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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
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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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Text
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'D DA/RYLAND hhh[~COOPERAT/VE PO DOX817
- 2615 EAST AVE SO . LACROSSE, WISCONS (608) 788 4000 JAMES W. TAYLOR
' Gsneral Manager -
November 30, 1987 (RJop)yy j pg In reply, please L!Z refer to LAC-12451 ;.. 3 w: .~
h.
DOCKET NO. 50-409 g l Mr. A. Bert Davis, Regional Administrator U. S. Nuclear Regulatory Commission Directorate of Regulatory Operations Region'III
'799 Roosevelt Road Glen Ellyn, IL 60137 l
Dear Mr. Davis:
SUBJECT:
Dairyland Power Cooperative La Crosse Boiling Water Reactor (LACBWR)
Provisional Operating License No. DPR-45 Special Report
REFERENCES:
(1) LACBWR Technical Specifications, Section 4.2.18.1 (2) 'LACBWR Technical Specifications, Section 6.9.2-(3) DPC Letter, Taylor to Davis, LAC-12439, November 18, 1987.
In accordance with References 1 and 2, this letter serves as the follow-up to the Special Report submitted in Reference 3.
The internal portion of the fire suppression water system was removed from service at 0630 on November 18, 1987 in order to replace a section of piping. The two diesel-driven High Pressure Service Water Pumps control switches were turned off. The procedure controlling the internal fire suppression system removal from service states the pumps should be started if a fire occurs. Hoses were laid from the yard hydrants to areas inside the plant to provide backup fire suppression capability prior to removing the internal portion of the system from service.
A tee with an approximately 8 foot section of HPSW piping was replaced.
The piping'was successfully hydrostatically tested on November 20, 1987. The fire suppression system was returned to service at 1525 on November 20, 1987.
The plant has been permanently shut down and the reactor defueled.
PCl-39
. DECA ~ pvg7
'8712220d69 871130 -
PDR ADOCK 05000409 i Ss DCD 4, t j
O y
-) e Mr. A. Bert Davis LAC-12451
November 30, 1987 If there are any questions, please contact us, Sincerely, DAIRYLAND POWER COOPERATIVE
,E James W. Taylor General Manager JWT:LSG:sks cc: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 'z0555 Mr. Peter B. Erickson, LACBWR Project Manager Division of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mr. Ken Ridgway, NRC Resident Inspector I
l l
I PCl-39
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