LER-1980-039, /01T-0:on 800507,util Notified by GE That Qualification of Containment Atmospheric Monitoring Sys Hydrogen Sensors Has Not Been Demonstrated to Meet Purchase Specs.Operating Procedures & Instructions Changed |
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r1 irtIcOVfflu..Lu.h i et e.r rc:;CHirlis)N /.ND P o I p]l During normal operation CE notified TVA that nuclear qualification of the CAM g ; system hydrogen sensors (for units 1, 2, and 3) has not been demonstrated to be gl within the requirements of the purchase contract.
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There g ; was no significant resulting events.
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An analysis of the gg qualification test data was performed by CE to bound the instrument accuracy in g post-LOCA conditions.
Changes to applicable procedures and instructions have been g made to incorporate the conservative limits established by the analysis..GE hydrogen a ' sensor, Model 47E 22642BG2.
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s Tennessee Valley Authority Form BF-17 Br' owns Ferry Nuclear Plant BF 15.0 1/10/79 LEll SUPPLEMENTAL INFORMATION BF!lO 259 /,8039 Technical Specification Involved 3.7.H Reported Under Technical Specification 6.7.2.a(9)
Date of Occurrence 5/7/80 Time,of Occurrence 0700 Unit 1,2,&3 Identification and Det.cription of Occurrence:
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A letter was received from CE indicating that nuclear qualification.of the CAM system hydrogen sensors has not been demonstrated to meet purchase specifications at temperatures greater than 200 F, at temperature chaiges' greater than 27 F, or in utilizing sulfuric acid concentrations in a radiation field.
Conditions Prior to Occurrence:
Unit 1 @ 41%
Unit 2 @ 96%
UIit 3 @ 99%
Action specified in the Technical Specification Surveillance Requirements met due to inoperable _igguipment.
Describe.'
NA gparent Cause of occurrence:
Qualification testing has not demonstrated sensor capabilities to meet purchase j
specifications for all environmental conditions.
Analysis of Occu rence:
There was no damage to plant equipment. There was no activity release, no l
personnel exposure or injury and no danger to the health or safety of the public.
Corrective Action
Changes to operating procedures, surveillance instructions and instrument maintenance-instructions have been made to assure adequate plant performance.
GE's evaluation is in progress.
Failure Datai l
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criod - Iifetime; Responsibility - Administrative Supervisor
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BFRO-50-259/8039 ADDITIONAL INFORMATION REGARDING CALIBRATION OF HYDROCEN SENSORS BROWNS FERRY NUCLEAR PLANT The Containmer.t Atmosphere Monitoring System (CAM) at Browns Ferry Nuclear Plant consists of hydrogen monitors located inside the containment.
Four sensors are located in the drywell and two are in the torus. Only two sensors in the drywell and one in the torus are in active service at any time with the remaining sensors acting as backup. The purpose of the sensors is to monitor hydrogen concentration in the containment post-LOCA to provide guidance for use of the Containment Atmosphere Dilution System (CAD). TVA has previcusly prepared a design change to move the sensors cutside the containment to improve the maintainability during unit operation (access considerations).
This modification will be done during the fall 1980 refueling on units 2 and 3 and during spring 1981 on unit 1.
The installation work is significant since sample lines must be brought outside the containment. We estimate about four weeks critical path time is involved.
A-fginal sensor procurement specifications indicated that the hydrogen
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sensors manufactured by the General Electric Company (Valley Forge) were to have an accuracy of +2 percent of scale with a range of 0-20 percent hydrogen concentration.
GE, during a recent reevaluation of the environ-mental qualification of instrumentation, has identified certain areas where the CAM sensor accuracy has not been fully qualified within the original accuracy specification. The deviations were identified in TVA's report to NRC (I&E Atlanta) on May 8, 1980. Detailed discussion on each point follows.
Operation Above 200 F j
The hydrogen sensors have been integrity qualified up to 340 F. GE has informed us that the instrument accuracy cannot be guaranteed to be within specifications above 200 F.
This does not appear to be a significant shortcoming since LOCA analyses indicate that drywell temperatures will return to 175 F within 15 minutes of the LOCA (when containment.
cooling is initiated) and decline steasily thereafter. Torus temperatures are expected to be no greater than 130 F.
Also, as informed by GE, the accuracy of the sensors, after experiencing a temperature transient above 200*F, is qualified to be within +7.5 percent of full scale (20 percent) for temperatures below 200*F.
This accuracy is based on a GE analysis of hydrogen sensor test data acquired in sensor qualification testing to determine maximum expected error assuming post-LOCA operation of the CAM system hydrogen sensors without the recommended initial post-LOCA recalibra-tion.
Sulfuric Acid Concentration In May 1979, GE incorporated a product improvement which reduced the sulfuric acid concentration from 60 to 25 percent. This improvement was made for two reasons.
1.
The reduced acid concentration was safer to work with in the manu-facturing process.
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a 2.
Manufacturing data indicated the high acid concentration was respons-ible for an increased corrosion and leakage problem resulting in reduced sensor life. The reduced acid concentration was expected to increase sensor life and reliability.
Based on GE's evaluation of the manufacturer's data, total requalification of the sensors should not be necessary due to the acid concentration change.
CE, however, is reevaluating these data to determine if further testing is recommended.
Radiation Field Performance The CAM hydrogen sensors were originally qualified by subjecting the sensor to a radiation dose of approximately 3.2 x 10 RAD. The primary intent was to demonstrate that the sensor's performance was not degraded by radiation effects on sensor material. Based on the results of this test, GE concluded that the sensor's performance was unaltered by the radiation exposure. GE is, however, expanding the scope of the radiation tests and new tests are scheduled to be performed this summer.
Calibration After 27 F Change Based on the results of extensive vendor testing, the manufacturer has indicated that the original accuracy specifications can be assured only if the CAM sensor ambient temperature is within 27'F of the calibration tengerature. The hydrogen sensors are factory tested befor4 shipment at 9
135 F and 185 F.
The tes4 acceptance criteria calls for a -5 percent accuracy rather than the -2 percent criteria in the instrument specifications.
The torus sensors are calibrated at approximately 80 F and the drywell sensors at 130 F.
DBA LOCA temperatures will raise the ambient temperature greater than 27 F from the calibration temperatures. GE has accordingly recommended that the sensors be recalibrated following a LOCA to maintain specified accuracy. This calibration may be performed entirely from the control room and will permit an accurate H concentration measurement 2
within 6-8 hours. At least one sensor will be held in service while the others are being calibrated.
To ensure that the hydrogen concentration is maintained below four percent, operating instructions will be altered to initiate the CAD system while allowing for the possible presence of the additional instrument error (7.5 percent). Present analyses (assuming the worst case) indicates that the CAD system would not be needed for at least two hours. Analysis also indicates that with the earlier operation of the CAD system, hydrogen concentration levels and offsite dose limits are not exceeded. Once the hydrogen monitors are recalibrated to specification accuracy, CAD system operation may be returned to an as-needed basis.
Applicable surveillance and operating instructions will be altered to reflect the considerations expressed above. We are also working with GE to resolve specifics of the stated concerns regarding additional testing.
TVA realizes the overall advantages of removing these instruments outside the DBA environment as a long-term solution. We accordingly commit to relocating the sensors at the next refueling outage for each respective unit.
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| 05000259/LER-1980-001, Supplemental LER 80-001/01T-1:on 800107,during Performance of Ster 7902 Per IE Bulletin 79-23,diesel Generator 3A Lost Speed Control.Caused by Deteriorated Elastomer Spider Coupling.Spider Coupling Replaced | Supplemental LER 80-001/01T-1:on 800107,during Performance of Ster 7902 Per IE Bulletin 79-23,diesel Generator 3A Lost Speed Control.Caused by Deteriorated Elastomer Spider Coupling.Spider Coupling Replaced | | | 05000259/LER-1980-001-01, /01T-0:on 800107,in Cold Shutdown While Performing Tests Per IE Bulletin 79-28,speed Control on Diesel Generator 3A Was Lost.Caused by Broken Coupling Which Connects Speed Pickup to Generator Shaft.Coupling Replaced | /01T-0:on 800107,in Cold Shutdown While Performing Tests Per IE Bulletin 79-28,speed Control on Diesel Generator 3A Was Lost.Caused by Broken Coupling Which Connects Speed Pickup to Generator Shaft.Coupling Replaced | | | 05000296/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000260/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000296/LER-1980-001-03, /03L-0:on 791230,w/Unit 3 in Shutdown,Bus Tie Board Was de-energized for Startup.Caused by Feeder Cable Failure.Work in Progress to Bypass Bad Cable Sections | /03L-0:on 791230,w/Unit 3 in Shutdown,Bus Tie Board Was de-energized for Startup.Caused by Feeder Cable Failure.Work in Progress to Bypass Bad Cable Sections | | | 05000260/LER-1980-001-03, /03L-0:on 791229,during Normal Operation,While Performing SI 4.2.B-1,switch 1 on Reactor Water Level LITS-3-58D Failed to Operate.Caused by Rendom Failure of Switch in Yarway Model 4418CE.Switch Replaced | /03L-0:on 791229,during Normal Operation,While Performing SI 4.2.B-1,switch 1 on Reactor Water Level LITS-3-58D Failed to Operate.Caused by Rendom Failure of Switch in Yarway Model 4418CE.Switch Replaced | | | 05000259/LER-1980-002-03, /03L-0:on 800112,during Shutdown for Refueling, Wind Direction Channel at 33-ft Elevation Failed Upscale. 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Caused by Random Failure of Gear Tooth in Limit Switch,Size SMB-2,Model 3-G.Limit Switch Replaced | | | 05000260/LER-1980-005-03, /03L-0:on 800125,while Performing Special Instruction 4.2.B-1 During Normal Operation,Switches 1,2 & 4 on LIS-3-58A Did Not Operate at Proper Setpoint.Caused by Switch 4 Hanging on Magnet.Switches Adjusted | /03L-0:on 800125,while Performing Special Instruction 4.2.B-1 During Normal Operation,Switches 1,2 & 4 on LIS-3-58A Did Not Operate at Proper Setpoint.Caused by Switch 4 Hanging on Magnet.Switches Adjusted | | | 05000260/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000259/LER-1980-005, Forwards LER 80-005/01T-0 | Forwards LER 80-005/01T-0 | | | 05000296/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000259/LER-1980-005-01, /01T-0:on 800118,during Refueling Outage,While Performing Insp Per IE Bulletin 79-14,found No Seismic Restraints in Drywell of Reactor Bldg Closed Cooling Water 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800203,while Running Electrical Checks on Recirculation Pump,Reactor Recirculation Pump 2A Was Accidentally Tripped.Caused by Misinterpretation of Labels on Recirculation Pump Trip Breakers | | | 05000296/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000260/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000259/LER-1980-006-03, /03L-0:on 800122,during Refueling Operations, Control Rod Driveline Accumulator Level Switch LS-1-305-129 on Unit 38-11 Was Found Inoperable.Caused by Broken Reed Switch.Switch Replaced | /03L-0:on 800122,during Refueling Operations, Control Rod Driveline Accumulator Level Switch LS-1-305-129 on Unit 38-11 Was Found Inoperable.Caused by Broken Reed Switch.Switch Replaced | | | 05000259/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000260/LER-1980-007-03, /03L-0:on 800203,during Normal Operation,Reactor Recirculation Pump 2B Tripped.Caused by Pickup of Recirculation Motor 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Timers,B Logic Channel Did Not Isolate.Caused by Intermittent Sticking of Relay R1B Resulting in Time Delay Contacts Being Closed | /03L-0:on 800125,while Performing SI 4.2.A-16, Calibr Reactor Bldg Isolation &/Or Logic Timers,B Logic Channel Did Not Isolate.Caused by Intermittent Sticking of Relay R1B Resulting in Time Delay Contacts Being Closed | | | 05000296/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000296/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000260/LER-1980-008-31, /03L-0:on 800206,while Conducting Automatic Depressurization Sys Logic Functional Test,Relay 10A-K26 Manually Operated in Place of Relay 2E-K26 Causing Recirculation Pump 2B Trip.Caused by Operator Error | /03L-0:on 800206,while Conducting Automatic Depressurization Sys Logic Functional Test,Relay 10A-K26 Manually Operated in Place of Relay 2E-K26 Causing Recirculation Pump 2B Trip.Caused by Operator Error | | | 05000296/LER-1980-008-03, /03L-0:on 800402,3B Diesel Generator Governor Actuator Would Not Respond Properly During Operability Surveillance Instruction.Cause Unknown.Oil Contamination Suspected.Sump Flushed & Refilled | /03L-0:on 800402,3B Diesel Generator Governor Actuator Would Not Respond Properly During Operability Surveillance Instruction.Cause Unknown.Oil Contamination Suspected.Sump Flushed & Refilled | | | 05000259/LER-1980-008, Forwards Updated LER 80-008/03L-1 | Forwards Updated LER 80-008/03L-1 | | | 05000260/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000259/LER-1980-008-03, During Scheduled Refueling Outage,Hpci Turbine Had Crack in Coupling Bearing Support Pedestal.Possibly Caused by Water Hammer in Main Steam Supply Line | During Scheduled Refueling Outage,Hpci Turbine Had Crack in Coupling Bearing Support Pedestal.Possibly Caused by Water Hammer in Main Steam Supply Line | | | 05000296/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 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Caused by Natural Aging of Relay.Relay & Fuse Replaced | /03L-0:on 800404,during Normal Operation,Relay 16A-K63B Overheated & Failed,Blowing Fuse Causing Containment Isolation Sys Group 6 Valves to Fail Closed. Caused by Natural Aging of Relay.Relay & Fuse Replaced | |
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