a result failed to adequately address these concerns on the job work order. Therefore the work proceeded without the proper fire watch controls in place. Thus for a five hour period of time the door was open without the posting of a fire watch. During this time the security guard (not fire watch trained) was continually posted at the door and the fire detection and automatic suppression systems in the area were in service. At no time during this period did a fire condition exist that could have impacted the safety equipment in the area.
Drumming Room Door On 1-12-86 at 0245 Security personnel during a routine plant tour discovered tape covering the latching mechanism on the double door leading from the Primary Auxiliary Building into the Waste Drumming Room.
Security notified the Control Room and the tape was immediately removed and the door properly latched.
Investigation revealed that the door latch had been taped by a radioactive waste handling contractor performing work in the Drumming Room on 1-11-86.
He had taped the door latch to facilitate repeated exit and re-entry maneuvers from the room.
It is believed that the door was in the inoperable condition for less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being discovered and remedied. During the time the door was incapable of latching and therefore inoperable. No fire conditions existed in the area and the fire dete,ction and suppression systems were in service during the incident.
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION oeaoveo oMno uso-oio4 t u PtRis 8731 25 FactLITV NAME 414 DOCRET NUMBER (2)
LER NUMBER 16 PAGE(31 "ROJ'.
'U.?,70 "aa Haddam Neck o l5 lo l0 [o l 2l1 l 3 8 l6
- - 0l0l1 0 l0 0 l3 OF 0 l3 TEXT (Xmore spece a recured use N /W3C Form JfEA 'sA 11h Cause/ Corrective Action Both incidents were similar in nature in that contractor personnel on site to assist in maintenance and refueling activities were responsible for the non-conformances. These personnel were not aware of the exact requirements associated with fire doors. All Haddam Neck personnel and contractor personnel have since been reinstructed, via a written notice, of the station procedures and regulations regarding the use of fire doors. The licensee notes that the probability of occurrence of incidents such as this is increased substantially during a major outage when a large population of contractor personnel is on-site.
The licensee, however, feels that the existence of other fire protection equipment, coupled with the vigilance of station personnel (who discovered both of these discrepancies) will ensure that adequate fire protection is maintained for safety-related equipment. No further corrective action is planned.
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT RR#1
- EAST HAMPTON, CONN.06424 February 5, 1986 SS-86-25 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C.
20555
Reference:
Facility Operating License No. DPR-61 Docket No. 50-213 Reportable Occurrence LER 50-213/86-001-00 Gentlemen:
This letter forwards the Licensee Event Report 86-001-00, required to be submitted within thirty days, pursuant to the requirements of Connecticut Yankee Technical Specificat!.ons.
Very truly yours, l
WW Richard H. Graves Station Superintendent RHG:RMR/ lac
Attachment:
LER 86-001-00 cc:
Dr. T. E. Murley, Region I Y o
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| 05000213/LER-1986-001, :on 860107 & 12,discovered That Two Tech Spec Fire Doors Inoperable.Caused by Contractor Personnel Error. All Plant & Contractor Personnel Reinstructed in Station Procedures & Regulations |
- on 860107 & 12,discovered That Two Tech Spec Fire Doors Inoperable.Caused by Contractor Personnel Error. All Plant & Contractor Personnel Reinstructed in Station Procedures & Regulations
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1986-003, :on 860127,during Eddy Current Testing of Steam Generator 2,results Placed Generator in C-3 Category.Caused by Steam Generator Tubes Experiencing Corrosive Degradation, Forming Pits at or Above Tubesheet |
- on 860127,during Eddy Current Testing of Steam Generator 2,results Placed Generator in C-3 Category.Caused by Steam Generator Tubes Experiencing Corrosive Degradation, Forming Pits at or Above Tubesheet
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1986-004, :on 860105,RCS Overpressure Protection Sys Would Not Permit Opening of Four motor-operated Valves. Caused by Failure of Temp Bistable for Valves 596 & 598 to Reset.Temp Bistable Recalibr & Retested |
- on 860105,RCS Overpressure Protection Sys Would Not Permit Opening of Four motor-operated Valves. Caused by Failure of Temp Bistable for Valves 596 & 598 to Reset.Temp Bistable Recalibr & Retested
| | | 05000213/LER-1986-005, :on 860115,electric Switchgear Room Halon Fire Suppression Sys Automatic Actuation Capability Removed from Svc to Prevent Inadvertent Discharge of Halon During Mod of Inadequate Core Cooling Instrumentation Sys |
- on 860115,electric Switchgear Room Halon Fire Suppression Sys Automatic Actuation Capability Removed from Svc to Prevent Inadvertent Discharge of Halon During Mod of Inadequate Core Cooling Instrumentation Sys
| | | 05000213/LER-1986-007, :on 860207,turbine Bldg Crane Bay Deluge Spray Sys Not Tested Per Tech Spec Requirement.Caused by Unfamiliarity of Personnel W/Details of Fire Protection Sys. Procedures Reviewed/Written & Implemented |
- on 860207,turbine Bldg Crane Bay Deluge Spray Sys Not Tested Per Tech Spec Requirement.Caused by Unfamiliarity of Personnel W/Details of Fire Protection Sys. Procedures Reviewed/Written & Implemented
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1986-008, :on 860205,discovered That 27 Containment Electrical Penetrations Not Leak Tested Properly.Caused by Procedures Not Updated to Reflect Design Changes.Procedure Re Integration Valve Verification Changed |
- on 860205,discovered That 27 Containment Electrical Penetrations Not Leak Tested Properly.Caused by Procedures Not Updated to Reflect Design Changes.Procedure Re Integration Valve Verification Changed
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1986-010, :on 860226,unauthorized Maint Electrician Found Exiting Locked High Radiation Area.Caused by Failure of Mgt Personnel to Provide Adequate Instruction to Workers on Use & Control of High Radiation Key |
- on 860226,unauthorized Maint Electrician Found Exiting Locked High Radiation Area.Caused by Failure of Mgt Personnel to Provide Adequate Instruction to Workers on Use & Control of High Radiation Key
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1986-011, :on 860228,discovered That Fire Protection Water Sys Line & Sprinkler Line Inadvertently Isolated on 860226.Caused by Misinterpretation of Tech Specs.Hourly Fire Watch Established |
- on 860228,discovered That Fire Protection Water Sys Line & Sprinkler Line Inadvertently Isolated on 860226.Caused by Misinterpretation of Tech Specs.Hourly Fire Watch Established
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1986-012, :on 860226,discovered That Fuel Assembly R-01 Removed from Core & Dropped.Caused by Bent Fuel Alignment Pin.Nonessential Personnel Evacuated from Containment.Pin Repaired |
- on 860226,discovered That Fuel Assembly R-01 Removed from Core & Dropped.Caused by Bent Fuel Alignment Pin.Nonessential Personnel Evacuated from Containment.Pin Repaired
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000213/LER-1986-014, :on 860308,electric Fire Pump Removed from Svc Due to High Vibrations & Fluctuating Discharge Pressure Noted During 860306 Surveillance Test.Caused by Worn Pump Wear Rings.Pump Repairs Initiated |
- on 860308,electric Fire Pump Removed from Svc Due to High Vibrations & Fluctuating Discharge Pressure Noted During 860306 Surveillance Test.Caused by Worn Pump Wear Rings.Pump Repairs Initiated
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1986-015, :on 860319,eddy Current Insp Performed on Rod Cluster Control Assemblies (Rcca) Indicated Clad Cracking, Sliding Wear & Guide Card Wear.Worst Case Rccas Replaced W/Onsite Spares |
- on 860319,eddy Current Insp Performed on Rod Cluster Control Assemblies (Rcca) Indicated Clad Cracking, Sliding Wear & Guide Card Wear.Worst Case Rccas Replaced W/Onsite Spares
| | | 05000213/LER-1986-017, :on 860317,inoperable Fire Barrier Penetration Seals Found During 18-month Surveillance Insp.Caused by Degraded Grout Seals.Penetrations Temporarily Sealed.W/ |
- on 860317,inoperable Fire Barrier Penetration Seals Found During 18-month Surveillance Insp.Caused by Degraded Grout Seals.Penetrations Temporarily Sealed.W/
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1986-019, :on 860506,tube in Steam Generator 2 Not Plugged.Caused by Typo in Procedure & Inadequate Review Process.Procedure Sur 5.7-82 Will Be Revised to Include Signed Double Verification |
- on 860506,tube in Steam Generator 2 Not Plugged.Caused by Typo in Procedure & Inadequate Review Process.Procedure Sur 5.7-82 Will Be Revised to Include Signed Double Verification
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1986-020, :on 860508,automatic Reactor & Turbine Trip Occurred During Turbine Vibration Tests.Caused by Operator Accelerating Turbine at Too High Rate.Shift Supervisor & Operators Counseled |
- on 860508,automatic Reactor & Turbine Trip Occurred During Turbine Vibration Tests.Caused by Operator Accelerating Turbine at Too High Rate.Shift Supervisor & Operators Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000213/LER-1986-021, :on 860524,one of Four ex-core Channels Failed to Meet Acceptance Criteria for Dropped Rod Load Runback Setpoint.Caused by Setpoint Drift.Setpoint Recalibr & Weekly Surveillances Established |
- on 860524,one of Four ex-core Channels Failed to Meet Acceptance Criteria for Dropped Rod Load Runback Setpoint.Caused by Setpoint Drift.Setpoint Recalibr & Weekly Surveillances Established
| | | 05000213/LER-1986-022, :on 860517,dropped rod-turbine Load Runback Initiated While Adjusting Setpoint Gains.Caused by Adjusting Gain Too Rapidly.Load Runback Signal Reset Manually |
- on 860517,dropped rod-turbine Load Runback Initiated While Adjusting Setpoint Gains.Caused by Adjusting Gain Too Rapidly.Load Runback Signal Reset Manually
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000213/LER-1986-023, :on 860518,nuclear Instrumentation power-range Channel 34 Spuriously Generated Dropped rod-load Runback Signal.Caused by Load Limiter Mechanically Binding.Load Limiter Clutch Adjusted |
- on 860518,nuclear Instrumentation power-range Channel 34 Spuriously Generated Dropped rod-load Runback Signal.Caused by Load Limiter Mechanically Binding.Load Limiter Clutch Adjusted
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000213/LER-1986-024, :on 860609,at 100% Power,Dropped Rod Turbine Load Runback Initiated.Caused by Spurious Signal in Power Range 34.Load Runback Reset Manually & Power Range Channels Will Be Replaced |
- on 860609,at 100% Power,Dropped Rod Turbine Load Runback Initiated.Caused by Spurious Signal in Power Range 34.Load Runback Reset Manually & Power Range Channels Will Be Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000213/LER-1986-025, :on 860619,reactor Trip Occurred Due to Fuse Replacement in Failed Nuclear Instrumentation Sys Channel Drawer Power Supply Generating Voltage Dip.Caused by Elevated Control Room Temp |
- on 860619,reactor Trip Occurred Due to Fuse Replacement in Failed Nuclear Instrumentation Sys Channel Drawer Power Supply Generating Voltage Dip.Caused by Elevated Control Room Temp
| 10 CFR 50.73(a)(2) | | 05000213/LER-1986-026, :on 860622,while in Mode 1,reactor Trip Occurred When Power Increased Above 10%.Caused by Ceiling Tile Stuck in Relay,Causing RCS Low Flow Indication.Debris Removed & Scram Circuits Tested |
- on 860622,while in Mode 1,reactor Trip Occurred When Power Increased Above 10%.Caused by Ceiling Tile Stuck in Relay,Causing RCS Low Flow Indication.Debris Removed & Scram Circuits Tested
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000213/LER-1986-027, :on 860606 & 17,two Unit Trips from 100% Power Manually Initiated on Low Suction Pressure to Steam Generator Feedwater Pumps.Caused by Failure of Stem/Actuator Coupling on Heater Drain Tank Control Valve |
- on 860606 & 17,two Unit Trips from 100% Power Manually Initiated on Low Suction Pressure to Steam Generator Feedwater Pumps.Caused by Failure of Stem/Actuator Coupling on Heater Drain Tank Control Valve
| 10 CFR 50.73(a)(2) | | 05000213/LER-1986-028, :on 860610,switchgear Room Halon Sys Declared Inoperable.Caused by Failure to Perform Adequate Retest of Sys Mod & Document Basis for Test Waiver.Continuous Fire Watch Posted |
- on 860610,switchgear Room Halon Sys Declared Inoperable.Caused by Failure to Perform Adequate Retest of Sys Mod & Document Basis for Test Waiver.Continuous Fire Watch Posted
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1986-028-01, :on 860610,switchgear Room Halon Sys Declared Inoperable.Caused by Failure to Perform Adequate Retest. Completion of long-term Corrective Mod Deferred Until 1987 Refueling Outage |
- on 860610,switchgear Room Halon Sys Declared Inoperable.Caused by Failure to Perform Adequate Retest. Completion of long-term Corrective Mod Deferred Until 1987 Refueling Outage
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1986-029, :on 860617,MSIV Failed to Meet Surveillance Procedure Acceptance Criteria.Caused by Inadequate Initial Design of MSIV Accumulator.Accumulator Will Be Upgraded to Ensure safety-related Operability |
- on 860617,MSIV Failed to Meet Surveillance Procedure Acceptance Criteria.Caused by Inadequate Initial Design of MSIV Accumulator.Accumulator Will Be Upgraded to Ensure safety-related Operability
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000213/LER-1986-030, :on 860627,during Operation in Mode 1,dropped rod-load Runback Signal Generated Spuriously on Channel 34 of Nuclear Instrumentation Sys.No Rod Motion in Progress. Cause Not Yet Defined.Sys Will Be Replaced |
- on 860627,during Operation in Mode 1,dropped rod-load Runback Signal Generated Spuriously on Channel 34 of Nuclear Instrumentation Sys.No Rod Motion in Progress. Cause Not Yet Defined.Sys Will Be Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000213/LER-1986-032, :on 860710,one of Four ex-core Channels Failed to Meet Acceptance Criteria for Dropped Rod Load Runback Setpoint.Caused by Setpoint Drift.Setpoint Recalibr |
- on 860710,one of Four ex-core Channels Failed to Meet Acceptance Criteria for Dropped Rod Load Runback Setpoint.Caused by Setpoint Drift.Setpoint Recalibr
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000213/LER-1986-033, :on 860715,w/plant in Mode 4,RCS Low Temp Overpressurization Protection (Ltod) Sys Interlock Would Not Permit Opening One Train of LTOP Isolation Valves.Tech Spec Temp Limits Reduced |
- on 860715,w/plant in Mode 4,RCS Low Temp Overpressurization Protection (Ltod) Sys Interlock Would Not Permit Opening One Train of LTOP Isolation Valves.Tech Spec Temp Limits Reduced
| | | 05000213/LER-1986-035, :on 860715,NRC Notified of Plan to Shutdown & Plug 119 Tubes in 3 of 4 Steam Generators Based on Sample of 575 Tubes W/Undefined Eddy Current Signals.Caused by Mfg Defects.Monitoring & Repair Program Initiated |
- on 860715,NRC Notified of Plan to Shutdown & Plug 119 Tubes in 3 of 4 Steam Generators Based on Sample of 575 Tubes W/Undefined Eddy Current Signals.Caused by Mfg Defects.Monitoring & Repair Program Initiated
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000213/LER-1986-036, :on 860708,while Metering Charging Pump Out of Svc,Charging Pump a Taken Out of Svc Due to Broken Shaft. Caused by Metal Fatigue.Plant Placed in Hot Shutdown. Procedures Re Pumps Revised |
- on 860708,while Metering Charging Pump Out of Svc,Charging Pump a Taken Out of Svc Due to Broken Shaft. Caused by Metal Fatigue.Plant Placed in Hot Shutdown. Procedures Re Pumps Revised
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1986-037, :on 860708,opening of Manual Isolation Valves Conflicted W/Tech Spec Definition of Containment Integrity. Caused by Imprecise Wording & Misinterpretation of Tech Specs.Surveillance Procedure Revised |
- on 860708,opening of Manual Isolation Valves Conflicted W/Tech Spec Definition of Containment Integrity. Caused by Imprecise Wording & Misinterpretation of Tech Specs.Surveillance Procedure Revised
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1986-038, :on 860806,w/unit at 94% Rated Thermal Power, Variations on in-core Axial Offset Monitoring Channels Observed.Caused by Invalidated in-core/ex-core Axial Offset Correlation.Correlation Performed |
- on 860806,w/unit at 94% Rated Thermal Power, Variations on in-core Axial Offset Monitoring Channels Observed.Caused by Invalidated in-core/ex-core Axial Offset Correlation.Correlation Performed
| 10 CFR 50.73(a)(2)(i) | | 05000213/LER-1986-040, :on 860724,discovered That No 3-inch Diameter or Equivalent Opening Present in RCS Pressure Boundary During Low Temp Surveillance Test.Caused by Conflicting Tech Spec Test.Performance Interval Changed |
- on 860724,discovered That No 3-inch Diameter or Equivalent Opening Present in RCS Pressure Boundary During Low Temp Surveillance Test.Caused by Conflicting Tech Spec Test.Performance Interval Changed
| | | 05000213/LER-1986-041, :on 860830,feedwater Regulating Valve FW-FCV-1301-1 to Steam Generator 1 Became Stuck Open,Causing Manual Reactor Trip.Caused by Failure of Weld Between Stem & Plug.Failed Part of Weld Sent to Mfg |
- on 860830,feedwater Regulating Valve FW-FCV-1301-1 to Steam Generator 1 Became Stuck Open,Causing Manual Reactor Trip.Caused by Failure of Weld Between Stem & Plug.Failed Part of Weld Sent to Mfg
| 10 CFR 50.73(a)(2) | | 05000213/LER-1986-042, :on 861016,discovered Chain on Valve SI-MOV-24 Disengaged & Lock Open.Caused by Operator Error in Using Faulty Lock & Failure to Check Status of Lock.Further Operator Training Re Lock Surveillance Planned |
- on 861016,discovered Chain on Valve SI-MOV-24 Disengaged & Lock Open.Caused by Operator Error in Using Faulty Lock & Failure to Check Status of Lock.Further Operator Training Re Lock Surveillance Planned
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1986-043, :on 861108,wide-range Noble Gas Stack Monitor RMS-14B Failed Low.Caused by Improper Setting for New Photomultiplier Tube Preventing Pulses from Passing Through & Being Registered by Electronics |
- on 861108,wide-range Noble Gas Stack Monitor RMS-14B Failed Low.Caused by Improper Setting for New Photomultiplier Tube Preventing Pulses from Passing Through & Being Registered by Electronics
| | | 05000213/LER-1986-044, :on 861130,feedwater Control Valve for Loop 3 Failed in Closed Position,Resulting in Automatic Reactor Trip.Caused by Inadequate Control Over Repair Activities. Improved Job Planning Initiated |
- on 861130,feedwater Control Valve for Loop 3 Failed in Closed Position,Resulting in Automatic Reactor Trip.Caused by Inadequate Control Over Repair Activities. Improved Job Planning Initiated
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000213/LER-1986-045, :on 861114,portion of Turbine Bldg Sprinkler Sys Removed from Svc for More than 14 Days to Facilitate App R Mods Resulting from Listed Insp.Continuous Fire Watch Posted.Work Will Be Completed by 870101 |
- on 861114,portion of Turbine Bldg Sprinkler Sys Removed from Svc for More than 14 Days to Facilitate App R Mods Resulting from Listed Insp.Continuous Fire Watch Posted.Work Will Be Completed by 870101
| | | 05000213/LER-1986-047, :on 861207 & 08,reactor Coolant Loop 1 Lined Up W/Loop Stop Valves Open & Reactor Coolant Pump Shut Down, Causing Unanalyzed Configuration.Caused by Failure to Translate Assumptions Into Procedures |
- on 861207 & 08,reactor Coolant Loop 1 Lined Up W/Loop Stop Valves Open & Reactor Coolant Pump Shut Down, Causing Unanalyzed Configuration.Caused by Failure to Translate Assumptions Into Procedures
| 10 CFR 50.73(a)(2)(iii)(A) | | 05000213/LER-1986-048, :on 861212,discovered That Adequate Core Cooling Could Not Be Insured for Intermediate Break LOCA Postulated in Core Deluge Sys.Caused by Inaccurate Tech Specs.Sys Mods Initiated |
- on 861212,discovered That Adequate Core Cooling Could Not Be Insured for Intermediate Break LOCA Postulated in Core Deluge Sys.Caused by Inaccurate Tech Specs.Sys Mods Initiated
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
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