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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20138B7771997-04-25025 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 ML20127D3901993-01-13013 January 1993 SE Supporting Amend 67 to License DPR-45 ML20245J7351989-04-26026 April 1989 Safety Evaluation Supporting Amend 65 to License DPR-45 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 ML20235B5711987-09-15015 September 1987 Safety Evaluation Supporting Amend 57 to License DPR-45 ML20206G6421987-04-0808 April 1987 Safety Evaluation Supporting Amend 55 to License DPR-45 ML20214N3921986-09-10010 September 1986 Safety Evaluation Supporting Amend 54 to License DPR-45 ML20209E9241986-09-0505 September 1986 Safety Evaluation Rept Supporting Amend 53 to License DPR-45.Neither EIS Nor Environ Assessment Necessary ML20209D9681986-09-0202 September 1986 Safety Evaluation Supporting Amend 52 to License DPR-45 ML20212N6121986-08-22022 August 1986 Safety Evaluation of Util 840530 Response to Generic Ltr 84-11, Insp of BWR Stainless Steel Piping. Response Did Not Meet Requirements NUREG-0827, Safety Evaluation Supporting Proposed Installation of remotely-operated Solenoid in Pipe Tunnel Outside Containment for Offgas Vent Line1986-08-0606 August 1986 Safety Evaluation Supporting Proposed Installation of remotely-operated Solenoid in Pipe Tunnel Outside Containment for Offgas Vent Line ML20204J2601986-07-30030 July 1986 Safety Evaluation Supporting Amend 51 to License DPR-45 ML20203H3161986-07-15015 July 1986 Safety Evaluation Supporting Amend 50 to License DPR-45 ML20207G2791986-07-15015 July 1986 Safety Evaluation Supporting Amend 49 to License DPR-45 ML20199K3891986-06-26026 June 1986 Safety Evaluation Supporting Exemption from Certain Requirements of 10CFR50.54(w) Re Primary Onsite Property Damage ML20141F4271986-04-14014 April 1986 Safety Evaluation Supporting Amend 48 to License DPR-45 ML20141D6331986-03-31031 March 1986 Safety Evaluation Denying 821029 Request for Amend to License DPR-45,eliminating Four Type B Tests ML20154S4771986-03-27027 March 1986 Safety Evaluation Supporting Amend 47 to License DPR-45 ML20140F3571986-03-25025 March 1986 Safety Evaluation Supporting Amend 46 to License DPR-45 ML20140D7311986-03-20020 March 1986 Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1 & 3.2.2 Re post-maint Testing IR 05000409/19840091986-03-10010 March 1986 Safety Evaluation Supporting Util 850208 Proposed Installation of Two Check Valves in Series in Sample Line to Improve Capability to Isolate Containment Atmosphere from Environ,Per Insp Rept 50-409/84-09 ML20141F9831986-01-0606 January 1986 Safety Evaluation Supporting Amend 45 to License DPR-45 ML20133F6491985-10-0808 October 1985 Safety Evaluation Supporting Amend 44 to License DPR-45 ML20205B7701985-09-0606 September 1985 SER Supporting Stability of Containment & Stacks Under Flood Conditions ML20126E5121985-06-0707 June 1985 Safety Evaluation Supporting Amend 43 to License DPR-45 ML20125D2041985-06-0505 June 1985 Safety Evaluation Supporting Amend 42 to License DPR-45 ML20138K0751984-12-12012 December 1984 Safety Evaluation on 831025 & 850918 Responses to Generic Ltr 83-28,Item 1.1 Re post-trip Review Program & Procedures. Program & Procedures Acceptable ML20062D9761982-07-30030 July 1982 Safety Evaluation Supporting Amend 29 to License DPR-45 ML20062B9961978-10-11011 October 1978 Safety Evaluation Supporting Amend 14 to License DPR-45 1997-04-25
[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
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SAFETY EVALUATION BY THE ,
0FFICE OF NUCLEAR REACTOR REGULATION LACROSSE BOILING WATER REACTOR (LACBWR) :
DOCKET NO. 50-409 t SHUTDOWN CONDENSER SAMPLE LINE
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, Introduction i As a result of the SEP review of containment isolation systems at LACBWR, i several corrective actions concerning administrative controls, procedures .
l and locking devices for valves were identified (NUREG-0827 Section 4.21). '
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During the region's verification of the licensee's actions, the staff
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identified an additional containment isolation issue, which is discussed in Inspection Report 50-409/84-09 dated October 5, 1984. The licensee ,
proposed corrective actions in a letter dated February 8, 198 (
Discussion I The shutdown condenser, located inside containment, provides a heat sink ,
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, when the reactor is isolated from the main condenser. Steam from the i main steam line passes through the tube side of the shutdown condenser where it is condensed by evaporating water on the shell side. The steam t
generated in the shell is exhausted to atmosphere, through a non-isolable vent line. A sampling line (1/2") is connected to the shell side to allow the water to be sampled. Two manual valves are provided on this Ifne,
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which are locked closed (with independent verification) except when a
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sample is in progress. The sample is taken inside containment and the
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manual valves can only be cot. trolled locally. The shutdown condenser is sampled twice per month and after use to ensure maintenance of high i purity water such that the tube heat transfer characteristics are not
! degrade Should an event occur that releases steam to the containment while a sample is in progress, the individual perfoming the sampling may be unable to reclose the manual valves before leaving the containment. If the containment
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pressure exceeds the head of water in the sample line, a direct path from the .L
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1 containment atmosphere to the shell side of the shutdown condenser and thus -
- to the environment would exis Evaluation .
- In response to the staff's concern, Dairyland Power Cooperative (DPC)
proposed to install two check valves in series in the sample line. This'
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arranqement would permit samples to be drawn, by opening of the two (existing) ,
manua' valves, but the check valves would prevent backflow of air through i the line even if the manual valves are not close , 1 As noted above, the two manual valves would normally provide the isolation
- function. The check valves will enhance the capability to isolate the ;
containment from the environment by providing additional barriers. The i l modifications proposed by the licensee will provide an isolation boundary
between the containment atmosphere and the environment should an accident ,
occur during the limited time periods while sampling is in progrc.. ,
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Conclusion The staff concludes that the proposed modifications, in conjunction with the existing valving and administrative controls, provide acceptable isolation for the shutdown condenser sample lin Principal Contributors: E. McKenn Dated: March 10, 198 .
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