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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000457/LER-1993-0061993-08-26026 August 1993 LER 93-006-00:on 930727,2A RHR Pump Motor Bearing Oil Reservoir Unable to Be Drained,During Oil Change.Caused by Corrosion Particles Resulting from Previous Seal Leak.Rhr 2A Pump replaced.W/930826 Ltr 05000457/LER-1993-0041993-08-11011 August 1993 LER 93-004-00:on 930712,time Frame for Performing Core Normalization Surveillance Exceeded Due to Personnel Error. Commenced Performance of Required Surveillance.Surveillance Procedure Bwvs 1.1.1.2-1 Will Be revised.W/930811 Ltr 05000457/LER-1990-0101990-07-0303 July 1990 LER 90-010-00:on 900609,reactor Trip Occurred During Plant Startup from Low Steam Generator Water Level.Caused by Malfunctioning Bypass Feedwater Regulating Valve.Operator Training provided.W/900706 Ltr 05000457/LER-1990-0091990-07-0202 July 1990 LER 90-009-00:on 900604,pressures for Active & Standby Accumulators Identified to Be Below 4,800 Psig Required for Operability.Caused by Component Failure.Four Way Valve & Hydraulic Oil Filter Used for MSIV replaced.W/900629 Ltr 05000456/LER-1990-0081990-07-0202 July 1990 LER 90-008-00:on 900608,reactor Trip Occurred Due to High Flux Rate Signal from Power Range Nuclear Instrumentation. Caused by Voltage Transient,Resulting from Lightning Striking Containment.Power Supply reset.W/900629 Ltr 05000456/LER-1990-0071990-06-28028 June 1990 LER 90-007-00:on 900601,during Removal of Ohmmeter Probe, Operator Touched Probe to Exposed Terminal Point,Resulting in Automatic Start of Auxiliary Feedwater Pump 1A.Caused by Methodology Deficiency.Probes modified.W/900628 Ltr 05000457/LER-1990-0061990-06-18018 June 1990 LER 90-006-00:on 900521,containment Fuel Handling Incident Area Radiation Monitor Failed Automatic Checksource Test Due to Low Count Rate.Caused by Component Failure.Detector replaced.W/900618 Ltr 05000457/LER-1990-0051990-05-24024 May 1990 LER 90-005-00:on 900426,discovered That Diesel Generator 2A Starting Air Distribution Sys Tubing Crisscrossed to Cylinders 6L & 9L.Caused by Preservice Mfg Deficiency. Custom-routed Airlines replaced.W/900524 Ltr 05000457/LER-1990-0041990-05-14014 May 1990 LER 90-004-00:on 900416,diesel Generator 2A Speed Oscillations Occurred Due to Defective Resistor.Caused by Failure of One Dropping Resistor in Governor Unit.Resistors replaced.W/900516 Ltr 05000456/LER-1988-012, Advises That LER 88-012-00 Withdrawn.Investigation Revealed That Operator Did Indicate That Room Temps Less than Tech Spec Limits1989-04-21021 April 1989 Advises That LER 88-012-00 Withdrawn.Investigation Revealed That Operator Did Indicate That Room Temps Less than Tech Spec Limits ML20203L0281986-04-25025 April 1986 Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points 1993-08-26
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & BW990066, Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety BW990056, Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With ML20210R6421999-08-13013 August 1999 ISI Outage Rept for A2R07 ML20210U8111999-08-0404 August 1999 SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a BW990048, Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With ML20210K9861999-07-30030 July 1999 Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20216D3841999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function BW990038, Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With BW990029, Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With ML20209H7481999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2 ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations BW990021, Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With BW990016, Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205C5101999-03-21021 March 1999 Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections ML20196A0721999-03-16016 March 1999 Cycle 8 COLR in ITS Format & W(Z) Function ML20207J4371999-03-0808 March 1999 ISI Outage Rept for A1R07 ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations BW990010, Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With ML20206U9011999-02-15015 February 1999 COLR for Braidwood Unit 2 Cycle 7. Page 1 0f 13 of Incoming Submittal Was Not Included BW990004, Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With1999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with BW990001, Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With ML20206B4001998-12-31031 December 1998 Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations ML20206U9081998-12-17017 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function BW980076, Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195D3561998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Braidwood Generating Station,Units 1 & 2.With ML20155B6711998-10-26026 October 1998 Safety Evaluation Accepting Requests for Relief Associated with Second 10-yr Interval ISI Program Plan ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20154D4401998-10-0202 October 1998 Safety Evaluation Authorizing Second 10-yr Interval ISI Program Request for Relief 12R-30 for Plant,Units 1 & 2 ML20155C2601998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Braidwood Generating Station,Units 1 & 2 ML20195F5911998-09-11011 September 1998 Special Rept:On 980812,addl Unseated Wires Were Discovered. Cause Is Unknown at Present Time.Util Evaluated Number of Unseated/Ineffective Wires & Determined Effect on Containment Structural Integrity.Commitments,Encl ML20196B3711998-09-0808 September 1998 Cycle 8 Operating Limits Rept (Olr) ML20151X6671998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Braidwood Generating Station,Units 1 & 2.With ML20238F3281998-08-31031 August 1998 SER Approving Second 10-year Interval Inservice Insp Program Request for Relief 12R-14 for Braidwood Station,Units 1 & 2 ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237A1091998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Braidwood Generating Station,Unit 1 & 2 ML20236N7001998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Braidwood Generating Station,Units 1 & 2 ML20198A0151998-06-18018 June 1998 10CFR50.59 Summary Rept 960619 Through 980618, Vols I & Ii,Consisting of Descriptions & SE Summaries for Changes to Procedural UFSAR Changes,Tests & Experiments & FP Rept.Without Fp,Rept ML20249A5451998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Braidwood Generating Station Units 1 & 2 ML20247F7711998-05-0808 May 1998 Special Rept:On 980403 & 980503 Seismic Monitoring Sys Was Declared Inoperable.Caused by 5-volt Power Supply & Regulator Card Failure.Imd & Sys Engineering Are Continuing to Identify & Resolve Problems So Sys Can Be Operable ML20247L7591998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Braidwood Generating Station,Units 1 & 2 ML20217K6331998-04-20020 April 1998 Safety Evaluation Accepting Methodology & Criteria Used in Generating Flaw Evaluation Charts for RPV of Braidwood IAW Section XI of ASME Code ML20216C6621998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Braidwood Generating Station,Units 1 & 2 1999-09-30
[Table view] |
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text
.. _
. ,[
) Commonwealth Edison Braldwood Nuct:sr Pati:r Stati:n
.(/N c; Route #1. Box 64 Braceville. lilinois 60407 N Telephone 815/458-2801 i
June 18,1990 BW/90-0638 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Dear Str:
The enclosed Licensee Event Report from Braldwood Generating Station is being transmitted to you in accordance with the requirements of 10CFR50.73(a)(2)(lv) which requires a 30-day written report.
This report is number 90-006-00; Docket No. 50-457.
Very truly yours,
't ,
l ylR. E. Querto Station Manager i Braldwood Nuclear Station l
REQ /JDW/sjs (7126z)
Enclosure:
Licensee Event Report No. 90-006-00 cc: NRC Region Ill Administrator l NRC Resident inspector INPO Record Center CECO Distribution List l
9006250211 900618 PDR Fi ADOCK 05000407 PDC sff ff;t
, LICENSEE EvtNI RLPORT (tER) farfLBet.2J_
Facility HNne (1) Docket Number (2) .139tJ3)
JulbooLL DL5LoLOLolll_117 1 I ed..oja.
Title (4) lant ainmenLVentila tten._linis tinn_ht._t o_e._hih LDrittier_enlnat tineenLA t t ale dlalis nlentie r LytntaattJh1 _ltalumber_161 Retati_DattlZl_ OtberlatilliitilarciredJB1 Month Day Year Year /// Sequential /// Revision Month Day Year _latillinhamtl. ..Dotteilumitris )
fff fff
_ _ - ul Jumbat_._ ul _Numbet Nant _QL$1JLo1Sl_1 I JLLJLt ALL JLL LLoJ_t LLL J 11JLe J10 JL3LoLoLoLLL TMi$ REPORT l$ SUBMITTED PURSUANT TO IME REQUIREMENi$ OF 10CFR OPMW LChetLonter_ mort _cLihe_ic11cuinal (111 gggt g9) 4
_.__ 20.402(b) _. 20.405(c) 2. 50.73(a)(2)(iv) __ 73.71(b)
POWER _ 20.405(a)(1)(1) .__. 50.36(CHI) _ 50.73(aH2)(v) _ 73.71(c)
LEVEL _.__ 20.405(a)(1)(ll) 50.36(c)(2) __._ 50.73(a)(2)(vli) ____ Other (Specify
_110 L ..._0_! _0 } _ _0_ _ 20.405(a)(1 Hill) _ 50.731a)(2)(i) _ 50.73(aH2)(vili)(A) in Abstraet
/ /, ////////// ////,// _ 20.405(a)(1)(tv) __ 50.73(a)(2)(ii) .___ 50.73(a)(2)(viii)(B) below and in 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x) fest)
/}/ /////////////}/// -
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Name _ItLEnt0NLHVilDER AREA CODE MilitJytrJech_5tallIngireer Eati_2210 BJ LLLJL1LaL-lllallL1 IOMPitiLONE.LINLfDR.LAttLCOMt0NLNLfAILVRLDISCRioLD ItLittl5JLPORLi13)
CAUSE SY$1EM COMPONENT mNUFAC- REPORTABLE CAUSE $Y$1EM COMPONENT MNUFAC- REPORTABLE
_JURER___ JO_MEEQL _IURER lolERQL x _LLL JilllL_ ._5LfL21] NO ! ._1_L_J _ ._.L L.J _
1 _LJ_L _1 1 1 1 J_L.J _ _LLJ SVEELLt!LHIALRLE0KLiitLLILQJ14) E=rected MonthIDantlett Submission lle s. .( I L y t L_c omp1s t ellfLLLED__5VDM15310LDAI[ 1 K l NQ
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At 1117 on May 21, 1990 a Containment - fuel Mandling incident Area Radiation Monitor failed its automatic ch;cksource test due to a low countrate. The checksource test is generated by the microprocessor circuitry of the monitor every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Upon failure, the monitor reverted to the Interlock position. This generated a C:ntainment Ventilation Isolation $lgnal for train A which resulted in the closure of Mint-Purge Exhaust valves and tripped the running Mint-Purge Exhaust Ian. 1he operator acknowledged the Checksource Failure Alarm and v: rifled all automatic actions. The cause of this event was component failure. The detector checksource circuit failed causing the Radiation Monitor to revert to the interlock condition which resulted in the Train A C:ntainment Ventilation Isolation. The Detector was replaced, recalibrated and returned to service. The cintainment fuel Handling Incident Radiation Honitor detectors are replaced on an 18 month frequency in accordance with the Environmental Qualification program. The f ailed detector in this event had been in service since April 26. 1990. A review of component failure histories did not identify any adverse trend concern for this type of detector. Previous corrective actions were not appilcable to this even'..
I l
1 l 3030m(061590)/2
~ , . . . . . . . . , . - .. .. .. . -.___._;.
3- t i(LM LLEYENLRLf9RL.1LERLILKIl0HllWAltpy raraJuld.
~ FAClll1Y NAMF.*(1) DOCKET NUMBER (2)- _LLILWt9LlL16) P3gt.,13} -
Sequential Revision s* Year fff fu .lvmber .
fff Lil _ & mkti Dr.atdwood 2' QJ 5J DJ 0 1 0 lA L5]J 9 10 -
0I0!6 - ___ _0_ L_g_ Jjl jt JL3 T LKi - Energy Industry Identification System (Ell $) codes are identified in the text as (XX)
. -PLANT CONDITIONS PRIOR TO EVENT:
Unit: Braldwood 2: Event Date: May 21, 1990; Event ilme: 1117; Mode: 4 - Hot $hutdown; Rx Power: 0%;
RCS (AB) Temperature /Prissure: NOT/NOTt
..DESCRIPIl0N OF EVENT:
There were no systems or components inoperable at the beginning of the event which contributed to the severity of th) event. Containment Release G-0102 was in progress.
At 1117 on May 21, 1990 the Containment - Fuel Handling Incident Area Radiation Honitor (AR) (IL), 2RT.AR01),
f ailed its automatic checksource test due to a low countrate. The checksource test is generated by the cicroprocessor circuitry of the monitor every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Upon f ailure of the self diagnostic test the monitor
. reverted.to the interlock position. This generated a Containment Ventilation isolation Signal for Train A which-resulted in the closure of Mint-Purge Exhaust (VQ) (VA) valves 2VQ005A and C, and tripped the running Hint-Purge Exhtust Fan.
The Unit 2 Nuclear Station Operator (N50) (Licensed Reactor Operator) acknowledged the Checksource railure Alarm and verified all automatic actions.
^lhe 2RT-AR011 wa' n elared inoperable and the appropriate Technical. Specification Action Statements were entered and compiled with.
The appropriate NRC notification via the ENS phone system was made at 1222 pursuant to 10CFR50.72(b)(2)(ii)..
An investigation revealed that the Detector Checksource circuit had f ailed. The Detector was replaced.
~
At 1050 on Hay 24,1990 the 2RT-AR011 was declared operable and the Technical Specificatiten Statements were exited.
This event is being reported pursuant to 10CFR50.73(a)(2)(iv) - any event of condition that resulted in manual or autonatic actuation of any Engineered Safety Feature, including the Reactor Protection System.
. CAUSE OF EVENT:
..The root cause of this event was component failure. The detector checksource circuit f ailed causing the Radiation
.Ho'nitor to revert to the interlock condition which resulted in the Train A Containment Ventilation Isolation.
?030m(061590)/3
LIC[ttSI LEVIHL. REP 0AL1L LR)J LXL.C0!(11mfl0ti ForeLRer 1 9.
F ACIL I,1Y N'AME '( 1) DOCKET NUNDER (2) ll!L1Mt91PJb) Page_13)
// //
l./j/
j Revision LfL _1!umkeL L _Humber praldyggd_2 ___0J _5j _0j_0_.l 01.fil31.2_1_LO -
011.lJt_ -
0J.JL DL3 _0L _.Ql_.3
-lEXT Energy Industry identification System (Ells) codes are identified in the text as (XX)
~ D. SAFETY ANALYSIS:
This event had no effect on the safety of the plant or the public. All systems operated as designed, lhe monitor reverts to its Engineered Safety Feature (ESF) safe configuration upon detector checksource failure.
Th) redundant AR monitor, 2RT-AR012 was operable and available to provide indication and Train B Containment V:ntilation Isolation. l Under the worst case condition of total monitor f ailure there would still be no eflect. The radiation monitoring system is designed such that the monitor reverts to the tripped condition and the appropriate ESF actuation occurs upon failure of the monitor, detector, or automatic diagnostic testing as was the case in this event.
E. CORRECTIVE ACi10NS:
lhe Detector for 2RT-AR0ll was replaced. The monitor was recalibrated and returned to service.
The Containment fuel Handling incident Radiation Monitor detectors are replaced on an 18 month frequency in accordance with the Environmental Qualification program. The failed detector in this event had been in service since April 26, 1990. A review of component failure histories did not identify any adverse trend c ncern for this type of detector.
F. PREVIOUS OCCURRENCES:
There have been previous occurrences of radiation monitor f ailures resulting in ESF actuations. -The correttive actions were implemented addressing both root and contributing causes. Previous corrective actions are not applicable to this event.
G .' COMI'0HENT FAltVRE DATA:
Manufacturer Nomenclature Model Number /HFG Part Number
$;rrento Electronics Area Detector Assy 0281-0760-002 30302(061590)/4
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05000457/LER-1990-004 | LER 90-004-00:on 900416,diesel Generator 2A Speed Oscillations Occurred Due to Defective Resistor.Caused by Failure of One Dropping Resistor in Governor Unit.Resistors replaced.W/900516 Ltr | | 05000457/LER-1990-005 | LER 90-005-00:on 900426,discovered That Diesel Generator 2A Starting Air Distribution Sys Tubing Crisscrossed to Cylinders 6L & 9L.Caused by Preservice Mfg Deficiency. Custom-routed Airlines replaced.W/900524 Ltr | | 05000457/LER-1990-006 | LER 90-006-00:on 900521,containment Fuel Handling Incident Area Radiation Monitor Failed Automatic Checksource Test Due to Low Count Rate.Caused by Component Failure.Detector replaced.W/900618 Ltr | | 05000456/LER-1990-007 | LER 90-007-00:on 900601,during Removal of Ohmmeter Probe, Operator Touched Probe to Exposed Terminal Point,Resulting in Automatic Start of Auxiliary Feedwater Pump 1A.Caused by Methodology Deficiency.Probes modified.W/900628 Ltr | | 05000456/LER-1990-008 | LER 90-008-00:on 900608,reactor Trip Occurred Due to High Flux Rate Signal from Power Range Nuclear Instrumentation. Caused by Voltage Transient,Resulting from Lightning Striking Containment.Power Supply reset.W/900629 Ltr | | 05000457/LER-1990-009 | LER 90-009-00:on 900604,pressures for Active & Standby Accumulators Identified to Be Below 4,800 Psig Required for Operability.Caused by Component Failure.Four Way Valve & Hydraulic Oil Filter Used for MSIV replaced.W/900629 Ltr | | 05000457/LER-1990-010 | LER 90-010-00:on 900609,reactor Trip Occurred During Plant Startup from Low Steam Generator Water Level.Caused by Malfunctioning Bypass Feedwater Regulating Valve.Operator Training provided.W/900706 Ltr | |
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