|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K9401999-10-0606 October 1999 Submits Safeguards Event Log for Calendar Quarter Ending 990930,IAW 10CFR73.71.No Safeguards Events Occurred ML20210R9181999-08-13013 August 1999 Forwards Insp Rept 50-409/99-02 on 990726-28.No Violations Noted ML20210F3651999-07-0909 July 1999 Submits Safeguards Event Log for Calendar Quarter Ending 990630,IAW 10CFR73.71 & LACBWR Security Plan ML20196D5161999-06-21021 June 1999 Discusses Rev 19 to Various Portions of Lacrosse Boiling Water Reactor Emergency Plan Submitted Under Provisions of 10CFR50.54(q).NRC Initial Review of Changes Will Be Subject to Insp to Confirm No Decrease in Effectiveness of Plan ML20207G1991999-06-0303 June 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Reorganization Chart Encl ML20206R9211999-05-10010 May 1999 Forwards Annual Financial Rept & Certified Financial Statements for DPC for Years 1998 & 1997,IAW 10CFR50.71(b). Util Will Forward 1998 Annual Rept as Soon as Rept Is Completed ML20206H6771999-05-0505 May 1999 Forwards Insp Rept 50-409/99-01 on 990414-16.No Violation Noted.Overall Performance During Decommissioning/Safe Storage Activities Was Good ML20206J3671999-04-30030 April 1999 Forwards Rev 13 to QA Program Description, IAW 10CFR50.54(a)(3) & 50.4(b)(7).Changes in Rev 13 Listed ML20205R4261999-04-0808 April 1999 Submits Ltr for Calendar Quarter Ending 990331 IAW 10CFR73.71, Reporting of Safeguards Events. No Safeguards Events Occurred During Quarter ML20204F8291999-03-0909 March 1999 Forwards Annual Rept on Status of Decommissioning Funding for La Crosse Boiling Water Reactor,Iaw 10CFR50.75(f)(1) ML20207C2661999-02-19019 February 1999 Forwards Radioactive Effluent Rept & Radiological Monitoring Rept for 1998 for Lacbwr. Lacbwr,Pcp & ODCM, Encl ML20207A9431999-02-11011 February 1999 Forwards Revised Pages to LACBWR Decommissioning Plan. Each Page with Change Will Have Bar in right-hand Margin to Designate Location of Change ML20198E4371998-12-17017 December 1998 Forwards Insp Rept 50-409/98-05 on 981207-10.No Violations Noted.Activities in Areas of Facility Mgt & Control,Spent Fuel Safety & Radiological Safety Were Examined ML20196A8921998-11-23023 November 1998 Forwards Rev 12 to LACBWR QA Program Description ML20155H4221998-11-0303 November 1998 Ack Receipt of Re Insp Rept 50-409/98-02,in Response to Transmitting Predecisional EC Summary & Exercise of Enforcement Discretion Re Compliance with Maint Rule ML20154K0191998-10-13013 October 1998 Forwards Insp Rept 50-409/98-04 on 980921-22.No Violations Noted ML20154P4351998-10-13013 October 1998 Responds to Re Insp Rept 50-409/98-02 & Refers to C/As Taken to Bring LACBWR Into Compliance with Maint Rule IR 05000409/19980021998-09-17017 September 1998 Discusses Predecisional Enforcement Conference Held on 980630 Re Insp Rept 50-409/98-02 & Exercise of Enforcement Discretion.Two Apparent Violations,Involving Failure to Implement Key Aspects of Maintenace Rule,Identified ML20151Z6501998-09-17017 September 1998 Discusses Predecisional Enforcement Conference Held on 980630 Re Insp Rept 50-409/98-02 & Exercise of Enforcement Discretion.Two Apparent Violations,Involving Failure to Implement Key Aspects of Maintenace Rule,Identified ML20153F7431998-09-14014 September 1998 Informs That Changes Made in Rev 12 Are Adminstrative in Nature & Do Not Result in Reduction in Commitment to Safety & Reliably Operate LACBWR in Safstor Condition,Per 980909 Telcon with NRC ML20237D8861998-08-21021 August 1998 Advises That Rev 18 to Portions of Emergency Plan Do Not Decrease Effectiveness of Plan & Plan Continues to Meet Relevant Stds of 10CFR50.47(b) & Therefore,Nrc Approval Not Required ML20237B9181998-08-17017 August 1998 Forwards Insp Rept 50-409/98-03 on 980811-12.No Violations Were Noted.Insp Included Review of Physical Security Plan for LACBWR ML20236W8111998-08-0303 August 1998 Forwards Summary of Decommissioning Insp Plan for Oct 1998 - Apr 1999,for Info.Plan Will Be Updated Approx Twice Yearly & May Be Revised at Any Time Based on Future Insp Findings, Events & Resource Availability ML20237E2631998-07-15015 July 1998 Forwards Rev 12 to QA Program Description. Page Change Locations Indicated by Bold Bar in right-hand Margin ML20236K7091998-07-0606 July 1998 Forwards Official Transcript Proceedings from 980513,public Meeting Held in Viroqua,Wi on Decommissioning of Lacrosse Boiling Water Reactor.Pen & Ink Changes Made to Original Transcript to Correct Errors & to Clarify Abbreviations ML20249A8331998-06-15015 June 1998 Expresses Appreciation for Support Provided for Recent Meeting Held at Viroqua High School - Middle School Complex on Decommissioning of Lacrosse Boiling Water Reactor ML20248M0461998-06-0909 June 1998 Expresses Appreciation for Support Provided for Recent Public Meeting Held at Viroqua High School on Decommissioning of LACBWR ML20216B9311998-05-0707 May 1998 Forwards Insp Rept 50-409/98-01 on 980420-0423.No Violations Noted ML20217K7121998-03-27027 March 1998 Forwards Rev 18 to LACBWR Emergency Plan.Bar Lines in right- Hand Margins Note Changes.Description of Each Change & Reason for Change Is Included as Cover Pages to Plan Rev ML20203K2041998-02-27027 February 1998 Forwards Summary of Decommissioning Insp Plan for Remainder of FY1998.Plan Will Be Updated Approx Twice Each Yr & May Be Revised Any Time Based on Future Insp Findings,Events, Resource Availabilty,Etc ML20202J4261998-02-16016 February 1998 Forwards Revised LACBWR Decommissioning Plan & Revised LACBWR Initial Site Characterization Survey for Safstor. Both Documents Revised Jan 1998 ML20202J0381998-02-10010 February 1998 Forwards Revised LACBWR Decommissioning Plan. Each Page W/Change Will Have Bar in right-hand Margin to Designate Location of Change ML20199A9351998-01-19019 January 1998 Forwards Insp Rept 50-409/97-01 on 971209-11 & 980107.No Violations Noted.Activities in Areas of Facility Mgt, Decommissioning Support,Spent Fuel Safety & Radiological Safety Were Examined During Insp ML20199J4111997-11-21021 November 1997 Informs That NRC Regional Oversight Responsibilities for LACBWR Has Been Transferred to Region III Div of Nuclear Matls Safety.Effective 971105 D Nelson Became Region III Point of Contact for Routine LACBWR Insp Matters ML20198R9721997-10-24024 October 1997 Forwards Changes to Physical Security Plan,Contingency Plan & Guard Force Training & Qualification Plan.Encl Withheld ML20149G1311997-07-10010 July 1997 Submits Ltr Re Quarterly Submittal of Safeguards Events Log for Quarter Ending 970630.No Safeguards Events During Past Quarter ML20148S9131997-07-0303 July 1997 Forwards Annual Financial Rept & Certified Financial Statements for Dairyland Power Cooperative for 1996 & 1995 ML20141H5581997-05-20020 May 1997 Discusses Change in Ofc as of 970520.Project Mgt for Facility BWR Will Be Assumed by Pw Harris.Site Visit Will Be Arranged Convenient to Both Staff & Scheduled Activities ML20141B7521997-05-0909 May 1997 Forwards TS Re Changes to LACBWR Controlling Documents ML20138H8011997-04-29029 April 1997 Forwards Corrected Page to Safety Evaluation,Issued by NRC, by Ltr Dtd 970425.W/o Ltr ML20138B6821997-04-25025 April 1997 Forwards Corrected Page 8 of SE for Amend 69 to La Crosse Boiling Water Reactor License ML20138A6431997-04-15015 April 1997 Forwards Rev 11 to LACBWR QA Program Description ML20137R7651997-04-11011 April 1997 Forwards Safety Evaluation Approving Changes to QAP Description ML20138B7261997-04-10010 April 1997 Submits Ltr for Calendar Quarter Ending 970331,IAW 10CFR73.71 & LACBWR Security Plan ML20134H1841997-01-31031 January 1997 Submits Quarterly Safeguards Event Log Re License DPR-45 ML20133A3721996-12-16016 December 1996 Forwards Rev 17 to LACBWR Emergency Plan ML20132F8601996-12-10010 December 1996 Forwards Revised LACBWR Decommissioning Plan. Each Page W/ Change Will Have Bar in right-hand Margin to Designate Location of Change ML20134M2421996-11-0505 November 1996 Forwards Rev 11 to QA Program Description, Clarifying Section I, Organization Paragraph 7.d Revised to Assure Majority of SRC Members Be Degreed Individuals ML20149F2461994-08-0202 August 1994 Ack Receipt of 10CFR50.54(a) Submittal Dtd 940620,which Incorporates Changes in Quality Assurance Program Description ML20058P1281993-12-0909 December 1993 Forwards Changes to Physical Security Plan,Contingency Plan & Guard Force Training & Qualification Plan.Encls Withheld (Ref 10CFR2.790(d)) 1999-08-13
[Table view] Category:NRC TO UTILITY
MONTHYEARML20059N6281990-10-0505 October 1990 Forwards Insp Rept 50-409/90-01 on 900917-18.No Violations Noted ML20247A7251989-09-0101 September 1989 Forwards Safety Insp 50-409/89-02 on 890801-11.No Violations Noted ML20247K3871989-05-25025 May 1989 Forwards Insp Rept 50-409/89-01 on 890508-11.No Violations Noted ML20245J7131989-04-26026 April 1989 Forwards Amend 65 to License DPR-45,environ Assessment & Finding of No Significant Impact & Safety Evaluation.Amend Revises Tech Specs in Partial Response to 871221,880222,1013 & 890215 Applications ML20196C9621988-12-0505 December 1988 Advises That 881115 Rev 6 to QA Program Consistent W/ Provisions of 10CFR50,App B & Acceptable.Rev Involves Organization Changes,Including Fire Protection Responsibility Now Assigned to Technical Support Engineer ML20206K4961988-11-18018 November 1988 Forwards Temporary Exemption from 10CFR50.54(w)(5)(i) Schedular Requirements of Property Insurance Rule Re Insurance Policies That Prioritize Insurance Proceeds for Stabilization & Decontamination After Accident ML20206J4931988-11-18018 November 1988 Forwards Physical Security Insp Rept 50-409/88-09 on 881021-26 & 1101.No Violations Noted ML20206B5421988-11-0707 November 1988 Ack Receipt of Transmitting Scope & Objectives for 1988 Emergency Preparedness Exercise Scheduled for 881220.Scope & Objectives Acceptable ML20205P1791988-10-31031 October 1988 Advises That 880908 Rev 3 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20151R3101988-08-0303 August 1988 Forwards Safety Insp Rept 50-409/88-05 on 880501-0630.No Violations Noted ML20207F8881988-07-27027 July 1988 Forwards Latest Rev of NRC Manual Chapter 0516, Salp. Region III Will Begin Using New Functional Areas Set Forth in Rev for All SALP Rept Periods Which Extend Beyond 880606 Effective Date of Procedure ML20150D7011988-07-0808 July 1988 Forwards Safety Evaluation Supporting Rev 10 to Emergency Plan ML20150D3781988-07-0707 July 1988 Forwards Request for Addl Info Re Proposed Decommissioning Plan & Amend to Tech Specs Per 871221 & 880222 Applications. Response Requested by 880815 ML20150B8211988-06-23023 June 1988 Forwards Draft Rev 5 to ES-601, Administration of NRC Requalification Program Evaluations. W/O Encl ML20155D3851988-06-0303 June 1988 Forwards Safety Insp Rept 50-409/88-06 on 880517-20 & Notice of Violation ML20154H5701988-05-19019 May 1988 Notifies That Paragraphs 2.C.(3) & 2.C.(4) Deleted from License DPR-45.Paragraphs Should Have Been Deleted by 880518 Amend 61 to License,Revising Physical Security Plan ML20151W3051988-04-27027 April 1988 Forwards Safeguards Insp Rept 50-409/88-02 on 880321-22.No Violations Noted ML20151G0531988-04-11011 April 1988 Forwards Amend 60 to Provisional License DPR-45 & Safety Evaluation.Amend Revises Tech Specs in Response to 871112 Application as Revised on 880129.Environ Assessment Also Encl ML20151E1041988-04-11011 April 1988 Forwards Notice of Consideration of Issuance of Amend to License DPR-45 & Opportunity for Hearing Re 870924 Application ML20151D7561988-04-0505 April 1988 Forwards Safety Insp Rept 50-409/88-03 on 880207-0320. Violation Involving Failure to Maintain Min Shift Crew Composition Noted.Response Addressing Lack of Attention to Responsibilities & Controls to Prevent Recurrence Requested ML20150D3581988-03-21021 March 1988 Advises That Changes to QA Plan Consistent W/Provisions of 10CFR50,App B & Acceptable.Notification Required for Changes for Other Operative QA Commitments Outside QA Program Description ML20148C3471988-03-15015 March 1988 Forwards Amend 59 to License DPR-45,safety Evaluation & Environ Assessment.Amend Revises Tech Specs to Reflect Exemption from 10CFR50.54(o) & 10CFR50,App J Requirements to Perform Type a Containment Bldg Integrated Leak Rate Tests ML20147H9351988-03-0303 March 1988 Requests Util Help in Allowing NRC Through Contractor Westinghouse Hanford Co to Collect Relevant Info on Plant BWR Decommissioning Activities for NRC Data Collection Survey ML20147C4491988-02-24024 February 1988 Forwards Safety Insp Rept 50-409/88-01 on 871206-880206.No Violations Noted ML20149J8381988-02-19019 February 1988 Documents 880120 & 21 Telcons Between R Christians,J Parkyn & L Nelson of Util & R Meck,J Foster & P Erickson of NRC Re Comments & Questions Arising from Review of Proposed Rev 10 to Emergency Plan Submitted on 870929 ML20149E4141988-01-11011 January 1988 Requests Addl Info Re 871112 Application for Amend to License DPR-45 Reducing Shift Crew Requirements.Spec Should Be Proposed to Require Individual Qualified in Radiation Protection on Site When Potential for Release Exists ML20147D5581988-01-0808 January 1988 Notifies of Cancellation of SALP 7 for Assessment Period 860701-871031,due to Permanent Plant Shutdown on 870430 ML20149G0431988-01-0404 January 1988 Forwards Amend 58 to License DPR-45,safety Evaluation & Environ Assessment & Finding of No Significant Impact.Amend Revises Tech Specs to Show possession-only Status & Grants Exemption from 10CFR50,App R Re Fire Brigade Requirements ML20238C8651987-12-23023 December 1987 Forwards Exemption to 10CFR50,App E,Section IV.F.2 & 10CFR50.47(b)(7) Re Requirements to Conduct 1987 Emergency Preparedness Exercise & Requirement to Produce & Distribute Annual Info Brochure to Public.Environ Assessment Also Encl ML20236S7721987-11-24024 November 1987 Advises That 871111 Rev to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20236P6181987-11-17017 November 1987 Advises That Util Will Not Be Billed for FY88 Annual Fees Under Current Requirements of 10CFR171 Since License DPR-45 Amended on 870804 to Authorize Possession,But Not Operation of Plant,Per 871030 Request ML20236J5461987-10-30030 October 1987 Forwards Safety Insp Rept 50-409/87-14 on 871013-16.No Violations Noted ML20236J4441987-10-28028 October 1987 Forwards FEMA Negative Findings on Emergency Preparedness, Impacting States of Wi,Mn & IA & Vernon County.Negative Findings Concerned Alerting & Notification Sys for 5-mile EPZ ML20236J7481987-10-26026 October 1987 Forwards Safety Insp Rept 50-409/87-11 on 870822-1016.No Violations Noted IR 05000409/19870131987-09-29029 September 1987 Forwards SNM Control & Accountability Insp Rept 50-409/87-13 on 870908-11.No Violations Noted.Rept Withheld (Ref 10CFR2.790) ML20235J0361987-09-24024 September 1987 Forwards Physical Security Insp Rept 50-409/87-12 on 870908-16.No Violations Noted ML20235F4221987-09-22022 September 1987 Forwards NRR Position Re Entry Into Limiting Condition for Operation Based on Inservice Testing Surveillance Results within Required Action Range.Review of Practices for Performing Inservice Testing Surveillances Recommended ML20239A2011987-09-16016 September 1987 Forwards Order Imposing Civil Monetary Penalty in Amount of $25,000 for 870224 Notice of Violation Re Importance of Developing & Maintaining Effective Program to Protect Safeguards Info ML20235B5301987-09-15015 September 1987 Forwards Amend 57 to License DPR-45 & Safety Evaluation. Amend Revises Tech Specs to Delete Requirements for Inservice Insp & Nuclear Instrumentation ML20237J4041987-08-28028 August 1987 Forwards Safety Insp Rept 50-409/87-10 on 870718-0821.No Violations Noted ML20236D7471987-07-24024 July 1987 Forwards Safety Insp Rept 50-409/87-09 on 870601-0717.No Violations Identified ML20235G7941987-07-0808 July 1987 Concludes That Review of Revised Physical Security Plan Advisable Since Near Submission of Revised Security Plan Addressing Criteria for Possession Only Facility Not Envisioned.Implementation of Util 870429 Rev Allowed ML20235E1381987-07-0606 July 1987 Forwards SALP Rept 50-409/86-01 for Jan 1985 - June 1986. Util 861107 Submittal of Addl Info to Justify Upgrading of Fire Protection Rating Confirmed That Fire Protection Rating Should Be Raised to Category 1 ML20215M1751987-06-23023 June 1987 Ack Receipt of .Revised Pages Encl in Ltr Will Be Inserted Into Mqs Insp,Inc Rept Per Request ML20215L1971987-06-18018 June 1987 Advises That a Bournia Has Recently Been Reassigned to New Duties in Organization.Pb Erickson Has Been Designated as NRC Project Manager for Decommissioning of Plant Effective 870607 ML20215G7071987-06-12012 June 1987 Forwards Safety Insp Rept 50-409/87-08 on 870415-0530.No Violations Noted ML20215A0661987-06-10010 June 1987 Ack Receipt of Which Transmitted Rev of Facility Security Plan.Reiterates Licensee Plans to Shut Down Facility as First Step Toward Eventual Plant Decommissioning ML20214U9841987-06-0303 June 1987 Forwards Revised NRC Form 398,personal Qualifications statement-licensee & NRC Form 396,certification of Medical Exam by Facility Licensee.Forms Revised to Reflect Changes to 10CFR55 Effective on 870526.W/o Encls IR 05000409/19870021987-05-18018 May 1987 Discusses Deficiency Identified in Insp Rept 50-409/87-02 Re Implementation of Environ Qualification Program.Based on Review,Encl Notice of Violation Issued ML20213G4901987-05-12012 May 1987 Forwards Safety Insp Rept 50-409/87-06 on 870407-09 & Notice of Violation.Util Should Reevaluate LER 86-012 Re Failure to Follow Alarm Response Procedure Requiring Isolation of Tank to Address Indication of Mgt Weakness 1990-10-05
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20210R9181999-08-13013 August 1999 Forwards Insp Rept 50-409/99-02 on 990726-28.No Violations Noted ML20196D5161999-06-21021 June 1999 Discusses Rev 19 to Various Portions of Lacrosse Boiling Water Reactor Emergency Plan Submitted Under Provisions of 10CFR50.54(q).NRC Initial Review of Changes Will Be Subject to Insp to Confirm No Decrease in Effectiveness of Plan ML20207G1991999-06-0303 June 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Reorganization Chart Encl ML20206H6771999-05-0505 May 1999 Forwards Insp Rept 50-409/99-01 on 990414-16.No Violation Noted.Overall Performance During Decommissioning/Safe Storage Activities Was Good ML20198E4371998-12-17017 December 1998 Forwards Insp Rept 50-409/98-05 on 981207-10.No Violations Noted.Activities in Areas of Facility Mgt & Control,Spent Fuel Safety & Radiological Safety Were Examined ML20155H4221998-11-0303 November 1998 Ack Receipt of Re Insp Rept 50-409/98-02,in Response to Transmitting Predecisional EC Summary & Exercise of Enforcement Discretion Re Compliance with Maint Rule ML20154K0191998-10-13013 October 1998 Forwards Insp Rept 50-409/98-04 on 980921-22.No Violations Noted ML20151Z6501998-09-17017 September 1998 Discusses Predecisional Enforcement Conference Held on 980630 Re Insp Rept 50-409/98-02 & Exercise of Enforcement Discretion.Two Apparent Violations,Involving Failure to Implement Key Aspects of Maintenace Rule,Identified IR 05000409/19980021998-09-17017 September 1998 Discusses Predecisional Enforcement Conference Held on 980630 Re Insp Rept 50-409/98-02 & Exercise of Enforcement Discretion.Two Apparent Violations,Involving Failure to Implement Key Aspects of Maintenace Rule,Identified ML20237D8861998-08-21021 August 1998 Advises That Rev 18 to Portions of Emergency Plan Do Not Decrease Effectiveness of Plan & Plan Continues to Meet Relevant Stds of 10CFR50.47(b) & Therefore,Nrc Approval Not Required ML20237B9181998-08-17017 August 1998 Forwards Insp Rept 50-409/98-03 on 980811-12.No Violations Were Noted.Insp Included Review of Physical Security Plan for LACBWR ML20236W8111998-08-0303 August 1998 Forwards Summary of Decommissioning Insp Plan for Oct 1998 - Apr 1999,for Info.Plan Will Be Updated Approx Twice Yearly & May Be Revised at Any Time Based on Future Insp Findings, Events & Resource Availability ML20236K7091998-07-0606 July 1998 Forwards Official Transcript Proceedings from 980513,public Meeting Held in Viroqua,Wi on Decommissioning of Lacrosse Boiling Water Reactor.Pen & Ink Changes Made to Original Transcript to Correct Errors & to Clarify Abbreviations ML20249A8331998-06-15015 June 1998 Expresses Appreciation for Support Provided for Recent Meeting Held at Viroqua High School - Middle School Complex on Decommissioning of Lacrosse Boiling Water Reactor ML20248M0461998-06-0909 June 1998 Expresses Appreciation for Support Provided for Recent Public Meeting Held at Viroqua High School on Decommissioning of LACBWR ML20216B9311998-05-0707 May 1998 Forwards Insp Rept 50-409/98-01 on 980420-0423.No Violations Noted ML20203K2041998-02-27027 February 1998 Forwards Summary of Decommissioning Insp Plan for Remainder of FY1998.Plan Will Be Updated Approx Twice Each Yr & May Be Revised Any Time Based on Future Insp Findings,Events, Resource Availabilty,Etc ML20199A9351998-01-19019 January 1998 Forwards Insp Rept 50-409/97-01 on 971209-11 & 980107.No Violations Noted.Activities in Areas of Facility Mgt, Decommissioning Support,Spent Fuel Safety & Radiological Safety Were Examined During Insp ML20199J4111997-11-21021 November 1997 Informs That NRC Regional Oversight Responsibilities for LACBWR Has Been Transferred to Region III Div of Nuclear Matls Safety.Effective 971105 D Nelson Became Region III Point of Contact for Routine LACBWR Insp Matters ML20141H5581997-05-20020 May 1997 Discusses Change in Ofc as of 970520.Project Mgt for Facility BWR Will Be Assumed by Pw Harris.Site Visit Will Be Arranged Convenient to Both Staff & Scheduled Activities ML20138B6821997-04-25025 April 1997 Forwards Corrected Page 8 of SE for Amend 69 to La Crosse Boiling Water Reactor License ML20137R7651997-04-11011 April 1997 Forwards Safety Evaluation Approving Changes to QAP Description ML20149F2461994-08-0202 August 1994 Ack Receipt of 10CFR50.54(a) Submittal Dtd 940620,which Incorporates Changes in Quality Assurance Program Description ML20058B6791993-11-15015 November 1993 Ack Receipt of 931101 Response to Violations Noted in Insp Rept 50-409/93-17 ML20057G0841993-10-0606 October 1993 Forwards Insp Rept 50-409/93-01 on 930903-24 & Notice of Violation ML20057B3241993-05-0404 May 1993 Partial Response to FOIA Request for Documents.Forwards Documents Listed in App Q Which Are Being Made Available at Pdr.Documents Listed in App R Are Partially Withheld (Ref FOIA Exemption 5) ML20058M0361993-04-12012 April 1993 Partial Response to FOIA Request for Documents.Forwards Records in App L Which Are Being Withheld Partially for Listed Reasons,(Ref FOIA Exemptions 5) ML20127D3481993-01-13013 January 1993 Forwards Amend 67 to License DPR-45,SE & Request for Fr Publication.Amend Revises TS by Deleting Requirement That Radioactive Effluent Release Rept Be Submitted on Semiannual Basis & Adds Requirement That Rept Be Submitted Annually ML20128P5051992-11-23023 November 1992 Final Response to FOIA Request for Documents Re SECY-87-100 & 870622 Memo from Sj Chilk to V Stello & Wc Parler.Forwards Documents Listed in App a Which Are Being Made Available in PDR ML20141K0261991-08-0707 August 1991 Partial Response to FOIA Request for Documents Re Oyster Creek Nuclear Plant.Forwards App a Documents Which Are Being Made Available in PDR ML20059N6281990-10-0505 October 1990 Forwards Insp Rept 50-409/90-01 on 900917-18.No Violations Noted IA-89-409, Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6)1989-09-26026 September 1989 Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6) ML20247R3361989-09-26026 September 1989 Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6) ML20247A7251989-09-0101 September 1989 Forwards Safety Insp 50-409/89-02 on 890801-11.No Violations Noted ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20247K3871989-05-25025 May 1989 Forwards Insp Rept 50-409/89-01 on 890508-11.No Violations Noted ML20245J7131989-04-26026 April 1989 Forwards Amend 65 to License DPR-45,environ Assessment & Finding of No Significant Impact & Safety Evaluation.Amend Revises Tech Specs in Partial Response to 871221,880222,1013 & 890215 Applications ML20247M8271989-03-30030 March 1989 Discusses Licensee Requests for Changes to Requalification Program.Requests Include Extension of Max Time Period of 24 Months for Requalification Cycle to Account for Changes in Outage Schedules & Reorganization of Training Programs ML20196C9621988-12-0505 December 1988 Advises That 881115 Rev 6 to QA Program Consistent W/ Provisions of 10CFR50,App B & Acceptable.Rev Involves Organization Changes,Including Fire Protection Responsibility Now Assigned to Technical Support Engineer ML20206J4931988-11-18018 November 1988 Forwards Physical Security Insp Rept 50-409/88-09 on 881021-26 & 1101.No Violations Noted ML20206K4961988-11-18018 November 1988 Forwards Temporary Exemption from 10CFR50.54(w)(5)(i) Schedular Requirements of Property Insurance Rule Re Insurance Policies That Prioritize Insurance Proceeds for Stabilization & Decontamination After Accident ML20206B5421988-11-0707 November 1988 Ack Receipt of Transmitting Scope & Objectives for 1988 Emergency Preparedness Exercise Scheduled for 881220.Scope & Objectives Acceptable ML20205P1791988-10-31031 October 1988 Advises That 880908 Rev 3 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20154A1521988-08-17017 August 1988 Final Response to FOIA Request for Documents.Forwards Documents Listed in App A.Documents Also Available in Pdr. App B Documents Totally Withheld (Ref FOIA Exemption 5).App C Documents Partially Withheld (Ref FOIA Exemption 5) ML20151T0921988-08-0808 August 1988 Forwards Safety Evaluation Accepting & Approving Util Revised Onsite Emergency Plan to Reflect Current Status of Reactor ML20151R3101988-08-0303 August 1988 Forwards Safety Insp Rept 50-409/88-05 on 880501-0630.No Violations Noted ML20207F8881988-07-27027 July 1988 Forwards Latest Rev of NRC Manual Chapter 0516, Salp. Region III Will Begin Using New Functional Areas Set Forth in Rev for All SALP Rept Periods Which Extend Beyond 880606 Effective Date of Procedure ML20150D7011988-07-0808 July 1988 Forwards Safety Evaluation Supporting Rev 10 to Emergency Plan ML20150D3781988-07-0707 July 1988 Forwards Request for Addl Info Re Proposed Decommissioning Plan & Amend to Tech Specs Per 871221 & 880222 Applications. Response Requested by 880815 ML20150B8211988-06-23023 June 1988 Forwards Draft Rev 5 to ES-601, Administration of NRC Requalification Program Evaluations. W/O Encl 1999-08-13
[Table view] |
Text
,
i-
.
JAN 8 1987 Docket No. 50-409 Dairyland Power Cooperative ATTN: Mr. J. W. Taylor General Manager 2615 East Avenue - South La Crosse, WI 54601 Gentlemen:
This refers to the routine safety inspection conducted by A. G. Januska of this office on December 8-12,15 and 16,1986 of activities at La Crosse Boiling Water Reactor (LACBWR) authorized by Nuclear Regulatory Commission Operating License No. DPR-45 and to the discussion of our findings with Mr. G. Boyd and others of your staff at the conclusion of the inspectio '
The enclosed copy of our inspection report identifies areas examined during the inspection. Within these areas, the inspection consisted of a sulective examination of procedures and representative records, observations, and interviews with personnel. In addition, our Mobile Laboratory was at the site (
during the inspection to perform independent measurements of radioactivit No violations of NRC requirements were identified during the course of this
inspectio In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC Public Document Roo We will gladly discuss any questions you have concerning this inspectio
Sincerely 3' Original ai;0d by U.D. Shafer2'
8701140097 870108 PDR ADDCK 05000409 O PDR W. D. Shafer, Chief Emergency Preparedness and Radiological Protection Branch
Enclosure:
Inspection Report No. 50-409/86016(DRSS)
See Attached Distribution i
J ka r mach w fr h
'
.
.
Dairyland Power Cooperative 2 JAN 8 1987 Distribution
REGION III==
Report No. 50-409/86016(DRSS)
Docket No. 50-409 License No. DPR-45 Licensee: Dairyland Power Cooperative 2615 East Avenue - South La Crosse, WI 54601 Facility Name: Lacrosse Boiling Water Reactor (LACBWR)
Inspection At: LACBWR, Genoa, Wisconsin Inspection Conducted: December 8-16, 1986
[. . o w Ih ,
Inspector: A.G.bnuska 67 Date Yf,/hWit/6 Approved By: M. Schumacher, Chief Radiological Effluents and Date Chemistry Section Inspection Summary Inspection on December 8-16, 1986 (Inspection Report No. 50-409/86016(DRSS))
Areas Inspected: Routine unannounced inspection of (1) the confirmatory measurements program including sample split and onsite analysis with the Region III Mobile Laboratory, (2) the radiological environmental monitoring program and (3) open items identified during previous inspection Results: No violations or deviations were identifie . . . .
-
.
.
DETAILS 1. Persons Contacted
- G. Boyd, Operations Supervisor
- L. Nelson, Health and Safety Supervisor
- P. Shafer, Radiation Protection Engineer
- R. Wery, Quality Assurance Supervisor A. Hansen, Senior Health Physics Technician J. Gaynor, Health Physics Technician G. Roediger, Health Physics Technician M. Land, Health Physics Technician
- Denotes those present at the exit interview on December 12, 198 . Licensee Action on Previous Inspection Findings (Closed) Open Item (409/84015-05): Evaluate the effect of high alpha efficiency on effluent data for 1984. The licensee prepared an Am-241 standard and determined a new counter efficiency. An appropriate correction factor was applied to the first and second quarter 1984 effluent results which had already been submitted in a semiannual report. The corrected values for the first and second quarter, along with the third and fourth quarter results, were published in the 1984 Radioactive Effluent Report, (Closed) Open Item (409/85021-01): Continue efforts to solve chloride analytical problem. The licensee has continued to evaluate the chloride problem since the last inspection and has revised both technique and procedure. More rigid routine probe maintenance has been implemented to compensate for drift which was thought to be a significant part of the problem. A 20 minute test using laboratory demineralized water must result in less than a 2mV drift before a standard check on a 20, 40, 80, 120, or 160 ppb standard can be run. Although no finite numerical acceptance range has been determined corrective measures are taken based on management review. The inspector examined results for the first, second, and third quarters of 1986 for the analytical chemistry cross check with DPC Central Lab on chloride measurement Results for the three quarters show an improvement over previous test (0 pen) Open Item (409/85021-02): Analyze split sample for beta, gamma, H-3, Sr-89, and Sr-90 and report results to Region II Results of the sample comparisons are listed in Table 2; comparison criteria are given in Attachment The lone disagreement, Sr-90, was from the portion of the sample analyzed by the licensee's environmental contractor. In order to determine the validity of the result the licensee purchased a spike and had it analyzed by the contractor. Results of the analysis were not available at the close of the inspection. This item will remain open until the l results are submitted to Region III.
,
_ . - _ _ - . . - - . _
-
.
l
. ,
,
3. Confirmatory Measurements Seven samples (air particulate, charcoal, retention tank, gas, reactor coolant and two spike particulates) were analyzed for gamma emitting isotopes by the licensee and in the Region III mobile laboratory onsit Results are listed in Table 1. The licensee achieved 40 agreements out of 41 comparison A stack air particulate filter counted yielded only one nuclide, Co-60, which was not used for comparison because of poor counting statistic To check this geometry, the licensee's calibration standard was counted and analyzed as an unknown (F SPIKED LIC). The inspector relaxed the test criteria because of the differences in the NRC and licensee's calibration. Although this resulted in agreements, the NRC's spiked air particulate was counted (F SPIKED NRC) because of an apparent conservative bias which was also observed in a previous inspection. A gas sample analyzed resulted in a disagreement for Xe-135. As no reason could be found for the disagreement, the licensee agreed to (1) prepare a new standard, analyze it as an unknown and examine the 249 and 608 kev areas and (2) generate a new efficiency curve to be compared with the current curve before the next off gas sample is collected (0 pen Item 409/86016-01). In addition to the disagreement, the analysis also indicated a conservative bias. Discussion with the licensee revealed that these calibrations were performed using a liquid to simulate the particulate filter and the ga Liquid calibrations did not exhibit this bias. The licensee stated that the use of air particulate and gas standards supplied by an independent manufacturer will be evaluated (0 pen Item 409/86016-02) and purchased if determined to be advantageous. A reactor coolant sample split with the licensee initially resulted in eight disagreements in 19 comparisons. The results averaged 20%
nonconservative with only two comparisons being conservative. Multiple liquid geometries were compared by both the licensee and the NRC on portions of the sane initial sampl It was finally determined that some of the sample preferentially adhered to the NRC's plastic bottle and not the licensee's glass vial for the short period between putting the sample in the containers and adding dilution water. Another split, made adding the sample to dilution water already in the respective containers, resulted in all agreement The licensee agreed to analyze a portion of a retention tank sample (L WASTE) for gross S, tritium, strontium-89 and strontium-90 and submit the results to Region III (0 pen Item 409/86016-03).
4. Quality Control of Measurements The licensee participates in cross check programs for inplant measurements with a commercial contractor and for environmental measurements with the EPA. Results of the annual inplant analyses for 1986 were examined and found to be in complete agreemen Quality Assurance Audit Report 70-86-1, conducted August 11 through September 29, 1986, was examined. No findings were noted in the
[ Analytical Chemistry section of the audi j i I 3 ,
i 1 l
,
- - - -.. - - - - - - - - - - , . . ~ , , , - - , , , , , -
---, - --, , . , - - - , , - - - --,.e , --
-
.
. Radiolegical Environmental Monitoring Program The inspector examined five environmental air sample stations in the company of a licensee representative during a normal scheduled sample change. All stations were operating and in good repair. The representative appeared very knowledgeable about sample change requirement The inspector reviewed the 1985 Radiological Environmental Monitoring Report. The program is conducted as required by Technical Specification The results do not indicate a significant effect due to the operation of the plant. Although there were disagreements between the licensee and the State of Wisconsin for tritium in water samples, the licensee's values were less than the NRC LLD requirements in all but one instanc The licensee changed gross counting equipment during the period which resulted in closer agreement with the Stat . Open Items Open items are matters which have been discussed with the licensee, which will be reviewed further by the inspector, and which involve some action on the part of the NRC or licensee or both. Open items identified during the inspection are discussed in Section . Exit Interview The inspector met with licensee representatives denotes in Section 1 on December 12, 1986. The scope and findings were discussed. The licensee acknowledged the need to resolve the bias in the air particulate and gas geometries and agreed to count a portion of the retention tank sample and report the results to Region II During the exit interview, the inspector discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection. Licensee representatives did not identify any such documents or processes as proprietar Attachments:
1. Table 1, Confirmatory Measurements Program Results, 4th Quarter 1986 2. Table 2, Confirmatory Measurements Program Results, 4th Quarter 1985 3. Attachment 1, Criteria for Comparing Analytical Measurements
- . . -- .- . . - - .
. - . . .-- ------ - ...----
-
.
.
TABLE 1 U S NUCLEAR REGULATORY COMMISSION J+[
v ;<,
OFFICE'OF INSPECTION AND ENFORCEMENT --w
'
CONFIRMATORY MEASUREMENTS. PROGRAM
-
FACILITY: LACBWR '
FOR THE 4 QUARTER OF 1986 NRC- --
LICENSEE---- ---LICENSEE:NRC----
SAMPLE ISOTOPE RESULT ERROR' RESULT ERROR RATIO RES T L WASTE NN-54 4.5E-05 6.9E-07 4.3E-05 4.OE-07 9.6E-01 6.5E 01 A C O - 5 8 J- 1.8E-06 3.5E-07 1.6E-06 1.8E-07 8.9E-01 5.1E 00 A CO-60 1.5E-04 1.OE-06 1.4E-04 7.2E-07 9.3E-01 1.5E O2 A NP-239 5.8E-06 5.1E-07 6.3E-06 7.1E-07 1.1E 00 1.1E 01 A SR-91 1.3E-05 2.2E-06 7.9E-06 8.8E-07 6.1E-01 5.9E 00 A SR-92 1.5E-06 4.8E-07 2.OE-06 1.9E-07 1.3E 00 3.1E 00 A CS-137 1.6E-05 5.OE-07 1.5E-05 2.9E-07 9.4E-01 3.2E 01 .A LA-140 2.5E-06 2.1E-07 2.3E-06 1.4E-07 9.2E-01 1.2E 01 A OFF GAS KR-85M 4.6E-03 7.5E-05 5.OE-03 1.5E-05 1.1E 00 6.1E 01 A KR-88 1.5E-02 1.OE-03 1.8E-02 8.9E-05 1.2E 00 1.5E 01 A XE-133 2.2E-03 1.2E-05 2.6E-03 1.OE-05 1.2E 00 1.8E O2 A XE-133M 1.5E-04 2.5E-05 1.8E-04 2.OE-05 1.2E 00 6.OE 00 A XE-135 2.7E-02 5.1E-05 3.6E-02 2.5E-05 1.3E 00 5.3E O2 C FILTER I-131 1.1E-11 2.3E-13 1.OE-11 1.2E-13 9.1E-01 4.8E 01 A I-133 2.7E-11 3.SE-13 2.5E-11 1.8E-13 9.3E-01 7.1E 01 A I-135 1.7E-11 1.2E-12 1.8E-11 4.7E-13 1.1E 00 1.4E 01 A F SPIKED CO-57 1.OE-03 3.1E-05 1.4E-03 3.5E-05 1.4E 00 3.2E 01 A*
LIC CO-60 6.1E-03 1.6E-04 7.1E-03 1.9E-03 1.2E 00 3.8E 01 A*
-
Y-88 7.6E-03 1.8E-04 1.2E-02 2.SE-04 1.6E 00 4.2E 01 A*
CD-109 2.OE-02 6.7E-04 2.9E-02 8.OE-04 1.5E 00 3.OE 01 A*
SN-113 4.4E-03 1.OE-04 6.1E-03 1.3E-04 1.4E 00 4.4E 01 A*
CS-137 7.OE-03 1.6E-04 8.1E-03 1.6E-04 1.2E 00 4.4E 01 A*
CE-139 1.1E-03 3.5E-05 1.7E-03 4.5E-05 1.5E 00 3.1E 01 A+
PRIMARY CR-51 6.3E-03 5.1E-04 7.2E-03 4.1E-04 1.1E 00 1.2E 01 A MN-54 4.5E-03 1.2E-04 4.2E-03 1.1E-04 9.3E-01 3.7E 01 A FE-59 2.6E-03 2.OE-04 2.8E-03 1.9E-04 1.1E 00 1.3E 01 A CO-58 3.7E-03 1.4E-04 3.5E-03 1.1E-04 9.5E-01 2.6E 01 A CO-60 1.6E-02 1.8E-04 *1.3E-02 2.1E-04 8.1E-01 8.9E 01 A
':f >yg '
T TEST RESULTS:
A= AGREEMENT D= DISAGREEMENT o= CRITERIA RELAXED N=NO COMPARISON
_ - _ _ _ _ _ _ . - . . . . . . . ~
'.
.
TABLE 1 U S NUCLEAR REGULATORY COMMISSION a
^
OFFICE'OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS, PROGRAM
-
FACILITY: LACBWR -
FOR THE 4 QUARTER OF 1986
NRC------- ----LICENSEE---- ---LICENSEE:NRC----
SAMPLE _ ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T PRIMARY- W-187 8.5E-03 5.4E-04 7.1E-03 4.2E-04 8.4E-01 1.6E 01 A NP-239 5.4E-03 1.9E-04 4.9E-03 3.7E-04 9.1E-01 2.8E 01 A I-131 2.1E-04 5.4E-05 2.1E-04 4.3E-05 1.OE 00 3.9E 00 A I-133 6.9E-04 1.6E-04 6.2E-04 1.2E-04 9.OE-01 4.3E 00 A ZR-97 4.6E-04 1.2E-04 3.8E-04 1.1E-04 8.3E-01 3.8E 00 A RU-103 8.5E-04 7.OE-05 6.2E-04 5.8E-05 7.3E-01 1.2E 01 A BA-140 2.oE-03 2.OE-04 2.OE-03 2.7E-04 1.OE 00 1.OE 01 A CE-141 3.6E-04 5.1E-05 3.3E-04 3.5E-05 9.2E-01 7.1E 00 A CE-144 3.4E-03 3.3E-04 2.7E-03 2.OE-04 7.9E-01 1.OE 01 A F SPIKED CO-57 2.OE-04 3.SE-05 2.4E-04 1.9E-05 1.2E 00 -5.3E 00 A gge CO-60 1.5E-02 3.6E-04 1.5E-02 2.6E-04 1.OE 00 4.2E 01 A CD-109 3.9E-02 1.3E-03 4.7E-02 1.OE-03 1.2E 00 3.OE 01 A CS-137 1.9E-02 3.5E-04 2.1E-02 2.3E-04 1.1E 00 5.4E 01 A T TEST RESULTS:
A= AGREEMENT D= DISAGREEMENT o= CRITERIA RELAXED
'N=NO COMPARISON-s- ,.
' .;i k
- i Y- s u
.- . . - - - - - _ , - , -
_- . - - -. . -._ . .
', *
_
.
TABLE'2 U S NUCLEAR REGULATORY COMMISSION _g OFFICE OF INSPECTION AND ENFORCEMENT M k?
'
CONFIRMATORY MEASUREMENTS PPOGRAM
- FACILITY: LACBWR '
FOR THE 4 OUARTER OF 1985
NRC ---- -
LICENSEE---- ---LICENSEE:NRC SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T L VASTE BETA 6.6E-05 2.0E-06 6.0E-05 1.1E-06 9.1E-01 3.3E 01 A SR-90 5.3E-07 3. 0E- 09 3.5E-07 0.OE- .6E-01 1.PE 01 D CO-58- 3.?E-06 4.0E-07 2.5E-06 1.7E-07 7.7E-01 8.3E 00 A CO-60 6.4E-05 1.2E-06 7.2E-05 5.4E-07 1.!E 00 5.4E 01 A CS-137 1.4E-05 4.0E-07 1.5E-05 2.4E-07 1.1E 00 3.5E 01 A MN-54- 8.1E-06 3. 0E- 07 9.1E-06 2.4E-07 1.1E 00 2.7E 01 A T TEST RESULTS:
-AsAGREEMENT D= DISAGREEMENT
' NANO COMPARISON
'
.
.
e O
9
$
.-
o
.
.
_
$ ,
2 . 'i(g
' ut ;
e 3 D
_y--3- - - - ,,3-- . r
_ _
-
..
ATTACHMENT 1 CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS This attachment provides criteria for comparing results of capability tests and verification measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this progra In these criteria, the judgment limits are variable in relation to the comparison of the NRC's value to its associated one sigma uncertainty. As that ratio, referred to in this program as " Resolution", increases, the acceptability of a licensee's measurement should be more selective. Conversely, poorer agreement should be considered acceptable as the resolution decreases. The values in the ratio criteria may be rounded to fewer significant figures reported by the NRC Reference Laboratory, unless such rounding will result in a narrowed category of acceptanc RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE VALUE Agreement
, <4 0.4 - .5 - .6 - 1.66 16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25 200 - 0.85 - 1.18 Some discrepancies may result from the use of different equipment, techniques, and for some specific nuclides. These may be factored into the acceptance criteria and identified on the data sheet.
l l
l
_ __--. _ -, . - - .. -- _ . . . .,, .