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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N5521999-10-21021 October 1999 Forwards Operator Licensing Exam Rept 50-331/99-302(OL) for Tests Administered During Wk of 990920.Six Applicants Passed All Sections of Exam & Were Issued Operating Licenses ML20217H8921999-10-18018 October 1999 Forwards SER Accepting Eight of Licensee Relief Requests, NDE-R001,(Part a & B),NDE-R027,NDE-R028,NDE-R029,NDE-R030, NDE-R032 & NDE-R035,one Request Relief NDE-R036,denied & Relief Request NDE-R034 Unnecessary ML20217F4801999-10-14014 October 1999 Provides Individual Exam Results for Applicants Who Took Sept 1999 Initial License Exam.Informs That Info Considered Proprietary & That Listed Info,Supplements & Exam Rept Will Be Issued Shortly NG-99-1405, Informs That Util Has Completed Addl Review to Ensure That All Related Requirements for Repair/Replacements Have Been Addressed,Per Util Requesting Approval of Several Inservice Insp Relief Request1999-10-0808 October 1999 Informs That Util Has Completed Addl Review to Ensure That All Related Requirements for Repair/Replacements Have Been Addressed,Per Util Requesting Approval of Several Inservice Insp Relief Request NG-99-1383, Forwards Response to NRC 990930 RAI on TS Change Request TSCR-010 Re Excess Flow Check Valve SRs1999-10-0808 October 1999 Forwards Response to NRC 990930 RAI on TS Change Request TSCR-010 Re Excess Flow Check Valve SRs ML20217F7221999-10-0707 October 1999 Forwards Insp Rept 50-331/99-11 on 990820-0930.No Violations Noted ML20212L0411999-10-0505 October 1999 Informs That Privacy Info Identified in Util Re Duane Arnold Energy Center Emergency Telephone Book,Rev 61 Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(a)(6) & Section 103(b) of Atomic Energy Act NG-99-1358, Forwards DAEC plant-specific Response to 990927 RAI Re TS Change Request on Excess Flow Check Valve Surveillance requirements.TSTF-334,included1999-10-0505 October 1999 Forwards DAEC plant-specific Response to 990927 RAI Re TS Change Request on Excess Flow Check Valve Surveillance requirements.TSTF-334,included NG-99-1378, Clarifies TS Change Requests for Revised Safety Limit Min Critical Power Ratio.Approval of 990510 & 0716 Application for Amends to License DPR-49 Requested Prior to Scheduled Start of Cycle 17 & Effective Date No Earlier than 9910221999-10-0404 October 1999 Clarifies TS Change Requests for Revised Safety Limit Min Critical Power Ratio.Approval of 990510 & 0716 Application for Amends to License DPR-49 Requested Prior to Scheduled Start of Cycle 17 & Effective Date No Earlier than 991022 NG-99-1327, Forwards IST Relief Request VR-24 Re Excess Flow Check Valve Test Frequency,Per 10CFR50.55a(a)(3)(i),for NRC Approval1999-10-0404 October 1999 Forwards IST Relief Request VR-24 Re Excess Flow Check Valve Test Frequency,Per 10CFR50.55a(a)(3)(i),for NRC Approval ML20212J8761999-09-30030 September 1999 Forwards RAI Re Util 990412 Request to Revise Duane Arnold Energy Ctr TS SR 3.6.1.3.7 to Allow Representative Sample of Reactor Instrumentation Line EFCV to Be Tested Every 24 Months,Instead of Testing Each EFCV Every 24 Months ML20217A9331999-09-30030 September 1999 Informs That NRC Plan to Conduct Addl Insp by Resident Inspectors Beyond Core Insp Program Over Next 7 Months to Assess Preparation for Implementation of Refuel Outage Activities.Historical Listing of Plant Issues Encl ML20212H2121999-09-27027 September 1999 Forwards Request for Addl Info Re 990412 Licensee Request to Revise DAEC TS SR 3.6.1.3.7 to Allow Representative Sample of Reactor Instrumentation Line EFCV to Be Tested Every 24 Months,Instead of Testing Each EFCV Every 24 Months ML20212H2151999-09-22022 September 1999 Forwards Amend 228 to License DPR-49 & Safety Evaluation. Amend Revises DAEC TS SR 3.4.3.1, Safety/Relief Valves & Safety Valves NG-99-1262, Forwards License Renewal Application for G Thullen,License SOP 30232-2.Thullen Has Completed Requalification Program for Daec.Encls Withheld,Per 10CFR2.790(a)(6)1999-09-20020 September 1999 Forwards License Renewal Application for G Thullen,License SOP 30232-2.Thullen Has Completed Requalification Program for Daec.Encls Withheld,Per 10CFR2.790(a)(6) NG-99-1214, Forwards Voluntary Info Requested in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Re Estimated Number of Operator Licensing Exams & Applicants for Years 2000 Through 20031999-09-15015 September 1999 Forwards Voluntary Info Requested in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Re Estimated Number of Operator Licensing Exams & Applicants for Years 2000 Through 2003 NG-99-1278, Forwards Corrected TS Page 3.3-52 Re TS Change Request TSCR-003,removing Requirements for Hpcis & Rcics Isolation Manual Initiation Instrumentation.Page Indicates Deletion of Condition G as Well as or G from Condition H1999-09-15015 September 1999 Forwards Corrected TS Page 3.3-52 Re TS Change Request TSCR-003,removing Requirements for Hpcis & Rcics Isolation Manual Initiation Instrumentation.Page Indicates Deletion of Condition G as Well as or G from Condition H ML20212A8711999-09-14014 September 1999 Informs That 990716 Application Which Submitted Affidavit & Attachment Re Addl Info Re Cycle Specific SLMCPR for Plant Cycle 17, June 1999,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) NG-99-1249, Requests Exemption from Certain Requirements Applicable to ECCS Evaluation Models Performed IAW App K to 10CFR50 for DAEC1999-09-10010 September 1999 Requests Exemption from Certain Requirements Applicable to ECCS Evaluation Models Performed IAW App K to 10CFR50 for DAEC NG-99-1252, Informs That There Is No Longer Need for Any Waiver Associated with Senior Operator License Application for MR Pettengill Due to Completion of All Five Manipulations1999-09-0909 September 1999 Informs That There Is No Longer Need for Any Waiver Associated with Senior Operator License Application for MR Pettengill Due to Completion of All Five Manipulations NG-99-1192, Forwards marked-up Copies of Affected Tables & Ref Matl Which Supports Changes Re DAEC Reactor Vessel Integrity Database (Rvid),As Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity1999-09-0808 September 1999 Forwards marked-up Copies of Affected Tables & Ref Matl Which Supports Changes Re DAEC Reactor Vessel Integrity Database (Rvid),As Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20211M5621999-09-0202 September 1999 Forwards Insp Rept 50-331/99-08 on 990712-16 & 0810-12.No Violations Noted.Insp Consisted of Review of Source Term Reduction & Integration of ALARA Into Work Planning & Execution,Calibration & Maint NG-99-1216, Requests Waiver to Allow MR Pettengill to Participate in Upcoming Senior Operator Examination on 990920.Util Intends to Ensure That Pettengill Completes All Five Required Manipulations as Soon as Possible1999-09-0101 September 1999 Requests Waiver to Allow MR Pettengill to Participate in Upcoming Senior Operator Examination on 990920.Util Intends to Ensure That Pettengill Completes All Five Required Manipulations as Soon as Possible NG-99-1182, Forwards Certified License Applications IAW Provisions of Examiner Standard (ES)-201 for SA Arebaugh,Sd Bahnsen,Jd Kalamaja,Ja Miell,Bd Musel & MR Pettengill.Encls to Ltr Withheld Per 10CFR2.790(a)(6)1999-08-31031 August 1999 Forwards Certified License Applications IAW Provisions of Examiner Standard (ES)-201 for SA Arebaugh,Sd Bahnsen,Jd Kalamaja,Ja Miell,Bd Musel & MR Pettengill.Encls to Ltr Withheld Per 10CFR2.790(a)(6) ML20211M5811999-08-31031 August 1999 Forwards Proprietary Version of Rev 61 to DAEC Emergency Telephone Book. Proprietary Encl Withheld NG-99-1205, Forwards FFD Rept of Program Performance Info for DAEC During Six Month Period from 990101-06301999-08-30030 August 1999 Forwards FFD Rept of Program Performance Info for DAEC During Six Month Period from 990101-0630 ML20211F7831999-08-26026 August 1999 Forwards Insp Rept 50-331/99-09 on 990708-0819.Violation Re Failure to Log Entry Into TS Limiting Condition for Operation When Power Lost to Drywell Sump Pump Level Switches,Noted & Being Treated as NCV ML20210V1231999-08-17017 August 1999 Forwards Insp Rept 50-331/99-10 on 990802-06.No Violations Noted.Insp Examined Activities Conducted Under Emergency Preparedness Program ML20211A8731999-08-16016 August 1999 Ack Receipt of 990212 & 0402 Ltrs,Which Transmitted Changes Identified as Revs 39 & 40 to DAEC Security Plan,Submitted Under Provisions of 10CFR50.54(p).NRC Review Comments for Subject Plans,Encl NG-99-1146, Forwards Validated Exam Matls for Initial License Exam to Be Administered at Facility,Wk of 990920,IAW Guidelines in NUREG-1021,Rev 8,dtd April 19991999-08-16016 August 1999 Forwards Validated Exam Matls for Initial License Exam to Be Administered at Facility,Wk of 990920,IAW Guidelines in NUREG-1021,Rev 8,dtd April 1999 NG-99-1126, Submits Rept Re Changes in Calculated Peak Cladding Temp for Daec,Iaw 10CFR50.46(a)(3)(ii),guidance in NRC Info Notice 97-015 & Suppl 1.Rept Covers Period from Last Annual Rept Through June 19991999-08-13013 August 1999 Submits Rept Re Changes in Calculated Peak Cladding Temp for Daec,Iaw 10CFR50.46(a)(3)(ii),guidance in NRC Info Notice 97-015 & Suppl 1.Rept Covers Period from Last Annual Rept Through June 1999 NG-99-1050, Informs That Recommendation in BWRVIP-18,incorrectly Interpreted During RFO 15 & 25% of Creviced Welds Examined. All of Inspected Creviced Welds Were Found to Be Acceptable1999-07-28028 July 1999 Informs That Recommendation in BWRVIP-18,incorrectly Interpreted During RFO 15 & 25% of Creviced Welds Examined. All of Inspected Creviced Welds Were Found to Be Acceptable ML20210L8311999-07-27027 July 1999 Forwards Insp Rept 50-331/99-05 on 990601-0701.Violations Noted.Insp Included Assessment & Evaluation of Engineering Support,Design Change & Mod Activities Including 10CFR50.59 Safety Evaluations,Applicability Reviews & C/As ML20210E9781999-07-26026 July 1999 Informs That Info Submitted by Ltr (Nep 99-0067), Ies Utilities,Inc,Will Be Withheld from Public Disclosure, Per 10CFR2.790(a)(6) ML20210E1431999-07-22022 July 1999 Provides Summary of 990715 Meeting with Alliant Utilities & Duane Arnold Energy Ctr Mgt Re Recent Plant Performance Review Issued by NRC for Duane Arnold Energy Ctr.Associated Meeting Summary & Alliant Utilities Meeting Handout Encl NG-99-0993, Submits Amend to Commitment Contained in Util 990623 Response to NRC RAI Re Third ten-year Interval ISI Relief Requests.Licensee Now Commits to Meeting Code Requirement of Asme,Section XI,1989 Edition,Paragragh IWB/IWC-2420(a)1999-07-21021 July 1999 Submits Amend to Commitment Contained in Util 990623 Response to NRC RAI Re Third ten-year Interval ISI Relief Requests.Licensee Now Commits to Meeting Code Requirement of Asme,Section XI,1989 Edition,Paragragh IWB/IWC-2420(a) ML20210B7161999-07-20020 July 1999 Forwards Audit Rept on Y2K Contingency Planning Program at Duane Arnold Energy Center Conducted on 990615-16 as follow-up to NRC GL 98-01 ML20210B5271999-07-16016 July 1999 Forwards Insp Rept 50-331/99-07 on 990526-0707.Two Violations Being Treated as Noncited Violations NG-99-0989, Provides Estimate of Number of Licensing Requests That Will Be Submitted in FY00 & 01,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-16016 July 1999 Provides Estimate of Number of Licensing Requests That Will Be Submitted in FY00 & 01,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20209E8401999-07-13013 July 1999 Discusses Completion of NRC GL 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling & Containment Heat Removal Pumps for Plant NG-99-0990, Forwards License Renewal Applications for Ta Zimmerman SOP 30772 & Ba Westcot SOP 30771.Encls Withheld,Per 10CFR2.7901999-07-13013 July 1999 Forwards License Renewal Applications for Ta Zimmerman SOP 30772 & Ba Westcot SOP 30771.Encls Withheld,Per 10CFR2.790 ML20209G4991999-07-12012 July 1999 Forwards Insp Rept 50-331/98-05 on 990622-24.No Violations Noted ML20207H6741999-07-0606 July 1999 Forwards Operating Licensing Exam Rept 50-331/99-301(OL) on 990525.Staff Administered Written Exam to One Reactor Operator Applicant Previously Demonstrating Unsatisfactory Results During Jul 1998 Exam NG-99-0928, Forwards Response to NRC 980902 Comments Re Design Basis NPSH Analyses as Requested by GL 97-041999-07-0101 July 1999 Forwards Response to NRC 980902 Comments Re Design Basis NPSH Analyses as Requested by GL 97-04 NG-99-0859, Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants,Per GL 98-01.Y2K Readiness Disclosure for Plant Encl1999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants,Per GL 98-01.Y2K Readiness Disclosure for Plant Encl ML20212J4521999-06-25025 June 1999 Discusses Closure of TAC MA1188 Re Response to RAI to GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity NG-99-0880, Informs That Util Commits to Repeating Newly Established Sequence of Component Exams During Successive Insp Intervals for NDE-R035,in Response to NRC Re Inservice Insp Relief Requests1999-06-23023 June 1999 Informs That Util Commits to Repeating Newly Established Sequence of Component Exams During Successive Insp Intervals for NDE-R035,in Response to NRC Re Inservice Insp Relief Requests ML20196F9531999-06-21021 June 1999 Forwards Proprietary Rev 60 to Duane Arnold Energy Center Emergency Telephone Book.Proprietary Info Withheld ML20196A1431999-06-18018 June 1999 Confirms Discussion Between Members of Staffs to Have Meeting on 990715 at Training Ctr at Duane Arnold Energy Ctr to Discuss Results of Plant Performance Review Process ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARNG-99-1383, Forwards Response to NRC 990930 RAI on TS Change Request TSCR-010 Re Excess Flow Check Valve SRs1999-10-0808 October 1999 Forwards Response to NRC 990930 RAI on TS Change Request TSCR-010 Re Excess Flow Check Valve SRs NG-99-1405, Informs That Util Has Completed Addl Review to Ensure That All Related Requirements for Repair/Replacements Have Been Addressed,Per Util Requesting Approval of Several Inservice Insp Relief Request1999-10-0808 October 1999 Informs That Util Has Completed Addl Review to Ensure That All Related Requirements for Repair/Replacements Have Been Addressed,Per Util Requesting Approval of Several Inservice Insp Relief Request NG-99-1358, Forwards DAEC plant-specific Response to 990927 RAI Re TS Change Request on Excess Flow Check Valve Surveillance requirements.TSTF-334,included1999-10-0505 October 1999 Forwards DAEC plant-specific Response to 990927 RAI Re TS Change Request on Excess Flow Check Valve Surveillance requirements.TSTF-334,included NG-99-1327, Forwards IST Relief Request VR-24 Re Excess Flow Check Valve Test Frequency,Per 10CFR50.55a(a)(3)(i),for NRC Approval1999-10-0404 October 1999 Forwards IST Relief Request VR-24 Re Excess Flow Check Valve Test Frequency,Per 10CFR50.55a(a)(3)(i),for NRC Approval NG-99-1378, Clarifies TS Change Requests for Revised Safety Limit Min Critical Power Ratio.Approval of 990510 & 0716 Application for Amends to License DPR-49 Requested Prior to Scheduled Start of Cycle 17 & Effective Date No Earlier than 9910221999-10-0404 October 1999 Clarifies TS Change Requests for Revised Safety Limit Min Critical Power Ratio.Approval of 990510 & 0716 Application for Amends to License DPR-49 Requested Prior to Scheduled Start of Cycle 17 & Effective Date No Earlier than 991022 NG-99-1262, Forwards License Renewal Application for G Thullen,License SOP 30232-2.Thullen Has Completed Requalification Program for Daec.Encls Withheld,Per 10CFR2.790(a)(6)1999-09-20020 September 1999 Forwards License Renewal Application for G Thullen,License SOP 30232-2.Thullen Has Completed Requalification Program for Daec.Encls Withheld,Per 10CFR2.790(a)(6) NG-99-1278, Forwards Corrected TS Page 3.3-52 Re TS Change Request TSCR-003,removing Requirements for Hpcis & Rcics Isolation Manual Initiation Instrumentation.Page Indicates Deletion of Condition G as Well as or G from Condition H1999-09-15015 September 1999 Forwards Corrected TS Page 3.3-52 Re TS Change Request TSCR-003,removing Requirements for Hpcis & Rcics Isolation Manual Initiation Instrumentation.Page Indicates Deletion of Condition G as Well as or G from Condition H NG-99-1214, Forwards Voluntary Info Requested in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Re Estimated Number of Operator Licensing Exams & Applicants for Years 2000 Through 20031999-09-15015 September 1999 Forwards Voluntary Info Requested in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Re Estimated Number of Operator Licensing Exams & Applicants for Years 2000 Through 2003 NG-99-1249, Requests Exemption from Certain Requirements Applicable to ECCS Evaluation Models Performed IAW App K to 10CFR50 for DAEC1999-09-10010 September 1999 Requests Exemption from Certain Requirements Applicable to ECCS Evaluation Models Performed IAW App K to 10CFR50 for DAEC NG-99-1252, Informs That There Is No Longer Need for Any Waiver Associated with Senior Operator License Application for MR Pettengill Due to Completion of All Five Manipulations1999-09-0909 September 1999 Informs That There Is No Longer Need for Any Waiver Associated with Senior Operator License Application for MR Pettengill Due to Completion of All Five Manipulations NG-99-1192, Forwards marked-up Copies of Affected Tables & Ref Matl Which Supports Changes Re DAEC Reactor Vessel Integrity Database (Rvid),As Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity1999-09-0808 September 1999 Forwards marked-up Copies of Affected Tables & Ref Matl Which Supports Changes Re DAEC Reactor Vessel Integrity Database (Rvid),As Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity NG-99-1216, Requests Waiver to Allow MR Pettengill to Participate in Upcoming Senior Operator Examination on 990920.Util Intends to Ensure That Pettengill Completes All Five Required Manipulations as Soon as Possible1999-09-0101 September 1999 Requests Waiver to Allow MR Pettengill to Participate in Upcoming Senior Operator Examination on 990920.Util Intends to Ensure That Pettengill Completes All Five Required Manipulations as Soon as Possible ML20211M5811999-08-31031 August 1999 Forwards Proprietary Version of Rev 61 to DAEC Emergency Telephone Book. Proprietary Encl Withheld NG-99-1182, Forwards Certified License Applications IAW Provisions of Examiner Standard (ES)-201 for SA Arebaugh,Sd Bahnsen,Jd Kalamaja,Ja Miell,Bd Musel & MR Pettengill.Encls to Ltr Withheld Per 10CFR2.790(a)(6)1999-08-31031 August 1999 Forwards Certified License Applications IAW Provisions of Examiner Standard (ES)-201 for SA Arebaugh,Sd Bahnsen,Jd Kalamaja,Ja Miell,Bd Musel & MR Pettengill.Encls to Ltr Withheld Per 10CFR2.790(a)(6) NG-99-1205, Forwards FFD Rept of Program Performance Info for DAEC During Six Month Period from 990101-06301999-08-30030 August 1999 Forwards FFD Rept of Program Performance Info for DAEC During Six Month Period from 990101-0630 NG-99-1146, Forwards Validated Exam Matls for Initial License Exam to Be Administered at Facility,Wk of 990920,IAW Guidelines in NUREG-1021,Rev 8,dtd April 19991999-08-16016 August 1999 Forwards Validated Exam Matls for Initial License Exam to Be Administered at Facility,Wk of 990920,IAW Guidelines in NUREG-1021,Rev 8,dtd April 1999 NG-99-1126, Submits Rept Re Changes in Calculated Peak Cladding Temp for Daec,Iaw 10CFR50.46(a)(3)(ii),guidance in NRC Info Notice 97-015 & Suppl 1.Rept Covers Period from Last Annual Rept Through June 19991999-08-13013 August 1999 Submits Rept Re Changes in Calculated Peak Cladding Temp for Daec,Iaw 10CFR50.46(a)(3)(ii),guidance in NRC Info Notice 97-015 & Suppl 1.Rept Covers Period from Last Annual Rept Through June 1999 NG-99-1050, Informs That Recommendation in BWRVIP-18,incorrectly Interpreted During RFO 15 & 25% of Creviced Welds Examined. All of Inspected Creviced Welds Were Found to Be Acceptable1999-07-28028 July 1999 Informs That Recommendation in BWRVIP-18,incorrectly Interpreted During RFO 15 & 25% of Creviced Welds Examined. All of Inspected Creviced Welds Were Found to Be Acceptable NG-99-0993, Submits Amend to Commitment Contained in Util 990623 Response to NRC RAI Re Third ten-year Interval ISI Relief Requests.Licensee Now Commits to Meeting Code Requirement of Asme,Section XI,1989 Edition,Paragragh IWB/IWC-2420(a)1999-07-21021 July 1999 Submits Amend to Commitment Contained in Util 990623 Response to NRC RAI Re Third ten-year Interval ISI Relief Requests.Licensee Now Commits to Meeting Code Requirement of Asme,Section XI,1989 Edition,Paragragh IWB/IWC-2420(a) NG-99-0989, Provides Estimate of Number of Licensing Requests That Will Be Submitted in FY00 & 01,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-16016 July 1999 Provides Estimate of Number of Licensing Requests That Will Be Submitted in FY00 & 01,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates NG-99-0990, Forwards License Renewal Applications for Ta Zimmerman SOP 30772 & Ba Westcot SOP 30771.Encls Withheld,Per 10CFR2.7901999-07-13013 July 1999 Forwards License Renewal Applications for Ta Zimmerman SOP 30772 & Ba Westcot SOP 30771.Encls Withheld,Per 10CFR2.790 NG-99-0928, Forwards Response to NRC 980902 Comments Re Design Basis NPSH Analyses as Requested by GL 97-041999-07-0101 July 1999 Forwards Response to NRC 980902 Comments Re Design Basis NPSH Analyses as Requested by GL 97-04 NG-99-0859, Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants,Per GL 98-01.Y2K Readiness Disclosure for Plant Encl1999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants,Per GL 98-01.Y2K Readiness Disclosure for Plant Encl NG-99-0880, Informs That Util Commits to Repeating Newly Established Sequence of Component Exams During Successive Insp Intervals for NDE-R035,in Response to NRC Re Inservice Insp Relief Requests1999-06-23023 June 1999 Informs That Util Commits to Repeating Newly Established Sequence of Component Exams During Successive Insp Intervals for NDE-R035,in Response to NRC Re Inservice Insp Relief Requests ML20196F9531999-06-21021 June 1999 Forwards Proprietary Rev 60 to Duane Arnold Energy Center Emergency Telephone Book.Proprietary Info Withheld NG-99-0468, Informs That There Have Been No Changes in Organizational Structure or Ownership from That Previously Submitted in .Ies Util Remains Owner & Operator of Duane Arnold Energy Center1999-06-0303 June 1999 Informs That There Have Been No Changes in Organizational Structure or Ownership from That Previously Submitted in .Ies Util Remains Owner & Operator of Duane Arnold Energy Center NG-99-0625, Informs NRC That SRO License for B Westcot & SRO License SOP 30772 for T Zimmerman Should Be Modified to Require Corrective Lenses for Near & Distant Vision While Performing Licensed Duties.Nrc Forms 396,withheld,per 10CFR2.790(a)(b)1999-05-24024 May 1999 Informs NRC That SRO License for B Westcot & SRO License SOP 30772 for T Zimmerman Should Be Modified to Require Corrective Lenses for Near & Distant Vision While Performing Licensed Duties.Nrc Forms 396,withheld,per 10CFR2.790(a)(b) NG-99-0741, Forwards Remaining Validated Exam Matls for Initial License Exam to Be Administered at Licensee Facility Week of 990524. Exam Matls Should Be Withheld from Public Disclosure Until After Exam Completed1999-05-19019 May 1999 Forwards Remaining Validated Exam Matls for Initial License Exam to Be Administered at Licensee Facility Week of 990524. Exam Matls Should Be Withheld from Public Disclosure Until After Exam Completed NG-99-0700, Forwards License Renewal Applications for SA Brewer OP-30975,EE Harrison SOP-31293 & SD Kottenstette SOP-31294. Encls Withheld Per 10CFR2.790(a)(6)1999-05-17017 May 1999 Forwards License Renewal Applications for SA Brewer OP-30975,EE Harrison SOP-31293 & SD Kottenstette SOP-31294. Encls Withheld Per 10CFR2.790(a)(6) ML20206S7951999-05-11011 May 1999 Informs That Temporary Addendum to DAEC Security Plan Is No Longer Required & Should Be Removed.Addendum Was Transmitted to NRC in 981015 Licensee Ltr NG-99-0664, Forwards Certified Application Re Reactor Operator License Reapplication IAW Provisions of Examiner Standard (ES)-201 for Ma Ruchko.Examination Is Scheduled for 990525.Encl Withheld Per 10CFR2.7901999-05-10010 May 1999 Forwards Certified Application Re Reactor Operator License Reapplication IAW Provisions of Examiner Standard (ES)-201 for Ma Ruchko.Examination Is Scheduled for 990525.Encl Withheld Per 10CFR2.790 NG-99-0636, Forwards Radiological Environ Monitoring Program (REMP) for DAEC for Jan-Dec 1998, IAW TS Section 5.6.2 Reporting Requirements1999-04-29029 April 1999 Forwards Radiological Environ Monitoring Program (REMP) for DAEC for Jan-Dec 1998, IAW TS Section 5.6.2 Reporting Requirements NG-99-0633, Forwards DAEC 1998 Annual Radioactive Matls Release Rept for Jan-Dec 1998. Rept Satisfies Requirements for Annual Radioactive Matl Release Rept,As Stated in Section 5.6.3 of Tech Specs1999-04-29029 April 1999 Forwards DAEC 1998 Annual Radioactive Matls Release Rept for Jan-Dec 1998. Rept Satisfies Requirements for Annual Radioactive Matl Release Rept,As Stated in Section 5.6.3 of Tech Specs NG-99-0622, Forwards Validated Exam Matls for Initial License Exam to Be Administered During Week of 990524,per NUREG-1021.Without Encl1999-04-28028 April 1999 Forwards Validated Exam Matls for Initial License Exam to Be Administered During Week of 990524,per NUREG-1021.Without Encl NG-99-0605, Forwards Response to NRC Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Duane Arnold Energy Center1999-04-28028 April 1999 Forwards Response to NRC Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Duane Arnold Energy Center NG-99-0493, Forwards non-certified Application Re Reactor License Reapplication in Accordance with Provisions of Examiner Std (ES)-201 for Ma Ruchko.Nrc License Exam Scheduled for 990525.Without Encl1999-04-19019 April 1999 Forwards non-certified Application Re Reactor License Reapplication in Accordance with Provisions of Examiner Std (ES)-201 for Ma Ruchko.Nrc License Exam Scheduled for 990525.Without Encl NG-99-0495, Informs NRC That RW Pfeil Did Not Take BWR Generic Fundamentals Exam Section of Written Operator Licensing Exam Administered on 990407.R Pfeil Is No Longer Enrolled in DAEC Operator Licensing Training Program1999-04-19019 April 1999 Informs NRC That RW Pfeil Did Not Take BWR Generic Fundamentals Exam Section of Written Operator Licensing Exam Administered on 990407.R Pfeil Is No Longer Enrolled in DAEC Operator Licensing Training Program NG-99-0529, Forwards Outline of Exam to Be Given Week of 990524 as Requested in Telcon with G Thullen & Requests Exam Matls Be Withheld from Public Disclosure Until After Exam Completed on 9905281999-04-0808 April 1999 Forwards Outline of Exam to Be Given Week of 990524 as Requested in Telcon with G Thullen & Requests Exam Matls Be Withheld from Public Disclosure Until After Exam Completed on 990528 ML20205M2471999-04-0202 April 1999 Transmits Change 40 to DAEC Security Plan,Per Requirements of 10CFR50.54(p).Changes Are Intended to Enhance Capability of Onsite Security Force to Defend Against Design Basis Threat.Plan Withheld,Per 10CFR73.21 NG-99-0491, Requests Relief from Noted Requirements,For Relief Requests MC-R002 Through MC-R006,MC-P001 & NDE-R015,rev 1.Approval Is Requested Prior to Refueling Outage 16,scheduled to Begin on 9910081999-04-0202 April 1999 Requests Relief from Noted Requirements,For Relief Requests MC-R002 Through MC-R006,MC-P001 & NDE-R015,rev 1.Approval Is Requested Prior to Refueling Outage 16,scheduled to Begin on 991008 NG-99-0281, Forwards Decommissioning Funding Rept for Daec,Iaw 10CFR50.75(f)(1).Rept Is Being Submitted by DAEC Joint Owners Ies Utilities,Inc,Central IA Power Cooperative & Corn Belt Cooperative1999-03-31031 March 1999 Forwards Decommissioning Funding Rept for Daec,Iaw 10CFR50.75(f)(1).Rept Is Being Submitted by DAEC Joint Owners Ies Utilities,Inc,Central IA Power Cooperative & Corn Belt Cooperative NG-99-0273, Forwards 1999 DAEC Simulator Certification Rept, Per 10CFR55.45 Every Four Years on Anniversary of Certification. Required Info Contained in Attachments 1-71999-03-24024 March 1999 Forwards 1999 DAEC Simulator Certification Rept, Per 10CFR55.45 Every Four Years on Anniversary of Certification. Required Info Contained in Attachments 1-7 ML20207L8351999-03-10010 March 1999 Forwards Proprietary Rev 59A to Deac Emergency Telephone Book & non-proprietary Rev 20 to Section H of DAEC Emergency Plan, IAW 10CFR50,App E.Proprietary Info Withheld NRC-99-0300, Forwards Rev 15 to Pump & Valve IST Program for Daec1999-03-0101 March 1999 Forwards Rev 15 to Pump & Valve IST Program for Daec NG-99-0302, Forwards Fitness for Duty Program Performance for DAEC During Six Month Period Jul-Dec 1998 in Accordance with 10CFR26.71(d)1999-02-28028 February 1999 Forwards Fitness for Duty Program Performance for DAEC During Six Month Period Jul-Dec 1998 in Accordance with 10CFR26.71(d) ML20203G3041999-02-12012 February 1999 Informs of Rev to Security Plan for DAEC to Improve Flexibility in Deployment of Members of Security Force. Security Plan Change 39,reflecting Changes,Encl.Encl Withheld NG-99-0115, Submits Request for Enforcement Discretion to Tech Spec Surveillance Requirement 3.8.1.7 for Edgs.Listed New Commitment Being Made by Ltr1999-01-21021 January 1999 Submits Request for Enforcement Discretion to Tech Spec Surveillance Requirement 3.8.1.7 for Edgs.Listed New Commitment Being Made by Ltr ML20206S1691999-01-18018 January 1999 Forwards Proprietary Rev 59 to DAEC Emergency Telephone Book. Proprietary Encl Withheld NG-98-2102, Informs That Util Completed Commitment to Assess & Implement Severe Accident Mgt Guidelines at Daec,Based Upon Generic Guidelines Developed by BWROG1998-12-31031 December 1998 Informs That Util Completed Commitment to Assess & Implement Severe Accident Mgt Guidelines at Daec,Based Upon Generic Guidelines Developed by BWROG NG-98-2059, Provides Response to NRC Request for Background Summary of TS Change (TSCR-006), Revise TS 3.6.1.3 Condition E & Add TS for Control Bldg/Standby Gas Treatment (Cb/Sbgt) Instrument Air Sys1998-12-21021 December 1998 Provides Response to NRC Request for Background Summary of TS Change (TSCR-006), Revise TS 3.6.1.3 Condition E & Add TS for Control Bldg/Standby Gas Treatment (Cb/Sbgt) Instrument Air Sys 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARNG-90-2226, Forwards Proposed Operator Licensing Exam Schedule for FY91- FY94 in Response to Generic Ltr 90-071990-09-17017 September 1990 Forwards Proposed Operator Licensing Exam Schedule for FY91- FY94 in Response to Generic Ltr 90-07 NG-90-2088, Forwards Summary of Root Cause & Corrective Action Plan Re Operator Requalification Training Program,Per NRC 900713 Confirmatory Action Ltr CAL-RIII-90-131990-08-25025 August 1990 Forwards Summary of Root Cause & Corrective Action Plan Re Operator Requalification Training Program,Per NRC 900713 Confirmatory Action Ltr CAL-RIII-90-13 ML1124202601990-08-17017 August 1990 Forwards Summary of Changes Omitted from 900814 Transmittal of Emergency Plan NG-90-1894, Forwards Licensed Operator Requalification Exams & Evaluations for Accelerated Remedial & Enhanced Training1990-08-0101 August 1990 Forwards Licensed Operator Requalification Exams & Evaluations for Accelerated Remedial & Enhanced Training ML1122122061990-07-27027 July 1990 Forwards Exams & Evaluations for Licensed Operator Requalification Documentation of Remedial & Enhanced Training.Both Types of Training Conducted in Segments of 30 H & 20 H.Encl Withheld ML1122122001990-07-20020 July 1990 Forwards Licensed Operator Requalification Documentation of Remedial & Enhanced Training,Per 900713 Confirmatory Action Ltr.Encl Withheld ML20043H2471990-06-18018 June 1990 Forwards Description of Security Plan Change SPC-24, Evaluation of Change W/Respect to 10CFR50.54(p),security Plan & Security Plan Addendum Re Intake Structure Mods.Encl Withheld (Ref 10CFR73.21) ML20042E6381990-04-20020 April 1990 Forwards Environ Radiological Monitoring Program for Duane Arnold Energy Ctr,Annual Rept - Part I Summary & Interpretation,Jan-Dec 1989. ML20011F7961990-02-28028 February 1990 Forwards Rev 23 to Plant Security Plan & Contingency Plan, Incorporating Numerous Editorial Changes & Upgrades made-to- Date on Perimeter Barrier Surrounding Plant Protected Area. Rev Withheld (Ref 10CFR73.21) ML20006D9781990-02-0909 February 1990 Responds to Notice of Violation & Proposed Imposition of Civil Penalty Transmitted in NRC 900110 Ltr.Corrective Actions:Secondary Containment Operability Test Revised to Require Securing Main Plant Exhaust Sys During Test ML20006B9551990-01-26026 January 1990 Responds to NRC 891227 Ltr Re Violations & Proposed Imposition of Civil Penalty.Corrective Actions:Fourteen Improperly Insulated Splices Repaired Per Facility Environ Qualification Program ML20005G0321989-12-19019 December 1989 Forwards Security Plan Change 22,per Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs. ML19324C3921989-11-0606 November 1989 Responds to Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs. Vital Equipment Identified Using Station Blackout Safe Shutdown Equipment List NG-89-2589, Forwards Proposed Operator Licensing Exam Schedule Format Estimating Number of Candidates to Be Examined & Dates for Scheduled Requalification Exams1989-08-29029 August 1989 Forwards Proposed Operator Licensing Exam Schedule Format Estimating Number of Candidates to Be Examined & Dates for Scheduled Requalification Exams ML20245K8201989-06-30030 June 1989 Forwards Security Plan Change 21,addressing Concerns Noted in Insp Rept 50-331/89-08.Change Withheld (Ref 10CFR73.21) ML20247A1491989-05-15015 May 1989 Forwards Response to Violations Noted in Insp Rept 50-331/89-08 Per Unresolved Item in Insp Rept 50-331/85-07 Re Security Plan.Response Withheld ML20245E9731989-04-26026 April 1989 Forwards 1988 Annual Radiological Environ Operating Rept for Plant ML20246D9401989-04-21021 April 1989 Forwards Public Version of Rev 2C to Emergency Telephone Book NG-88-3744, Responds to Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Corrective Actions:Util Has Taken Steps to Preclude Future Installation of Unqualified Butt Splices in Circuits,Per 10CFR50.491988-11-21021 November 1988 Responds to Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Corrective Actions:Util Has Taken Steps to Preclude Future Installation of Unqualified Butt Splices in Circuits,Per 10CFR50.49 NG-88-3593, Requests Approval to Defer Insp of Piping Susceptible to IGSCC Until Cycle 10/11 Due to Welds in RWCU Not Previously Examined,Per Generic Ltr 88-011988-10-21021 October 1988 Requests Approval to Defer Insp of Piping Susceptible to IGSCC Until Cycle 10/11 Due to Welds in RWCU Not Previously Examined,Per Generic Ltr 88-01 NG-88-2390, Forwards NPDES Monthly Operating Repts for Apr 1985,Jan-Aug 1987 & Jan-Feb 19881988-10-0606 October 1988 Forwards NPDES Monthly Operating Repts for Apr 1985,Jan-Aug 1987 & Jan-Feb 1988 NG-88-3187, Responds to NRC Bulletin 88-007, Power Oscillations in Bwrs. Evaluation Consisted of Review of Operating Procedures,Licensed Operator Training Program & Neutron Monitoring Hardware1988-09-19019 September 1988 Responds to NRC Bulletin 88-007, Power Oscillations in Bwrs. Evaluation Consisted of Review of Operating Procedures,Licensed Operator Training Program & Neutron Monitoring Hardware ML19318G2431988-09-0909 September 1988 Submits Licensee Schedule of Best Estimates for Operator Licensing Exams & Requalification Exams for FY89-92 Per Generic Ltr 88-13 ML20154J3371988-08-30030 August 1988 Forwards Security Plan Changes 19 & 16A.Changes Withheld (Ref 10CFR73.21) ML20207H2711988-08-17017 August 1988 Forwards Response to Concerns Noted in Insp Rept 50-331/88-15.Response Withheld (Ref 10CFR2.790 & 73.21) ML20151U8831988-04-22022 April 1988 Forwards Parts 1 & 2 to Environ Radiological Monitoring Program Annual Rept for 1987 ML20147F1541988-02-24024 February 1988 Forwards Response to Violations Noted in Insp Rept 50-331/88-02.Response Withheld (Ref 10CFR2.790 & 73.21) ML20196G4391988-02-24024 February 1988 Forwards Response to Insp Rept 50-331/88-02.Encl Withheld (Ref 10CFR2.790 & 73.21) ML20237D8771987-12-17017 December 1987 Forwards Addl Info on 861202 Proposed Security Plan Change Re Generic Ltr 87-08, Miscellaneous Amends & Search Requirements, Per 870915 Request.Encl Withheld ML20236H5691987-10-26026 October 1987 Forwards Security Plan Change 18 to Security Plan.Change Does Not Decrease Safeguards Effectiveness of Security Plan. Change Withheld (Ref 10CFR73.21) ML20234B0151987-09-15015 September 1987 Forwards Monthly Operating Rept for Aug 1987 & Revised Monthly Operating Repts for May,June & Jul 1987 NG-87-1918, Forwards Exemption Request Re Combustible Foam Matl in Drywell Liner Expansion Gap.Per Exemption request,3 H Fire Barrier Unnecessary to Ensure That One Train of Safe Shutdown Equipment Free of Fire Damage.Fee Paid1987-08-25025 August 1987 Forwards Exemption Request Re Combustible Foam Matl in Drywell Liner Expansion Gap.Per Exemption request,3 H Fire Barrier Unnecessary to Ensure That One Train of Safe Shutdown Equipment Free of Fire Damage.Fee Paid ML20238A0321987-08-25025 August 1987 Forwards Radioactive Effluent Releases Semiannual Rept for Jan-June 1987, Per Radiological Tech Specs NG-87-3176, Responds to Violations Noted in Insp Rept 50-331/87-16. Corrective Actions:Fire Watch Reestablished in Accordance W/Procedure & Contract Personnel Will Meet W/Fire Marshall Before Commencing W/Hot Work Activities1987-08-21021 August 1987 Responds to Violations Noted in Insp Rept 50-331/87-16. Corrective Actions:Fire Watch Reestablished in Accordance W/Procedure & Contract Personnel Will Meet W/Fire Marshall Before Commencing W/Hot Work Activities ML20236K5691987-07-28028 July 1987 Forwards App B to Analyses for Gamma-Emitting Isotopes of Samples W/Elevated Gross Beta Activity Resulting from Chernobyl Nuclear Plant Accident (Ussr) on 860826. Addendum Consists of Samples Collected on 860515 & 22 NG-87-1881, Responds to Generic Ltr 87-06 Requiring List of All Pressure Isolation Valves W/Description of Periodic Testing Requirements & Operational Limits for Each Valve.Applicable Valves Listed.Testing Requirements Described1987-06-11011 June 1987 Responds to Generic Ltr 87-06 Requiring List of All Pressure Isolation Valves W/Description of Periodic Testing Requirements & Operational Limits for Each Valve.Applicable Valves Listed.Testing Requirements Described NG-87-1090, Responds to Emergency Response Facility Appraisal Rept 50-331/86-20 Open Items.Corrective Actions:Procedure for Generating Offsite Dose Projections for Unmonitored Releases Will Be Developed for Midas Dose Projection Sys1987-04-0101 April 1987 Responds to Emergency Response Facility Appraisal Rept 50-331/86-20 Open Items.Corrective Actions:Procedure for Generating Offsite Dose Projections for Unmonitored Releases Will Be Developed for Midas Dose Projection Sys NG-87-1015, Responds to Violations Noted in Insp Rept 50-331/86-19 on 861202-870116.Corrective Actions:Maint Procedure MD-017 Revised to Require That Maint Engineering Be Notified of Measuring & Test Equipment Found to Be out-of-calibr1987-03-20020 March 1987 Responds to Violations Noted in Insp Rept 50-331/86-19 on 861202-870116.Corrective Actions:Maint Procedure MD-017 Revised to Require That Maint Engineering Be Notified of Measuring & Test Equipment Found to Be out-of-calibr NG-87-0830, Notifies of Annual Emergency Planning Exercise on 871027. Exercise Will Be During Normal Working Hours & Will Involve Full County Participation.State of IA Will Not Be Participating1987-03-0505 March 1987 Notifies of Annual Emergency Planning Exercise on 871027. Exercise Will Be During Normal Working Hours & Will Involve Full County Participation.State of IA Will Not Be Participating ML20212J5031987-02-27027 February 1987 Forwards Change 17 to Physical Security Plan.Entire Plan Resubmitted Due to Binding Procedure,However,No Changes Involve Guard Training & Qualification Program.Change Withheld (Ref 10CFR73.21) NG-86-4544, Forwards Scotch Brand Tapes Maint Procedure GMP-ELEC-008, Installation Instructions, Rev 0 to QUAL-M345-00, Preliminary Equipment Qualification Record for 3 M Tapes & QUAL-A602-00, Qualification of Splices ..1986-12-19019 December 1986 Forwards Scotch Brand Tapes Maint Procedure GMP-ELEC-008, Installation Instructions, Rev 0 to QUAL-M345-00, Preliminary Equipment Qualification Record for 3 M Tapes & QUAL-A602-00, Qualification of Splices .. ML20215C1841986-12-0505 December 1986 Forwards Changes 12-15 to Security Plan & Guard Training & Qualification Plan.Changes Withheld (Ref 10CFR73.21) ML20214V3511986-12-0202 December 1986 Forwards Changes to Personnel Search Requirements of Security Plan,In Response to Amends to 10CFR50 & 73.Approval Requested.Fee Paid.Security Plan Changes Withheld (Ref 10CFR73.21) ML20214F4031986-11-0707 November 1986 Forwards Response to Safeguards Inadequacies Noted During Regulatory Effectiveness Review Conducted from 860331-0404. Encl Withheld (Ref 10CFR73.21) NG-86-3988, Responds to IE Bulletin 86-003.Facility Does Not Have air-operated Min Flow Bypass Valves in ECCS Min Flow Bypass Lines or Min Flow Bypass Valve Configuration or Logic1986-10-30030 October 1986 Responds to IE Bulletin 86-003.Facility Does Not Have air-operated Min Flow Bypass Valves in ECCS Min Flow Bypass Lines or Min Flow Bypass Valve Configuration or Logic NG-86-3044, Suppls 860528 Response to IE Bulletin 85-003,Item E Re motor-operated Valve Common Mode Failures During Plant Transients.Max Expected Differential Pressures During Opening & Closing of Valves Provided1986-10-0101 October 1986 Suppls 860528 Response to IE Bulletin 85-003,Item E Re motor-operated Valve Common Mode Failures During Plant Transients.Max Expected Differential Pressures During Opening & Closing of Valves Provided ML20210A9341986-09-15015 September 1986 Forwards Monthly Operating Rept for Aug 1986 & Revised Page 1 for Monthly Operating Repts for June & Jul 1986.Page Revised Due to Mathematical Errors NG-86-2722, Forwards State of IA NPDES Permit 57-00-1-04,per 830425 Agreement to Submit Permit Changes Based on License Amend 84 Re Water Quality Requirements.Cooling Tower Maint Chemicals, Containing Zinc or Chromium,Not Used by Util1986-08-22022 August 1986 Forwards State of IA NPDES Permit 57-00-1-04,per 830425 Agreement to Submit Permit Changes Based on License Amend 84 Re Water Quality Requirements.Cooling Tower Maint Chemicals, Containing Zinc or Chromium,Not Used by Util ML20214K6151986-08-15015 August 1986 Forwards Monthly Operating Rept for Jul 1986 & Revised Page 1 to Monthly Operating Rept for June 1986 ML20209B2461986-08-0606 August 1986 Responds to Request for Info Concerning Allegation Re Contract Supervisor Failing to Meet Criteria for Continued Unescorted Access to Vital Areas.Unescorted Access Terminated Due to Conviction of Felony 1990-09-17
[Table view] |
Text
,. ,
[gi
( 2.201(a),2.205
, Iowa Electric Light and Power Company February 9, 1990 I NG-90-0318 Mr.- James Lieberman, Director L Office of Enforcement l
[ U. S. Nuclear Regulatory Commission l L- Attn: Document Control Desk !
Washington, DC 20555' t
!: i i _ ..
i l
Subject:
Duane Arnold Energy Center '
l
[ Docket No: 50-331 ;
F Op. License No: DPR-49' Reply to Notice of Violation and Proposed Imposition of ;
- Civil Penalty (EA 89-214) !
File: A-102, A-289 i
Dear Mr. Lieberman:
i 1
1 A letter from Mr. A. Bert Davis, USNRC Region III Regional Administrator.-to !
Iowa-Electric Light and Power Company dated January 10, 1990, transmitted a Notice of Violation and Proposed Imposition of Civil Penalty. The letter and NRC regulations require Iowa Electric to reply within thirty days. This letter a and its attachments constitute the required reply. !
Pursuant to the requirements of 10 C.F.R. S 2.201(a), in Attachment 1, " Reply i to a Notice of Violation," Iowa Electric admits the violation and identifies y
- the reasons for the violation, the corrective steps that have been taken and l the results achieved, the corrective steps that will be taken to avoid further ;
violations, and the date when full compliance was achieved. Attachment 2 filed pursuant to 10 C.F.R. 6 2.205, is Iowa Electric's " Answer to the Proposed Imposition of Civil Penalty." In that Answer, we ask that NRC reconsider its decision to impose a penalty in this case and we set forth the basis for that requested action.
i We believe that the facts of this case argue strongly for the NRC to exercise s its discretion under 10 C,F.R. Part 2, Appendix C to refrain from imposing a civil penalty. That the violation occurred and persisted over a long period is acknowledged. However, the Iowa Electric personnel who detected and resolved this problem did an excellent job. Iowa Electric is proud of their performance.
.We note that in the referenced letter of January 10, 1990, the NRC stated, "The !
. o.no alertness and understanding. demor e,trated. . 1s commendable."
ty e j- 9 -
During a scheduled maintenance outage, a persistent and imaginative Iowa Electric system engineer identified a hole in ventilation shaft ductwork. The
.$ 8 SGTS surveillance test was performed immediately -- and unsuccessfully. Iowa 80 Electric personnel promptly began a deliberate and careful process of defining M the' problem. Precise problem identification was complex as was the development i om of comprehensive corrective action. Although that resolution may seem obvious
_88 in hindsight, it was not. Iowa Electric personnel analyzed the problem and ggy conducted tests to develop information about the various DAEC ventilation
- f w 4-General Of)in
- Cedar ifapids, lona 52406
h .. _ _______ -_ - ___. .--
Cr. James Licberman February 9, 1990 NG-90-0318 Page 2 :
i systems and the interactions between and among those systems in a comprehensive and prudent manner. Corrective actions (including revision of the SGTS ,
surveillance procedure) were decided upon and implemented with careful attention to detail and in accordance with the applicable procedures.
The system engineer who identified this subtle problem has been commended and rewarded for his initiative and persistence. We are equally pleased with the deliberate, careful, and effective way in which lowa Electric personnel evaluated the problem and resolved it. In our view, imposition of a civil :
penalty sends a wrong signal to a staff whose diligence and thorough j understanding of the plant led to the identification and resolution of this problem. We urge NRC to consider whether imposition of the penalty is consistent with the NRC's goal of encouraging and supporting licensee initiatives to identify and comprehensively correct problems.
This response, consisting of the letter and attachments, is true and accurate to the best of my knowledge and belief.
4 IOWA ELECTRIC LIGHT AND POWER COMPANY By DANIEL L. MINECK Manager, Nuclear Division Subscr and sworn to be ore me on this -a day of - '
- Mmete 1990. /
$$fU 2Lnt1A i
No'taryPublicinandfortheState of Iha DLM/PMB/pjv+
l Attachments: (1) Response to a Notice of Violation j- (2) Answer to Proposed Imposition of Civil Penalty cc: P. Bessette L. Liu L. Root i R. McGaughy 6 J. R. Hall (NRC-NRR)
A. Bert Davis (Region III) l NRC Resident Office Commitment Control #900007 l
I
r-m Attachment I to NG-90-0318 Page 1 10WA ELECTRIC LIGHT AND POWER COMPANY Response to Notice of Violation Transmitted with Inspection Report 89-026 NRC NOTICE OF VIOLATION (SEVERITY LEVEL III)
, 10 CFR Part 50, Appendix B, Criterion XI, Test Control, requires, in part, that
! a test program be established to assure that all testing required to demonstrate j that structures, systems, and components will perform satisfactorily in service j is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents.
- Technical Specification Limiting Condition for Operation (LCO) 3.7.C.1 requires secondary containment integrity to be maintained during all modes of plant operation unless specific exception criteria are met. In addition, Technical Specification Surveillance Requirement 4.7.C.1.c requires that the Standby Gas Treatment System capability to maintain 1/4 inch of water vacuum under calm wind
(< 5 MPH) conditions with a filter train flow rate of not more than 4,000 SCFM, shall be demonstrated at each refueling outage prior to refueling.
Contrary to the above, from 1974 until September 20, 1989, the licensee failed to establish an adequate surveillance test to demonstrate that the Standby Gas Treatment System could maintain 1/4 inch of water vacuum under calm wind
, conditions with a filter train flow rate of not more than 4000 SCFM. The l
surveillance test was inadequate in that interaction with other ventilation systems was not properly considered.
RESPONSE TO NOTICE OF VIOLATION
- 1. Admission of the Violation Iowa Electric Light and Power Company (IELP) admits that the secondary containment surveillance test procedure in place on September 20, 1989, was not adequate to ensure that the Standby Gas Treatment System (SGTS) could maintain the P.eactor Building (RB) at the required 1/4 inch of water vacuum.
- 2. Reasons for the Violation This violation was caused by our failure to recognize th6t negative pressure regions adjacent to secondtry containment could affect the results of this test. Operation of the plant exhaust fans during the tect, while not prohibited, masked a breach in the ventilation shaft ductwork and prevented detection of the deterioration of secondary containment seals and penetrations.
- 3. The Corrective Stens That Have Been Taken and the Results Achieved The secondary containment operability test procedure has been revised. It now requires that the main plant exhaust and turbine building and radwaste building ventilat'on systems be secured during the test, thus precluding the existence of negative pressure regions adjacent to the secondary containment boundary.
- p. g ,, .
- m. :
~
Attachment I to NG-90-0318 Page 2 All other surveillance test procedures applicable to safety-related HVAC -
L systems were reviewed to determine whether other previously unknown a v- interactions-could affect the accuracy of test'results. This review verified ,
that the procedures are adequate to determine whether Technical Specification ='
surveillance requirements are satisfied and that no mechanical system i
< interactions with other HVAC systems could mask inadequate or degraded system
-performance. No deficiencies were identified in the. test procedures, s
The breach in the reactor building ventilation shaft ductwork initially ,
identified by the system engineer has been repaired and the ductwork housing L has been reinforced to ensure seismic adequacy. The degraded seals and penetrations identified after the secondary containment surveillance ~ test procedure had been revised were~ repaired or replaced. The DAEC Preventative
, Maintenance Program now includes periodic inspection and replacement of boot i and airlock door seals. . The SGTS is currently able to maintain the RB at
! -greater than 0.3. inches of water vacuum.
L , ,
l
-Operating procedures and alarm response procedures have been revised to require that the main plant exhaust fans be secured upon receipt of a RB vent stack radiation alarm during secondary containment isolation conditions. The ,
changes assure that any bypass of the SGTS which can result from operation of the main plant exhaust' fans will be terminated during actual accident conditions, 1
- 4. ' Corrective Steos That Will Be Taken to Avoid Further Violations.
L As described soove, this deficiency has been completely corrected. However,-
p .to preclude recurrence of ductwork failures of this type, we will be inspecting all Class'l ductwork to verify that the as-built configuration meets the applicable design specifications. Most of these inspections will be completed .
- dur t:.g the next refueling outage; all inspections will be complete before -
g . December 31, 1990.
In addition, the inclusion of boot and airlock door seals in the Preventative Maintenance Program will ensure that any deterioration of these seals will be r detected.
? 5. : D. ate When Full Como11ance Will Be Achieved
-IELP'was in full compliance as of October 22, 1989, the date the DAEC was I returned to operation following the Fall 1989 maintenance outage.
I F
s
V :.,,' <;
' Attachment 2 to- -
NG-90-0318 Page 1
, .1 IOWA ELECTRIC LIGHT AND POWER COMPANY i Answer to Proposed Imposition of Civii Penalty Introduction F
On January 10, 1990, the NRC advised Iowa Electric that it proposes to assess a civil penalty in the amount of $25,000 for violation of 10 C.F.R. Part 50, Appendix '
B,-and DAEC Technical Specifications 3.7 C.1. and 4.7.C.1.c. In brief, a ,
surveillance test procedure intended to demonstrate that the Standby Gas Treatment ,
System meets the Technical Specification ~ requirement was not adequate to do so. <
Iowa Electric's response to the Notice of Violation pursuant to 10 C.F.R. $ 2.201 is separately stated. This document is Iowa Electric's Answer to the proposed civil penalty.
Iowa Electric's Positign Iowa Electric respectfully requests that NRC reconsider its decision to impose a penalty in this case. We submit that proper application of the NRC Enforcement ,
Policy (set out at 10 C.F.R. Part 2, Appendix C) leads to a determination that .
no enforcement action beyond the Notice of Violation is appropriate.
Iowa Electric admits that the violction charged occurred and that its Severity Level (III) has correctly been assessed. However, we believe that, in the circumstances of this case viewed as a whole, exercise of agency discretion will lead,to the decision not to impose a civil penalty.
Pertinent Provisions of NRC Enforcement Poliev - The Exercise of Discretion Under NRC's Enforcement Policy, "(a) notice of violation is normally the.only enforcement action taken, except in cases where the criteria for civil penalties '
and orders, as set forth in Sections V.B and V.C respectively, are met." (10 C.F.R. Part 2, Appendix C, Section V. A. ) In the case of a Severity Level III -
violation,'Section V.B states that a civil penalty is to be " considered" (as distinguished from Level I and II violations where penalties "are proposed absent mitigating circumstances"). The Policy makes clear that, for Severity Level III 1 violations, imposition of civil penalties may " warrant the _ exercise of discretion p under Section V.G." This exercise of discretion is separate and apart from the
, consideration of mitigating and escalating factors once a decision is made that assessment of a civil penalty is the appropriate course. (10 C.F.R. Part 2, Appendix C, Section V.B.)
The stated purpose of providing explicitly in the policy for this exercise of discretion (and in certain cases the discretion not even to issue notices of l ,
violation) is that L
. . . the NRC wants to encourage and support licensee initiative for l self-identification and correction of problems. . . .
(10 C.F.R. Part 2, 4ppendix C,Section V.G.)
l
. . ,. 3 Attachment 2 to NG-90-0318 l
Page 2 t
One category of discretion is precisely applicable to the situation which gave rise to the Notice of Violation forwarded by the NRC's letter of January 10, 1990, to Iowa Electric:
The NRC may-refrain from proposing a civil penalty for a Severity Level III violation not involving an overexposure or_ release of radioactive material
- that meets all of the following criteria.
- a. It was identified by the licensee and reported;
- b. Comprehensive corrective action has been taken or is well underway within a reasonable time following identification;
- c. It was not a violation that either (1) was reasonably preventable by the licensee's action in response to a previous regulatory concern identified within-the past two years of the inspection or since the last two _ inspections whichever is longer or (ii) reasonably should have been corrected prior to the violation because the licensee had prior notice of ,
the problem involved; and
- d. It was not a willful violation or indicative of a breakdown in management controls.
(10 C.F.R. Part 2, Appendix'C,Section V.G.3.)
Aoolication of Discretion to the Violation in Question
-The NRC _ letter of January 10,.1990, and its enclosure do not give explicit
~1ndication of the factors which the-NRC Staff considered in deciding whether to assess a civil-' penalty for this-violation. The -letter describes-the circumstances of the violation, its discovery, and certain related judgments by the Staff._ The letter then states that a civil penalty is proposed in order "(t)o emphasize the 4 'importance of having and using proper surveillance test procedures and engineering
- control s . . . ." -It then discusses possible escalation and. mitigation of the base penalty,
! The January 10, 1990, letter does not explicitly address application of the.
criteria set out in Section V.G.3 of Appendix C to the facts which gave rise to this violation. Iowa Electric submits that those criteria have been met in'this case. _-Iowa Electric. identified the problem and reported it'promptly. Iowa Electric undertook comprehensive corrective action as described in Attachment 1 and completed it before the plant resumed operation. Certain additional inspections (to further assure that installation of ventilation system ductwork satisfies design requirements) will be completed by the end of 1990. No -regulatory concern had.been raised previously which was in any way related to the violation or could have put Iowa Electric on notice of the problem. Finally, the violation
-was not willful and does not suggest a breakdown in management controls.
We have carefully examined the January 10, 1990, letter and the NRC report on "the special safety inspection . . . of containment integrity issues . . . ." (Report 89-26, transmitted by NRC letter dated November 7,1989.) We respectively suggest that these documents may reflect a misperception regarding Iowa Electric's invest _igation of the basic problem and its timeliness in developing a comprehensive corrective action. In view of the possibility that this perception ;
,. x, .
Attachment 2 to 4 NG-90-0318 Page 3 l 1ed'the Staff. to propose a civil penalty before it had considered exercise of its discretion, we wish to clarify several points. '
The DAEC had been shut down on September 15 for a scheduled maintenance outage and remained shut down on September 20, 1989. An Iowa Electric employee identified the hole in ductwork associated with the Standby Gas Treatment System (SGTS) at
.approximately 09:55'on September 20, 1989. The SGTS surveillance _ test was performed within minutes (at approximately 10:13) with the hole open and the main !
plant exhaust fans off; the test failed. It was evident to DAEC personnel that the main plant exhaust fans had been " helping" the SGTS to draw the required vacuum on the Reactor Building. Plant documentation indicates that the NRC was notified.
at approximately 12:54 of the hole in the ductwork and the failed test.
Shortly thereafter (probably on September 20 or 21, 1989), an NRC inspector at DAEC asked the engineer who had discovered the hole in the ductwork whether the procedure (STP) governing the secondary containment surveillance test would be changed to require securing the main plant exhaust fans during the test. The ,
engineer responded appropriately that such a decision should be made following repair of the hole and appropriate testing. We believe that this reaction may :
- not-have been regarded by the NRC as wholly responsive. ;
L It was clear 'to the Iowa Electric personnel, however, that definition of the -
underlying problem and development of a comprehensive resolution,- one aspect of which was the correction'of the STP, were not simple tasks and that all proper corrective actions were not immediately apparent. They recognized that it was essential to explore and evaluate all design and safety aspects and ramifications of securing'the main plant exhaust fans before making any commitment to secure them. They also recognized that other surveillance test procedures applicable
.to safety-related HVAC systems had to be reviewed to determine whether there were other previously-unknown interactions. The process of investigation and evaluation was started immediately after the hole in the ductwork was discovered.
The factors which influenced their judgment to proceed promptly but with 3 deliberation include the following: j
- 1. If the main plant exhaust fans are secured while the plant is in operation, '
l' temperatures in the vicinity of the steam-lines increase. The Primary-Containment Isolation System instrumentation may then incorrectly sense a steam leak, signal a Group 1 isolation, and a reactor scram is likely to occur.
- 2. In the course of continued testing during the period from September 20 until ,
October 11, 1989, when the SGTS test was completed successfully, IE was able l to develop much valuable information about the various DAEC ventilation systems-(e.g. . Turbine Building, Radwaste Building, Reactor Building) and interactions between and among them. This information helped us develop a comprehensive resolution including an appropriate, effective secondary containment STP while verifying that other test procedures were valid.
l: 3. Sound consideration and implementation of procedural changes requires formality and attention to detail. At DAEC, permanent STP changes are approved by the Operations Supervisor, Plant Performance Supervisor, and Quality Control Supervisor, and reviewed by the ALARA Coordinator. A permanent change
- l. must be reviewed by the Operations Committee before it is submitted for final l approval by the Plant Superintendent-Nuclear.
1 ,; i.g --
^ -
Attachment 2 to NG-90-0318 f Page 4 This process was not identified nor was the corrective protiss initiated by anyone other than IE's own staff. The company did not require a regulatory.
stimulus to undertake this action. Nor was the-company recalcitrant in implementing corrective action suggested by the NRC Staff. Our- j udgment, expressed in a telephone conversation with. Region III staff on October 12, that lit would be premature to commit to manual. isolation or a design change was based solely on the fact that, although our_ evaluation was proceeding in a-timely fashion, it was not yet complete at that time. In_ our view, any suggestion of. inappropriate delay in completing our evaluation is not supported. The plant was shut down-(until October-22) in a maintenance outage extended to address environmental qualification matters. The Plant Safety Analysis and Technical Specifications did not require this system to be operable during this period. Under those conditions evaluation of the SGTS problem was being conducted at an appropriate pace. In due course,-changes were made in our alarm response and operating procedures but only after a-safety evaluation had been prepared and a design change made to the Turbine Building ventilation system.
Conclusion We respectfully request that the NRC reexamine the circumstances which surround the violation and Iowa Electric's response and consider or reconsider the violation .in accordance with Section V.G.3. of the Enforcement Policy. We believe that_a careful consideration of the facts will lead to the conclusion that it is appropriate to refrain from proposing a civil penalty. We therefore -
request that the penalty be remitted.
i