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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 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 ML20041F9771982-03-11011 March 1982 Safety Evaluation Supporting Amend 28 to License DPR-45 ML20032D5181981-11-0606 November 1981 Safety Evaluation Supporting Amend 26 to License DPR-45 ML20033A2081981-11-0505 November 1981 Evaluation of Adequacy of Station Electric Distribution Sys Voltages.Measurements Taken to Verify Analysis Shows That Calculated Values Are Accurate Representations of Worst Case Conditions Analyzed ML20032A5751981-10-23023 October 1981 Safety Evaluation Supporting Amend 25 to License DPR-45 ML20005B2741981-06-11011 June 1981 Safety Evaluation Re 790427,0502,23,29,0816 & 800114 Responses to IE Bulletin 79-08, Events Re BWRs Identified During TMI Incident. Licensee Has Acceptably Responded to Bulletin ML20003J0751981-04-23023 April 1981 Safety Evaluation Supporting Relief from Requirements of Section XI ASME Code Re Inservice Valve Testing.Core Requirements & Staff Position Re Verification of Pressure Isolation Valve Leak Tight Integrity Encl ML20008E6491981-02-13013 February 1981 Suppl 1 to 790727 Fire Protection Safety Evaluation Supporting Amend 17 to License DPR-45 ML19341C7171981-02-0404 February 1981 Safety Evaluation Supporting Amend 23 to License DPR-45 ML20003A5261981-01-16016 January 1981 Safety Evaluation Supporting Amend 22 to License DPR-45 ML19331D5301980-08-29029 August 1980 Safety Evaluation in Support of Licensee Position That Design & Installation of Site Dewatering Sys Not Required.Supporting Documentation Encl ML19323E8081980-05-13013 May 1980 Safety Evaluation Supporting Amend 20 to License DPR-45 ML19262C6071980-02-0404 February 1980 Revised Safety Evaluation Supporting Amend 18 to License DPR-45 ML19259D2881979-07-31031 July 1979 Safety Evaluation Supporting Change in Tech Specs to Increase Capacity of Spent Fuel Storage Pool & Provide Protection from Postulated Cask Drop Accident.Certificate of Svc Encl ML20062B9961978-10-11011 October 1978 Safety Evaluation Supporting Amend 14 to License DPR-45 ML20002A4041977-06-16016 June 1977 Safety Evaluation Supporting Amends 40,36 & 30 to Licenses DPR-3,DPR-28 & DPR-36,respectively 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 05000409/LER-1999-001, :on 990305,excessive back-flow Through Return Line Check Valve Was Noted.Check Valve Were Declared Inoperable.Compensatory Actions for Fesw Sys Pipe Break Were Established.With1999-03-29029 March 1999
- on 990305,excessive back-flow Through Return Line Check Valve Was Noted.Check Valve Were Declared Inoperable.Compensatory Actions for Fesw Sys Pipe Break Were Established.With
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 ML20196A9241998-07-31031 July 1998 Rev 12 to LACBWR QA Program Description (Qapd) ML20237E2701998-07-31031 July 1998 Rev 12 to QA Program Description ML20202J0781998-01-31031 January 1998 Revised LACBWR Initial Site Characterization Survey for Safstor ML20202J0691998-01-31031 January 1998 Revised LACBWR Decommissioning Plan 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 05000409/LER-1997-001, :on 970102,1A EDG Trouble Annunciator Alarmed Due to High Coolant Temperature of 205 Degrees F.All PMs Associated W/Sys That Require Second Verification Will Be Reviewed & Revised as Necessary1997-01-21021 January 1997
- on 970102,1A EDG Trouble Annunciator Alarmed Due to High Coolant Temperature of 205 Degrees F.All PMs Associated W/Sys That Require Second Verification Will Be Reviewed & Revised as Necessary
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 05000409/LER-1996-003, :on 961210,generator Plant Battery Found to Have Pilot Cell Specific Gravity of 1.198 Resulting in Bus Being Declared Inoperable & Battery Being Placed on Equalizing Charge1996-12-30030 December 1996
- on 961210,generator Plant Battery Found to Have Pilot Cell Specific Gravity of 1.198 Resulting in Bus Being Declared Inoperable & Battery Being Placed on Equalizing Charge
ML20132F8721996-10-31031 October 1996 Revised LACBWR Decommissioning Plan 05000409/LER-1996-002, :on 961022,failure to Review Temporary Changes within 30 Days Occurred.Procedure Has Been Revised1996-10-30030 October 1996
- on 961022,failure to Review Temporary Changes within 30 Days Occurred.Procedure Has Been Revised
05000409/LER-1996-001, :on 960919,noted Documentation of Checks Not Being Performed as Required by Procedure.Caused by Area Radiation Monitor Chart Recorder Out of Svc for Repairs. Plant Manager Issued Memo to Personnel1996-10-11011 October 1996
- on 960919,noted Documentation of Checks Not Being Performed as Required by Procedure.Caused by Area Radiation Monitor Chart Recorder Out of Svc for Repairs. Plant Manager Issued Memo to Personnel
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 05000409/LER-1995-001, :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 Open1995-04-20020 April 1995
- 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
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 ML20046A6651993-06-30030 June 1993 Revs to Decommissioning Plan ML20127D3901993-01-13013 January 1993 SE Supporting Amend 67 to License DPR-45 ML20128D3421992-12-31031 December 1992 LACBWR Annual Rept 1992 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 ML20045D6201992-12-31031 December 1992 1992 Annual Rept 05000409/LER-1992-001, :on 920712,1B non-interruptible Bus Rendered Inoperable When Blade from Internal Cooling Fan Fell Onto Electrical Components Inverter.Event Originally Processed as Incident Rept.Update Will Be Submitted1992-08-31031 August 1992
- on 920712,1B non-interruptible Bus Rendered Inoperable When Blade from Internal Cooling Fan Fell Onto Electrical Components Inverter.Event Originally Processed as Incident Rept.Update Will Be Submitted
ML20029C1131991-02-28028 February 1991 Monthly Operating Rept for Feb 1991 for Lacrosse Boiling Water Reactor 05000409/LER-1990-004, :on 901013,diesel Generator 1A Failed to Successfully Complete 18-month Test1990-11-0202 November 1990
- on 901013,diesel Generator 1A Failed to Successfully Complete 18-month Test
ML20062B4761990-09-30030 September 1990 Monthly Operating Rept for Sept 1990 for LACBWR 05000409/LER-1990-003, :on 900608,five Required Fire Protection QA Audits Missed.Caused by Scheduling Error Since 890101.Util Reverted to Original QA Audit Schedule1990-07-0606 July 1990
- on 900608,five Required Fire Protection QA Audits Missed.Caused by Scheduling Error Since 890101.Util Reverted to Original QA Audit Schedule
ML20043A1191990-04-30030 April 1990 Monthly Operating Rept for Apr 1990 for La Crosse Bwr ML20034A3921990-03-31031 March 1990 Monthly Operating Rept for Mar 1990 for LACBWR 05000409/LER-1990-002, :on 900115,discovered That Data Recorded for 18-month Surveillance Test of Diesel Bldg Battery Charger, Completed on 871005,showed Less than 50 Amperes for 4 Consecutive Hours.Memo Issued to Personnel1990-02-0707 February 1990
- on 900115,discovered That Data Recorded for 18-month Surveillance Test of Diesel Bldg Battery Charger, Completed on 871005,showed Less than 50 Amperes for 4 Consecutive Hours.Memo Issued to Personnel
05000409/LER-1990-001, :on 900115,discovered That Weekly Battery Tests for Batteries Supplying Dc Buses,Emergency Diesel Generators & High Pressure Svc Diesels Not Performed for Wk of 890312-18.Second Electrician hired.W/9002051990-02-0505 February 1990
- on 900115,discovered That Weekly Battery Tests for Batteries Supplying Dc Buses,Emergency Diesel Generators & High Pressure Svc Diesels Not Performed for Wk of 890312-18.Second Electrician hired.W/900205
ML20006E2951989-12-31031 December 1989 LACBWR Annual Rept,1989 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 05000409/LER-1989-001, :on 890424,discovered That Weekly Battery Tests for Previous Wk Had Not Been Performed.Caused by Absences of Key Personnel Who Supervise & Perform Tests.Required Testing Procedures Performed1989-04-28028 April 1989
- on 890424,discovered That Weekly Battery Tests for Previous Wk Had Not Been Performed.Caused by Absences of Key Personnel Who Supervise & Perform Tests.Required Testing Procedures Performed
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 1999-04-30
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 54 TO PROVISIONAL OPERATING LICENSE NO. DPR-45 DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
DOCKET NO. 50-409
1.0 INTRODUCTION
i By application dated iobruary 21, 1986, Dairyland Power Cooperative (DPC) (the licensee) requested a change to Figure 6.2.2-1 of the La Crosse Boiling Water Reactor (LACBWR) Technical Specifications. The proposed amendment would: (a) change the position of Radiation Protection Engineering Specialist to Training Specialist, (b) transfer the Radiation Protection Engineer to the On-Site Technical Support Group, (c) designate a Technical Support Engineer as the Emergency Planning Coordinator, and (d) eliminate the position of Assistant General Manager-Power and transfer the related responsibilities to the General Manager.
2.0 EVALUATION l
The proposed changes involving transferring of the Radiation Protection Engineer to the On-site Technical Support group, eliminating the Radiation Protection Engineering Specialist and adding a Training Specialist report-i ing to the Health and Safety Supervisor involved a redistribution of j
responsibilities. The same number of people will remain with responsibili-l ties in radiation protection. The Radiation Protection Engineer will be concentrating on the engineering aspects, the Health and Safety Supervisor i
on managing the department, and the training specialist on performing technician and all other radiation protection training. Since responsi-bilities were redistributed, but not eliminated, the staff concludes these i
changes are acceptable.
(
f The addition to the chart of a note that a Technical Support Engineer is responsible for Emergency Planning provides additional clarifying information.
No position previously shown on the chart is being eliminated. Since this l
change only involves the addition of clarifying information, it is J
acceptable.
l The position of Assistant General Manager-Power is deleted from the LACBWR facility organization chart. The responsibilities previously assigned to the Assistant General Manager-Power regarding safe operation of LAC 8WR are now held by the General Manager. Since the chart shows the 4
LACBWR Plant Superintendent has direct access to the General Manager, the staff concludes this change is acceptable.
In addition, the licensee has changed the solid line on the organization chart between the General 4
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. Manager-Power and the Safety Review Committee to a dotted line. Adding the dotted line clarifies that the General Manager has communications with the safety review committee but is not the head of the committee.
The staff concludes this change provides only clarification and is, therefore, acceptable.
The designations "LS0" and "LO" following some position t'itles have been removed. The designation was not totally consistent in that some, not all, plant operators are licensed and some enaineers are licensed. Table 6.2.2-1, " Minimum Shift Crew Composition #" states the required number of licenses per shift. This table is not being changed. Additionally, Section 6.3 on Unit Staff Oualifications remains the same. Since neither the number and type of licenses needed to operate the facility, nor the unit staff qualifications are being changed, removina the designations "LS0" and "LO" from the organization chart is considered acceptable by the staff.
The staff concludes the three aforementioned LACRWR operating staff changes are acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, this amendment meets the eliaibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security nor to the health and safety of the public.
Principal Contributor:
J. Stang Dated: September 10, 1986
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