|
---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARML20203L0281986-04-25025 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 05000409/LER-1982-020, Updated LER 82-020/03X-1:on 821119-20,on Three Occasions Vacuum Pump Which Maintains Isokinetic Flow Rate to Stack Activity Monitors Tripped.Caused by Pump & Motor Overheating.Motor Thermal Overload Fuses Upgraded1983-04-21021 April 1983 Updated LER 82-020/03X-1:on 821119-20,on Three Occasions Vacuum Pump Which Maintains Isokinetic Flow Rate to Stack Activity Monitors Tripped.Caused by Pump & Motor Overheating.Motor Thermal Overload Fuses Upgraded ML20150E1351978-12-0404 December 1978 /03L-0 on 781202:periodic Leakage Rate Test for Personnel Did Not Meet Type B Test Criteria as Specified by Tech Specs.Test Strongbacks Were Not Completely Tightened Thereby Causing Seal to Stretch Upon Initial Pressurization ML20062E1121978-11-27027 November 1978 /01T-0 on 781126:Leakage Rate Test for Emergency Airlock Did Not Meet Type B Test Criteria Req by Tech Specs. Leakage Rate Was 1.037 Scfh in Excess of Limit.Leakage Was Due to Scratches on Valve Seats.Valve Was Replaced ML20147A9391978-09-15015 September 1978 /03L-0 on 780811:During Change of Engine Sump Lube Oil on 1A Diesel Generator,Lube Oil Was Diluted with Diesel Fuel oil.1B Diesel Generator & Other AC Sources Provided Required Elec Pwr.(Encl to 7809270110) ML20062E6341978-08-10010 August 1978 /03L-0 on 780620:zone 13 Fire & Smoke Detection Sys Placed on Bypass Following False Alarms.Caused by Malfunctioned Detector Head Which Had Been Overlooked by Personnel Implementing Tech Specs 1986-04-25
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20210A6361999-04-30030 April 1999 Rev 13 to Quality Assurance Program Description ML20206J3751999-04-29029 April 1999 Rev 13 to QA Program Description ML20207A9591999-01-31031 January 1999 Revised LACBWR Decommissioning Plan ML20196G0751998-12-31031 December 1998 1998 Annual Rept for Dairyland Power Cooperative ML20204D8371998-12-31031 December 1998 Annual Rept for 1998 - Rept of Changes,Tests & Experiments for Lacbwr. with ML20237E2701998-07-31031 July 1998 Rev 12 to QA Program Description ML20196A9241998-07-31031 July 1998 Rev 12 to LACBWR QA Program Description (Qapd) ML20202J0691998-01-31031 January 1998 Revised LACBWR Decommissioning Plan ML20202J0781998-01-31031 January 1998 Revised LACBWR Initial Site Characterization Survey for Safstor ML20203K0041997-12-31031 December 1997 Annual Operating Rept for 1997 - Rept of Changes,Tests & Experiments ML20249B7101997-12-31031 December 1997 Navigating for Our Future Dairyland Power 1997 Annual Rept. W/O Ltr ML20138B7771997-04-25025 April 1997 Corrected Page 8 of SE for Amend 69 to La Crosse Boiling Water Reactor License ML20137R7731997-04-11011 April 1997 Safety Evaluation Approving Changes to QAP Description ML20149K2071996-12-31031 December 1996 Conquering New Frontiers,Dairyland Power Cooperative 1996 Annual Rept ML20135C3901996-12-31031 December 1996 Annual Rept for 1996 - Rept of Changes,Tests & Experiments ML20132F8721996-10-31031 October 1996 Revised LACBWR Decommissioning Plan ML20134M2531996-02-20020 February 1996 Revised Rev 11 to QA Program Description ML18012A9001995-12-31031 December 1995 Annual Rept - 1995 of Changes,Tests & Experiments. W/ 960220 Ltr ML18011B1461995-04-20020 April 1995 LER 95-001-00:on 950417,noted That HPSW to Containment Building Isolated.Caused by Momentary LOP Due to Operational Test of 1A Edg.Procedures for Test Being Modified to Include Instructions to Verify Value Being open.W/950420 Ltr ML20056E2631993-08-10010 August 1993 LACBWR Containment Bldg Structural Analysis. W/One Oversize Drawing ML20056E2621993-07-31031 July 1993 Nonproprietary Analysis of Potential Blast Effects on LACBWR Reactor Bldg Due to 16 Inch Natural Gas Pipeline Failure,Suppl Analysis for Fast Closing Valve ML20127D3901993-01-13013 January 1993 SE Supporting Amend 67 to License DPR-45 ML20128K6011992-12-31031 December 1992 Corrected App a Re Std Format for Reporting Number of Personnel & man-rem by Work & Job Function,To Annual Rept for 1992 - Rept of Changes,Tests & Experiments ML20128D3421992-12-31031 December 1992 LACBWR Annual Rept 1992 ML20062B4761990-09-30030 September 1990 Monthly Operating Rept for Sept 1990 for LACBWR ML20248D0941989-08-31031 August 1989 Monthly Operating Rept for Aug 1989 for LACBWR ML20245G6571989-07-31031 July 1989 Monthly Operating Rept for Jul 1989 for LACBWR ML20245F9681989-06-30030 June 1989 Monthly Operating Rept for June 1989 for LACBWR ML20245J7351989-04-26026 April 1989 Safety Evaluation Supporting Amend 65 to License DPR-45 ML20245F8241989-02-28028 February 1989 Monthly Operating Rept for Feb 1989 for La Crosse Bwr.W/ ML20235S2441989-02-16016 February 1989 Suppl to 880104 Special Rept Re Inoperability of High Pressure Svc Water Diesel 1B.Fuel Supplu Sys Was Source of Problem.Fuel Supply Sys Will Be Replaced W/Above Ground Tanks for Both Diesels ML20245F7771989-01-31031 January 1989 Monthly Operating Rept for Jan 1989 for LACBWR ML20246H8771988-12-31031 December 1988 1988 Dairyland Power Cooperative Annual Rept ML20205T1271988-10-31031 October 1988 Monthly Operating Rept for Oct 1988 for La Crosse Bwr.W/ ML20151T0991988-08-0808 August 1988 Safety Evaluation Supporting Approval of Util Rev 10 to Emergency Plan ML20150D7051988-07-0808 July 1988 Safety Evaluation Supporting Rev 10 to Emergency Plan ML20155F9161988-05-31031 May 1988 Safety Evaluation Supporting Amend 62 to License DPR-45 ML20151G0591988-04-11011 April 1988 Safety Evaluation Supporting Amend 60 to Provisional License DPR-45 ML20148C3941988-03-15015 March 1988 Safety Evaluation Supporting Amend 59 to License DPR-45 ML20149G0711988-01-0404 January 1988 Safety Evaluation Supporting Amend 58 to License DPR-45 ML20147A9731987-12-31031 December 1987 Decommissioning Plan ML20149J3441987-12-31031 December 1987 LACBWR Annual Rept 1987 ML20195D7811987-12-31031 December 1987 1987 Dairyland Power Cooperative Annual Rept ML20237C6781987-11-30030 November 1987 Special Rept:On 871118,internal Portion of Fire Suppression Water Sys Removed from Svc to Replace Section of Piping.On 871120,piping Successfully Hydrostatically Tested & Fire Suppression Sys Returned to Svc ML20236W2731987-11-23023 November 1987 Special Rept:On 871028,following Initiation of 24 H Run for 18-month Diesel Generator Test,Emergency Diesel Generator 1B Stopped Running.No Cause for Trip Determined.Procedure Will Be Revised So Alarm Conditions Tested Before Run ML20236X0081987-11-18018 November 1987 Special Rept Re Inoperability of Fire Suppression Water Sys. Internal Portion of Sys Removed from Svc on 871118 to Replace Section of Piping.Initially Reported on 871118.Plant Permanently Shut Down & Reactor Defueled ML20234C3931987-10-20020 October 1987 Rev 5 to QA Program Description ML20151B2351987-10-20020 October 1987 Revised Rev 5 to QA Program Description ML20235R0531987-09-30030 September 1987 Determination of Potential Radiological Consequences to Members of Public from Fuel Handling Accident at La Crosse Nuclear Facility ML20235B5711987-09-15015 September 1987 Safety Evaluation Supporting Amend 57 to License DPR-45 1999-04-30
[Table view] |
Text
_ m 3
. , LICENSEE LVEN I HEPOH 1 l
CONT ROL BLOCK: l l l l l l l (PLE ASE PRINT OR TYPE ALL REQUIRED INFORMATIONI 1 ti 10 l1 7 H 9 ] l W l Il L l B l R l 1l@lbl0l0l-10l0l0l0l0l-l0l0l@l4l1l1l1l1l@l LICEN5EE CODE 14 LICE NSE. NUMU E R 26 2b LICENSE TYPE JO l
b7 CAT 68 l@
CON'T 10l11 "7 [ l L60 l@l 610 l 5 l 0DOCKET l - 10 l 4 l 0 l 689 @l 01811 l1 l 718 l@l019REPORT 14 7$ l1 l 5DATEl 7 I RB0 l@
7 8 NUMBER 69 EVENT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l
lo l2l l1A DIESEL GENERATOR WAS TAKEN OUT OF SERVICE FOR ONE HOUR AND TWELVE MIN
[o l3 l lUTES DURING REACTOR OPERATION TO CHANGE ENGINE SUMP LU% OIL. LUBE OIL l lo l4 } i WAS DILUTED WITH DIESEL FUEL OIL. 'B DIESEL GENERATOR AND OTHER A.C. S I lolsl l OURCES REMAINED OPERABLE TO PROVI' ', REQUIRED BACKUP A.C. ELECTRICAL POW j lo lo ] l ER. I 10 l 71 l _j I
l o 181 l 80 7 8 9 C DE CODE SUBC DE COMPONENT CODE SUBC DE SUS E 10191 l E l E lh l X lh [Z j @ LZ,l Z I Z l Z l Z l Z l@ l Z lh [Zj 18 19 20 7 8 9 10 11 12 12 SEQUENTI AL OCCURRf NCE REPORT R E VISION EVENT YEAR REPORT NO. CODE TYPE N O.
Ogg LEP 40 17181 L-J 1011101 1-1 10131 IL I l-l 101
_ 21 22 23 24 26 27 26 29 30 31 32 ThKE A T ON ON PL ANT ' MET HOURS SJB IT F OR Ai h 8. SU PLIER MAN F CTURER IX l@l2 l@ lM Z l@ l36Zl@ l0 10 l 0 l O_j [Y_j @
41 lNl@ j Zl@ l44Z l 9 l 9 l 947l@
33 34 3 40 42 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS ,
l i j o l l PARTIAL DILUTION OF LUBE OIL ATTRIBUTED TO RESIDUAL FUEL OIL IN INJECTOR l l
li l1 l lS. FOLLOWING OIL CHANGE. TECHNICAL SPECIFICATION SURVEILLANCE TESTING W 1
l i l 71 l AS PERFORMED ON BOTH DIESEL GENERATORS TO VERIFY OPERABILITY. ADDITIONA gii3l l L SAMPLING BY IMPROVED PROCEDURES WILL BE PERFORMED TO PROVIDE FURTHER B]
g ASIS FOR ACCEPTANCE CRITERIA AND DETERMINATION ( RATE OF DILUTION. l gii4i 7 8 9 80 ST S % POWER OTHE R ST ATUS ISCO RY DISCOVERY DESCRIPTION NA l l I1 I 5 l [ E_ J @ l 0 l 8 l 1 l @ l lBl@l LUBE OIL SAMPLE RESULTS A TIVI T Y CONTENT RELE ASED OF PELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE l
I1 16 l l Z l @ l Zl@l, ,
NA l l 46 NA 60 1 e 9 to 11 44 PERSONNEL F *POSURES NUMPER TYPE DESCRIPTION NA l li l 71 l 0 l 0101@l Z l@l *
' " ' NJ',N;URES n R NU,m R oE SCn, nO~ @
NA l li l aHl 91010101@l 1 11 12 80 LOh5 Of OH DAMAGE TO F ACILI TY TYPE DE SCRIPTION NA l I i I 9 I Lz_J@l 80 7 M 9 10 Pub t lCI T ' N RC USE ON L Y
, e gg["'"'"' ~ y, No D 7 o / K i 68 69 i , , i i i i i , , i i ii 80 5
/ MU fu R. E. SHIMSHAK pn og g . 608-689-2331 {
N AYE Of PHEPAHER __ . _
- . . = - - . . .. . -
.- .V ATTACHMENT TO LER. 78-010-030L-0 LAC-5459 DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
DOCKET NO. 50-409 On July 21, 1978, samples of lubricating oil were taken.from the respective-sumps (crank-cases) of emergency diesel generators lA and 1B. The sampling had been initiated as part of an improvement in the overall preventive maintenance program for mechanical equipment. .
On. August 11, 1978, a representative of the oil company laboratory performing the analysis informed the LACBWR Mechanical Engineer by telephone and later by telegraph that the lubricating oil sample from emergency diesel generator LA indicated 9.8% dilution with fuel oil. .Since this represented a gross dilution according to oil company standards, the representative recommended that the lube oil ,
be changed. The oil sample from emergency diesel generator.lB '
indicated moderate dilution with fuel oil, but a recommendation for oil change was not presented.
The reported results and recommendations were discussed by plant management personnel and it was decided to take the 1A emergency .
diesel out of service for a temporary period of time sufficient to changa the engine oil. This was done with the diesel generator being out of service for only one hour and twelve minutes. The reactor was being operated at approximately 81% with the generator connected to the Dairyland Power Cooperative grid at 39 MWe gross.
Following the oil change, emergency diesel generator lA was re-turned to service and test run satisfactorily. Surveillance requirements specified in Reference 2 were accomplished. Emergency diesel generator 1B was test run satisfactorily.
The engine lubricating oil for the diesel engines is normally changed on an annual basis. Experienced diesel engine service personnel have ;
indicated that the presence of fuel oil in the lubricating oil does not pose a problem unless the volume of the mixture in the crank- i case increases noticeably. Operating the engines at least twelve i continuous hours is regarded as a sufficient length of time to permit evaporation of the fuel oil' diluent.
Since no prior samples of lubricating oil had been taken-for analysis, a comparision basis had not been established. . Improvements in samp-ling procedures will better guarantee representative samples and a program offincreased sampling will enable a determination of the rate of dilution-and provide advisory information for preventive maintenance.
l
-.