LER-1983-020, /03L-0:on 830410,during Power Maneuvers for Recirculation Sys Testing,Calculated R Factor Was Less than R Setpoint for 2 H 45 Minutes.Caused by Power Peaking Due to Xenon Transients from Previous Power Changes |
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EVENT DESCRIPTION AND PROBABLE CoNSEGUENCES O'o l 0 l2 l l During power maneuvers on unit 2 to prepare for RTI-32 (Recirculation System l
jojall Testing), the calculated R factor (FRP/CHFLD) was less than the R setpoint for l
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2-hours 45 minutes (Tech. Spec. 2.1. A.1.a&c. ) The R setpoint was 1.0; the cal-l lolsll culated R was 0.918. There was no effect'on the health or safety of the public l l
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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS b27 [ijoll While preparing for RTI-32 testTng, Xenon transients from previous power l
li{ill changes caused power peaking, resulting in R factor violation.
The rod pattern l lil2ll was adjusted with TIP verification to restore R within limits in 2-hours 45 l
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Tech. Spec. revisions have been submitted for unit 2 (similar to l
Iil4Il present unit 1 Tech. Specs. ) to allow 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for correcting R.
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0305170340 830509 NRc usE oNu 121 o l [ Nj@l NA PDR ADOCK 05000260 S
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lllllllllllll NAME oF PREPARER M. D. Winno pwoNE. (205)729-0845 i
Tennessee 9 alley Authority Form BF 17 Browns Ferry Nuclear Plant BF 15.2 2/17/82 LER SUPPLEMENTAL INFORMATION 2.1.A.1.a&c BFRO-50 260 / 8320 Technical Specification involved 5-10-83 Reported Under Technical Specification 6.7.2.b(2)
- Date Due NRC Event Narrative:
Unit i vas operating at 99-percent power and unit 3 was operating at 80-parcent power. These units were unaffected by this event. With unit 2 at 70-percent power preparing for RTI-32 (Recirculation System Testing), the nuclear engineer calculated the "R" factor to be 0.918. This was less than the "R" setpoint of 1.0 (Technical Specification 2.1.A.1.a&c).
There was no effect on the public health or safety as the calculated APRM scram value was not exceeded during this, event.
The 120-percent scram clamp was operable during the event.
The cause of the event was maintaining maximum core flow and attaining a 70-percent load line for RTI-32 testing, following testing per RTI-23 The associated power increase and decrease prior to attaining the 70-percent load line resulted in significant Xenon transients.
At approximately 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on April 9, 1983, "R" was 1.03 Control rods were moved to set the power shape.
Computer problems developed during the "P2" and " BOP" computer program runs at 2359 hours0.0273 days <br />0.655 hours <br />0.0039 weeks <br />8.975995e-4 months <br />.
The "P1" program was delayed until 0102 hours0.00118 days <br />0.0283 hours <br />1.686508e-4 weeks <br />3.8811e-5 months <br /> on April 10, 1983 which calculated "R" to be 0.918. TIP data was taken and control rods were moved to mitigate the Xenon transient and restore "R" to within limits.
"R" was noted out of limits at 0102 on April 10, 1983 and was restored within limits at 0347 hours0.00402 days <br />0.0964 hours <br />5.737434e-4 weeks <br />1.320335e-4 months <br /> (2-hours 45 minutes.) Based on previous events and BWR Standard Technical Specifications, TVA has initiated changes to the technical specifications involved.
These changes have been approved and issued for unit 1.
When similar technical specification revisions are approved for units 2 and 3,' TVA will be allowed six hours for R factor corrections on all 3 units.
BFRO-50-259/82019 260/81018, 81037, 82022, 82013, 83013 296/81040, 81041, 81045, 82038, 82048, 82062 1
Retention :
'eriod - Lifetime; Responsibility - Document Control Supervisor h
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| 05000260/LER-1983-001, Forwards LER 83-001/03L-0 | Forwards LER 83-001/03L-0 | | | 05000260/LER-1983-001-03, /03L-0:on 830128,interlock Providing Rod Withdrawal Block Inoperable When Refuel Platform Moved Over Core.Caused by Failure of Limit Switch 2 Due to Stuck Plunger | /03L-0:on 830128,interlock Providing Rod Withdrawal Block Inoperable When Refuel Platform Moved Over Core.Caused by Failure of Limit Switch 2 Due to Stuck Plunger | | | 05000296/LER-1983-001, Forwards LER 83-001/03L-0 | Forwards LER 83-001/03L-0 | | | 05000259/LER-1983-001, Forwards LER 83-001/03L-0 | Forwards LER 83-001/03L-0 | | | 05000296/LER-1983-001-03, /03L-0:on 830107,during Surveillance Testing Drywell Containment Spray Isolation Valve 3-FCV-74-74 Failed to Operate.Caused by Fractured Worm Shaft Clutch Gear Due to Impact Load.New Clutch Gear Installed | /03L-0:on 830107,during Surveillance Testing Drywell Containment Spray Isolation Valve 3-FCV-74-74 Failed to Operate.Caused by Fractured Worm Shaft Clutch Gear Due to Impact Load.New Clutch Gear Installed | | | 05000259/LER-1983-001-03, /03L-0:on 830110,pressure Switch 1-PS-75-7 Found to Have Setpoint of 174 Psi.Tech Specs Require Setpoint to Be 185 + 10 Psi.Caused by Setpoint Drift.Mercoid Switch Recalibr | /03L-0:on 830110,pressure Switch 1-PS-75-7 Found to Have Setpoint of 174 Psi.Tech Specs Require Setpoint to Be 185 + 10 Psi.Caused by Setpoint Drift.Mercoid Switch Recalibr | | | 05000259/LER-1983-002-03, /03L-0:on 830117,during Surveillance Insp,Control Rod 10-39 Failed to Operate at Position 46.Probably Caused by Crud Accumulation in Valve Flow Orifice.Insert Directional Control Valve Replaced | /03L-0:on 830117,during Surveillance Insp,Control Rod 10-39 Failed to Operate at Position 46.Probably Caused by Crud Accumulation in Valve Flow Orifice.Insert Directional Control Valve Replaced | | | 05000296/LER-1983-002-03, /03L-0:on 830112,primary Purge Sys Failed to Achieve Required Flow Rate of Greater than 10% of Design. 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Barton Model 288 Switches Recalibr & Functionally Tested | | | 05000296/LER-1983-008, Forwards LER 83-008/01T-0 | Forwards LER 83-008/01T-0 | | | 05000260/LER-1983-009-03, /03L-0:on 830319,HPCI Turbine Failed Due to Erratic Flow Controller.Caused by Trapped Air in Hydraulic Oil Control Sys Due to Maint Work | /03L-0:on 830319,HPCI Turbine Failed Due to Erratic Flow Controller.Caused by Trapped Air in Hydraulic Oil Control Sys Due to Maint Work | | | 05000260/LER-1983-009, Forwards LER 83-009/03L-0 | Forwards LER 83-009/03L-0 | | | 05000296/LER-1983-009-03, /03L-0:on 830209,sample Pump Found Inoperative During Reactor & Turbine Bldg Vent Monitor CAM 3-RM-90-250 Daily Source & Background Check.Caused by Blown Fuse.Faulty Allied RS5D Relay Caused Control Room Alarm Malfunction | /03L-0:on 830209,sample Pump Found Inoperative During Reactor & Turbine Bldg Vent Monitor CAM 3-RM-90-250 Daily Source & Background Check.Caused by Blown Fuse.Faulty Allied RS5D Relay Caused Control Room Alarm Malfunction | | | 05000259/LER-1983-009-01, Design Review of Emergency Diesel Generator Engine Coolers Showed Coolers May Not Be Able to Maintain Cooling Water Below Hot Setpoint. 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Switch 3-PS-1-76 Recalibr | | | 05000296/LER-1983-010, Forwards LER 83-010/03L-0 | Forwards LER 83-010/03L-0 | | | 05000259/LER-1983-010, Forwards LER 83-010/03L-0 | Forwards LER 83-010/03L-0 | | | 05000260/LER-1983-010-03, /03L-0:on 830322,CRD 10-39 Failed to Scram While Performing SI 4.3.C.Caused by Valve Stem Separating from Valve Seat in Valve 85-617 | /03L-0:on 830322,CRD 10-39 Failed to Scram While Performing SI 4.3.C.Caused by Valve Stem Separating from Valve Seat in Valve 85-617 | | | 05000259/LER-1983-010-03, /03L-0:on 830224,while Performing SI 4.7.B-3, Standby Gas Treatment Train B Declared Inoperable Due to Failure to Meet Flow Distribution Requirements.Caused by Debris in HEPA Filters.Filters Replaced | /03L-0:on 830224,while Performing SI 4.7.B-3, Standby Gas Treatment Train B Declared Inoperable Due to Failure to Meet Flow Distribution Requirements.Caused by Debris in HEPA Filters.Filters Replaced | | | 05000296/LER-1983-011, Forwards LER 83-011/03L-0 | Forwards LER 83-011/03L-0 | |
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