ML20071N446
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| ML20071N446 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/24/1983 |
| From: | Coffey J TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| RO-50-296-8331, NUDOCS 8306070059 | |
| Download: ML20071N446 (1) | |
Similar Documents at Browns Ferry | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20199F6501997-11-14014 November 1997
[Table view]Special Rept:On 971031,one High Range Primary Containment Radiation Monitor Declared Inoperable for More than Seven Days.Caused by Component/Equipment Failure Inside Drywell. Will Repair or Replace Detector or Associated Cable ML20207K9241988-10-0707 October 1988 RO 88-01:on 880725,during Inventory of Snm,Discrepancy Noted for Intermediate Range Monitor Detector Removed from Core Location C.Caused by Inadequage SNM Control & Accountability Practices Existing at Time of Installation & Shipment ML20235J4541987-07-0202 July 1987 Special Rept 87-01,Rev 1:on 870321,three Seismic Triggers Would Not Provide Required Control Room Annunciation Upon Receipt of Horizontal 0.1 G Seismic Acceleration.All Instruments Removed from Site Repaired.Instructions Revised ML20117N7501985-05-0808 May 1985 Advises That Rept Will Not Be Prepared for RO BFRO-50-296/85011 ML20086G5971984-01-0303 January 1984 Telecopy RO 50-259/83073:on 831231,reactor Water Sample Indicated Chloride Concentration of 525 Ppb.Steam Flow Greater than 100,000 Lbm/H.Caused by Possible Resin Intrusion.Investigation in Progress ML20083E1551983-12-15015 December 1983 Telecopy RO 50-296-83060:on 831214,nine of 13 two-stage Relief Valves Tested Initially Failed to Lift within Allowable Range.Cause Being Evaluated W/Manufacturer.Nine Valves Will Be Reset & Retested Prior to Installation ML20082V3411983-12-12012 December 1983 Telecopy RO 50-259/83068:on 831210,RHR Pump 1C Motor Sparked & Smoked.Motor Shut Down & Restarted,Then Tripped on Overcurrent.Pump Declared Inoperable.Caused by Winding Failure.Motor Will Be Replaced ML20083A4301983-12-0808 December 1983 Telecopy Ro:On 831207,linear Crack Indication Identified by NDE in Weld DSHS-3-2 of Head Spray Piping of RHR Sys. Apparently Caused by Intergranular Stress Corrosion Cracking.Insp Per IE Bulletin 83-02 Will Be Performed ML20082D0251983-11-14014 November 1983 Telecopy Ro:On 831110,HPCI Isolated Due to Failure of Exhaust Rupture Disc.Cause Unknown.Maint Request Issued to Replace Disc.Investigation Continuing ML20078M9781983-10-14014 October 1983 Telecopy Ro:On 831013,routine Analysis of 831007 Scram Revealed That 2-LT-85-45A Did Not Initiate Trip When SDIV Exceeded 50 Gallons.On 831014,testing of Transmitter Revealed Slow & Erratic Response to Measured Variable ML20078H3281983-10-0606 October 1983 Telecopy RO 83061:on 831004,hydrogen-oxygen Analyzer Sample Pump B Determined Inoperable Following Notification from Metal Bellows Corp of Generic Deficiency.Pump Replaced W/ Upgraded Model in Stock on 831005 ML20080L8961983-09-20020 September 1983 Telecopy Ro:On 830919,Surveillance 4.7.A.2.G3 Determined Leakage Rates Exceeded for MSIV Lines A,C & D.Caused by Leakage Past Main Valve Seat.Seating Surfaces Modified ML20076J5841983-08-28028 August 1983 Telecopy Ro:On 830826,cracks Discovered on Core Spray Welds DCS-1-7 & DCS-1-8 & Reactor Water Cleanup Welds DSRWC-1-3 & DSRWC-1-2.Total Welds to Be Inspected Increased from 53 to 79.Updated Insp Results Encl ML20076J7451983-08-25025 August 1983 Telecopy RO BFRO-50-259/83049 R9:on 830825,weld Crack Indications Discovered in Welds on Core Spray & Reactor Water Cleanup.Number of Welds to Be Inspected Increased from 53 to 79 ML20076F3351983-08-23023 August 1983 Telecopy RO 50-259/83-49:on 830811,pipe Weld Cracking Indications Revealed by Addl Ultrasonic Insps.Possibly Caused by Corrosion.Addl Welds Inspected.Insp Repts to Be Submitted Periodically ML20080D6921983-08-22022 August 1983 Telecopy RO 83049R7:on 830812,indications Discovered on Core Spray Welds DCS-1-7 & DCS-1-8 & Reactor Water Cleanup Welds DSRWC-1-3 & DSRWC-1-2.Addl 29 Welds Will Be Inspected.Insp Results Encl ML20080E0771983-08-22022 August 1983 Telecopy Ro:On 830812,cracks Found on Welds DCS-1-7, DSRWC-1-3,DCS-1-8 & DSRWC-1-2.Cause Not Stated.Total Number of Welds to Be Inspected Increased from 53 to 79 ML20080D5721983-08-18018 August 1983 Telecopy Ro:On 830812,weld Cracks Discovered in Core Spray & Reactor Water Cleanup Sys.Addl 29 Welds Will Be Inspected. Insp Results Encl ML20076F6911983-08-17017 August 1983 Telecopy Ro:On 830812,indications Found on Pipe Welds for Core Spray & Reactor Water Cleanup.Addl 29 Welds Will Be Inspected Increasing Total Number of Welds to Be Inspected to 82 ML20076F8641983-08-15015 August 1983 Telecopy Ro:On 830815,indications Identified on Welds DCS-1-7,DSRWC-1-3,DCS-1-8 & DSRWC-1-2.Weld Insp Results Encl ML20076F5211983-08-15015 August 1983 Telecopy Ro:On 830812,core Spray Weld DCS-1-7 Had Intermittent Indication on Pipe Side of Weld Approx 41% Through Wall Depth.Reactor Water Cleanup Weld DSRWC-1-3 Had Two Indications Approx 5 Inches Long ML20076F5351983-08-12012 August 1983 Telecopy Ro:On 830812,during Routine Surveillance Testing, Four of Four Turbine first-stage Permissive Switches Discovered Out of Tech Spec Limits.Caused by Setpoint Drift. Setpoints Reset ML20077A0341983-07-12012 July 1983 Supplemental Ro:On 830604,13,14 & 15 Standby Gas Treatment Train B Declared Inoperable.Caused by Increased Damper Closure Since Measurements Made in May 1983.Dampers Returned to Preset Position ML20077A2791983-07-0606 July 1983 Telecopy RO 50-259/83036:on 830705,seven two-stage Target Rock Relief Valves Tested at Wyle Labs for as-found Set Pressure Failed to Lift within Allowable Range.Caused Under Evaluation.Valves Will Be Reset & Retested ML20071N4461983-05-24024 May 1983 Telecopy RO 50-286/8331:on 830520,reactor Low Pressure Switches PS-3-74B & PS-68-96,switch 2 Found Below Tech Spec Limits.Caused by Setpoint Drift.Setpoints Reset & Design Change Request DCR 1398 Initiated to Replace Switches ML20071H5801983-05-18018 May 1983 Telecopy RO 50-259/83024:on 830517,design Review of Emergency Diesel Generator Room Ventilation Sys Capabilities Revealed Design Temp Limits of Some Electrical Components May Be Exceeded.Caused by Error in Heat Dissipation Data ML20069M4551983-04-25025 April 1983 Telecopy RO 50-259/83021:on 830424,130 Fuel Bundles Unloaded from Core & Placed in High Density Fuel Storage Rack in Spent Fuel Storage Pool Not Tested for Boron Concentration. Caused by Inadequate Procedures ML20069L3361983-04-20020 April 1983 Telecopy RO 50-296/83024:on 830419,review of Licensing Documents Revealed Lead Test Assemblies Could Reach Max of 18.8 Kw/Ft in Event of Rod Withdrawal Error.Caused by Error in Preparation & Review of GE Licensing Documents ML20069K7371983-04-18018 April 1983 Telecopy RO 50-259/83020:on 830418,leakage Rate for Line a MSIV Found Above Tech Spec Limit.Caused by Leakage Past Main Valve Seat.Corrective Maint & long-term Mod Planned ML20064N9851983-02-0909 February 1983 Telecopy Message of RO 50-260-8302:on 830208,pressure Switches PS-68-96,PS-3-74A & PS-3-74B Found Out of Tech Spec Limits During Performance of Surveillance Instruction 4.2.B-7.Caused by Setpoint Drift.Switches Recalibr ML20064L2561983-02-0808 February 1983 Telecopy Ro:On 830207,reactor Low Water Level Switches Found Out of Tolerance.Caused by Instrument Drift.Switches Recalibr,Tested & Returned to Svc.Switches Will Be Replaced W/Analog Transmitter/Trip Unit Sys at Later Date ML20064M1461983-02-0707 February 1983 Telecopy Message of RO 50-259/83006:on 830205,relief Valve PCV 1-22 Failed to Reseat Fully After Actuation to Control Reactor Pressure.Probably Caused by Excessive Leakage of Pilot Valve.Pilot Valve & Solenoid Actuator Replaced ML20062K3021980-12-0303 December 1980 RO 50-259/8085:on 801123 Reservoir Water Temp Exceeded Max Allowable Temp.Caused by Influence of Colder Water Upstream.Load on Unit 3 Reduced in Four Stages to Shutdown & Water Flows Increased ML20064K3461980-10-29029 October 1980 Ro:On 801029,HPCI Removed from Svc Due to Ground Occurring on Gland Seal Condensor Pump Motor.Cause Attributed to Moisture Found in Pump.Hpci Was Returned to Svc ML20204B8501978-09-14014 September 1978 RO 50-259/7827:on 780913,recirculation Loop a Flow Decreased from 41,000 to 33,000 Cpm W/Corresponding Increase in Pump Delta F.Caused by Valve Stem Separating from Valve Disc ML20084T9131976-09-21021 September 1976 Telecopy RO BFRO-50-259/7615:on 760921,HPCI & RCIC Failed Test.Reactor Shutdown Effected & Pressure Reduced to 100 Psi ML20084T8931976-09-21021 September 1976 Telecopy RO BFRO-50-259/7617:on 760921,prescribed Rate of Reactor Coolant Change During Normal Heatup Exceeded When Averaged Over 1 H Period ML20084U3211976-09-0707 September 1976 Telecopy RO BFRO-50-260/7610:on 760906,out-of-sequence Control Rod Withdrawn.Cause Not Stated ML20084U2691976-07-28028 July 1976 Telecopied RO BFRO-50-296/762T:on 760728,during Surveillance Testing,Control Rod Accumulators Found Discharged W/O Control Rod Drive Electrically Disarmed.Cause Not Stated ML20084U3521976-07-0909 July 1976 Telecopy RO BFRO-50-260/768T:on 760709,unit Scrammed Due to Loss of Neutron Monitoring Battery 2A.Cause Not Stated ML20084U4541976-06-19019 June 1976 Telecopied RO BFRO-50-260/765T:on 760619,water Supply Valves 85-612 & 85-615 to Hydraulic Control Unit 30-32 Found Closed.No Cause Stated.Valves Opened ML20085E9531975-07-0404 July 1975 Telecopy Message of Ro:On 750703,facility Became Inoperable Due to Governor Problems.Manual Operation Possible.Lee Gas Turbine Could Not Be Tied in Through Isolated Line to Supply & Buy Power.Investigation Continuing ML20085F7001975-03-11011 March 1975 Telecopy RO BFAO-50-259/754T:on 750311,drywell Atmosphere Above Permissible Oxygen Concentration.Cause Not Stated ML20085F7901975-02-27027 February 1975 Telecopy RO BFAO-50-259/753T:on 750226,pressure Relief Valve PCVI-4 Prematurely Lifted & Failed to Reseat Until Pressure Reached 480 Psig.Reactor in Cold Shutdown Condition for Valve Replacement.Cause Not Stated ML20085G0901975-01-19019 January 1975 Telecopy Ro:On 750119,pressure Relief Valve PCV-1-4 Operated Several Times W/No Appreciable Blowdown.Unit in Cold Shutdown for Investigation & Possible Repair ML20085G1011975-01-0707 January 1975 Telecopy RO BFAO-50-260/751T:on 750107,RCIC Failed to Operate Following Planned full-load Trip ML20085G6141974-12-27027 December 1974 Telecopy RO BFAO-50-259/7461T:on 741227,proper Documentation Not Issued Prior to Installation of Dampening Pin for Main Steam Line high-flow Pressure Switch Snubbers.Cause Not Stated ML20085G6281974-12-25025 December 1974 Telecopy Ro:On 741224,both Channels of Offgas Radiation Monitor Taken Out of Svc to Repair Leaking Flow Indicator. Cause Not Stated ML20085G1801974-12-19019 December 1974 Telecopy RO BFAO-50-260/7436T:on 741218,drywell Air Sampling Monitor Failed.Cause Not Stated ML20085G2561974-12-18018 December 1974 Telecopy RO BFAO-50-260/7435T:on 741218,RHR Valve 2-FCV-74-66 Closed During Routine Surveillance Testing & Could Not Be Opened.Cause Not Stated 1997-11-14 Category:TEXT-SAFETY REPORT MONTHYEARML18039A9041999-10-15015 October 1999
[Table view]LER 99-010-00:on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily ML18039A8981999-10-14014 October 1999 LER 99-009-00:on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug ML18039A8951999-10-0808 October 1999 LER 99-008-00:on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions ML18039A8751999-09-30030 September 1999 LER 99-005-00:on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With 990930 Ltr ML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20212E6341999-09-23023 September 1999 Suppl to SE Resolving Error in Original 990802 Se,Clarifying Fact That Licensee Has Not Committed to Retain Those Specific Compensatory Measures That Were Applied to one-time Extension ML20212D3831999-09-20020 September 1999 Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV ML20212B8561999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Browns Ferry Nuclear Plant.With ML18039A8821999-08-31031 August 1999 Increased MSIV Leakage Tech Spec Change Submittal - Seismic Evaluation Rept. ML18039A8391999-08-0606 August 1999 BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts. ML20210N1221999-08-0202 August 1999 Safety Evaluation Accepting Licensee Request for Relief from ASME B&PV Code,Section XI Requirements.Request 3-ISI-7, Pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210R0931999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8201999-07-26026 July 1999 LER 99-004-00:on 990625,facility Core Spray Divisions I & II Inoperable at Same Time Due to Personnel Error.Electrical Supply Breaker to Core Spray Division II Pump 3B Returned to Normal Racked in Position ML18039A8171999-07-20020 July 1999 LER 99-007-00:on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With 990720 Ltr ML18039A8161999-07-19019 July 1999 LER 99-006-00:on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With 990719 Ltr ML20209J0771999-07-16016 July 1999 Safety Evaluation Concluding That Licensee Provided Adequate Information to Resolve ampacity-related Points of Concern Raised in GL 92-08 for BFN & That No Outstanding Issues Re GL 92-08 Ampacity Issues for Browns Ferry NPP Exist ML18039A8121999-07-12012 July 1999 LER 99-005-00:on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With 990712 Ltr ML20209H4381999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8101999-06-28028 June 1999 LER 99-004-00:on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset ML20196F8811999-06-23023 June 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves ML18039A8071999-06-14014 June 1999 LER 99-003-00:on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram ML18039A8021999-06-14014 June 1999 LER 99-002-00:on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With 990614 Ltr ML18039A8011999-06-14014 June 1999 LER 99-001-00:on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With 990614 Ltr ML20196B8051999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A7791999-05-0606 May 1999 LER 99-003-00:on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened ML18039A7761999-04-30030 April 1999 Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3. ML20206R0731999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Bfnp.With ML18039A7561999-04-23023 April 1999 Bfnp Risk-Informed Inservice Insp (RI-ISI) Program Submittal. ML18039A7671999-04-0808 April 1999 Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr. ML18039A7461999-04-0707 April 1999 LER 99-001-00:on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20205F9341999-04-0101 April 1999 Safety Evaluation Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST Testing,Valve Program for Plant,Units 1,2 & 3 ML20205T5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bfnp.With ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205S0661999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with No Status Change from Previous Update,990331, Atlas Corp ML18039A7361999-03-11011 March 1999 Rev 4 to TVA-COLR-BF2C10, Bfnp,Unit 2,Cycle 10 Colr. ML20204C7891999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A6951999-02-19019 February 1999 LER 99-002-00:on 990122,LCO Was Not Entered During Calibration Testing of 3D 480 Volt Rmov Board.Caused by Personnel Error.Tva Has Briefed Operations Personnel to Preclude Recurrence of Event.With 990219 Ltr ML18039A6871999-02-12012 February 1999 LER 99-001-00:on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With 990212 Ltr ML18039A6931999-02-0303 February 1999 Rev 3 to TVA-COLR-BF2C10, Bfnp Unit 2 Cycle 10 Colr. ML18039A6941999-02-0303 February 1999 Rev 1 to TVA-COLR-BF3C9, Bfnp Unit 3 Cycle 9 Colr. ML18039A6671998-12-31031 December 1998 LER 98-004-00:on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With 981231 Ltr ML18039A6661998-12-31031 December 1998 Ro:On 981215,HRPCRM 2-RM-90-273C Was Declared Inoperable. Caused by Downscale Indication.Containment RM Will Be Utilized as Planned Alternate Method of Monitoring Until Hrpcrm 2-RM-90-273C Can Be Returned to Operable Status ML20199K8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Browns Ferry Nuclear Plant.With ML20199F2721998-12-31031 December 1998 ISI Summary Rept (NIS-1), for BFN Unit 3,Cycle 8 Operation ML18039A6471998-12-15015 December 1998 LER 98-007-00:on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor ML18039A6371998-12-0707 December 1998 LER 98-006-00:on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With 981207 Ltr ML20199F2791998-12-0303 December 1998 Bfnp Unit 3 Cycle 8 ASME Section XI NIS-2 Data Rept ML20198D9621998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bfn,Units 1,2 & 3. with ML18039A6071998-11-12012 November 1998 LER 98-005-00:on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.With 981112 Ltr 1999-09-30 |
Text
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r cp v> c-TELECOPY TO NRC $ 7%
May 24, 1983 3 70 v3 ?9 s
3@a U. S. Nuclear Regulatory Commission Region II y,/ Q$
-n t 101 Marietta Street, NW **
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Suite 3100 Atlanta,-Georgia 30303 $ v BFRO-50-296/8331 Reported under Technical Specification 6.7.2.A.5 Telecony : Date 5/23/83 Time: 1530 Telechone : Date 5/23/83 Time: 1500 Person Contacted : Ross Butcher Date of Occurrence: 5/20/83 Time of Occurrence: 0900 Unit 3 Technical Specification Involved: 3 2.B Conditions Prior to Occurrence Unit 1 - refueling outage Unit 2 - normal operation 3194 wt Unit 3 - normal operation 3287 MWt Identification and Descrintion of Occurrence During routine surveillance testing (Surveillance Instruction 4.2.B-7) reactor low-pressure switches PS-3-74B switch 2 and PS-68-96 switch 2 were found below technical specification limits. The greatest out-of-tolerance was 1.2 percent below technical specification limits.
Annarent Cause of Occurrence Setpoint drift
.Qther Related Events BFRO-50-259/81038, 81064, 82038, 77002 BFRO-50-260/83002, 81033, 78018, 82003, 82013 BFRO-50-296/79010, 79028 Corrective Action Taken or Planned g$
a-Setpoints were reset to their proper value, and the surveillance
- Q instructions completed satisfactorily. Additionally, a design change En request (DCR 1398) has been initiated to replace these switches with an p8 analog transmitter trip switch.
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.g J. A. Coffey ME Acting Power Plant Superintendent
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Browns Ferry Nuclear Plant OFFICIAL COP Ig
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