Similar Documents at Byron |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20045A6941993-06-0404 June 1993 LER 93-003-00:on 930511,turbine Emergency Trip Oil Header Pressure Low Alert Received Followed by Reactor Trip & Turbine Trip Above P-8.Caused by Actuation of Overspeed Trip Relay.Faulty Power Supply Board replaced.W/930604 Ltr ML20024H2041991-05-22022 May 1991 LER 91-005-01:on 900817,preoutage Mod Work Initiated W/O Proper Operability Review Due to Programmatic Deficiencies. Daily Const Work Authorization Sheet formalized.W/910522 Ltr ML20029A6461991-02-20020 February 1991 LER 90-007-01:on 900612,main Steam Line Isolation Sys Declared Inoperable Due to Failure to Test Manual Initiation Handswitch.Caused by Deficiency in Procedure.Procedures reviewed.W/910219 Ltr ML18041A2251990-10-0303 October 1990 LER 90-006-00:on 900903,reactor Containment Fan Cooler 2C, Low Speed Fan Breaker Did Not Close,Resulting in Train a Safety Injection Signal.Caused by Miscommunication & Procedure Deficiency.Procedure revised.W/901003 Ltr ML20029A6901990-09-13013 September 1990 LER 90-011-01:on 900819,reactor Trip Occurred Due to Power Surge.Caused by Lightning Strike.Rod Drive Sys Will Be Modified W/New Model of Power Supply Less Likely to Cause Reactor trip.W/910221 Ltr ML20044B0991990-07-12012 July 1990 LER 90-007-00:on 900612,discovered That Steam Line Isolation Handswitch on Main Control Board Panel 1PM06J Not Tested During Past Refueling Outages.Caused by Deficient Procedure. All Similar Equipment Will Be reviewed.W/900712 Ltr ML20044A9871990-07-11011 July 1990 LER 89-005-01:on 890501,diesel Generator 1A Failed to Load to 5,500 Kw within 60 as Required.Caused by Max Fuel Setting on Fuel Control Sys Being Set Too Low.Vendor Instructions Added to Maint procedures.W/900629 Ltr ML20043D5841990-06-0101 June 1990 LER 90-006-00:on 900503,as Surveillance Underway All Indication on Digital electro-hydraulic Computer Panel Was Lost.Caused by Failure of Ampere Fuse Due to Short Circuit in Pushbutton.Lighting Circuit rewired.W/900530 Ltr ML20042G9121990-05-0808 May 1990 LER 87-012-01:on 870408,component Cooling Pump 1A Tripped When Surge Tank Level Dropped to Low Level Pump Trip Setpoint.Caused by Breakdown in Communication.Mod to Component Cooling Sys completed.W/900507 Ltr ML20042E1561990-04-0606 April 1990 LER 90-003-00:on 900307,individual Cell Voltage for Cell 53 Found to Be at 2.11 Volts,Contrary to Tech Spec Limit.Caused by Electrician Using Improper Acceptance Criteria Format & Inadequate Mgt Review of surveillance.W/900406 Ltr ML20006F7161990-02-16016 February 1990 LER 90-001-00:on 900118,determined That Containment Purge Isolation Sys Not Demonstrated Operable 100 H Prior to Start of Core Alterations.Caused by Cognitive Personnel Error. Task Force Formed to Review Tech Specs.W/900109 Ltr ML20006E1161990-02-0909 February 1990 LER 90-001-00:on 900118,during Functional Surveillance on Steam Generator Pressure Channel 526,channel 525 Spiked Low, Causing Reactor Trip & Safety Injection.Caused by Failure of Pressure Transmitter.Transmitter replaced.W/900126 Ltr ML20006D7401990-02-0505 February 1990 LER 87-004-01:on 870225,inadvertent Safety Injection Occurred During Maint Troubleshooting.Caused by Cognitive Personnel Error by Control Sys Technician Involved. Disciplinary Action Taken & Counseling done.W/900124 Ltr ML20005E2391989-12-26026 December 1989 LER 89-003-01:on 890227,area Radiation Monitor 2RT-AR012 Failed Automatic Checksource Test,Actuating Containment Ventilation Isolation Alarm.Caused by Faulty Detector. Detector Replaced & Monitor Returned to svc.W/891221 Ltr ML19327B9021989-11-0303 November 1989 LER 89-009-00:on 891005,conflicting Info Re Signals That Initiate Automatic Isolation of Steam Generator Blowdown Lines Found.Caused by Preservice Design Implementation Deficiency.Lines Isolated & Procedure changed.W/891103 Ltr ML19354D4681989-11-0101 November 1989 LER 89-008-01:on 890830,one Auxiliary Feedwater Suction Pressure Transmitter Calibr Not Head Corrected & Bases of Original Setpoints Not Questioned.Caused by Inadequate Procedures & Setpoint calculations.W/891101 Ltr 1993-06-04
[Table view] Category:RO)
MONTHYEARML20045A6941993-06-0404 June 1993 LER 93-003-00:on 930511,turbine Emergency Trip Oil Header Pressure Low Alert Received Followed by Reactor Trip & Turbine Trip Above P-8.Caused by Actuation of Overspeed Trip Relay.Faulty Power Supply Board replaced.W/930604 Ltr ML20024H2041991-05-22022 May 1991 LER 91-005-01:on 900817,preoutage Mod Work Initiated W/O Proper Operability Review Due to Programmatic Deficiencies. Daily Const Work Authorization Sheet formalized.W/910522 Ltr ML20029A6461991-02-20020 February 1991 LER 90-007-01:on 900612,main Steam Line Isolation Sys Declared Inoperable Due to Failure to Test Manual Initiation Handswitch.Caused by Deficiency in Procedure.Procedures reviewed.W/910219 Ltr ML18041A2251990-10-0303 October 1990 LER 90-006-00:on 900903,reactor Containment Fan Cooler 2C, Low Speed Fan Breaker Did Not Close,Resulting in Train a Safety Injection Signal.Caused by Miscommunication & Procedure Deficiency.Procedure revised.W/901003 Ltr ML20029A6901990-09-13013 September 1990 LER 90-011-01:on 900819,reactor Trip Occurred Due to Power Surge.Caused by Lightning Strike.Rod Drive Sys Will Be Modified W/New Model of Power Supply Less Likely to Cause Reactor trip.W/910221 Ltr ML20044B0991990-07-12012 July 1990 LER 90-007-00:on 900612,discovered That Steam Line Isolation Handswitch on Main Control Board Panel 1PM06J Not Tested During Past Refueling Outages.Caused by Deficient Procedure. All Similar Equipment Will Be reviewed.W/900712 Ltr ML20044A9871990-07-11011 July 1990 LER 89-005-01:on 890501,diesel Generator 1A Failed to Load to 5,500 Kw within 60 as Required.Caused by Max Fuel Setting on Fuel Control Sys Being Set Too Low.Vendor Instructions Added to Maint procedures.W/900629 Ltr ML20043D5841990-06-0101 June 1990 LER 90-006-00:on 900503,as Surveillance Underway All Indication on Digital electro-hydraulic Computer Panel Was Lost.Caused by Failure of Ampere Fuse Due to Short Circuit in Pushbutton.Lighting Circuit rewired.W/900530 Ltr ML20042G9121990-05-0808 May 1990 LER 87-012-01:on 870408,component Cooling Pump 1A Tripped When Surge Tank Level Dropped to Low Level Pump Trip Setpoint.Caused by Breakdown in Communication.Mod to Component Cooling Sys completed.W/900507 Ltr ML20042E1561990-04-0606 April 1990 LER 90-003-00:on 900307,individual Cell Voltage for Cell 53 Found to Be at 2.11 Volts,Contrary to Tech Spec Limit.Caused by Electrician Using Improper Acceptance Criteria Format & Inadequate Mgt Review of surveillance.W/900406 Ltr ML20006F7161990-02-16016 February 1990 LER 90-001-00:on 900118,determined That Containment Purge Isolation Sys Not Demonstrated Operable 100 H Prior to Start of Core Alterations.Caused by Cognitive Personnel Error. Task Force Formed to Review Tech Specs.W/900109 Ltr ML20006E1161990-02-0909 February 1990 LER 90-001-00:on 900118,during Functional Surveillance on Steam Generator Pressure Channel 526,channel 525 Spiked Low, Causing Reactor Trip & Safety Injection.Caused by Failure of Pressure Transmitter.Transmitter replaced.W/900126 Ltr ML20006D7401990-02-0505 February 1990 LER 87-004-01:on 870225,inadvertent Safety Injection Occurred During Maint Troubleshooting.Caused by Cognitive Personnel Error by Control Sys Technician Involved. Disciplinary Action Taken & Counseling done.W/900124 Ltr ML20005E2391989-12-26026 December 1989 LER 89-003-01:on 890227,area Radiation Monitor 2RT-AR012 Failed Automatic Checksource Test,Actuating Containment Ventilation Isolation Alarm.Caused by Faulty Detector. Detector Replaced & Monitor Returned to svc.W/891221 Ltr ML19327B9021989-11-0303 November 1989 LER 89-009-00:on 891005,conflicting Info Re Signals That Initiate Automatic Isolation of Steam Generator Blowdown Lines Found.Caused by Preservice Design Implementation Deficiency.Lines Isolated & Procedure changed.W/891103 Ltr ML19354D4681989-11-0101 November 1989 LER 89-008-01:on 890830,one Auxiliary Feedwater Suction Pressure Transmitter Calibr Not Head Corrected & Bases of Original Setpoints Not Questioned.Caused by Inadequate Procedures & Setpoint calculations.W/891101 Ltr 1993-06-04
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H5221999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Byron 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 ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With ML20210E2251999-07-21021 July 1999 B1R09 ISI Summary Rept Spring 1999 Outage, 980309-990424 ML20209G1751999-07-0808 July 1999 SG Eddy Current Insp Rept,Cycle 9 Refueling Outage (B1R09) ML20207H7941999-06-30030 June 1999 Rev 0 to WCAP-15180, Commonwealth Edison Co Byron,Unit 2 Surveillance Program Credibility Evaluation ML20207H8071999-06-30030 June 1999 Rev 0 to WCAP-15178, Byron Unit 2 Heatup & Cooldowm Limit Curves for Normal Operations ML20207H7851999-06-30030 June 1999 Rev 0 to WCAP-15183, Commonwealth Edison Co Byron,Unit 1 Surveillance Program Credibility Evaluation ML20207H7771999-06-30030 June 1999 Rev 0 to WCAP-15177, Evaluation of Pressurized Thermal Shock for Byron,Unit 2 ML20209H3711999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Byron Station, Units 1 & 2.With ML20207H7561999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20207H7621999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20195J8001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Byron Station,Units 1 & 2.With 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 ML20206R6991999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Byron Station Units 1 & 2.With ML20195C7961999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) M980023, Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A)1999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) ML20205P7001999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Byron Station,Units 1 & 2.With ML20205B5091999-03-26026 March 1999 SER Accepting Relief Requests 12R-24,Rev 0 & 12R-34,Rev 0, Related to Second 10-year Interval Inservice Insp for Byron Station,Units 1 & 2 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 ML20204G3831999-03-19019 March 1999 Safety Evaluation Accepting Second 10-yr Interval ISI Request for Relief 12R-11 M990004, Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function1999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function ML20206A8831999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20204C7671999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Byron Station,Units 1 & 2.With ML20199G8271998-12-31031 December 1998 Rev 1 Comm Ed Byron Nuclear Power Station,Unit 1 Cycle 9 Startup Rept ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20202F6181998-12-31031 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function ML20206B4001998-12-31031 December 1998 Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations ML20199E6371998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Byron Station,Units 1 & 2.With ML20202F6021998-12-31031 December 1998 Cycle 9 COLR in ITS Format & W(Z) Function ML20196K6731998-12-31031 December 1998 10CFR50.59 Summary Rept for 1998 ML20207H7731998-11-30030 November 1998 Rev 0 to WCAP-15125, Evaluation of Pressurized Thermal Shock for Byron,Unit 1 ML20207H8011998-11-30030 November 1998 Rev 0 to WCAP-15124, Byron Unit 1 Heatup & Cooldown Limit Curves for Normal Operation ML20198D1501998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Byron Nuclear Power 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 ML20195F8321998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Byron Nuclear Power Station,Units 1 & 2.With 05000454/LER-1998-018, Corrected LER 98-018-00:on 980912,inoperable Unit 1 DG Was Noted.Caused by Low Lube Oil Pressure Condition.Immediately Entered Into Lcoar for AC Sources TS 3.8.1.1,Action a1998-10-0909 October 1998 Corrected LER 98-018-00:on 980912,inoperable Unit 1 DG Was Noted.Caused by Low Lube Oil Pressure Condition.Immediately Entered Into Lcoar for AC Sources TS 3.8.1.1,Action a ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20154L5501998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20197C9051998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20151Z9651998-08-31031 August 1998 Revised MOR for Aug 1998 for Byron Nuclear Power Station. Rept Now Includes Page 9 Which Was Omitted from Previously Issued Rept ML20238F6551998-08-28028 August 1998 SE Authorizing Licensee Request for Relief NR-20,Rev 1 & NR-25,Rev 0 Re Relief from Examination Requirement of Applicable ASME BPV Code,Section XI for First ISI Interval Exams ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237B3361998-08-14014 August 1998 B2R07 ISI Summary Rept,Spring 1998 Outage, 961005-980518 ML20237B4841998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Byron Nuclear Power Station Units 1 & 2 1999-09-30
[Table view] |
Text
_
^ Commonwoahh Edison
/ j ByronNuclearStation i j ' 4450 NorthC:rman Church Road
April 6, 1990 Ltrl BYRON 90-0351 !
I U. S. Nuclear Regulatory Commission 5
Document Control Desk washington, D.C. 20555 j t
i Dear Sirt i 1
The enclosed Licensee Event Report from Byron Generating Station is being '
transmitted to you in accordance with the requirements of 10CTR50.73(a)(2)(1).
This report is number 90-003; Docket No. 50-454.
?
Sincerely, ;
t
/
R. Pleniewicz / -
Station Manager g/
I Byron Nuclear Powet Station =
l
\
l- RP/dm Enclosures Licensee Event Report No.90-003 cc A. Bert Davis, NRC itegion III Administrator l W. Kropp, NRC Senior Resident Inspector l It4PO Record Center [
CECO Distribution List i
I l
9004200283 900406 PDR ADOCK 05000454 ,
S PDC l
(0553R/0065R) Ik I
/ .t i
y .
tlCCC$tt CV[NT R[p0RT (LER)
- facilityName21) Docket Number (2) Pace (3)
Bytan. Unit 1 Of El 01 01 01 41 51 4 1lefl0l4 Title (4)
Mebb e t LER Number (6)
Other Facilities Involved (B) 1YtAL.lt.le ($1 Rttert Date (7)
Month Day Year Year ///
fff Sequential ///j ff Revision Month Oay Year la.cl11tv.Natts J 2tte Lfkehtt(s. L _
/// Number /// Numler NONE _01ELDLOLoJ_1 L
~~~
01 3 01 7 91 0 9l 0 ~'.31013 01 0 0l4 0l 6 9] 0. 01 51 01 01 Ol I L THl$ REPORT l$ $UBMITTED PUR$VANT TO THE REQVIREHENi$ OF 10CIR MERATING
((htik one er meed of the followino) f11) 1 20.402(b) 20.40$(c) 50.73(a)(2)(iv) 73.71(b)
POWER _ 20.405(a)(1)(1) _ 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)
LCVtl 20.405(a)(1)(11) __ 50.36(c)(2) _ 50.73(a)(2)(vii) Other ($pecify (101 4 8 20.40$(a)(1)(Iti) .)L. 50.73(a)(2)(1) 50.73(a)(2)(viii)(A) in Abstract
/ / /// / /,// //, /,// / /,/,/ / /,/ / / / / / 20.405(a)(1)(iv) 50.73(a)(2)(ll) _, 50.73(a)(2)(viii)(B) below and in
//////j////',////}/}///}///////
/
j ,_ 20.405(a)(1)(v) _ 50.73(a)(2)(iii) 50.73(a)(2)(r) text)
LICEN$tt CONTACT FOR THl$ LER (12)
Name TELEPHONE NUMBER AREA Coot
.A._hhtnkapeutinnlnninter h b._2116 81 1 I k_ IL.}314 I -LELaL4U c0MPLETE ONE LINE FOR EACH COM 0 FAILURE DESCRIBiD IN THli REPORT (131 CAV$t $Y$ftM COMPONENT MANUFAC- REPORTABLE CAU$E $YSTCH COMPONENT MANUFAC- REPORTABLE TURER TO NPRD$ 11LPER TO NPRDS I _] l 1 1_ l I i j I 1. I I I I l l l 1 1 I I l l l l l l SUPPLEMENTAL REPORT EXPECTED (14) tapected tionth l Day I Ytat Submi sion
}1tl._UL3ts. eemel ietEXPECTED $UBlinHQRJATE) X l NO Date (15) ; lg ll AB$iRACI (Limit to 1400 spaces, i.e. approximately fif teen single-space typewritten lines) (16)
, On March 7,1990, while reviewing IDHS 8.2.1.2.b-1, "125 Volt Battery Bank Quarterly (Mvision 111) $urveillance".
(performed on 01/23/90) for system trending purposes, the individual cell voltage fe' eell *53 was found to be at
( 2.11 volts. This value is below the Technical Specification limit of }. 2.13 volts t t greater than the allowable l value of > 2,07 volts. The cell voltage was trenediately rechecked and confirmed * ~ ee low. The Division 111 f attery Bus was declared inoperable and timiting Condition for Operation Action krquirement (LC0AR) 100$ 8.2.1-la l was entered.
l l The root cause of this event is two fold. The electrician performing the surveillance did not correctly interpret
( the acceptance criteria stated in the surveillance due to improper acceptance criteria format. the acceptance criteria was in the form of a table instead of comparing As Found data with numerical setpoints noted as ccceptoce criteria. In addition, a management review of the surveillance proved inadequate due to lack of attention to detail combined with the improper acceptante criteria format.
Corrective actions include procedure revisions to clarify the surveillance requirements.
This event is reportable pursuant to 10CFR50.73 (a)(2)(1)(B) for operation prohibited by the plant's Technical Specifications.
(0553R/0065R)
e .-
LIEEN$ft EVENT REPORT (LER) TEXT CONTINUATION Form Rev 2.0 FACILITY NAML (1)
DOCKET NUMBER (2) LER NUPSER (6) Pegt J 1 e Year Sequential
/// /// Revision fff fff
/// Number /// Number h ton. Unit 1 0 i L l 01010141 $14 910 - 01013 - 0I O 01 2 Or _nL4 TEXT Energy Industry Identification System (E!!$) codes are identifled in the text as (XX)
A. PLANT CONDITIONS PRIOR TO EVENT:
Ever.t Date/ Time 03/07/90 / 1445
- Unit 1 MODE _1._ - Power Operation Rx Power 481,_ RCS (AB) Temperature / Pressure yormal Operatina Unit 2 MODE 1 - power Ocaration __ Rx Power 81% RC$ (AB) Temperature / Pressure Normal Operatina._
B. QUERIPTION OF EVENT On 3/7/90, while reviewing 1BHS B.2.1.2.b-1, "125 Volt Battery Bank Quarterly (Division 111) Surveillance" ,
(performed on 1/23/90) for system trending data, the individual cell voltage for cell #53 was found to be at 2.11 volts. This value is below the Technical Specification limit of 12.13 volts but greater than the allowable value of > 2.07 volts. The cell voltage was immediately rechecked and found to be 2.095 volts.
This was less than the minimum 2.13 volts and therefore the Division 111 Battery Bus was declared ,
inoperable and Limiting CondItlon for Operation Action Requirement (LC0AR) 180$ 8.2.1-la was entered. NWR B74716 was written to place a single cell charger on the affected cell to restore the voltage to >2.13 volts.
No plant systems or components were previously (noperable that contributed to this event. No operator actions were taken which either increased or decreased the severity of this event. No safety system j actuations occurred during this event.
, $1nce the inoperability of the battery can be traced to the executed surveillance, the LC0AR should have l been entered on 1/23/90 which requires the parameter to be restored within 7 days. This event is .,
l reportable per 10CRF$0.73(a)(2)(1)(B) for an operation or condition prohibited by the plant's Technical Specifications.
C. (& $E OF EVENT:
The cause of this event is two-fold. The electrician performing the surveillance did not correctly interpret the acceptance criteria stated in the surveillance. In addition, a management review of the surveillance f ailed to identify the low cell voltage.
l The root cause of the electrician (non-licensed) not realizing the cell voltage was below its acceptance ,
criteria was due to confusion in reading the Battery Surveillance Requirements provided in the surveillance l due to improper acceptance criteria format.
Currently the acceptance criteria in the surveillance is listed in the form of a table which is a subset of '
l the table and notes appearing in Techt.ical Specifications. This table is divided into two categories l relating to the battery parameters, one category listing the minimum " LIMITS FOR EACH CONNECTED CELL" and a ,-
second category listing the minimum " ALLOWABLE VALUE FOR EACH CONNECTED CELL". The individual performing the surveillance incorrectly read the table believing the battery was operable provided each connected cell was within its ALLOWABLE value even though the cell voltage was less than its LIMIT. - However, per a note explaining the LIMIT parameters, the actual requirement is that the battery may only be considered operable provided the voltage is restored to within its LIMITS within seven days. This note did not explicitly require a LC0AR entry. Therefore, believing the voltage was within its acceptance criteria, the -
appropriate personnel were not notified.
(0$$3R/0065R) t f
LICENSLE EVENT REPORT (LER) TEXT CONTINUATION form Rev 2.0
, FACILITY NAME (1) 00CKE1 NUPeER (3) . LEll nut 9ER (6) Page (3)
///
/// Number
(//
///
f Number. l Byron. Unit 1 0 1 5 1 0 1 0 1 0 1 41 51 4 910 - Ol013 - 01 0 01 3 0F 01 4 TEXT Energy Industry Identification System (E!!$) codes are identifled in the text as [XX) l The root cause of the (Ladequate management review of the completed surveillance was due to cognitive personne' error because the people performing the review did not recognize the low voltage condition.
Contributing to the inadeovate review was the procedure format which did not clearly state the acceptance criteria and compare the Technical Specification values to surveillance data.
The surveillance was signed complete by the electrician at 1430, on 1/23/90, as documented on the "
, surveillance data package cover sheet. The Electrical Maintenance Foreman (non-licensed) completed the surveillance sunnary checklist on the surveillance cover sheet at 1435, on 1/23/90. The Foreman Indicated the surveillance was found within the acceptance criteria, and that no failures were found during the surveillance. The SRO acknowledgement and review was completed by a Shift Foreman (licensed) at 1500 on 1/23/90. A subsequent review of results was performed by a Maintenance $taf f Supervisor (non-licensed) on 1/29/90, Operating Engineer (licensed) on 2/21/90, and Technical Staff Engineer (non-licensed) on 2/28/90, and all reviews failed to identify the low voltage reading.
D. $AFETY ANALY$11:
There was no effect on plant or public safety. With one cell's voltage low, the individual cell had experienced some degradation, however, the cell would not have affected the ability of the battery bank to perforin its safety function. Also, during this period, the battery bus voltage was maintained at >126 volts at all times. In addition, IBV5 8.2.1.2.d-1, "125 Volt Battery Bank Service Test", performed 1/17/90, demonstrated the battery bank was capable of carrying all the required accident loads on the bus.
Finally, a previous analysis has shown that the battery bank with only 57 of $8 connected cells, and not cross-tied to the opposite unit, has suf ficient capacity to carry the actual I?vs 111 loads. During the period between 1/23/90 and 3/7/90, the Olvision 111 Battery Bank was not cross-tied to the opposite unit and therefore was capable of performing its design safety function.
Had this event occurred under a more severe set of initial conditions, the redundant train of batteries was always operable to provide the required DC power.
( E. CORRECTIVE ACTIONS:
Upon discovery of the low voltage condition on cell #53, LC0AR 180$ 8.2.1-la was immediately entered and NWR 874716 was written to place a single cell charger on Cell #53 to restore the cell to the required voltage. On 03/14/90 at 0856, cell #53 was jumpered out of the battery bank via Temporary Alteration 90-1-011 as interim corrective action. To complete this alteration, 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> LC0AR 180$ B.2,1-la was !
entered. At 0925 on 03/14/90, the installation of the Temporary Alteration was completed, and the Olvision r 111 Battery was restored. LC0AR 180$ 8.2.1-la was exited. As permanent corrective action, the cell was ;
i replaced under NWR B74736 on 03/31/90. !
l A Personnel Error Review Board and a Human Performance Enhancement System GIPES) evaluation has been l conducted for this event. The corrective actions to ensure the acceptance criteria are properly identified l and ensure the procedure is adequately reviewed are as follows:
l
- 1. Remove the existing Technical Specification Table used for the acceptance criteria, and replace it with specific setpoint limits relating to minimum voltage, specific gravity, temperature and corrosion.
This will enable an easier comparison of actual data vs. Its associated Technical $pecification value.
Action Item Record (AIR)90-079 will track this item.
- 2. Add notes to the surveillance ahead of acceptance criteria steps stating to stop and contact the $hif t Engineer when the acceptance criteria is not met. AIR 90-079 will track this item.
(0553R/0065R)
- p. ,
~
LIEEN$EE EVENT REPORT (LER) TEXT CON 11 M LION form ptLM FACILITY NAMC* -(1) DOCKET nut @ER (2) LER NUPSER (6) page (3) ,
- ** Year / Sequential // Revision j/j/j/
// Number j///j/j Number
.h ron. Unit 1 0 l 5 i O l 0 1 0 1 41 51 4 910 - 01013 - 01 0 0! 4 0F 01 4 Text Energy Industry Identification System (E!!$) codes are identified in the text as (XX)
- 3. Add a signof f to the data sheets to verify the acceptance criteria for each step has been met. AIR 90-079 will track this action.
- 4. The Electrical Maintenance Department will be briefed on this event and the corrective actions to be
- taken. AIR 90-080 wt11 track this action.
- 5. Add acceptance criteria "g" signs to the Data $heets to properly identify when acceptance criteria data is being taken. AIR 90-079 will track this action. l
- 6. Review other Electrical Maintenance surveillances for similiar problems, and make any changes as '
necessary. AIR 90 081 will track this item.
- 7. A Required Reading package etntaining a summary of the event and a copy of the performed data sheets will be routed within the Electrical Maintenance and Operating Departments. AIR 90-082 will track this item.
While reviewing the calculations allowing the temporary alteration to be Installed, a potentially reportable condition was discovered. A supple
- ental report will be submitted upon completion of the investigation if the event is determined to be reportable. AIR 90-087 will track the in estigation.
F. PREVIOU$ OCCURRENCE 11 One previous event was identified at Byron that resulted in a missed LC0AR and increased surveillance
, frequency due to inadequate surveillance review and improper procedure format.
WTER 111LE LER 89-001 (Docket 454) Technical $pecification Hot Channel Far. tor Surveillance Performed Late Due .
to Personnel Error.
G. (QMPONENT FAILURE DATAt l
- a. tRNUFACTURER @l4ENCLATURE W DEL NUPSER MFG PART NUtBER GNB Battery Lead-Calcium Battery M01-2014-92 762098
- b. RESULTS OF NpRDS SEARCH:
A Nuclear Plant Reliability Data Systems (NPRD$) search of wet cell battery f ailures identified 75 failure reports. Of these, 24 reports were due to low voltage and indicated the f ailure was thought to be due to normal / age related f ailures. A common mode failure mechanism was not identified. A .
Component Failure Analysis Report (CFAR) did not prove significant since this was the first f ailure at Byron, i
(0553R/0065R)