ML20196H353
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Other: 0CAN048804, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant, 3F0288-18, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-420, A07039, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage, BECO-88-050, Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-001, ML20147F998, ML20147G854, ML20148A890, ML20148B666, ML20148K225, ML20148Q724, ML20149M198, ML20150A899, ML20150B182, ML20150B526, ML20150C407, ML20150D397, ML20151A945, ML20151B202, ML20151E018, ML20151E419, ML20151E868, ML20151G115, ML20151G791, ML20151H779, ML20151H965, ML20151Q920, ML20154D233, ML20154E154, ML20155A456, ML20155E392, ML20196H353, ML20205P688, ML20235J165, ML20235J168, ML20236A614, ML20236A849, ML20236D105, ML20236F547, ML20236S018, ML20247K075, NRC-88-0072, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers, RBG-27645, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant, W3P88-0051, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin | |
MONTHYEARML20235S2971987-10-0202 October 1987
[Table View]Summary of 870923 Meeting W/Westinghouse Re Technical Basis for Westinghouse Recommended Actions,Criteria & Conclusions in to Utils That Use Models DS-416,DSL-416, DS-420,DS-206 & DSL-206 Switchgear in Class 1E Svc Project stage: Meeting ML20236A6141987-10-16016 October 1987 Advises That Util Insp of Reactor Trip Breakers Revealed Catawba Pole Shaft Which Had Welds W/Indications of Cracking.Forwards Informal Technical Communication from Franklin Research Ctr Re Initial Observation Project stage: Other ML20236A8491987-10-16016 October 1987 Forwards I.6177-5-1, Interim Rept on McGuire Reactor Trip Breaker 2B Failure Evaluation & Rcommended Corrective Actions from Westingtonhouse. Rept Explains Mechanical Binding Which Kept Breaker from Opening on 870702 Project stage: Other ML20236D1051987-10-21021 October 1987 Provides Record of 871020 Telcon Between D Hood,D Sellers & V Hodge of NRC & J Mcvicker & Cowne of Bg&E Re Unit 1 480 Volt Circuit Breaker W/Broken Weldment Connecting Ctr Pole Lever to Pole Shaft.Util Exam Results in 860918 Memo Project stage: Other ML20236F5471987-10-23023 October 1987 Documents 871020 Telcon W/Util Re Unit 2 Circuit Breaker Pole Shaft Weld Failure Project stage: Other ML20236F9651987-10-27027 October 1987 Notification of 871103 Meeting W/Util & Westinghouse in Philadelphia,Pa to Discuss Results of Franklin Research Ctr Exam of Cracks in Pole Shaft Welds of Reactor Trip Breaker Project stage: Meeting ML20236S0181987-11-18018 November 1987 Summarizes 871020 Telcon Between NRC & Util Re Two Broken Fillet Welds on Pole Shaft Assembly of Circuit Breaker That Energizes Emergency Fire Protection Pumps for Facility. Photographs Attached to 870710 Memo to NRC Encl Project stage: Other ML20149M1981988-02-16016 February 1988 Advises That Since Util No Longer Operating Reactor Licensee Due to 870430 Shutdown & 870804 Amend,Modifying License DPR-45 to Possess But Not Operate Status,Generic Ltr 88-01 Determined Inapplicable to Facility Project stage: Other 3F0288-18, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-4201988-02-23023 February 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-420 Project stage: Other ML20196H3531988-02-25025 February 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Ds Series Circuit Breakers Installed at Facility Project stage: Other ML20147G8541988-03-0101 March 1988 Responds to NRC Bulletin 88-001 Re Westinghouse Ds Series Circuit Breakers Used in safety-related Applications.Plant Does Not Have Any Westinghouse Ds Series Circuit Breakers Project stage: Other ML20147F9981988-03-0404 March 1988 Submits Response to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Author Does Not Utilize Any Westinghouse Circuit Breakers,As Identified in Subj Bulletin,In Class 1E Applications at Facility Project stage: Other ML20150B1821988-03-0707 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breakers in Class 1E Applications So Bulletin 88-001 Does Not Apply to Plant Project stage: Other ML20148A8901988-03-0707 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Unit 1 Has No Westinghouse Ds Circuit Breakers Used in Class 1E Application.Unit 2 Reactor Trip & Bypass Breakers Insp Initiated Per Info Notice 87-035 Project stage: Other ML20150A8991988-03-0909 March 1988 Provides Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Determined That Westinghouse Series Ds Circuit Breakers Not Employed at Plant.Insp Required by Bulletin Not Applicable to Plant Project stage: Other ML20150C4071988-03-11011 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Determined That Westinghouse Type Ds Circuit Breakers Not Used at Plant Project stage: Other BECO-88-050, Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-0011988-03-15015 March 1988 Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-001 Project stage: Other ML20148B6661988-03-16016 March 1988 Responds to 880205 NRC Compliance Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Westinghouse Ds Series Circuit Breakers Not Used in Class IE Svc at Plant Project stage: Other NRC-88-0072, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers1988-03-24024 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers Project stage: Other ML20148K2251988-03-25025 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Two Reactor Trip Breakers & Two Reactor Trip Bypass Breakers Subj to Bulletin Used at Millstone Unit 3.Main Pole Shaft Weld Insps Completed by 880225 Project stage: Other ML20151G7911988-03-28028 March 1988 Confirms That Westinghouse Ds Breakers Not Used at Facility, Per IE Bulletin 88-001, Defects in Westinghouse Circuit Breakers Project stage: Other W3P88-0051, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin1988-03-29029 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin Project stage: Other ML20151A9451988-03-30030 March 1988 Responds to IE Bulletin 88-001 Re Westinghouse Ds/Dsl Circuit Breakers.Ref Components Not Utilized at Facility Project stage: Other 0CAN048804, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant1988-04-0101 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant Project stage: Other ML20151B2021988-04-0404 April 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Insp of All Westinghouse DS-415 Reactor Trip & Bypass Breakers Completed on 880308 & Results Encl Project stage: Other RBG-27645, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant1988-04-0404 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant Project stage: Other ML20148Q7241988-04-0707 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Models DS-206,DSL-206, DS-416,DSL-416 or DS-420 Breakers in Class 1E Circuits at Hatch Project stage: Other ML20151H7791988-04-0707 April 1988 Informs That Westinghouse Ds Circuit Breakers Not Utilized in Any 1E Application at Plant But Used in non-1E Applications & Will Be Included in Util Preventive Maint Program Project stage: Other ML20151E4191988-04-0808 April 1988 Responds to 880205 NRC Bulletin 88-01 Re Defects in Westinghouse Circuit Breakers for Facilities.Westinghouse Ds Series Circuit Breakers Not Used at Plants.Other Provisions of Bulletin Do Not Apply to Plants Project stage: Other ML20151E8681988-04-11011 April 1988 Forwards Response to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers in Class 1E Svc.All Required long-term & short-term Insps Completed Project stage: Other ML20151H9651988-04-13013 April 1988 Responds to NRC Bulletin 88-001, Deficiencies in Westinghouse Circuit Breakers. Bulletin Addresses Deficiencies Exclusive to Westinghouse Ds/Dsl Type Circuit Breakers & Outlines Specific Insps to Be Performed Project stage: Other ML20151G1151988-04-13013 April 1988 Ack Receipt of in Response to NRC Bulletin 88-001 Re Westinghouse Circuit Breakers.Plant Does Not Use or Plan Use of Circuit Breakers,Therefore Matter Closed Project stage: Other ML20205P6881988-04-20020 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Circuit Breakers Subj to Bulletin Installed in Plant Project stage: Other ML20155E3921988-06-0909 June 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit breakers.Sixty-six of sixty-seven Breakers Required New Pole Shafts Due to Failure of Welds to Meet Bulletin Requirements Resulting from Insp Project stage: Other ML20150B5261988-06-30030 June 1988 Informs That All Class 1E DS-416 Breakers Now in Use Comply W/Nrc Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers Project stage: Other ML20150D3971988-07-0505 July 1988 Advises That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20151E0181988-07-14014 July 1988 Advises That Util 880407 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20151Q9201988-08-0202 August 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20154D2331988-09-0909 September 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory & No Further Reply Necessary Project stage: Other ML20154E1541988-09-0909 September 1988 Advises That 880408 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20155A4561988-09-29029 September 1988 Requests Addl Info Re Util 880908 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Response Requested within 70 Days of Ltr Date Project stage: Other ML20235J1681989-02-17017 February 1989 Advises That 880314 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers Satisfactory. Westinghouse Ds Series Circuit Breakers Not Used in safety-related Applications at Plant Project stage: Other ML20235J1651989-02-17017 February 1989 Provides Final Response to NRC Bulletin 88-001, Defects in Westinhouse Circuit Breakers. Alignment Check Specified in 871201 Submittal Satisfactorily Performed During Installation of Replacement Pole Shaft in Breakers Project stage: Other ML20247C7191989-05-15015 May 1989 Forwards Supplemental Response to NRC Bulletin 88-001 Re Westinghouse Series Ds Circuit Breakers.Insp Info Corrected Project stage: Supplement ML20247K0751989-05-24024 May 1989 Responds to NRC Bulletin 88-001 Re Defects of Westinghouse Circuit Breakers.All forty-seven Westinghouse Type Ds Breakers Inspected Were Found to Have Acceptable Breaker Mechanism Alignment Project stage: Other A07039, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage1989-07-24024 July 1989 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage Project stage: Other 1988-03-07 |
| ML20196H353 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/25/1988 |
| From: | Taylor J DAIRYLAND POWER COOPERATIVE |
| To: | Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-88-001, IEB-88-1, LAC-12506, TAC-65955, TAC-65956, NUDOCS 8803100202 | |
| Download: ML20196H353 (2) | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K9401999-10-0606 October 1999
[Table view]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. 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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 Category:INCOMING CORRESPONDENCE MONTHYEARML20217K9401999-10-0606 October 1999
[Table view]Submits Safeguards Event Log for Calendar Quarter Ending 990930,IAW 10CFR73.71.No Safeguards Events Occurred ML20210F3651999-07-0909 July 1999 Submits Safeguards Event Log for Calendar Quarter Ending 990630,IAW 10CFR73.71 & LACBWR Security Plan 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 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 ML20196A8921998-11-23023 November 1998 Forwards Rev 12 to LACBWR QA Program Description 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 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 ML20237E2631998-07-15015 July 1998 Forwards Rev 12 to QA Program Description. Page Change Locations Indicated by Bold Bar in right-hand Margin 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 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 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 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 ML20138A6431997-04-15015 April 1997 Forwards Rev 11 to LACBWR QA Program 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 ML20058P1281993-12-0909 December 1993 Forwards Changes to Physical Security Plan,Contingency Plan & Guard Force Training & Qualification Plan.Encls Withheld (Ref 10CFR2.790(d)) ML20059G6131993-11-0101 November 1993 Responds to Re Violations Noted in Insp Rept 50-409/93-01 on 930903 & 22 & 24.Corrective Actions: Reassigned Mechanics & Instrument Technician to LACBWR Staff ML20056E2601993-08-12012 August 1993 Forwards Nonproprietary & Proprietary Version of Analysis of Potential Blast Effects on LACBWR Reactor Bldg Due to 16 Inch Natural Gas Pipeline Failure,Suppl Analysis for Fast Closing Valve. Proprietary Version Withheld ML20056E2681993-05-11011 May 1993 Requests That Proprietary Analysis of Potential Blast Effects on LACBWR Reactor Bldg Due to 16 Inch Natural Gas Pipeline Failure,Suppl Analysis for Fast Closing Valve Be Withheld,Per 10CFR2.790(b)(4) ML20128P4611993-02-11011 February 1993 Forwards Rev to Annual Decommissioning Plan,Changing Requirement to Maintain Hourly Meteorological Data Logging for Effluent Release Calculations & Removing Makeup Demineralizer Sys ML20128K5891993-02-0909 February 1993 Forwards Corrected App a to Annual Rept for 1992 - Rept of Changes,Tests & Experiments ML20055H6371990-07-25025 July 1990 Forwards Decommissioning Fund Rept for Plant ML18041A2111989-11-16016 November 1989 Responds to Generic Ltr 89-19 Re Request for Action Re Resolution of USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants. Actions or Recommendations in Generic Ltr Will Not Be Performed ML20248C5941989-09-21021 September 1989 Forwards Revised Radioactive Effluent Rept for LACBWR (Jan- June 1989), Incorporating Sr-89/90 & Fe-55 Analysis Data ML20247A1931989-08-22022 August 1989 Forwards Proposed Operator Licensing Exam Schedule Format for FY90 - FY93,in Response to Generic Ltr 89-12 ML20245G0911989-07-27027 July 1989 Advises That Util Already Exempt from 10CFR26, Fitness-for- Duty Program Because of Safstor Status.Request for Exemption Will Not Be Necessary Since License Amended to possession-only License Via Amend 63 ML20246K8411989-07-10010 July 1989 Responds to Generic Ltr 89-06, Task Action Plan Item I.D.2, Spds. All Spent Fuel Transferred from Reactor to Spent Fuel Storage Well & on 870804,License DPR-45 Amended to possess- but-do-not-operate Status ML20246B8371989-06-27027 June 1989 Forwards Endorsements 71,72,73,74,75 & 76 to Nelia Policy NF-217 ML20245A1231989-06-0606 June 1989 Submits Whole Body Dose Estimates & Request for Changes to Tech Specs 6.8.3.1 & 6.8.4 ML20248C2861989-06-0101 June 1989 Responds to Generic Ltr 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning. Generic Ltr Does Not Apply to Plant Since No Sys Operate as High Energy Sys ML20247B3121989-05-0808 May 1989 Responds to NRC Re Conduct of Backfit Process, Informing NRC of Plant Permanent Shutdown in Apr 1987 ML20248F1421989-04-0707 April 1989 Forwards Annual Financial Rept & Certified Financial Statements for 1987 & 1988.W/o Annual Financial Rept ML20246N8041989-03-17017 March 1989 Submits Info Re on-site Property Damage Insurance for License DPR-45 for Period 880919 - 890919 ML20204G9191988-10-13013 October 1988 Requests Immediate Relief from Several Sampling & Analysis Requirements of Radiological Environ Monitoring Program to Check for Prescence of I-131.Tech Spec Changes Encl ML20155A3101988-09-30030 September 1988 Responds to NRC 880707 Request for Addl Info Re Decommissioning Plan.Info Includes Flooding Potential & Protection Requirements,Flood Conditions & Effects of High Water Level on Structures ML20154L3511988-09-0909 September 1988 Forwards Answers to Request for Addl Info Re Decommissioning Plan & Safe Storage Tech Specs.Some Answers Suggest Changes to Either Tech Specs or Decommissioning Plan ML20154J3411988-09-0808 September 1988 Forwards Revs to Security,Training & Qualification & Contingency Plans.Revs Withheld (Ref 10CFR2.790(d)) ML20154E4671988-08-30030 August 1988 Responds to Generic Ltr 88-13, Operator Licensing Exams. NRC Will Require Qualified Individuals to Be in Charge of Control Room & Fuel Handling Operations ML20207D1801988-08-0303 August 1988 Advises That Generic Ltr 88-11 Re Radiation Embrittlement of Reactor Vessel Matls Inapplicable to Facility.Reactor Vessel Will Not Be Subj to Pressurization in Plant Safstor Condition 1999-07-09 Category:UTILITY TO NRC MONTHYEARML20055H6371990-07-25025 July 1990
[Table view]Forwards Decommissioning Fund Rept for Plant ML18041A2111989-11-16016 November 1989 Responds to Generic Ltr 89-19 Re Request for Action Re Resolution of USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants. Actions or Recommendations in Generic Ltr Will Not Be Performed ML20248C5941989-09-21021 September 1989 Forwards Revised Radioactive Effluent Rept for LACBWR (Jan- June 1989), Incorporating Sr-89/90 & Fe-55 Analysis Data ML20247A1931989-08-22022 August 1989 Forwards Proposed Operator Licensing Exam Schedule Format for FY90 - FY93,in Response to Generic Ltr 89-12 ML20245G0911989-07-27027 July 1989 Advises That Util Already Exempt from 10CFR26, Fitness-for- Duty Program Because of Safstor Status.Request for Exemption Will Not Be Necessary Since License Amended to possession-only License Via Amend 63 ML20246K8411989-07-10010 July 1989 Responds to Generic Ltr 89-06, Task Action Plan Item I.D.2, Spds. All Spent Fuel Transferred from Reactor to Spent Fuel Storage Well & on 870804,License DPR-45 Amended to possess- but-do-not-operate Status ML20246B8371989-06-27027 June 1989 Forwards Endorsements 71,72,73,74,75 & 76 to Nelia Policy NF-217 ML20245A1231989-06-0606 June 1989 Submits Whole Body Dose Estimates & Request for Changes to Tech Specs 6.8.3.1 & 6.8.4 ML20248C2861989-06-0101 June 1989 Responds to Generic Ltr 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning. Generic Ltr Does Not Apply to Plant Since No Sys Operate as High Energy Sys ML20247B3121989-05-0808 May 1989 Responds to NRC Re Conduct of Backfit Process, Informing NRC of Plant Permanent Shutdown in Apr 1987 ML20248F1421989-04-0707 April 1989 Forwards Annual Financial Rept & Certified Financial Statements for 1987 & 1988.W/o Annual Financial Rept ML20246N8041989-03-17017 March 1989 Submits Info Re on-site Property Damage Insurance for License DPR-45 for Period 880919 - 890919 ML20204G9191988-10-13013 October 1988 Requests Immediate Relief from Several Sampling & Analysis Requirements of Radiological Environ Monitoring Program to Check for Prescence of I-131.Tech Spec Changes Encl ML20155A3101988-09-30030 September 1988 Responds to NRC 880707 Request for Addl Info Re Decommissioning Plan.Info Includes Flooding Potential & Protection Requirements,Flood Conditions & Effects of High Water Level on Structures ML20154L3511988-09-0909 September 1988 Forwards Answers to Request for Addl Info Re Decommissioning Plan & Safe Storage Tech Specs.Some Answers Suggest Changes to Either Tech Specs or Decommissioning Plan ML20154J3411988-09-0808 September 1988 Forwards Revs to Security,Training & Qualification & Contingency Plans.Revs Withheld (Ref 10CFR2.790(d)) ML20154E4671988-08-30030 August 1988 Responds to Generic Ltr 88-13, Operator Licensing Exams. NRC Will Require Qualified Individuals to Be in Charge of Control Room & Fuel Handling Operations ML20207D1801988-08-0303 August 1988 Advises That Generic Ltr 88-11 Re Radiation Embrittlement of Reactor Vessel Matls Inapplicable to Facility.Reactor Vessel Will Not Be Subj to Pressurization in Plant Safstor Condition ML20151Q5001988-07-29029 July 1988 Responds to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs ML20151E8791988-07-18018 July 1988 Requests Revised Submittal of Deadline of 881001 to Facilitate Review of Questions Re Decommissioning Plan. Partial Submittal Will Be Made as Soon as Possible ML20151D4161988-07-15015 July 1988 Responds to NRC Bulletin 87-002,Suppls 1 & 2, Fastener Testing to Determine Conformance W/Applicable Matl Specs. Fastener Purchases Will Be Monitored Through Procurement Control & Receipt Insp Processes ML20196J2371988-06-22022 June 1988 Responds to NRC Re Violations Noted in Insp Rept 50-409/88-06.Semiannual Whole Body Counts Required by Procedure But Not by Regulation ML20196J1391988-06-22022 June 1988 Responds to NRC Bulletin 88-005 & Suppl 1 to Bulletin Re Nonconforming Matls Supplied by Piping Suppliers,Inc.Review of Procurement Documents Indicated That No Procurement Made W/Piping Suppliers,Inc ML20155E3431988-06-0606 June 1988 Responds to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Demineralized Water Transfer Sys Has Potential for dead-heading of One Pump,But Sys Not safety-related.No Actions Planned in Response to Bulletin ML20154J3291988-05-18018 May 1988 Forwards Change to Rev 10 to Emergency Plan Section 3.8.1, Radiological Protection of Onsite Personnel, Per 880511 Request.Change Describes Conditions for Precautionary Onsite Sheltering & Control Room Ventilation Isolation ML20154F9581988-05-16016 May 1988 Responds to NRC Bulletin 85-003,Suppl 1, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. No Addl safety-related motor- Operated Valves Found ML20154D5871988-05-10010 May 1988 Submits Info Re Level & Sources of Onsite Property Damage Insurance,Per 10CFR50.54(w).Effective Dates of Primary Coverage Are 870919-880919 ML20154P7371988-04-29029 April 1988 Responds to NRC Re Violations Noted in Insp Rept 50-409/88-03.Corrective Actions:Operations Review Committee Meeting Convened to Discuss Implications of Event.Individual Counseled Re Attention to Duty ML20151U0351988-04-28028 April 1988 Forwards Rev 2 to Plant Physical Security,Guard Force Training & Safeguards Contingency Plans.Encls Withheld (Ref 10CFR2.790(d)) ML20151M7871988-04-18018 April 1988 Forwards Annual Financial Rept & Cetified Financial Statements for 1986 & 1987.Annual Rept for 1987 Will Be Forwarded as Soon as Possible ML20151M8251988-04-15015 April 1988 Responds to 880128 & 0219 Requests for Addl Info Re Plant Emergency Plan & Forwards Rev 10 to Plan.Map of LACBWR Site Defining Emergency Planning Zone Will Be Added to Emergency Plan as Figure A-2 on Page A-15 ML20151B2131988-03-28028 March 1988 Forwards Revised Rev 5 to QA Program Description for possession-only Condition.Revised Pages Reflect Recent Organizational Change ML20148H0511988-03-28028 March 1988 Forwards Revs to Amended Security,Guard Force Training & Qualification & Safeguards Contingency Plans Submitted on 870924.Encls Withheld (Ref 10CFR2.790) ML20196H3531988-02-25025 February 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Ds Series Circuit Breakers Installed at Facility ML20149N0351988-02-22022 February 1988 Forwards Revised Pages to 870930 Application for Amend to License DPR-45 ML20149J1261988-02-16016 February 1988 Responds to Generic Ltr 88-02 Re Isap Ii.Participation in Program Would Not Further Interests of Util,Since Facility Permanently Shut Down on 870430 & Defueling Completed on 870611 ML20234C3601987-12-21021 December 1987 Forwards Rev 5 to Facility QA Program Description.Analyses Show That No Postulated Accident Would Result in Release Exceeding 10CFR100 Limits,In Present Plant Condition ML20147A8031987-12-21021 December 1987 Forwards Decommissioning Plan & Suppl to Environ Rept for Facility post-operating License Stage,For Review.Proposed Tech Specs for Safstor Period Will Be Submitted Separately. Fee Paid ML20236X8671987-11-30030 November 1987 Forwards 870929 Application Fee for Review of Emergency Plan Rev,In Response to from Diggs to Taylor ML20236M4541987-11-0505 November 1987 Discusses Review of Surveillance Testing Performed Due to 870430 Plant Shutdown.Performance of Listed Tests No Longer Required by Tech Specs Terminated ML20236J8301987-10-30030 October 1987 Confirms That Util Not Required to Pay Annual Fee for Power Reactor OLs or Seek Renewal of Exemption Reducing Amount of Such Fee,Per Issuance of Amend 56 to License DPR-45 on 870804 ML20236J4471987-10-30030 October 1987 Forwards Application Fee for Amend to License DPR-45, Inadvertently Omitted from ML20235X0991987-10-12012 October 1987 Forwards Payment in Amount of $25,000 in Response to 870224 Notice of Violation & Proposed Imposition of Civil Penalty ML20235R1541987-10-0101 October 1987 Provides Supplemental Info Re Requesting Exemption from Requirements to Conduct Annual Emergency Preparedness Exercise.Util Plans to Conduct Exercise within 180 Days After NRC Approval of 870930 Rev ML20235R0161987-09-29029 September 1987 Forwards Emergency Plan Rev,Reflecting Current Status of LACBWR Facility for NRC Approval.Technical Rept,Justifing Proposed Emergency Planning Zone Boundary,Encl ML20235S3321987-09-29029 September 1987 Informs That La Crosse BWR Permanently Shutdown on 870430. Reactor Defuelling Completed on 870611.Listed Active Licensing Actions No Longer Necessary ML20235H4791987-09-24024 September 1987 Forwards Changes to Physical Security,Security Guard Force Training & Qualification & Safeguards Contingency Plans.Fee Paid.Changes Withheld (Ref 10CFR73.21) ML20234E3641987-09-0909 September 1987 Submits Response to IE Bulletin 87-001, Thinning of Pipe Walls in Nuclear Power Plants, Dtd 870709.Formal Insp Program Not Necessary for Continued Safe Fuel Storage at Facility Due to Permanent Termination of Plant Operations ML20238C5201987-09-0202 September 1987 Forwards Endorsements 68 & 69 to Nelia Policy NF-217 ML20238F7371987-09-0101 September 1987 Requests Exemption from 10CFR50,App E Requirement to Conduct Annual Emergency Preparedness Exercise & Requirements to Prepare & Distribute Info Brochure to Residents within 5-mile Epz.Requirements Unnecessary 1990-07-25 |
Text
-. .
. . . .a :
1 0 DA/RYLAND hh[f=/[COOPERATlVE 2615 EAST AVE, SO . PO BOX 817 . LA CROSSE %1SCON l (606) 788-4000
, JAMES W. TAYLOR j Gsneral Manager
) February 25, 1988 8 i
l 1
In reply, please l
! refer to LAC-12506 !
l DOCKET No. 50-409 i !
J
! l 1
i Mr. A. Bert Davis, Regional Administrator 3 U. S. Nuclear Regulatory Comission
', Directorate of Regulatory Operations I Region III l 1
799 Roosevelt Road Glen Ellyn, IL 60137 j
Dear Mr. Davis:
i l~
SUBJECT:
Dairyland Power Cooperative La Crosse Boiling Water Reactor (LACBWR) j Provisional License No. DPR-45 i NRC Bulletin No. 88-01: Defects in j Westinghouse Circuit Breakers (TACS 65955/65956J l
l
REFERENCES:
(1) NRC Letter, Charles E. Rossi, to All Holders
]
of Operating Licenses or Construction Permits
- for Nuclear Power Reactors, dated February 5, 1988.
i Dairyland Power Cooperative has reviewed NRC Bulletin No. 88-01 3 (Reference 1) regarding defects in Westinghouse Circuit Breakers. We have i determined that no Westinghouse DS Series Circuit Breakers are installed at LACBWR.
This letter is intended to meet the reporting requirements of NRC Bulletin No. 88-01. This bulletin does not apply to LACBWR, therefore no action will be taken.
8803100202 880225 PDR ADOCK 05000400 0 DCD PCl-39
i l , .. ' .
l .
'. Mr. A. Bert Davis LAC-12506 Page 2 February 25, 1988 If you have any questions regarding this reply, please contact us.
' Sincerely.- -
t DAIRYLAND POWER COOPERATIVE James W. Taylor General Manager JWT:GSB sks cc: Document Control Desk U. S. Nuclear Regulatory Comission Washington, DC 20555 Mr. Peter B. Erickson, LACBWR Project Manager Division of Nuclear Reactor Regulation U. S. Nuclear Regulatory Comission Mr. Ken Ridgway, NRC Resident Inspector STATE OF WISCONSIN )
)
COUNTY OF LA CROSSE )
Personally came before me this O f day of , 1988, the above named. James W. Taylor, to me known to be the person who executed the foregoing instrument and acknowledge the same.
s i .
/
Notary Public Lp tr' osse County Wisconsin My comission expires February 23, 1992.
PCl-39
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