LER-1981-001, Updated LER 81-001/01T-1:on 810109,turbine Runback & Automatic Rod Withdrawal Block Protection Defeated W/Power Range Channel N41 Being Out of Svc.Caused by Improper Rod Drop Analysis.Administrative Controls Revised |
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NRC FORM 366
" UPDATE REPORT - PREVIOUS REPORT DATE 1/23/81" u.S. NUCLEAR REGULATORY COMMISSION (7-77 F LICENSEE EVENT REPORT 0
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8 60 61 DOCK ET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h l o l 2 l l0n January 9,1981, with the unit at 100% power, it was determined that operation with l g o,3, lthe RPI System input to the turbine runback and auto rod withdrawal defeated and power l
, o g,, [ range channel N41 input out of service is contrary to the assumptions in the safety l
, o g g analysis prepared during the fuel reload safety evaluation.
Still the probability of l l
g lnot sensing a dropped rod is small since three of the power range detectors were l
l o l, l [ ope rab le. 'Ihis occurrence is reportable pursuant to Technical Specifications l
.9.2.a(6).
No adverse consequences resulted from the above condition.
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were implemented f ollowing this event, will be revised to delete the 70% power m l restriction.
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6 SUPPLEMENTAL INFORMATION FOR LICENSEE EVENT UPDATE REPORT 81-001, REVISION 1 I.
Cause Description and Analysis, On January 7,1981, the Power Range Channel N41 was taken out of service.
Previous to this, the Rod Position Indication System (RPI) input to the turbine runback system and auto rod withdrawal circuit had been defeated due to spurious rod drop indications in an effort to prevent unnecessary thermal cycles to Reactor Coolant System (RCS) components. On January 9, 1981, it was determined, by a review of the H. B. Robinson, Unit No. 2 FSAR and Fuel Reload Safety Evaluation, that both of these documents assume that turbine runback and auto rod withdrawal defeat occur follow-ing a control rod drop.
These systems are actuated by any one RPI bottom signal or a rapid flux decrease on any one power range channel.
By having N41 inoperable, a few rods located in the core region nearest N41 might not be detected by the other three power range detectors if they were to drop.
Based on this review, therefore, the event was identified as reportabic pursuant to Technical Specification 6.9.2.a.6.
Since an RCCA drop event did not occur during this time, no adverse consequences resulted from the above situation.
II.
Corrective Action
All atfected systems were immediately returned to service when it was determined that having both inputs to the turbine runback and auto rod withdrawal systems defeated may be contrary to the FSAR and fuel reload
safety analysis
III. Correct ive Action To Prevent Recurrence A review of this issue has been completed, and an analysis has been performed by the fuel supplier.
On the basis of this analysis, it has i
been concluded that even without the turbine runback and automatic rod withdrawal block protection systems, H. B. Robinson, Unit No. 2 will have acceptable thermal margin with respect to a dropped rod transient.
The results of this analysis also envelope the current reduced temper-nture and power operation.
Following this event, administrative controis were implemented to ensure that both turbine runback and auto rod withdrawal block initiating circuits are not defeated at power levels greater than 70%.
Based on the analysis described above, the administrative controls governing the RPI and power range nuclear instrumentation inputs to be the tudi tne runback and automatic rod withdrawal block circuits will be revised to delete the requirement to reduce power to 70%.
In general, this action will be taken when instrument problems in the rod position indication system cause false rod bottom signals leading to needless turbine 1.nbacks, or when a power range NIS channel fails or is taken out of service for maintenance and/or testing.
The intent of the remaining controls will be to minimize the time these inputs are blocked. Normal operation will continue to be with the runback initiating circuits in place. No further action is considered necessary.
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| 05000261/LER-1981-001, Updated LER 81-001/01T-1:on 810109,turbine Runback & Automatic Rod Withdrawal Block Protection Defeated W/Power Range Channel N41 Being Out of Svc.Caused by Improper Rod Drop Analysis.Administrative Controls Revised | Updated LER 81-001/01T-1:on 810109,turbine Runback & Automatic Rod Withdrawal Block Protection Defeated W/Power Range Channel N41 Being Out of Svc.Caused by Improper Rod Drop Analysis.Administrative Controls Revised | | | 05000261/LER-1981-002, Updated LER 81-002/01T-2:on 810113,review of Svc Water Sys Revealed Potential Unmonitored Release Path on Svc Water Return Lines from Containment for Hydrogen Vent Header Motor Coolers.Caused by Design Error.Sys Will Be Modifie | Updated LER 81-002/01T-2:on 810113,review of Svc Water Sys Revealed Potential Unmonitored Release Path on Svc Water Return Lines from Containment for Hydrogen Vent Header Motor Coolers.Caused by Design Error.Sys Will Be Modified | | | 05000261/LER-1981-002-01, /01T-3:on 810113,review of Svc Water Sys Revealed Potential Unmonitored Release Path to Environ.Caused by Lack of Radiation Monitoring on Svc Water Return Lines from Containment.Discharge Lines Modified | /01T-3:on 810113,review of Svc Water Sys Revealed Potential Unmonitored Release Path to Environ.Caused by Lack of Radiation Monitoring on Svc Water Return Lines from Containment.Discharge Lines Modified | | | 05000261/LER-1981-004, Forwards Updated LER 81-004/03L-1 | Forwards Updated LER 81-004/03L-1 | | | 05000261/LER-1981-004-03, Primary Coolant Sys Leak Found.Caused by Sample Cooler Tube Bundle Leakage Due to Normal Wear.Bundle Replaced.Review of Maint Records Revealed No Generic Problems | Primary Coolant Sys Leak Found.Caused by Sample Cooler Tube Bundle Leakage Due to Normal Wear.Bundle Replaced.Review of Maint Records Revealed No Generic Problems | | | 05000261/LER-1981-006-01, /01T-0:on 820715,motor Cooler Leak Found in Containment Fan Cooler HVH-2.HVH-2 Shut Down & Svc Water to Unit Isolated.Caused by Corrosion/Erosion of Cooler Tubing. Leak Repaired & Motor Coolers Will Be Replaced W/New Units | /01T-0:on 820715,motor Cooler Leak Found in Containment Fan Cooler HVH-2.HVH-2 Shut Down & Svc Water to Unit Isolated.Caused by Corrosion/Erosion of Cooler Tubing. Leak Repaired & Motor Coolers Will Be Replaced W/New Units | | | 05000261/LER-1981-007, Updated LER 81-007/01T-1:on 810122,potential Modeling Error in ECCS Model Used for LOCA Analysis Reported.Caused by Shift in Peak Clad Temp.New ECCS Analysis Performed in Aug 1981.No Impact on Public Health & Safety | Updated LER 81-007/01T-1:on 810122,potential Modeling Error in ECCS Model Used for LOCA Analysis Reported.Caused by Shift in Peak Clad Temp.New ECCS Analysis Performed in Aug 1981.No Impact on Public Health & Safety | | | 05000261/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000261/LER-1981-008-03, /03L-0:on 810225 While Performing Monthly Periodic Test CPL-PT-5.5,Hagan Signal Comparator Module Found Inoperable.Cause Not Stated.Comparator Replaced | /03L-0:on 810225 While Performing Monthly Periodic Test CPL-PT-5.5,Hagan Signal Comparator Module Found Inoperable.Cause Not Stated.Comparator Replaced | | | 05000261/LER-1981-013, Forwards Updated LER 81-013/03L-1 | Forwards Updated LER 81-013/03L-1 | | | 05000261/LER-1981-013-03, Determined Containment Isolation Valves Not Tested in Required Manner.Seven of Eight Valves Functioning as Designed.Eighth Valve Tested & Shown Operable.Test Undergoing Revision | Determined Containment Isolation Valves Not Tested in Required Manner.Seven of Eight Valves Functioning as Designed.Eighth Valve Tested & Shown Operable.Test Undergoing Revision | | | 05000261/LER-1981-014-03, /03L-0:on 810523,discovered That Hagan Summator PM-446B Had Shifted Nonconservatively Approx 3%.Caused by Failure of Filter Capacitor Due to Normal Wear.Faulty Capacitor Replaced | /03L-0:on 810523,discovered That Hagan Summator PM-446B Had Shifted Nonconservatively Approx 3%.Caused by Failure of Filter Capacitor Due to Normal Wear.Faulty Capacitor Replaced | | | 05000261/LER-1981-014, Forwards LER 81-014/03L-0 | Forwards LER 81-014/03L-0 | | | 05000261/LER-1981-015, Forwards LER 81-015/03L-0 | Forwards LER 81-015/03L-0 | | | 05000261/LER-1981-015-03, /03L-0:on 810525,computer Box FM-475 Found to Be Out of Acceptable Tolerances & Several Checkpoints Showed Erratic Readings During Loop a Steam Flow Channel Investigation.Caused by Two Worn Electronic Components | /03L-0:on 810525,computer Box FM-475 Found to Be Out of Acceptable Tolerances & Several Checkpoints Showed Erratic Readings During Loop a Steam Flow Channel Investigation.Caused by Two Worn Electronic Components | | | 05000261/LER-1981-016, Forwards LER 81-016/03L-0 | Forwards LER 81-016/03L-0 | | | 05000261/LER-1981-016-03, /03L-0:on 810611,during Startup,Motor Driven Auxiliary Feedwater Pump a Tripped Due to Low Discharge Pressure While Feeding Steam Generators.Event Reoccurred on 810716.Caused by Backleakage Through Discharge Valve AFW-40 | /03L-0:on 810611,during Startup,Motor Driven Auxiliary Feedwater Pump a Tripped Due to Low Discharge Pressure While Feeding Steam Generators.Event Reoccurred on 810716.Caused by Backleakage Through Discharge Valve AFW-40 | | | 05000261/LER-1981-017-03, /03L-0:on 810619,auxiliary Feedwater Pump a Tripped on Low Discharge Pressure.Caused by Improper Throttle Setting of Discharge Valve.Valve Repositioned | /03L-0:on 810619,auxiliary Feedwater Pump a Tripped on Low Discharge Pressure.Caused by Improper Throttle Setting of Discharge Valve.Valve Repositioned | | | 05000261/LER-1981-017, Forwards LER 81-017/03L-0 | Forwards LER 81-017/03L-0 | | | 05000261/LER-1981-018-03, /03L-0:on 810701,Channel I (PI-474) of a Steam Generator Steam Line Pressure Indicated High Compared to Two Redundant Channels.Caused by Throttled Root Isolation Valve MSV-14.Valve Reopened | /03L-0:on 810701,Channel I (PI-474) of a Steam Generator Steam Line Pressure Indicated High Compared to Two Redundant Channels.Caused by Throttled Root Isolation Valve MSV-14.Valve Reopened | | | 05000261/LER-1981-018, Forwards LER 81-018/03L-0 | Forwards LER 81-018/03L-0 | | | 05000261/LER-1981-019-03, /03L-0:on 810705,w/unit at 95% Power,Svc Water Booster Pump (Swbp) a Motor Tripped.On 810706,SWBP a Motor Tripped Again.Caused by Normal Wear of Motor Bearings & Possible Breaker Problem,Respectively | /03L-0:on 810705,w/unit at 95% Power,Svc Water Booster Pump (Swbp) a Motor Tripped.On 810706,SWBP a Motor Tripped Again.Caused by Normal Wear of Motor Bearings & Possible Breaker Problem,Respectively | | | 05000261/LER-1981-019, Forwards LER 81-019/03L-0 | Forwards LER 81-019/03L-0 | | | 05000261/LER-1981-020-03, /03L-0:on 810902,containment Spray Check Valve SI-890B & Associated Flow Path Declared Inoperable.Caused by Failure to Perform Post Maint Testing Prior to Startup Due to Oversight.Valve Tested.Procedures Will Be Revised | /03L-0:on 810902,containment Spray Check Valve SI-890B & Associated Flow Path Declared Inoperable.Caused by Failure to Perform Post Maint Testing Prior to Startup Due to Oversight.Valve Tested.Procedures Will Be Revised | | | 05000261/LER-1981-020, Forwards LER 81-020/03L-0 | Forwards LER 81-020/03L-0 | | | 05000261/LER-1981-021, Forwards LER 81-021/01T-0 | Forwards LER 81-021/01T-0 | | | 05000261/LER-1981-021-01, /01T-0:on 810925,w/unit at 50% Power,Group 2 Control Bank D Control Rods Were Inoperable & Reactor Shutdown Commenced.Caused by Faulty Input/Output Amplifier Printed Circuit Card in Control Rod Logic Cabinet | /01T-0:on 810925,w/unit at 50% Power,Group 2 Control Bank D Control Rods Were Inoperable & Reactor Shutdown Commenced.Caused by Faulty Input/Output Amplifier Printed Circuit Card in Control Rod Logic Cabinet | | | 05000261/LER-1981-022, Forwards LER 81-022/03L-0 | Forwards LER 81-022/03L-0 | | | 05000261/LER-1981-022-03, /03L-0:on 811015,w/unit at 50% Power,Lower than Normal Temp Indication Noted on Strip Chart Recorder for Valves on Discharge Line of Boron Injection Tank.Caused by Broken Wire Splice in Heat Tracing Circuit 70 | /03L-0:on 811015,w/unit at 50% Power,Lower than Normal Temp Indication Noted on Strip Chart Recorder for Valves on Discharge Line of Boron Injection Tank.Caused by Broken Wire Splice in Heat Tracing Circuit 70 | | | 05000261/LER-1981-023-03, /03L-0:on 811022,at 50% Power,Safety Injection Pump Started from Control Room for Routine Filling of Accumulators & Circuit Breaker Tripped.Cause Unidentified. No Further Action Considered Necessary | /03L-0:on 811022,at 50% Power,Safety Injection Pump Started from Control Room for Routine Filling of Accumulators & Circuit Breaker Tripped.Cause Unidentified. No Further Action Considered Necessary | | | 05000261/LER-1981-023, Forwards LER 81-023/03L-0 | Forwards LER 81-023/03L-0 | | | 05000261/LER-1981-024, Forwards LER 81-024/03L-0 | Forwards LER 81-024/03L-0 | | | 05000261/LER-1981-024-03, /03L-0:on 811028,heat Tracing for Motor Operated Valves on Discharge Line of Boron Injection Tank Found Failed.Caused by Short to Ground Resulting from Insulation Repairs.Personnel Cautioned Re Insulation | /03L-0:on 811028,heat Tracing for Motor Operated Valves on Discharge Line of Boron Injection Tank Found Failed.Caused by Short to Ground Resulting from Insulation Repairs.Personnel Cautioned Re Insulation | | | 05000261/LER-1981-025-03, /03L-0:on 811102,emergency Diesel Generator B Failed to Start Manually.Caused by Loss of Prime in Fuel Oil Sys,Possibly Due to Debris in Ball Check Valve.Generator Returned to Svc | /03L-0:on 811102,emergency Diesel Generator B Failed to Start Manually.Caused by Loss of Prime in Fuel Oil Sys,Possibly Due to Debris in Ball Check Valve.Generator Returned to Svc | | | 05000261/LER-1981-025, Forwards LER 81-025/03L-0 | Forwards LER 81-025/03L-0 | | | 05000261/LER-1981-026, Forwards LER 81-026/01T-0 | Forwards LER 81-026/01T-0 | | | 05000261/LER-1981-026-01, /01T-0:on 811120,primary to Secondary Leak of Approx 1.5 Gpm Found in Steam Generator A.Caused by Leaking Explosive Plug.Plant Shut Down,Plug Removed & Weld Repaired on 811127 | /01T-0:on 811120,primary to Secondary Leak of Approx 1.5 Gpm Found in Steam Generator A.Caused by Leaking Explosive Plug.Plant Shut Down,Plug Removed & Weld Repaired on 811127 | | | 05000261/LER-1981-028-03, /03L-0:on 811125,steam Generator low-low Level Trip & Alarm Bistables BS-494-A1 & BS-494-A2 Found to Be Inoperable During Periodic Test PT-5.5 W/Unit at Cold Shutdown.Caused by Failure of Instrument Channel LI-494 | /03L-0:on 811125,steam Generator low-low Level Trip & Alarm Bistables BS-494-A1 & BS-494-A2 Found to Be Inoperable During Periodic Test PT-5.5 W/Unit at Cold Shutdown.Caused by Failure of Instrument Channel LI-494 | | | 05000261/LER-1981-028, Forwards LER 81-028/03L-0 | Forwards LER 81-028/03L-0 | | | 05000261/LER-1981-029, Forwards LER 81-029/03L-0 | Forwards LER 81-029/03L-0 | | | 05000261/LER-1981-029-03, /03L-0:on 811130,w/unit at Hot Shutdown,Leak Was Discovered in Chemical & Vol Control Sys.Caused by Failed bonnet-to-body Gasket on Valve CVC-291.Gasket Replaced | /03L-0:on 811130,w/unit at Hot Shutdown,Leak Was Discovered in Chemical & Vol Control Sys.Caused by Failed bonnet-to-body Gasket on Valve CVC-291.Gasket Replaced | | | 05000261/LER-1981-030-03, /03L-0:on 811130,emergency Diesel Generator B Failed to Reach Rated Output Voltage Following Automatic Start Initiated by Safety Injection Signal.Caused by Faulty auto-voltage Adjust Reostat.Failure Due to Normal Wear | /03L-0:on 811130,emergency Diesel Generator B Failed to Reach Rated Output Voltage Following Automatic Start Initiated by Safety Injection Signal.Caused by Faulty auto-voltage Adjust Reostat.Failure Due to Normal Wear | | | 05000261/LER-1981-030, Forwards LER 81-030/03L-0 | Forwards LER 81-030/03L-0 | | | 05000261/LER-1981-031-01, /01T-0:on 811201,pressurizer Power Operated Relief Valve Block Valves Were Determined Not to Meet Design Specs. Valve Motor Operators Failed to Shut Valves Completely Following 811130 Transient.Block Valves Closed Manually | /01T-0:on 811201,pressurizer Power Operated Relief Valve Block Valves Were Determined Not to Meet Design Specs. Valve Motor Operators Failed to Shut Valves Completely Following 811130 Transient.Block Valves Closed Manually | | | 05000261/LER-1981-032-03, /03L-0:on 811205,boric Acid Transfer Pump a Tripped & Was Declared Inoperable.Caused by Error in Valve Lineup Procedure & Open Winding in Transfer Pump Motor. Procedure Revised & Motor Replaced | /03L-0:on 811205,boric Acid Transfer Pump a Tripped & Was Declared Inoperable.Caused by Error in Valve Lineup Procedure & Open Winding in Transfer Pump Motor. Procedure Revised & Motor Replaced | | | 05000261/LER-1981-032, Forwards LER 81-032/03L-0 | Forwards LER 81-032/03L-0 | | | 05000261/LER-1981-033, Forwards LER 81-033/01T-0 | Forwards LER 81-033/01T-0 | | | 05000261/LER-1981-033-01, /01T-0:on 811228,error in Tech Spec Heatup & Cooldown Curves Found to Be Not Reported to Nrc.Caused by Administrative Reporting Failure & Errors in Calculation. Info Will Be Reported as Tech Spec Change by 820131 | /01T-0:on 811228,error in Tech Spec Heatup & Cooldown Curves Found to Be Not Reported to Nrc.Caused by Administrative Reporting Failure & Errors in Calculation. Info Will Be Reported as Tech Spec Change by 820131 | | | 05000261/LER-1981-034-03, /03L-0:on 811211,loop 2 Steamline Pressure Channel Indicated Higher than Other Channels.Caused by Frozen Sensing Lines in Pressure Transmitter & Failure to Return Freeze Protection Circuit to Svc After Maint | /03L-0:on 811211,loop 2 Steamline Pressure Channel Indicated Higher than Other Channels.Caused by Frozen Sensing Lines in Pressure Transmitter & Failure to Return Freeze Protection Circuit to Svc After Maint | | | 05000261/LER-1981-034, Forwards LER 81-034/03L-0 | Forwards LER 81-034/03L-0 | |
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