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| {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM,(RIDS) | | {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM,(RIDS) |
| ACCESSION NBR: 9105170317 DOC.DATE: 91/05/11 NOTARIZED: | | ACCESSION NBR: 9105170317 DOC. DATE: 91/05/11 NOTARIZED: NO DOCKET FACIL:50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION WALLACE,J.E. Tennessee Valley Authority BYNUM,J.R. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION |
| NO DOCKET FACIL:50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH.NAME AUTHOR AFFILIATION WALLACE,J.E. | |
| Tennessee Valley Authority BYNUM,J.R. | |
| Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 91-003-00:on 910412,unplanned ESF occurred when four Unit 3 EDG unexpectedly auto-started during performance of common accident signal logic surveillance instruction.TVA suppl LER rept will be submitted 910617.W/910511 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR 3 ENCL L SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Tnciden&Rpt, etc.NOTES:1 Copy each to: S.Black,B.WILSON 05000296 RECIPIENT ID CODE/NAME KREBS,M.ROSS,T.INTERNAL: ACNW AEOD/DOA AEOD/ROAB/DSP NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7E NRR/DST/SRXB 8E RES/DSIR/EIB EXTERNAL EG&G BRYCE I J~H NRC PDR NSIC POORE,W.NOTES: COPIES LTTR ENCL 1'1 1 2 2 1 1 2 2 1 1 1 1 2 2 1 1 1 1 1 1 3 3 1 1 1 1 5 5 RECIPIENT ID CODE/NAME HEBDON,F ACRS AEOD/DSP/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFB11 NRR/DOEA/OEAB NRR/DST/SELB 8D NRR/D~S/SgLB8D1 REG.R7LE~=012 RGN2 FILE 01 L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 2'1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS: | | LER 91-003-00:on 910412,unplanned ESF occurred when four Unit 3 EDG unexpectedly auto-started during performance of common accident signal logic surveillance instruction.TVA suppl LER rept will be submitted 910617.W/910511 ltr. |
| y PLEASE-HELP US TO REDUCE Oi'ASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOXI Pl-37 (EXT.20079)TO'ELliXIINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 38 ENCL'38 IN J Tennessee Vatley Authority, t>0>Mar>ret Street.Chattanooga. | | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR 3 ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), Tnciden&Rpt, etc. |
| Tennessee 37402 Joseph R.Bynum Vice President Nuctear Operations QY i.i 18SlU.S.Nuclear Regulatory Commission ATTN: Document Control Desk washington, D.C.20555
| | L SIZE: |
| | NOTES:1 Copy each to: S. Black,B.WILSON 05000296 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL KREBS,M. 1' HEBDON,F 1 1 ROSS,T. 1 1 INTERNAL: ACNW 2 2 ACRS 2' AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB11 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/D~S/SgLB8D1 1 1 NRR/DST/SRXB 8E 1 1 REG .R7LE~=012 1 1 RES/DSIR/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL EG&G BRYCE I J ~ H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 NOTES: 5 5 NOTE TO ALL "RIDS" RECIPIENTS: |
| | y PLEASE -HELP US TO REDUCE Oi'ASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOXI Pl-37 (EXT. 20079) TO'ELliXIINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| | FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 38 ENCL '38 |
|
| |
|
| ==Dear Sir:==
| | IN J |
| TVA-BROWNS FERRY NUCLEAR PLANT (BFN)UNIT 3-DOCKET NO'.50-296-FACILITY OPERATING LICENSE DPR-68-REPORTABLE OCCURRENCE REPORT BFRO-50-296/91003 The enclosed report provides details concerning an unplanned engineered safety feature actuation that occurred resulting from personnel error while performing a common accident signal logic surveillance instruction.
| |
| This report is submitted in accordance with 10 CFR 50.73(a)(2)(IV).
| |
| TVA is continuing is investigation of this event and will issue a supplement to this report by June 17, 1991.Very truly yours, TENNESSEE VALLEY AUTHORITY h R.Bynum Enclosure cc: see page 2
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| U.S.Nuclear Regulatory Commission cc (Enclosure): | | Tennessee Vatley Authority, t >0> Mar>ret Street. Chattanooga. Tennessee 37402 Joseph R. Bynum Vice President Nuctear Operations QY i.i 18Sl U.S. Nuclear Regulatory Commission ATTN: Document Control Desk washington, D.C. 20555 |
| INPO Records Center Suite 1500 1100.Circle 75 Parkway Atlanta, Georgia 30339 NRC Resident Inspector, BFN Regional Administration U.S.Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, Suite 2900 Atlanta, Georgia 30323 Thierry M.Ross U.S.Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 i5 0 l. | | |
| NRC Form 366 (6-89)U.S.NUCLEAR REGULATORY COMMISSION i LICENSEE EVENT REPORT (LER)Approved OMB No.3150-0104 Expires 4/30/92 FACILITY NAHE (1)B w 1)DOCKET NUHBER (2))g~~~TITLE (4)An Unplanned Engineered Safety Feature Occurred From Personnel Error While Performing a Comnon Accident 1 i v'1 r V NT P T I I I.I I SE()UENTIAL I IREVISIONI I I I FACILITY NAMES N A N I I I I I I I I I I I ,,)DOCKET NUMBER(S)OPERATING MODE I ITHIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: I r f 1 w'OWER I LEVEL l I20.402(b) | | ==Dear Sir:== |
| I=I20.405(a)(l)(i) | | |
| )20.405(a)(1)(ii)
| | TVA BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 3 DOCKET NO'. 50-296 FACILITY OPERATING LICENSE DPR-68 REPORTABLE OCCURRENCE REPORT BFRO-50-296/91003 The enclosed report provides details concerning an unplanned engineered safety feature actuation that occurred resulting from personnel error while performing a common accident signal logic surveillance instruction. This report is submitted in accordance with 10 CFR 50.73(a)(2)(IV). |
| [20.405(a)(l)(iii)f20.405(a)(1)(iv) v-l20 405(c)F50.36(c)(1))50.36(c)(2) | | TVA is continuing is investigation of this event and will issue a supplement to this report by June 17, 1991. |
| I l50 73(a)(2)(i) f50.73(a)(2)(ii)
| | Very truly yours, TENNESSEE VALLEY AUTHORITY h |
| I (~[50.73(a)(2)(iv) | | R. Bynum Enclosure cc: see page 2 |
| [50.73(a)(2)(v) | | |
| )50.73(a)(2)(vii) | | U.S. Nuclear Regulatory Commission cc (Enclosure): |
| [50.73(a)(2)(viii)(A)
| | INPO Records Center Suite 1500 1100. Circle 75 Parkway Atlanta, Georgia 30339 NRC Resident Inspector, BFN Regional Administration U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, Suite 2900 Atlanta, Georgia 30323 Thierry M. Ross U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 |
| )50.73(a)(2)(viii)(B) | | |
| I73.71(b)i73.71(c)]OTHER (Specify in Abstract below and in j Text, NRC Form 366A)NT TF T m W 1 1'1 r]AREA CODE (P N N F MPNN I I I IREPORTABLEf A YTM NNT NF T P D I I P N F T)REPORTABLE' PPL M P T P D 14 I SUBMISSION i f ml XP TD I NOT N AT ABSTRACT (Limit to 1400 spaces, i.e., approximately.
| | i5 0 l. |
| fifteen single-space typewritten lines)(16)On April 12, 1991 at 1817,hours, an unplanned Engineered Safety Feature actuation occurred when the four Unit 3 emergency diesel generators unexpectedly auto-started during the performance of common accident signal logic Surveillance Instruction. | | |
| TUA is presently conducting an investigation of this event.TVA will report the results in a supplement to this Licensee Event Report.NRC Form 366(6-89) | | NRC (6-89) |
| II iJ NRC Form 366A (6-89).NUCLEAR REGULATORY CONNISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION Approved OMB No.3150-0104 Expires 4/30/92 FACILITY NANE (1)[DOCKET NUNOER (2)'I H I I ISEQUENTIAL | | Form 366 FACILITY NAHE (1) |
| /)REVISIONI I I I I I I I I TEXT (If more space is required, use additional NRC Form 366A's)'(l7)On April 12, 1991, at 1817 hours CST, an unplanned engineered safety feature (ESF)actuation occurred during the performance of Common Accident Signal (CAS)Logic Surveillance Instruction (SI)1/2 SI-4.9.A.3.a, when the four Unit 3 emergency diesel generators (EDGs)[EK]unexpectedly auto-started. | | B w 1 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) i Approved OMB No. 3150-0104 Expires 4/30/92 |
| In addition,.the Unit 3 4kV shutdown board manual transfer switches[EB]tripped to manual, and A3 residual heat removal service water (RHRSW)[CC]pump also started.The Unit 1/2 Common Accident Signal Logic Surveillance is performed to verify that both divisions of the CAS logic will function on actuation of the Core Spray (CS)System of each reactor to provide an automatic start signal to all 4 Unit 1/2 EDGs and 4 RHRSW pumps and blocks transfer to the 4KV shutdown buses and boards.On.April 12, 1991, Division I testing of 1/2-SI-'4.9.A.3.a was completed at 1600 hours and Division II of the CAS logic testing was started at 1630 hours.At.approximately 1817 hours, the CAS logic circuitry was aligned for testing relay CASB-1.This involved placing test switches for the remaining relays of the division in the TEST position to prevent undesired init'iation of Units 1/2 ESF equipment. | | )DOCKET NUHBER (2) )g~~~ |
| The CASB-1 relay[RLX]was then energized using the CASB-C test switch.Contacts were verified to be operating properly, and the appropriate trip to manual bus reset circuit relays were verified to trip.Boots were installed on contacts 11-12 of the CS logic relay to inhibit a Unit 2 accident signal to the Unit 3 CAS logic circuitry. | | TITLE (4) An Unplanned Engineered Safety Feature Occurred From Personnel Error While Performing a Comnon Accident 1 i v'1 r V NT P T I I I . |
| A jumper with an in-line test switch in the open position was installed to the CS logic relay coil.The in-line test switch was closed, energizing CS logic relay.CASB-C test switch was then placed in the NORNAL position, and relay CASB-1 was verified to remain energized. | | I I SE()UENTIAL I IREVISIONI I I I FACILITY NAMES ,, )DOCKET NUMBER(S) |
| The in-line test switch was then opened, and relay CASB-1 verified to be de-energized. | | N A N I I I I I I I I I I I OPERATING I ITHIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: |
| Since this SI was being performed on Unit 2 and only the four Unit 3 EDGs actuated, the ENs did not realize that the Unit 3 EDGs had actuated.ENs continued performing the SI.At 1820 hours, ENs attempted to contact an Auxiliary Unit Operator (utility, non-licensed) to place the Unit 2 Division II CASB-1 in TEST position.At that time, the ENs were notified that the Unit 3 EDGs had actuated.The SI was stopped.Shutdown activity was completed by 1940 hours after the Unit Operator (utility, licensed)completed the manual shutdown of the Unit 3 EDGs.I EN TVA will issue a supplement to this Licensee Event Report by June 17, 1991.Energy Industry Identification System (EIIS)codes are identified in the text as[xx].NRC Form 366(6-89) iO t}} | | MODE I r f 1 I20.402(b) l20 405(c) w'OWER |
| | (~[50.73(a)(2)(iv) I73.71(b) |
| | I I=I20.405(a)(l)(i) F50.36(c)( 1) [50.73(a)(2)(v) i73.71(c) |
| | LEVEL l )20.405(a)(1)(ii) )50.36(c)(2) )50.73(a)(2)(vii) ]OTHER (Specify in |
| | [20.405(a)( l)(iii) I l50 73(a)(2)(i) [50.73(a)(2)(viii)(A) Abstract below and in f20.405(a)(1)(iv) f50.73(a)(2)(ii) )50.73(a)(2)(viii)(B) j Text, NRC Form 366A) v I NT TF T |
| | ] AREA CODE ( |
| | m W 1 1' 1 r P N N F MPNN I I I IREPORTABLEf I I )REPORTABLE' A YTM NNT NF T P D P N F T PPL M P T P D 14 I SUBMISSION i f ml XP TD I NOT N AT ABSTRACT (Limit to 1400 spaces, i.e., approximately. fifteen single-space typewritten lines) (16) |
| | On April 12, 1991 at 1817,hours, an unplanned Engineered Safety Feature actuation occurred when the four Unit 3 emergency diesel generators unexpectedly auto-started during the performance of common accident signal logic Surveillance Instruction. |
| | TUA is presently conducting an investigation of this event. TVA will report the results in a supplement to this Licensee Event Report. |
| | NRC Form 366(6-89) |
| | |
| | II iJ NRC Form 366A . NUCLEAR REGULATORY CONNISSION Approved OMB No. 3150-0104 (6-89) Expires 4/30/92 LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION FACILITY NANE (1) |
| | ' |
| | [DOCKET NUNOER (2) |
| | I I ISEQUENTIAL / )REVISIONI I I I I I I I I I H |
| | TEXT (If more space is required, use additional NRC Form 366A's) '(l7) |
| | On April 12, 1991, at 1817 hours CST, an unplanned engineered safety feature (ESF) actuation occurred during the performance of Common Accident Signal (CAS) |
| | Logic Surveillance Instruction (SI) 1/2 SI-4.9.A.3.a, when the four Unit 3 emergency diesel generators (EDGs) [EK] unexpectedly auto-started. In addition, |
| | .the Unit 3 4kV shutdown board manual transfer switches [EB] tripped to manual, and A3 residual heat removal service water (RHRSW) [CC] pump also started. |
| | The Unit 1/2 Common Accident Signal Logic Surveillance is performed to verify that both divisions of the CAS logic will function on actuation of the Core Spray (CS) System of each reactor to provide an automatic start signal to all 4 Unit 1/2 EDGs and 4 RHRSW pumps and blocks transfer to the 4KV shutdown buses and boards. |
| | On .April 12, 1991, Division I testing of 1/2-SI-'4.9.A.3.a was completed at 1600 hours and Division II of the CAS logic testing was started at 1630 hours. At |
| | .approximately 1817 hours, the CAS logic circuitry was aligned for testing relay CASB-1. This involved placing test switches for the remaining relays of the division in the TEST position to prevent undesired init'iation of Units 1/2 ESF equipment. The CASB-1 relay [RLX] was then energized using the CASB-C test switch. Contacts were verified to be operating properly, and the appropriate trip to manual bus reset circuit relays were verified to trip. Boots were installed on contacts 11-12 of the CS logic relay to inhibit a Unit 2 accident signal to the Unit 3 CAS logic circuitry. A jumper with an in-line test switch in the open position was installed to the CS logic relay coil. The in-line test switch was closed, energizing CS logic relay. CASB-C test switch was then placed in the NORNAL position, and relay CASB-1 was verified to remain energized. The in-line test switch was then opened, and relay CASB-1 verified to be de-energized. |
| | Since this SI was being performed on Unit 2 and only the four Unit 3 EDGs actuated, the ENs did not realize that the Unit 3 EDGs had actuated. ENs continued performing the SI. At 1820 hours, ENs attempted to contact an Auxiliary Unit Operator (utility, non-licensed) to place the Unit 2 Division II CASB-1 in TEST position. At that time, the ENs were notified that the Unit 3 EDGs had actuated. The SI was stopped. Shutdown activity was completed by 1940 hours after the Unit Operator (utility, licensed) completed the manual shutdown of the Unit 3 EDGs. |
| | I EN TVA will issue a supplement to this Licensee Event Report by June 17, 1991. |
| | Energy Industry Identification System (EIIS) codes are identified in the text as |
| | [xx]. |
| | NRC Form 366(6-89) |
| | |
| | iO t}} |
|
|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18039A9041999-10-15015 October 1999
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
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
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
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
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
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
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
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
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
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
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
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
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
ML18039A6031998-11-0404 November 1998
LER 98-004-00:on 981007,primary Containment Allowable Leak Rate Was Exceeded.Caused by Failure of Check Valve to Fully Seat Following Shutdown of Rbbccw Sys for Llrt.Valve Was Retested During Next Refueling Outage.With 981104 Ltr
ML18039A5971998-10-28028 October 1998
LER 98-003-00:on 981001,Unit 2 Received Full Automatic Scram from 100% Reactor Power.Caused by Failure of Normally Open Isolation Valve Which Blocked Flow of Stator Cooling Water Through Associated Heat Exchangers.Replaced Failed Valve
ML18039A5171998-09-15015 September 1998
LER 98-002-00:on 980816,personnel Observed Both Channels of Rod Block Monitor Sys Bypassed for Cr.Caused by Failure of Gene to Properly Document & Specify Adjustments.Will Implement Necessary Procedure Controls
ML18039A3311998-05-0404 May 1998
LER 98-003-00:on 980407,reactor Manually Scrammed to Prevent thermal-hydraulic Instability After Recirculation Pump Runback.Caused by Human Error.Strengthened Controls Associated W/Walkdowns in NEDP-11
ML18039A3141998-04-0909 April 1998
LER 98-002-00:on 980310,ESF Actuation Occurred Due to Failure of Alternate Feeder Breaker Position Switch.Will Continue Testing & Visual Insps on Addl Breaker Position Switches & Will Revise Applicable Maint Instructions
ML18039A3101998-04-0707 April 1998
LER 98-001-00:on 980308,ESF Actuations Occurred When 2B RPS Bus Was Transferred to de-energized Source.Caused by Failure of Preparing Clearance to Exercise Proper Attention. 2B RPS Bus Restored to Transformer Source
ML18039A3051998-04-0101 April 1998
LER 96-001-00:on 980121,determined That Temp Sensors for Certain HELB May Not Detect All Possible Break Locations. Caused by Differences in Computer Codes Rather than Actual Response.Computer Code Correctly Utilized
ML18039A2041997-12-0303 December 1997
LER 97-008-00:on 971104,main Steam Safety/Relief Valves Exceeded TS Setpoint Limit.Caused by Pilot Valve Disc/Seat Bonding.Replaced All 13 Unit 2 Main Steam SRV Pilot Cartridges
ML18038B9961997-11-25025 November 1997
LER 97-007-00:on 971028,Unit 2 Automatically Scrammed.Caused by Momentary Pressure Drop in electro-hydraulic Control Sys at Turbine Control Valves.Scram Contactor Replaced
ML18038B9931997-11-18018 November 1997
LER 97-006-00:on 971019,declared Unit 2 Hpcis Inoperable. Caused by High Condensate Level in HPCI Turbine Inlet Steam Line Drain Pot.Work Request Initiated
ML18038B9861997-11-10010 November 1997
LER 97-005-00:on 971012,ESF Components Were Actuated.Caused by Inadequate Procedure.Cs Pumps Were Secured & Injection Valves Were Closed & Refueling Floor Activities Were Stopped
ML18038B9701997-10-0909 October 1997
LER 97-004-00:on 970909,TS Surveillances Were Not Performed During Refueling Outage Timeframe.Caused by Personnel Error. Incorporated Missed Snubber & Vacuum Breaker Surveillances Into Refueling Outage Schedule
ML18038B9661997-10-0303 October 1997
LER 97-005-00:on 970824,LCO Was Not Entered When Valve Was Malfunctioning.Caused by Lack of Questioning Attitude by Operations Crew.Involved SROs Were Counseled & Problem Evaluation Rept Will Be Discussed
ML18038B9321997-08-0707 August 1997
LER 97-003-00:on 970711,determined That HPCI Turbine Speed Lower than Indicated.Caused by Improper Evaluation of Valve Leak.Work Orders to Troubleshoot HPCI Initiated
ML18038B9231997-07-25025 July 1997
LER 97-002-00:on 970626,discovered That Four Surveillance Instructions (Sis) Did Not Fully Test All Relay Logic Combinations.Caused by Personnel Error.Verified Relay Contacts Operable & Revised Applicable SIs.W/970725 Ltr
ML18038B8811997-05-14014 May 1997
LER 97-004-00:on 970414,unplanned Manual Start of EDG During Scheduled Redundant Start Test Occurred.Caused by Personnel Error.Edg 3D Shutdown & Returned to pre-event Configuration. W/970514 Ltr
ML18038B8801997-05-0808 May 1997
LER 97-002-00:on 970410,HPCI Declared Inoperable.Caused by Personnel Error.Operations Personnel Stopped Instrument Mechanics Testing & Returned HPCI to Standby Readiness. W/970508 Ltr
ML18038B8701997-04-29029 April 1997
LER 96-004-02:on 960717,loss of ECCS Division I & Division II Instrumentation Renders ECCS Equipment Inoperable.Caused by Loss of Inverter Output.Failed Components Replaced in Atu Inverter Circuitry & Instrumentation Logic Restored
ML18038B8521997-04-0909 April 1997
LER 97-003-00:on 970314,Unit 3 Main Steam SRVs Pilot Cartridges Failed Setpoint Tolerance Bench Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Drifting.Main Steam SRV Pilot replaced.W/970409 Ltr
ML18038B8511997-04-0909 April 1997
LER 95-003-02:on 950301,Unit 2 Main Steam SRVs Failed Setpoint Acceptance Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Upward Setpoint Drift.Valves Currently Being Retested & Recertified
ML18038B8481997-04-0909 April 1997
LER 96-004-01:on 960425,Unit 2 SRV Pilot Cartridges Failed Setpoint Acceptance Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints Deviating.Valves Currently Being Retested & Recertified
ML18038B8451997-04-0909 April 1997
LER 96-008-01:on 961101,Unit 2 Main Steam SRV Pilot Cartridges Failed Setpoint Tolerence Bench Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints.Srv Pilot Cartridges replaced.W/970409 Ltr
ML18038B8551997-04-0404 April 1997
LER 97-001-00:on 970305,loss of Offsite Power on Unit 3 During Refueling Outage Resulted from Shorted Component. Replaced Relays Involved in Event W/Less Sensitive Relays
ML18038B8441997-03-26026 March 1997
LER 95-001-02:on 950123,DG Turbocharger Failure Resulted in Noncompliance W/Ts Lco.Instituted Vibration Monitoring Program for EDG Turbochargers
ML18038B8071997-01-15015 January 1997
LER 96-008-00:on 961217,loss of ECCS Division II Instrumentation Caused ECCS Equipment to Be Inoperable. Replaced Cleared Fuse & Shorted SCR
ML18038B8041997-01-13013 January 1997
LER 96-007-00 on 961213,engineered Safety Feature Actuations Resulting from Inadequate Planning of step-text Work Order Occurred.Tripped Breaker Reset & LCO Condition Exited
ML18038B7931996-12-0404 December 1996
LER 96-006-00:on 961106,loss of ECCS Div 1 Instrumentation Rendered ECCS Equipment Inoperable.Caused by Cleared Fuse in ECCS Div.Fuse Replaced & Addl Testing to Challenge Replacement Fuse performed.W/961204 Ltr
ML18038B7921996-11-27027 November 1996
LER 96-008-00:on 961101,MS SR Valves Exceeded TS Required Setpoint Limit as Result of Disc/Seat Bonding.Caused by Corrosion Bonding of SRV Pilot Interface.Replaced All Thirteen Ms SR Valve Pilot cartridges.W/961127 Ltr
ML18038B7911996-11-27027 November 1996
LER 96-007-00:on 961029,Unit 2 Scram on Turbine Control Valve Fast Closure Occurred Due to Loss of Excitation to Main Generator.Exciter Brushes Inspected & Replaced & Procedures Revised
ML18038B7741996-10-15015 October 1996
LER 96-005-03:on 960915,reactor Scrammed as Required by TSs Due to Trip of Reactor Recirculation Motor Generator Set 3A. Caused by Bus Bar in Generator Armature Circuit Failing. Collector Rings Were replaced.W/961015 Ltr
1999-09-30
[Table view]
Category:RO)
MONTHYEARML18039A9041999-10-15015 October 1999
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
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
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
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
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
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
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
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
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
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
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
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
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
ML18039A6031998-11-0404 November 1998
LER 98-004-00:on 981007,primary Containment Allowable Leak Rate Was Exceeded.Caused by Failure of Check Valve to Fully Seat Following Shutdown of Rbbccw Sys for Llrt.Valve Was Retested During Next Refueling Outage.With 981104 Ltr
ML18039A5971998-10-28028 October 1998
LER 98-003-00:on 981001,Unit 2 Received Full Automatic Scram from 100% Reactor Power.Caused by Failure of Normally Open Isolation Valve Which Blocked Flow of Stator Cooling Water Through Associated Heat Exchangers.Replaced Failed Valve
ML18039A5171998-09-15015 September 1998
LER 98-002-00:on 980816,personnel Observed Both Channels of Rod Block Monitor Sys Bypassed for Cr.Caused by Failure of Gene to Properly Document & Specify Adjustments.Will Implement Necessary Procedure Controls
ML18039A3311998-05-0404 May 1998
LER 98-003-00:on 980407,reactor Manually Scrammed to Prevent thermal-hydraulic Instability After Recirculation Pump Runback.Caused by Human Error.Strengthened Controls Associated W/Walkdowns in NEDP-11
ML18039A3141998-04-0909 April 1998
LER 98-002-00:on 980310,ESF Actuation Occurred Due to Failure of Alternate Feeder Breaker Position Switch.Will Continue Testing & Visual Insps on Addl Breaker Position Switches & Will Revise Applicable Maint Instructions
ML18039A3101998-04-0707 April 1998
LER 98-001-00:on 980308,ESF Actuations Occurred When 2B RPS Bus Was Transferred to de-energized Source.Caused by Failure of Preparing Clearance to Exercise Proper Attention. 2B RPS Bus Restored to Transformer Source
ML18039A3051998-04-0101 April 1998
LER 96-001-00:on 980121,determined That Temp Sensors for Certain HELB May Not Detect All Possible Break Locations. Caused by Differences in Computer Codes Rather than Actual Response.Computer Code Correctly Utilized
ML18039A2041997-12-0303 December 1997
LER 97-008-00:on 971104,main Steam Safety/Relief Valves Exceeded TS Setpoint Limit.Caused by Pilot Valve Disc/Seat Bonding.Replaced All 13 Unit 2 Main Steam SRV Pilot Cartridges
ML18038B9961997-11-25025 November 1997
LER 97-007-00:on 971028,Unit 2 Automatically Scrammed.Caused by Momentary Pressure Drop in electro-hydraulic Control Sys at Turbine Control Valves.Scram Contactor Replaced
ML18038B9931997-11-18018 November 1997
LER 97-006-00:on 971019,declared Unit 2 Hpcis Inoperable. Caused by High Condensate Level in HPCI Turbine Inlet Steam Line Drain Pot.Work Request Initiated
ML18038B9861997-11-10010 November 1997
LER 97-005-00:on 971012,ESF Components Were Actuated.Caused by Inadequate Procedure.Cs Pumps Were Secured & Injection Valves Were Closed & Refueling Floor Activities Were Stopped
ML18038B9701997-10-0909 October 1997
LER 97-004-00:on 970909,TS Surveillances Were Not Performed During Refueling Outage Timeframe.Caused by Personnel Error. Incorporated Missed Snubber & Vacuum Breaker Surveillances Into Refueling Outage Schedule
ML18038B9661997-10-0303 October 1997
LER 97-005-00:on 970824,LCO Was Not Entered When Valve Was Malfunctioning.Caused by Lack of Questioning Attitude by Operations Crew.Involved SROs Were Counseled & Problem Evaluation Rept Will Be Discussed
ML18038B9321997-08-0707 August 1997
LER 97-003-00:on 970711,determined That HPCI Turbine Speed Lower than Indicated.Caused by Improper Evaluation of Valve Leak.Work Orders to Troubleshoot HPCI Initiated
ML18038B9231997-07-25025 July 1997
LER 97-002-00:on 970626,discovered That Four Surveillance Instructions (Sis) Did Not Fully Test All Relay Logic Combinations.Caused by Personnel Error.Verified Relay Contacts Operable & Revised Applicable SIs.W/970725 Ltr
ML18038B8811997-05-14014 May 1997
LER 97-004-00:on 970414,unplanned Manual Start of EDG During Scheduled Redundant Start Test Occurred.Caused by Personnel Error.Edg 3D Shutdown & Returned to pre-event Configuration. W/970514 Ltr
ML18038B8801997-05-0808 May 1997
LER 97-002-00:on 970410,HPCI Declared Inoperable.Caused by Personnel Error.Operations Personnel Stopped Instrument Mechanics Testing & Returned HPCI to Standby Readiness. W/970508 Ltr
ML18038B8701997-04-29029 April 1997
LER 96-004-02:on 960717,loss of ECCS Division I & Division II Instrumentation Renders ECCS Equipment Inoperable.Caused by Loss of Inverter Output.Failed Components Replaced in Atu Inverter Circuitry & Instrumentation Logic Restored
ML18038B8521997-04-0909 April 1997
LER 97-003-00:on 970314,Unit 3 Main Steam SRVs Pilot Cartridges Failed Setpoint Tolerance Bench Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Drifting.Main Steam SRV Pilot replaced.W/970409 Ltr
ML18038B8511997-04-0909 April 1997
LER 95-003-02:on 950301,Unit 2 Main Steam SRVs Failed Setpoint Acceptance Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Upward Setpoint Drift.Valves Currently Being Retested & Recertified
ML18038B8481997-04-0909 April 1997
LER 96-004-01:on 960425,Unit 2 SRV Pilot Cartridges Failed Setpoint Acceptance Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints Deviating.Valves Currently Being Retested & Recertified
ML18038B8451997-04-0909 April 1997
LER 96-008-01:on 961101,Unit 2 Main Steam SRV Pilot Cartridges Failed Setpoint Tolerence Bench Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints.Srv Pilot Cartridges replaced.W/970409 Ltr
ML18038B8551997-04-0404 April 1997
LER 97-001-00:on 970305,loss of Offsite Power on Unit 3 During Refueling Outage Resulted from Shorted Component. Replaced Relays Involved in Event W/Less Sensitive Relays
ML18038B8441997-03-26026 March 1997
LER 95-001-02:on 950123,DG Turbocharger Failure Resulted in Noncompliance W/Ts Lco.Instituted Vibration Monitoring Program for EDG Turbochargers
ML18038B8071997-01-15015 January 1997
LER 96-008-00:on 961217,loss of ECCS Division II Instrumentation Caused ECCS Equipment to Be Inoperable. Replaced Cleared Fuse & Shorted SCR
ML18038B8041997-01-13013 January 1997
LER 96-007-00 on 961213,engineered Safety Feature Actuations Resulting from Inadequate Planning of step-text Work Order Occurred.Tripped Breaker Reset & LCO Condition Exited
ML18038B7931996-12-0404 December 1996
LER 96-006-00:on 961106,loss of ECCS Div 1 Instrumentation Rendered ECCS Equipment Inoperable.Caused by Cleared Fuse in ECCS Div.Fuse Replaced & Addl Testing to Challenge Replacement Fuse performed.W/961204 Ltr
ML18038B7921996-11-27027 November 1996
LER 96-008-00:on 961101,MS SR Valves Exceeded TS Required Setpoint Limit as Result of Disc/Seat Bonding.Caused by Corrosion Bonding of SRV Pilot Interface.Replaced All Thirteen Ms SR Valve Pilot cartridges.W/961127 Ltr
ML18038B7911996-11-27027 November 1996
LER 96-007-00:on 961029,Unit 2 Scram on Turbine Control Valve Fast Closure Occurred Due to Loss of Excitation to Main Generator.Exciter Brushes Inspected & Replaced & Procedures Revised
ML18038B7741996-10-15015 October 1996
LER 96-005-03:on 960915,reactor Scrammed as Required by TSs Due to Trip of Reactor Recirculation Motor Generator Set 3A. Caused by Bus Bar in Generator Armature Circuit Failing. Collector Rings Were replaced.W/961015 Ltr
1999-09-30
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18039A9041999-10-15015 October 1999
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
[Table view] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM,(RIDS)
ACCESSION NBR: 9105170317 DOC. DATE: 91/05/11 NOTARIZED: NO DOCKET FACIL:50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION WALLACE,J.E. Tennessee Valley Authority BYNUM,J.R. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 91-003-00:on 910412,unplanned ESF occurred when four Unit 3 EDG unexpectedly auto-started during performance of common accident signal logic surveillance instruction.TVA suppl LER rept will be submitted 910617.W/910511 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR 3 ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), Tnciden&Rpt, etc.
L SIZE:
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Tennessee Vatley Authority, t >0> Mar>ret Street. Chattanooga. Tennessee 37402 Joseph R. Bynum Vice President Nuctear Operations QY i.i 18Sl U.S. Nuclear Regulatory Commission ATTN: Document Control Desk washington, D.C. 20555
Dear Sir:
TVA BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 3 DOCKET NO'. 50-296 FACILITY OPERATING LICENSE DPR-68 REPORTABLE OCCURRENCE REPORT BFRO-50-296/91003 The enclosed report provides details concerning an unplanned engineered safety feature actuation that occurred resulting from personnel error while performing a common accident signal logic surveillance instruction. This report is submitted in accordance with 10 CFR 50.73(a)(2)(IV).
TVA is continuing is investigation of this event and will issue a supplement to this report by June 17, 1991.
Very truly yours, TENNESSEE VALLEY AUTHORITY h
R. Bynum Enclosure cc: see page 2
U.S. Nuclear Regulatory Commission cc (Enclosure):
INPO Records Center Suite 1500 1100. Circle 75 Parkway Atlanta, Georgia 30339 NRC Resident Inspector, BFN Regional Administration U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, Suite 2900 Atlanta, Georgia 30323 Thierry M. Ross U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
i5 0 l.
NRC (6-89)
Form 366 FACILITY NAHE (1)
B w 1 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) i Approved OMB No. 3150-0104 Expires 4/30/92
)DOCKET NUHBER (2) )g~~~
TITLE (4) An Unplanned Engineered Safety Feature Occurred From Personnel Error While Performing a Comnon Accident 1 i v'1 r V NT P T I I I .
I I SE()UENTIAL I IREVISIONI I I I FACILITY NAMES ,, )DOCKET NUMBER(S)
N A N I I I I I I I I I I I OPERATING I ITHIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5:
MODE I r f 1 I20.402(b) l20 405(c) w'OWER
(~[50.73(a)(2)(iv) I73.71(b)
I I=I20.405(a)(l)(i) F50.36(c)( 1) [50.73(a)(2)(v) i73.71(c)
LEVEL l )20.405(a)(1)(ii) )50.36(c)(2) )50.73(a)(2)(vii) ]OTHER (Specify in
[20.405(a)( l)(iii) I l50 73(a)(2)(i) [50.73(a)(2)(viii)(A) Abstract below and in f20.405(a)(1)(iv) f50.73(a)(2)(ii) )50.73(a)(2)(viii)(B) j Text, NRC Form 366A) v I NT TF T
] AREA CODE (
m W 1 1' 1 r P N N F MPNN I I I IREPORTABLEf I I )REPORTABLE' A YTM NNT NF T P D P N F T PPL M P T P D 14 I SUBMISSION i f ml XP TD I NOT N AT ABSTRACT (Limit to 1400 spaces, i.e., approximately. fifteen single-space typewritten lines) (16)
On April 12, 1991 at 1817,hours, an unplanned Engineered Safety Feature actuation occurred when the four Unit 3 emergency diesel generators unexpectedly auto-started during the performance of common accident signal logic Surveillance Instruction.
TUA is presently conducting an investigation of this event. TVA will report the results in a supplement to this Licensee Event Report.
NRC Form 366(6-89)
II iJ NRC Form 366A . NUCLEAR REGULATORY CONNISSION Approved OMB No. 3150-0104 (6-89) Expires 4/30/92 LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NANE (1)
'
[DOCKET NUNOER (2)
I I ISEQUENTIAL / )REVISIONI I I I I I I I I I H
TEXT (If more space is required, use additional NRC Form 366A's) '(l7)
On April 12, 1991, at 1817 hours0.021 days <br />0.505 hours <br />0.003 weeks <br />6.913685e-4 months <br /> CST, an unplanned engineered safety feature (ESF) actuation occurred during the performance of Common Accident Signal (CAS)
Logic Surveillance Instruction (SI) 1/2 SI-4.9.A.3.a, when the four Unit 3 emergency diesel generators (EDGs) [EK] unexpectedly auto-started. In addition,
.the Unit 3 4kV shutdown board manual transfer switches [EB] tripped to manual, and A3 residual heat removal service water (RHRSW) [CC] pump also started.
The Unit 1/2 Common Accident Signal Logic Surveillance is performed to verify that both divisions of the CAS logic will function on actuation of the Core Spray (CS) System of each reactor to provide an automatic start signal to all 4 Unit 1/2 EDGs and 4 RHRSW pumps and blocks transfer to the 4KV shutdown buses and boards.
On .April 12, 1991, Division I testing of 1/2-SI-'4.9.A.3.a was completed at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> and Division II of the CAS logic testing was started at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />. At
.approximately 1817 hours0.021 days <br />0.505 hours <br />0.003 weeks <br />6.913685e-4 months <br />, the CAS logic circuitry was aligned for testing relay CASB-1. This involved placing test switches for the remaining relays of the division in the TEST position to prevent undesired init'iation of Units 1/2 ESF equipment. The CASB-1 relay [RLX] was then energized using the CASB-C test switch. Contacts were verified to be operating properly, and the appropriate trip to manual bus reset circuit relays were verified to trip. Boots were installed on contacts 11-12 of the CS logic relay to inhibit a Unit 2 accident signal to the Unit 3 CAS logic circuitry. A jumper with an in-line test switch in the open position was installed to the CS logic relay coil. The in-line test switch was closed, energizing CS logic relay. CASB-C test switch was then placed in the NORNAL position, and relay CASB-1 was verified to remain energized. The in-line test switch was then opened, and relay CASB-1 verified to be de-energized.
Since this SI was being performed on Unit 2 and only the four Unit 3 EDGs actuated, the ENs did not realize that the Unit 3 EDGs had actuated. ENs continued performing the SI. At 1820 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.9251e-4 months <br />, ENs attempted to contact an Auxiliary Unit Operator (utility, non-licensed) to place the Unit 2 Division II CASB-1 in TEST position. At that time, the ENs were notified that the Unit 3 EDGs had actuated. The SI was stopped. Shutdown activity was completed by 1940 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.3817e-4 months <br /> after the Unit Operator (utility, licensed) completed the manual shutdown of the Unit 3 EDGs.
I EN TVA will issue a supplement to this Licensee Event Report by June 17, 1991.
Energy Industry Identification System (EIIS) codes are identified in the text as
[xx].
NRC Form 366(6-89)
iO t
