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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20235S2441989-02-16016 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 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 ML20236Y2151987-05-15015 May 1987 Special Rept 87-02:on 870216,reactor Manually Scrammed Due to Erroneous Indication of Low Voltage on Turbine Bldg MCC1A.On 870406,reactor Power Dropped Following Trip of 1A Forced Circulation Pump ML20211E4971986-06-0404 June 1986 Special Rept 86-02:on 860307 & 0525,thermal Power Changed by Greater than 15% of Rated Thermal Power within 1 H on Three Occasions.Caused by Bus 1B Power Loss,Reactor Forced Circulation Pump Trip & Control Air Sys ML20138B7861986-03-11011 March 1986 Special Rept:On 860311,internal Portion of High Pressure Svc Water Sys Which Supplies Fire Suppression Sys Removed from Svc to Replace Valve Required to Be Tested by Inservice Testing Program ML20141P1241986-03-0606 March 1986 Incident Rept DPC-86-1:on 860104,seal Inject Supply Line Separated at Swagelock Fitting,Spraying Water & Resulting in Reactor Shutdown.Cause Unknown.Mechanical Seal on CRD 2 Reworked ML20138L8431985-10-21021 October 1985 Special Rept 85-02:on 850725,0909 & 14,reactor Thermal Power Changed by More than 15% of Rated Thermal Power within 1 H. Power History,Fuel Burnup,Cleanup Flow History,Offgas Activity Levels & Gross Alpha Activity Levels Discussed ML20138L7451985-10-0808 October 1985 Special Rept:Discusses Circumstances Which Led to Inaccuracies in Personnel Cumulative Lifetime Dose Records. Cumulative Permanent Doses in Radiation Dosimetry Rept Do Not Agree W/Records Maintained in Computer File ML20128N9141985-07-18018 July 1985 Special Rept 85-01:providing Results of Sampling & Analysis Actions & Addl Operational Info for Six Occasions When Reactor Thermal Power Changed by More than 15% of Rated Thermal Power within 1 H ML20062D1601982-07-26026 July 1982 Ro:On 820726,internal Portion of Fire Suppression Water Sys Removed from Svc in Order to Replace Fire Hose Cabinets Rendering Fire Suppression Water Sys Inoperable.Backup Capability Provided ML20054F1711982-06-0707 June 1982 RO 82-14:on 820605,w/reactor in Operating Condition 2 at 50 X 10-6% Power,Review of Shift Supervisor Log Revealed Primary Water Alpha Activity of 7.46 X 10-6 Uci/Gm.Reactor Shutdown Conducted 820605 in Accordance W/Tech Spec 1989-02-16
[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
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D DA/RYLAND h k COOPERAT/VE LA CROSSE BOILING WATER REACTOR (LACBWR) P.O. BOX 275 GENOA, WISCONSIN 54632 *(608) 689-2331 March 11, 1986 i l
l In reply, please refer to LAC-11462 DOCKET NO. 50-409 Mr. James G. Keppler Regional Administrator U.S. Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, IL 60137
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 SPECIAL REPORT
REFERENCE:
(1) LACBWR Technical Specifications, Section 4.2.18.1 (2) LACBWR Technical Specifications, Section 6.9.2
Dear Mr. Keppler:
In accordance with References (1) and (2), this letter constitutes the Special Reports required when the fire suppression water system is inoperable.
The internal portion of the High Pressure Service Water (HPSW) System, which supplies the fire suppression system was removed from service at 0906 on March 11, 1986. The external fire suppression system remained in service.
N Emergency Service Water Supply System Pumps were also available for deoloyment, if needed. The plant was in Operating Condition 4, Cold Shutdown.
The internal portion of the fire suppression system was isolated in order to replace a valve required to be tested by the Inservice Testing Program. The system was returned to service at 0922.
8603250161 860311
{ I PDR ADOCM 05000409 S g g PDR g g WPl.6.9 DA!RYLAND POWER COOPERATlVE CORPORATE HEADOUARTERS*P.O. BOX 817* LACROSSE, WISCONSIN 54601-(608)788-4000
Mr. Janas G. Kappler, Rtgional Administrator March 11, 1986
. U. S. Nuclear Regulatory Commission LAC-Il462 The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> telephone notification of removal from service was made to Ross Landsman, U. S. Nuclear Regulatory Commission Region III, at 1325 on March 11, 1986' by L. Goodman.
If you have any questions, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE NN ohn Parkyn, LACB Plant Superintendent JDP:LSG:sks cc: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 NRC Resident Inspector Mr. John Stang a
WPl.6.9 l
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