LER-1981-047, /03L-0:on 810715,required 4-h Reactor Coolant Samples Were Not Taken.Caused by Personnel Misunderstanding. Sample Taken & Analyzed & Parties Instructed of Need for Effective Communication |
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ZRC FCCM 366 U.S. NUCLEAR REGULATORY COMMISSitN lam LICENSFE EVENT REPORT e
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- 7 8 9 UCENSEE CODE 14 15 UCE.SE NUMBER 25 26 UCENSE TYPE JO 57 CAT 58
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8 60 61 DOCKET NUMBER 68 E3 EVENT DATE 74 75 REPORT DATE 80 EVEf4T DESCRIPTION AND PROBA8LE CONSEQUENCES h ll o 12 l l During normal dnit startup, the required 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Rx coolant samples were not taken l
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This was of minimal safety significance since, the grab sample results; l
ga;,g g for chloride and conductivity were acceptable and the conductivity r2 corder readings g
were stable. There was no effect on public health or safety. Previous occurrences:
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9 10 11 12 13 18 19 20 SEOUENTIAL OCCURRENCE REPORT REVISION LER/Ro EVENT YEAR REPORT No.
CODE TYPE NO.
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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS
!li lo l l Because of an apparent misunderstanding with the shift engineere office on the after-J g noon of 7/15/81, the lab discontinued 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Rx water sampling. Following discovery g ; of the error at 0430 or. 7/16/81, a sample was immediately taken and analyzed. Both
,,,,,l parties were briefed on the need for effective communication. No further action con-l sidered necessary.
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% POWER OTHER STATUS D1 O Y
ciSCOVERY DESCRIPTION f7Tsl I c ig l 0l 0l 1[gl N/A l
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A TIVITY CO TENT AMOUNT OF ACTIVITY @ l F.ELEASED OF RELEASE LOCATION OF RELEASE W @ lZ l@l N/A l
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8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUM8ER TYPE
DESCRIPTION
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P PERSONNE L INJU IES NUV8ER DESCRtPTION l3 la l [0 l0 l0l@l N/A l
7 8 9 11 12 80 LOSS OP OR DAMAGE TO PAcauTV TYPE DESCRl* TION 11191(,Zjhl l
N 8108210412 810813 7
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10 80 PusuciTv PDR ADOCK 05000237 NHC USE ONLY 45 ISSUED
DESCRIPTION
PDR 12101[,,_N,jhl N/A l
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8 9 1C 68 69 80 3 Gerald W. Bergan 815-942-2920 Ext. 529 o
NAME CF PRFDARFR PHONE
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(,_ )7 DEVIATION REPORT
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Commonwealth Ed.ison STA UNIT YEAR N O.
o 2-78 AR1 Il TI TLE OF DEV! ATION OCCU RRED 7/16/81 0445 Failure To Take Rx Coolant Samples Every 4 Hours DATE TIME SYSTEM AFFECTED
PLANT CONDITIONS
TESilNGO Rx Water Chemistry MODE StartuP PWR ivwT) 25.0
, LOAD (MWE) 0 YES NO DESCRIPflON OF EVENT During reactor startup, it was discovered that the last reactor coolant sample had been taken~at 1155 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.394775e-4 months <br /> on 7/15/81.
Tech. Specs. require sampling _every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during startup <100,000 lbm/hr steam flow.
DESCRIPTION OF CAUSE
~dTHER APPLICABLE INFORMATION
~
7eedwater low flow valve open 80% and #1 bypass valve open approx. 50% during this period.
Reactor water samnle roccived at 0500 hrs indicated all parameters were within specs.
EQUIPMENT YES DR NO.
WR NO.
W. Pietryga 7/16/81 FAILURE NO RESPON_SIBLE SUPERVISOR DATE PART 2 l OPER. TING ENGINEERS COMMENTS Samples prior to and after the missed samples were within Tech. Specs, limit. All personnel involved were spoken to.
SAFETY-TYPE OF CEVIAT!ON EVENT OF POTENTIAL TECH SPEC NON-REPORTABLE ANNUAL RELATED REPORTABLE Og URRENCE PUBLIC INTEREST VIOLATION OCCURRENCE REPORTING WR ISSUED YES ]
10CFR21 14 DAY YES l Xl 30 DAY
, h,h 0N NO NO X
REPORTABLE CCCURRENCE ACTION ITEM NO.
PROMPT ON-SI TE NOTI FI CATION NUMBER XXXX-81-47/031r-0 C. Sargent 7/
1 14 TI TLE CATE TIME 24-HOUR NRC NOTIFICATION PROMPT OFF-SITE NOTIFICATION TPH T. Tongue 7/16/81 1100 F. Palmer 7/16/81 1410
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REGION I1l DATE TIME
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TITLE DATE TIME TG\\1 REGION IIi & COL. CATE TIME TITLE CATE TIME RESPONSI BLE COMP ANY OF FI CER INFORMED OF 10 C F R 21 CONDI TIONS AND THEI R PEPORT TO NPC
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TITLE DATE TWL REvi EW AND COMPLETED OPERATING ENGt NEER DATE ACCEPTANCE BY STATION REVIEW
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DATE
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'N RESOLUTION APPROVED AND AUTHORIZED FOR DISTRIBUTION
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| 05000249/LER-1981-001, Has Been Cancelled | Has Been Cancelled | | | 05000010/LER-1981-001-03, /03X-1:on 801210,radwaste Storage Tank Sampling Frequency Failed to Meet Tech Spec Requirements.Caused by Personnel Failure to Follow Procedures.Personnel Reinstructed | /03X-1:on 801210,radwaste Storage Tank Sampling Frequency Failed to Meet Tech Spec Requirements.Caused by Personnel Failure to Follow Procedures.Personnel Reinstructed | | | 05000010/LER-1981-001, Forwards LER 81-001/03X-1 | Forwards LER 81-001/03X-1 | | | 05000249/LER-1981-003-03, /03L-0:on 810120,Model 288 Differential Pressure Indicating switch,3-1349B,tripped Above Tech Spec Limit. Caused by Instrument Drift.Switch Readjusted & Repeatability Verified | /03L-0:on 810120,Model 288 Differential Pressure Indicating switch,3-1349B,tripped Above Tech Spec Limit. Caused by Instrument Drift.Switch Readjusted & Repeatability Verified | | | 05000249/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000010/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000237/LER-1981-005, Forwards Updated LER 81-005/03X-L.Deviation Rept Encl | Forwards Updated LER 81-005/03X-L.Deviation Rept Encl | | | 05000237/LER-1981-005-03, During Local Leak Rate Testing,Measured Leakage of Single Isolation Valve Exceeded Tech Specs.Caused by Normal Deterioration of Valve Seat. Valve Replaced | During Local Leak Rate Testing,Measured Leakage of Single Isolation Valve Exceeded Tech Specs.Caused by Normal Deterioration of Valve Seat. Valve Replaced | | | 05000237/LER-1981-006, Forwards Updated LER 81-006/01X-1 | Forwards Updated LER 81-006/01X-1 | | | 05000237/LER-1981-006-01, Excessive Leakage Indicated Various Penetrations in Feedwater Check Valves. Caused by Cracked O Ring & Worn Swing Pins.Valves Repaired & Broken Components Replaced | Excessive Leakage Indicated Various Penetrations in Feedwater Check Valves. Caused by Cracked O Ring & Worn Swing Pins.Valves Repaired & Broken Components Replaced | | | 05000237/LER-1981-007-03, /03L-0:on 810122,temp Switch TS 2-261-18D Failed to Trip.Caused by Fill Matl Leakage Due to Broken Capillary Tube Close to Sensing Bulb.Broken Switch Replaced W/New Calibr Switch | /03L-0:on 810122,temp Switch TS 2-261-18D Failed to Trip.Caused by Fill Matl Leakage Due to Broken Capillary Tube Close to Sensing Bulb.Broken Switch Replaced W/New Calibr Switch | | | 05000237/LER-1981-007, /03L for Dresden, Unit 2 Re While Conducting Steam Line Area Temperature Switch Calibration Surveillance, Temperature Switch TS 2-261-180 Failed to Trip | /03L for Dresden, Unit 2 Re While Conducting Steam Line Area Temperature Switch Calibration Surveillance, Temperature Switch TS 2-261-180 Failed to Trip | | | 05000237/LER-1981-011-03, L-0 for Dresden, Unit 2 Re Observed Inadequacies in the Implementation of Administrative or Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection Systems or Engineered S | L-0 for Dresden, Unit 2 Re Observed Inadequacies in the Implementation of Administrative or Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection Systems or Engineered Safety Feature | | | 05000249/LER-1981-014, Forwards LER 81-014/03L-0 | Forwards LER 81-014/03L-0 | | | 05000249/LER-1981-014-03, /03L-0:on 810616,during Scram Air Sys Header Pressure Switch Calibr,Pressure Switches 3-302-99A & B Actuated W/Setpoint Lower than Required.Caused by Instrument Setpoint Drift.Switches Reset | /03L-0:on 810616,during Scram Air Sys Header Pressure Switch Calibr,Pressure Switches 3-302-99A & B Actuated W/Setpoint Lower than Required.Caused by Instrument Setpoint Drift.Switches Reset | | | 05000237/LER-1981-015, /03L-0 for Dresden, Unit 2 Re the Fire Marshall Discovered That the Heat Detectors Were Not Functionally Tested within the 6 Month Interval Required by Tech. Spec. 4.12.A.1 | /03L-0 for Dresden, Unit 2 Re the Fire Marshall Discovered That the Heat Detectors Were Not Functionally Tested within the 6 Month Interval Required by Tech. Spec. 4.12.A.1 | | | 05000249/LER-1981-015-03, /03L-0:on 810618,switch Actuated at 32.8 Inches During Calibr of Isolation Condenser Steam/Condensate Line High Flow.Caused by Instrument Drift.Switch Reset | /03L-0:on 810618,switch Actuated at 32.8 Inches During Calibr of Isolation Condenser Steam/Condensate Line High Flow.Caused by Instrument Drift.Switch Reset | | | 05000249/LER-1981-015, Forwards LER 81-015/03L-0 | Forwards LER 81-015/03L-0 | | | 05000237/LER-1981-016, Forwards LER 81-016/03X-1 | Forwards LER 81-016/03X-1 | | | 05000237/LER-1981-016-03, /03X-1:on 810408,noted That off-stream Liquid Effluent Monitor Had Not Been Functionally Tested on Monthly Basis.Caused by Deletion of Surveillance After Replacing on-stream Monitor w/off-stream Monitor | /03X-1:on 810408,noted That off-stream Liquid Effluent Monitor Had Not Been Functionally Tested on Monthly Basis.Caused by Deletion of Surveillance After Replacing on-stream Monitor w/off-stream Monitor | | | 05000249/LER-1981-016, Forwards LER 81-016/03L-0 | Forwards LER 81-016/03L-0 | | | 05000249/LER-1981-016-03, /03L-0:on 810618,water Level Instrument Surveillance Found LIS 263-57A Tripping Above Tech Spec Levels for Low Level Scram & Low Water Level Isolation. Caused by Instrument Setpoint Drift.Setpoint Adjusted | /03L-0:on 810618,water Level Instrument Surveillance Found LIS 263-57A Tripping Above Tech Spec Levels for Low Level Scram & Low Water Level Isolation. Caused by Instrument Setpoint Drift.Setpoint Adjusted | | | 05000249/LER-1981-017, Forwards Updated LER 81-017/03X-1 | Forwards Updated LER 81-017/03X-1 | | | 05000249/LER-1981-017-03, 3B Motor Generator Set Undervoltage Relay Failed to Trip on Undervoltage Signal. Caused by Sticking Relay Tripping Device.Tripping Device Cleaned,Lubed & Placed Back in Svc | 3B Motor Generator Set Undervoltage Relay Failed to Trip on Undervoltage Signal. Caused by Sticking Relay Tripping Device.Tripping Device Cleaned,Lubed & Placed Back in Svc | | | 05000237/LER-1981-017-03, /03L-0:on 810408,QA Audit Discovered That Temp of Cells Adjacent to Pilot Cell Had Not Been Taken,Per Tech Specs.Caused by Inadvertent Oversight Due to Inadequate Procedures.Change Will Be Implemented by June 1981 | /03L-0:on 810408,QA Audit Discovered That Temp of Cells Adjacent to Pilot Cell Had Not Been Taken,Per Tech Specs.Caused by Inadvertent Oversight Due to Inadequate Procedures.Change Will Be Implemented by June 1981 | | | 05000237/LER-1981-017, Forwards LER 81-017/03L-0 | Forwards LER 81-017/03L-0 | | | 05000249/LER-1981-018, Forwards LER 81-018/03L-0 | Forwards LER 81-018/03L-0 | | | 05000249/LER-1981-018-03, /03L-0:on 810619,LIS 263-72B Found Tripping Above Tech Spec Limit During Monthly Water Level ECCS Instrument Surveillance.Caused by Instrument Setpoint Drift.Setpoint Adjusted.Deviation Rept Encl | /03L-0:on 810619,LIS 263-72B Found Tripping Above Tech Spec Limit During Monthly Water Level ECCS Instrument Surveillance.Caused by Instrument Setpoint Drift.Setpoint Adjusted.Deviation Rept Encl | | | 05000249/LER-1981-019-03, /03L-0:on 810821,main Steam Line High Flow Switches Dpis 3-261-2 & 3-261-2D Found Above Tech Spec Limits.Caused by Torque Shaft Gears Binding on Linkage Gears from Normal Wear & Filings Buildup.Gears Cleaned | /03L-0:on 810821,main Steam Line High Flow Switches Dpis 3-261-2 & 3-261-2D Found Above Tech Spec Limits.Caused by Torque Shaft Gears Binding on Linkage Gears from Normal Wear & Filings Buildup.Gears Cleaned | | | 05000249/LER-1981-019, Forwards LER 81-019/03L-0 | Forwards LER 81-019/03L-0 | | | 05000237/LER-1981-020-01, During ASME Hydrostatic Test,Water Observed Seeping from Cracks in 2.5-inch Rx Head Spray Line.Caused by Chloride Induced Stress Corrosion Cracking.Cracks Cut Out & Piping Replaced | During ASME Hydrostatic Test,Water Observed Seeping from Cracks in 2.5-inch Rx Head Spray Line.Caused by Chloride Induced Stress Corrosion Cracking.Cracks Cut Out & Piping Replaced | | | 05000237/LER-1981-020, Forwards Updated LER 81-020/01X-1 | Forwards Updated LER 81-020/01X-1 | | | 05000249/LER-1981-020, Is Canceled | Is Canceled | | | 05000249/LER-1981-021-03, Pinhole Leak Found on Reactor Water Cleanup Line from Regenerative Heat Exchanger. Caused by Sensitization During Initial Welding.Other Internal Cracks Discovered.Heat Exchanger Loop Replaced | Pinhole Leak Found on Reactor Water Cleanup Line from Regenerative Heat Exchanger. Caused by Sensitization During Initial Welding.Other Internal Cracks Discovered.Heat Exchanger Loop Replaced | | | 05000249/LER-1981-021, Forwards LER 81-021/03L-0 | Forwards LER 81-021/03L-0 | | | 05000249/LER-1981-022, Forwards LER 81-022/03L-0 | Forwards LER 81-022/03L-0 | | | 05000249/LER-1981-022-03, /03L-0:on 810902,vessel low-low Water Level Isolation Switch Had Setpoint of 116.8 Inches,Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Setpoint Adjusted | /03L-0:on 810902,vessel low-low Water Level Isolation Switch Had Setpoint of 116.8 Inches,Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Setpoint Adjusted | | | 05000237/LER-1981-023, Forwards LER 81-023/03L-0 | Forwards LER 81-023/03L-0 | | | 05000237/LER-1981-023-03, /03L-0:on 810511,while Running HPCI Pump Test, Operator Observed Torus Wide Range Level Instrument Reading 0 Inches & Narrow Range Level Instrument Reading Approx 2 Inches & Oscillating.Caused by Personnel Error | /03L-0:on 810511,while Running HPCI Pump Test, Operator Observed Torus Wide Range Level Instrument Reading 0 Inches & Narrow Range Level Instrument Reading Approx 2 Inches & Oscillating.Caused by Personnel Error | | | 05000249/LER-1981-023-03, /03L-0:on 810904,while Conducting Quarterly Scram Discharge Vol Continuous Level Monitor Calibr Check,West & East Bank/East Transducer high-high Level Alarm Tripped. Caused by Setpoint Drift | /03L-0:on 810904,while Conducting Quarterly Scram Discharge Vol Continuous Level Monitor Calibr Check,West & East Bank/East Transducer high-high Level Alarm Tripped. Caused by Setpoint Drift | | | 05000249/LER-1981-023, Forwards LER 81-023/03L-0 | Forwards LER 81-023/03L-0 | | | 05000249/LER-1981-024-01, /01T-0:on 810914,ultrasonic Testing Revealed Water in Steam Supply Line to HPCI Turbine.Caused by Low Point in Horizontal Section of Pipe.Drain Line Installed in Low Point & Routed Back to Same Line at Lower Elevation | /01T-0:on 810914,ultrasonic Testing Revealed Water in Steam Supply Line to HPCI Turbine.Caused by Low Point in Horizontal Section of Pipe.Drain Line Installed in Low Point & Routed Back to Same Line at Lower Elevation | | | 05000237/LER-1981-024-03, /03L-0:on 810513,monthly Surveillance for Standby Liquid Control Tank Sampling Found 3 Days Overdue.Caused by Lack of Personnel Attention.Personnel Admonished.Tank Sampled | /03L-0:on 810513,monthly Surveillance for Standby Liquid Control Tank Sampling Found 3 Days Overdue.Caused by Lack of Personnel Attention.Personnel Admonished.Tank Sampled | | | 05000249/LER-1981-024, Forwards LER 81-024/01T-0 | Forwards LER 81-024/01T-0 | | | 05000237/LER-1981-024, /03L-0 for Dresden, Unit 2 Re While Conducting Routine Review of Surveillance, It Was Found That the Monthly Surveillance Required by Tech. Spec. 4.4.c.1 for Standby Liquid Control Tank Sampling Was Three Days Overdue | /03L-0 for Dresden, Unit 2 Re While Conducting Routine Review of Surveillance, It Was Found That the Monthly Surveillance Required by Tech. Spec. 4.4.c.1 for Standby Liquid Control Tank Sampling Was Three Days Overdue | | | 05000237/LER-1981-025, Forwards LER 81-025/03L-0 | Forwards LER 81-025/03L-0 | | | 05000237/LER-1981-025-03, /03L-0:on 810518,during Plant Tour by Operations Personnel,Low Pressure Leg of Isolation Condenser Level Indication Found Valved Out.Probably Caused by Valve Not Being Reopened After Sampling.Valve Opened | /03L-0:on 810518,during Plant Tour by Operations Personnel,Low Pressure Leg of Isolation Condenser Level Indication Found Valved Out.Probably Caused by Valve Not Being Reopened After Sampling.Valve Opened | | | 05000249/LER-1981-025-01, During Automatic Depressurization Sys Valve Operability Surveillance,B Electromatic Relief Valve Failed to Open at Rated Pressure. Caused by Excessive Leakage on Threads | During Automatic Depressurization Sys Valve Operability Surveillance,B Electromatic Relief Valve Failed to Open at Rated Pressure. Caused by Excessive Leakage on Threads | | | 05000249/LER-1981-025, Forwards Updated LER 81-025/01X-1 | Forwards Updated LER 81-025/01X-1 | | | 05000249/LER-1981-026-03, /03L-0:on 810915,while Shutting Down,Rod P-10 Showed Wrong Position on Rod Worth Minimizer.Caused by Several Diode Failures on Two Digital Output Printed Circuit Boards.Boards Removed,Repaired & Tested Satisfactorily | /03L-0:on 810915,while Shutting Down,Rod P-10 Showed Wrong Position on Rod Worth Minimizer.Caused by Several Diode Failures on Two Digital Output Printed Circuit Boards.Boards Removed,Repaired & Tested Satisfactorily | |
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