Letter Sequence RAI |
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MONTHYEARML20150D3781988-07-0707 July 1988 Forwards Request for Addl Info Re Proposed Decommissioning Plan & Amend to Tech Specs Per 871221 & 880222 Applications. Response Requested by 880815 Project stage: RAI 1988-07-07
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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
. July 7, 1988 Docket No. 50-409 Mr. James W. Taylor, General Manager Dairyland Power Cooperative 2615 East Avenue South La Crosse, Wisconsin 54602-0816
Dear Mr. Taylor:
SUBJECT:
LACBWR DECOMMISSIONING PLAN, REQUEST FOR ADDITIONAL I.NFORMATION (TAC-66950)
By application dated December 21, 1987 as revised February 22, 1988 you requested approval of a proposed Decommissioning Plan and proposed an amendment to the Technical Specifications for the La Crosse Boiling Water Reactor.
During our review of your application we determined that wa need additional information as identified in Enclosure 1. Please provide your response by August 15, 1988. The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
If there are any questions concerning these comments please contact me at (301) 492-1126.
Sincerely, Drlginni Signed By: ,
Peter B. Erickson, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
Req = st for Additional Information cc: See next page
.Distributio:
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Docket No. 50-409 Mr. James W. Taylor, General Manager Dairyland Power Cooperative 2615 East Avenue South La Crosse, Wisconsin 54602-0816
Dear Mr. Taylor:
SUBJECT:
1.ACBWR DECOMMISSIONING PLAN, REQUEST FOR ADDITIONAL INFORMATION (TAC-66950)
By application dated December 21, 1987 as revised February 22, 1988 you requested approval of a proposed Decommissioning Plan and proposed an anendment to the Technical Specifications for the La Crosse Boiling Water Reactor.
During our review of your application we determined that we need additional information as identified in Enclosure 1. Please provide your response by August 15, 1988. The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
If there are any questions concerning these comments please contact me at (301) 492-1126.
Sincerely, Peter B. Erickson, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc: See next page
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., l Mr.' James 11. Taylor Docket No. 50-409 l Dairyland Power Cooperative La Crosse Boiling Water Reactor cc:
Fritz Schubert, Esquire Staff Attorney Dairyland Power Cooperative 2615 East Avenue. South La Crosse, Wisconsin 54602 Mr. Kevin P. Gallen Newman & Holtzinger, P. C.
1615 L Street, NW llashington, D.C. 20036 Mr. John Parkyn, Plant Manager la Crosse Boiling Water Reactor Dairyland Power Cooperative P. O. Box 275 Genoa, Wisconsin 54632 U.S. Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1, Box 276 Genoa, Wisconsin 54632 Town Chairman Town of Genoa Route 1 Genoa, Wisconsin 54632 Chairman, Public Servi:e Commission of Wisconsin Hill Farms State Office Building P. O. Box 7854 Madison, Wisconsin 53707 Regional Administrator, Region III U.S. Nucle 6r Regulatory Conmission 799 Roosevelt Road Glen Ellyn, Illinois 60137
ENCLOSURE 1 REQUEST FOR ADDITIONAL INFORitATION FOR PROPOSED DECOMMISSIONING PLAN LA CROSSE BOILING WATER REACTOR DAIRYLAND POWER COOPERATIVE DOCKET NO. 50-409 A. Decommissioning Plan - SAFSTOR
- 1. p. 1-2 In addition to the technical reasons given in this Section 1 section for choosing SAFSTOR, a financial reason, particularly for plants like La Crosse that are being shut down prior to projected end-of-life, is that SAFSTOR period allows additionel time to accumulate decommissioning funds. This reason was implicitly stated in Section 6.7 and should be added to Section 1.1 for completeness.
- 2. p. 2-4 This section describes leakage from the stainless steel Section 2.5.2 liner in the Fuel Element Storage Well (FESW). Describe whether the contaninated FESW water is collected to prevent release offsite without monitoring and possible processing. Provide data on the present FESW 1eakage rates and the maximum concentrations of the radionuclides.
Provide also a safety analysis of the leakage. If FESW 1eakage is released offsite, determine radio-logical consequences to ascertain whether there are any safety implications. Discuss the history of the FESW 1eakage and what has been done and what can be done to repair it. Analyze the potential for an increase in the leakage and potential offsite exposure consequences.
- 3. p. 3-5 Provide a discussion on the effect of Mississippi River Section 3.4.4 flooding during the SAFSTOR period. How will fuel pool
& 3.4.6 cooling be maintained at the various flood levels and what level is all cooling capability lost? What will be the effects from no cooling? If there is a radio-active release to unrestricted areas through surface or r ground water, provide the source term, unless you can demonstrate that the low probability or risk negates l
! the need for evaluation.
l 4. p. 3-7 This section should also address the effects of high Section 3.4.7 water (Loss of pumps) on the ultimate heat sink.
See question 3 above.
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'- 5. p. 3-7 Provide a discussion of the surficial aquifier(s)
Section 3.4.8 including potable water supply wells near the site and the potential for radioactive contamination from an accidental spill at the site. Previde the surficial aquifer parameters (permeability, specific yield and groundwater contour map) necessary to evaluate the arc'n %ater travel times in the surficial aquifer.
- 6. p. 5-3 icomissioning Plan states that the "control rods Section 5.2.1 may De removed to the FESW or a licensed facility during SAFSTOR." Is the "licensed facility" a licensed disposal facility?
- 7. p. 5-13 The FESW currently contains 10 control rods in Section 5.2-11 addition to 333 irradiated fuel elements. Provide justification why the 29 control rods in the reactor vessel are not transferred to the FESW as part of SAFSTOR program.
- 8. p. 5-56 Discuss your plan for the disposition of sources of Section 5.6 radioactivity associated with this decomissioning operation.
- 9. pp. 6-1 and The Decomissioning Plan objectives include some 7-3. Sectior.s decontamination and dismantlement. These operations 6.1 and 7.3.2 should be addressed to discuss the specific systems and components, proposed decontamination methods, and expected waste generation. Expected quantities of wastes containing chelating agents and mixed wastes should be included.
- 10. p. 6-11 The statement is made in Section 6.7 that "A later Section 6.7 dismantling date will allow additional funds to accumulate to compensate for the cost of inflation."
This is generally true but it presupposes that the inflation rate for decamissioning cost will be less than annual rate of interest earnings on the decom-mission fund. In support of this and similar statements such as on page 6-13, the licensee should provide the assumptions of and bases for inflation and interest rates used in the Deccmmissioning Plan.
! 11. p. 6-12 The listing of SAFSTOR costs is confusing and perhaps too Section 6.7.1 cryptic. NUREG/CR-0672 "Technology, Safety and Costs of Decomnissioning a Reference Boiling Water Reactor Power Station" indicates that for a large commercial BWR, preparation for safe storage would cost approx-l inately $21.3 million in 1978 dollars with continuing care during the SAFSTOR period costing $75,000 per year.
NUREG/CR-0672, Addendum 3, which will update the 1978 l
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costs to 1986 dollars will be avail'able in early July 1988. Allowing for La Crosse's small size, the preparation-for-safe-storage costs appear low although not unreasonable. Given that spent fuel will be stored on-site during the SAFSTOR period, it would be expected that annual costs during the SAFSTOR period would be considerably higher than indicated in NUREG/CR-0672. With information provided in the plan however, there is no way to determine how reasonable the annual cost figures are. It would be helpful to have a more detailed breakdown of costs, particularly of oase year costs, as well as explicitly sr ting the
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escalation factor for the annual costs.
- 12. p. 6-13 In the paragraph addressing the 5 year updates of Section 6.7.2 decommissioning cost estimates, it would be appropriate to have a statement to the effect that the Board of Governors of Dairyland Power Cooperative agrees to increase Dairyland's decomistioning fund contribution by the amount indicated by the cost study update.
- 13. p. 7-3 Paragraph 7.3.2 discusses removal of unused equipment Section 7.3.2 during SAFSTOR after surveying and documenting that the equipment contains no detectable radioactive material (less than Lower Level of Detection, (LLD)). Since the LLD depends upon the surveying instrument used and the surveying method, the instruments and methods should be described.
- 14. p. 7-5 Indicate the range of the nobel gas detectors in the Section 7.4.3 stack effluent and the gamma monitors in the liquid waste line.
- 15. p. 8-2 Provide resumes of the principal decomissioning and Section 8.2.2 decontamination staff.
- 16. p. 8-4 In accordance with Section 12.5, NUREG-0800, confirm Section 8.3.1 that your health physics procedures for performing bioassay during the SAFSTOR period will conform to the recomendations of Regulatory Guide 8.26, "Application of Bioassay for Fission and Activation Products", or submit equivalent bioassay criteria.
- 17. p. 8-9 An estimate of the solid waste to be generated during Section 8.6 the SAFSTOR period should be provided so that we can assess the waste management impacts. This estimate should include breakdowns by waste stream (dry active waste, cartridge filters, filter sludge, bead resins, powered resins, activated metals, specific decontamination solutions, etc.) and waste class (A,B,C and Greater-Than-Class-C). The projected volumes and activities by nuclide should be provided for each waste stream and
. i 4 j waste class. These SAFSTOR projection: :hould be compared with operating mode waste generation data.
Any changes to the process control program, waste classification program, the qus11ty control program required under 10 CFR 20.311 and the transportation packaging program to reflect new waste streams or SAFSTOR modifications should be identified and infor-mation provided for our review.
- 18. Are you contemplating spent fuel pin consolidation onsite prior to shipment to the Federal High Level Waste Repository? If so, provide estimates of the expected occupational radiation exposures involved, of the volume of low level waste generated, and of the contribution of this activity to gaseous and liquid radioactivity releases to the environment.
- 19. Describe .* . rem a nt and monitoring to be provid.i
' for effl, ' from the refueling building ventilation exhaust, 11guid waste storage tankage vent exhaust, tot machine shoa vent exhaust, radwaste treatment building ventil'ation exhaust, the high-level solid radioactive waste storage vaults, the low-level waste storage building, the low-level waste handling building, and any other pathway for the release of radioactive materials.
- 20. In reference to onsite storage of combustible fuel, identify the fuel, its location, method of storage, method of resupply, and the maximum quantity stored at any time.
B. Technical Specifications I
! 21 p. 1-1 A local area map defining the unrestricted areas used I Section 1.1 for offsite dose calculations for gaseous and liquid l~ effluents should be included in TS.
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In addition, a site map clearly defining the restricted i area pursuant to 10 CFR 20.3(a)(14) should be included.
I l 22. p. 1-1 What' activities, such as decontamination and/or removal i Section 1.2 of structures, systems and components are permitted by
' the description titled "Principal Activities"? Reference to Regulatory Guide (R.G.) 1.86 may be used.
23, p 2-2 under Effluent Release Boundary definition, reference i
Section 2 is made to Figure 4/5.7. On p. 4-62 Figure 1 is the site map including effluent release i,oundary. Since thcre is no Figure 4/5.7, should Figure 1 be renumbered Figure 4/5.77
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- 24. p. 4-1 A cover can be installed over the FESW to preclude Section 4.1.1 droppage of objects into the pool and to provide a contamination control barrier. Does LACBWR presently have a cover or is one planned to be installed for SAFSTOR? This cover should be described in SAFSTOR
" Decomissioning Plan, if applicable.
?5. p. 4-1 The depth of water shielding over a fuel assembly Section while it is being transferred to a spent fuel rack is 4.1.1.2 less than 10 feet, and the dose rate 3 feet above the FESW water may be greater than 5 mR/hr above ambient radiation levels. Please submit a proposed Technical Specification which states the minimum depth of water shielding over the fuel assembly as it is being transferred, and the measures that will be taken to assure that this minimum depth will not be degraded.
- 26. p. 4-3. An action statement to require use of the cleanup Section 4.1.3 system above the limiting value should be provided.
If the activity cannot be reduced to less than the limit prior to the next required sample, a 30 day report to NRC should be made. If the peak activity for :ny measurement exceeds a value indicative of 10%
cladding degradation under static conditions an imediate report to NRC should be required.
- 27. p. 4-5. Section 4/5.1 indicates that the spent fuel storage Section 4/5.1 racks contain a baron poison slab between each storage location to ensure X eff 0.95. A description of these spent fuel storage racks with the poison slabs should appear to be in the SAFSTOR Decommissioning Plan.
- 28. p. 4-5 A specific minimum water coverage limit should be stated in the TS.
l- Section 4/5.'
- 29. p. 4-36 Revise this section to show the design features of the Section 4/5.6 monitoring system for the SAFSTOR decommissioning.
Include the offsite and onsite environmental nonitoring stations.
! 30. p. 4-38 Reporting requirements should be added for sources Section 4.6.3 that exceed the removable contamination limit. The following is suggested: "A report shall be prepared and submitted to the Regional Administrator, U.S.
Nuclear Regulatory Commission, Region III within 30 days of the date the leak test result (greater than 0.005 microcuries) is known. The report shall specify the source involved, the test results, and corrective action taken. Records of leak test results shall be kept in Units of microcuries."
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- 31. p. 4-56 Offsite dosimeters should have their location documented Table 4.8.1-1 on a map as part of the TS.
Offsite water sanpling should be specified (location and radionuclide). The sampling should be in a down-stream location with respect to surface water and groundwater.
Onsite sampling should be described as to radionuclides sampled and the location.
- 32. p. 6-3 The "Certified Fuel Handler" training program should be Section 6.4 reviewed and approved by the NRC. The TS should only require that to be certified, a worker successfully complete the program.
- 33. p. 6-3 TS should include training on 10 CFR Parts 19, 20, Section 6.4 61 and 71 as a minimum. A retaining frequency should be specified.
- 34. p. 6-3 The proposed composition includes all LACBWR Departnent Section 6.5.1 Supervisors, Engineers, Shift Supervisors and management personnel. We consider the membership should be fixed and considered in conjunction with the quorum requirements st.ch that the quorum is a majority of the committee trembers.
- 35. p. 6-4 We suggest expanding the Operations Review Committee Section responsibilities to include review of the waste 6.5.1.6 managenent quality control program required under 10 CFR Part 20.311, and the transportation packaging program.
- 36. p. 6-5 We suggest adding waste management as a review function Section of the Safety Review Committee.
6.5.2.1 l 37. p. 6-6 The mer ership of the SRC includes the position of Section Direct , of External Relations. Since this position 6.5.2.2 does .ut show on the Decommissioning Plan, we cannot conclude how that position contributes to the described functions of the SRC. Please provide the l
basis for including the individual filling this l position on the SRC.
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- 38. p. 6-7 The licensee has reduced the frequency of all audits Section required by Section 6.5.2.8 except for Quality 6.5.7.8 Assurance, the Fire Protection Program, and Off-site Dose Calculation Manual and the Process Control Program.
Please provide a basic for lengthening the period between audits.
- 39. p. 6-8 The Procedure list should include calibration of Section 6.6.1 instruments, effluent releases, transportation and emergency plan implementing procedures.
C. Supplement to Environmental Report
- 40. p. 4 Provide an estimate of the number of enployees required Section 5.2 for the SAFSTOR decomissioning time period. Provide a breakdown of the employees required by permanent and contractor workers. If this number is not expected to be relatively stable, give estimate of changes anticipated.
- 41. p. 8 In Section 7.2, you describe the LACBWR radwaste Section 7.2 system.
(a) Since LACBWR circulating water will not be avail-able for liquid radwaste dilution prior to discharge, state how you intend to provide adequate dilution of low level liquid radwaste to meet the maximum permissible concentration levels of 10 CFR Part 20 prior to discharge into the Mississippi River.
(b) State how you intend to process liquid radwaste generated from the operation of backwashable filters. These wet wastes (filter sludges) are not described in Section 8 of the Decomissioning Plan as a type of wet waste to be solified or dewatered.
(c) You identify decentamination liquids as pctential scurces of liquid wastes to be processed during SAFSTOR period. Describe the type and expected t
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major chemical composition and process method to be used.
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- 42. p. 14 You stated that after LACBWR was permanently shut down Section 7.3 in April, 1986, marked changes in the magnitude and composition of radioactive gaseous effluents were observed.
(a) Describe composition and quantities of radioactive gaseous effluent expected during the SAFSTOR period of decommissioning.
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e (b) Describe your plan to recalibrate LACBWR process and effluent radiation monitors in accordance with the energy levels of the radionuclides expected in liquid and gaseous effluents during the SAFSTOR period.
- 43. p. 17 The stated volumes and activities appear to be low Section 7.4 considering the statements in the Decommissioning Plan that some decontamination and dismantlement may take place during the SAFSTOR period. In addition, the Decoraissioning Plan also states that some activated metals may be shipped for disposal. If so, the activities in Table 7-9 may be substantially understated.
The bases for the values presented in Table 7-9 should also be discussed.
- 44. p. 17 _
Section 7.4 describes solid radwaste processing and Section 7.4 shipments.
(a) Provide the LACBUR Process Control Program to be used during the SAFSTOR period including (1) waste classification methods in accordance with 10 CFR 61.55 and (2) waste characteristics in accordance with 10 CFR 61.56.
(b) Describe the projected low level radioactive waste shipments from LACDWR during SAFSTOR in terms of type of waste (solidified or dewatered spent resin, dry radioactive waste, solidified filter sludges, solidified decontamination waste, etc.) and its radioactivity content.
- 45. p. 25 Evaluate potential accidental release of the FESW Section 9.1 cooling water and of liquids from the nost critical radioactive waste storage tank to the groundwater and surface water.