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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
i Iowa Electric Light and Pbwer Company July 23, 1980 LDR-80-200 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
This letter and enclosure are the response to Mr. Thomas Ippolito's letter dated April 25, 1980 concerning the effect of a DC power supply fail-ure on ECCS performance.
The information in the enclosure confirms the conclusions of the GE generic analysis referenced in Mr. Ippolito's letter. The plant design assumptions assumed in the GE analysis are conservative with respect to the Duane Arnold Energy Center.
Very truly yours, Larry D. oot Assistant Vice President Nuclear Generation LOR /RFS/mz enclosure cc: R. Salmon D. Arnold L. Liu S. Tuthill K. Meyer D. Mineck J. Van Sickel K. Eccleston (NRC)
File: A-107a, LC800425 80072809l mnw . m . w wmm m . m
ATTACHMENT 1 WORST CASE ECCS SYSTEM AVAILABILITY REQUEST
' Confirm the conclusion of the GE referenced study regarding the minimum ECCS equipment availability with a DC power failure. Include in your response a list of ECCS equipment that would be available for large and small (1) re-circulation loop discharge breaks, and (2) recirculation loop suction breaks.
The listing of equipment available should take into account not only DC power supply failure, but also the loss of equipment due to water spillage.
RESPONSE
Power supplies for all applicable ECCS equipment have been reviewed to determine the effect of a DC power failure. Table 1 indicates which power supplies are used for this ECCS equipment. Table 2 is a listing of available eqmipment given a DC power failure in either Division 1 or Division 2. No equipment loss is expected due to water spillage because the recirculation line break occurs inside of containment. All ECCS equipment is located outside containment. Table 2 does not distinguish between recirculation loop discharge breaks and suction breaks because this does not affect equipment availability.
Our review concludes that the plant design assumptions, which were used as the basis for GE's study, reflect the worst ECCS availability combinations for a DC power failure at DAEC. Based on these conclusions, Iowa Electric agrees that the conclusions reached by GE relative to a non-LPCI modified plant are applicable ':o DAEC.
p
IGER SIPitIES AftWritG ECG EUllittt2fr 10R G)RE SIHAY, IOf-f9ESSJRE tDRE IRJtX ION T (14tm SYS"lut),
M3D MtU IEEMESSIZATIGi SYS'11M Bjui[nent Rjullament Ibwer Control Ibwer Riuirunent thscription R&srher 6Tvision I Division 11 Division I Division II Itsnatks Auto <bprm surization valve SV-4400 1D13 (de) 1D23 (de) 1D13 (de) 1023 (de)
SV-4402 1013 (de) 1D23 (de) 1D13 (de) 1D23 (de)
Auto deprmsurization valve Auto (Uprmsurization valve SV-4405 1D13 (de) 1023 (de) 1D13 (de) 1023 (dc)
SV-4406 1D13 (Jc) ID23 (de) 1013 (de) ID23 (de)
Auto dermsurization valve IP-211A lA3 (ac) 1D13 (de)
Core stray gasnp .
1Dll (dc)
IP-211B 1A4 (ac) 1D23 (dc)
Core spray [asup 1D21 (dc)
Core spray System I suction valve K)-2100 1834 (ac) 1834 (ac) m-2120 1844 (ac) 1D44 (ac)
Core spray Systein 11 suction valve Core spray System I main isolation valve 70-2147 1834 (ac) 1834 (ac)
K)-2146 1844 (ac) 1844 (ac)
Core stray System 11 noin isolation valve N)-2117 1D34 (ac) 1D11 (de)
Core stray System I trboanl valve PO-2137 1844 (ac) ID21 (de)
Core spray System II trixwn! valve Core spray System I mininnsa flw laypass valve #0-2104 1034 (ac) 1834 (ac)
PO-2124 1844 (ac) 1844 (ac)
Core spray System 11 mininnan flow bytuss valve Core stray System I test trytuss valve K)-2112 1834 (ac) 1D11 (de)
K)-2132 1844 (ac) 1921 (de)
Core s[ ray System II test byguss valve Core spray Systein I outtxuni valve M)-2115 1834 (ac) IDil (de) to-2135 1044 (ac) ID21 (de)
Core sgray System II outixuni valve Rater sutply [wp IP-ll?A 189 (ac) 1Dll (de)
IP-117B IB20 (ac) 1D21 (dc)
Riter sugply [xsip IP-ll?C 189 (ac) 1D11 (dc)
Riter suiply [wp IP-ll7D 1B20 (ac) 1D21 (de)
Riter sugply [xsip
-~
Td21g I (cratirml)
Iljul[ ment _ Djulp2at_nt. Iower Control Itwer .
Djulgaigr3 fpscription t&mber Division I Division II Division I Division Ii ihsmarts Travelirvj screen drive notor A IP-36A 1891 (ac) 1891 (ac) i lt-368 1821 (ac) 1891 (ac)
- Travelirvj screen drive untor B Travelirvj screen wash pmp A IP-ll2A 1891 (ac) IDil (dcl Travelirvj screen wsh psip B IP-ll2B 1821 (ac) ID2L (dc)
Screen wash psip tozzle slutof f valve M)-2902 IB91 (ac) 1891 (ac)
Screen wash pag > runzle stutof f valve M)-2903 1B21 (ac) 1821 (ac)
Screen wash w t.r strainer IS-85A 1891 (ac) 1891 (ac)
IS-858 1821 (ac) 1821 (ac)
Screen wsh wter strainer M)-2910A 1891 (ac) 1891 (ac)
Screen wash wter strainer valve K)-2910B 1821 (ac) 1821 (ac)
Screen wash wter strainer valve Drmryency m vice wter guip IP-99A 1832 (ac) 1Dll (de)
IP-998 1842 (ac) 1D21 (de)
Dimmjency wrvice wter psip SV-1956A 1832 (ac) 101 'dct Die:tyercy mtvice wter paic solenoid valve '
SV-1956B 1842 (ac) 1D21 (de)
Dismjency mrvic' wter purp tuletioid valve Drasyency mtvice wwr psip solenoid valve SV-2080 1832 (ac) ID11 (de)
LV-2001 1842 (ac) ID21 (de)
Dreryency mtvice wter paic solenoid valve MJ-2039A 1832 (ac) 1832 (ac)
WIl ,
water inlet to anlers valve M)-20390 1842 (ac) 1832 (ac)
Wll water inlet in (nolers valve Wil water return valve M)-2077 1832 (ac) IDil (dc)
M)-2078 1842 (ac) ID21 (de)
Wil water return valve i<csidual 1 :at re.sivwal (luut) psip IP-229A lA3 (ac) IDl3 (dc)
IP-229B 1A4 (ac) ID23 (de) 15114 psip IP-229C 1A3 (ac) 1D13 (dc)
I4 fit pup IP-2290 1A4 (ac) 1D23 (dc) idut [nstp
{s Paje 3 of 6' r .
Tabli 1, pr% anxxil .
RIul lment ji) uipment Ihr Control Itwer D Wists I Divislosi 'I'i Division I DTvWs If iksmarts hju,igament. fwrigion 94 miner ~ .
14tn reactor leal spray isolation valve (irdeoard) 90-1900 1834 (ac) 1834 (ac) leut r: actor leaf stray isolation valve (outtxant) 70-1901 1D42 (de) ID42 (dc) laut stat 4mi coolinj isolation valve (irboant) 90-1908 1834 (ac) 1834 (ac) letR statam coolinj isolation valve (outboard) 60-1909 1D42 (dc) ID42 (de) 14tR disdiattje to riskaste isolation valve (outixurd) 90-1937 1D42 (dc) ID42 (dc) leut disdiattje to rakaste isolation valve (irixard) 90-1936 1834 (ac) 1834 (ac) 90-1935 1844 (ac) 1D23 (de) 14ut logi A minimma flw bypass valve 141R locp B minimum flow bylass valve 70-2009 1834 (ac) IDl3 (de) leut sanple line valve W-1972 M6 (ac) Mti (ac)
SV-2051 M s (ac) ids (ac)
Idut sanele line valve SV-1973 Ids (ac) les (ac) 14ut sample line valve SV-2052 Mti (ac) ids (ac) f404 sanple line valve W-1963 1023 (de) ID23 (de) 111CI inlet [ressure mntrol solernid valve SV-1964 1023 (de) ID23 (dc)
IIICI inlet [rmsure control soleroid valve 14Dt to reactor core isolatinj coolinj (RCIC) pressure control W-1966 1D23 (de) ID23 (de) solenoid valve illCI inlet gressure control enlenoid valve SV-2033 1013 (de) 1D13 (de)
W-2034 1D13 (de) ID13 (de)
IllCI inlet tressure cnitrol uolenoid valve 14th to ICIC presure control solenoid valve SV-203 1D13 (de) 1D13 (de) 14tn loop A cmtdirvient coolinj volve 70 -2000 1834 (ac) IDl3 (de) 30-1902 1B44 (ac) 1D23 (de) latit Icxp B contaitsiment cooliraj valve 141H lorp A contairanent coolinj rujulator valve 70-2001 1D34 (ac) IDl3 (dc) 70-1903 1844 (ac) ID23 (de) laut loop D contaissa s.t cuolirvj rojulator valve
Paje4off- ,
Tabt ,I (o :ninst) pluiptent. D1uinient Etust _
Qantrol Iber nauipmsnt Description Mader Division I Division II Division I Division II flesnarks .
IB34A (ac) IB34A (ac) 1013 (de) 1D23 (de) 14"1 lup A disdarge to Icw-pressure coolant injection (!JCI) MF2003 valve (irboard)
M)-1905 1844A (ac) IB'1A (ac) ID13 (de) ID23 (de) 14'l toty B disdurge to 1101 valve (irboard)
NF2004 IB34A (ac) IB34A (ac) 1D13 (de) ID23 (de) 143 lotp A disdurge to 1101 valve (outbaan.1)
MF1904 IB44A (ac) IB44A (ac) 1D13 (de) 1D23 (de) 14 A lotp B disdarije to IICI valve (outboard)
M)-2005 1834 (ac) 1D13 (de)
I4m loop A test. isolation valve M)-1932 1844 (ac), ID23 (de) 14'2 lorp B test isolation valve M)-2006 1834 (ac) ID13 (de) lem lorp A test to tonus valve MF1933 1844 (ac) ID23 (dc) fem locy B test to tonas valve M)-2007 1834 (ac) IDl3 (de) 14m locp A test to tonia valve M)-1934 1844 (ac) ID23 (dc)
Mm lorp B test to torus valve 14m cross' lu-p leater valve M)-2010 1B34 (ac) 1834 (ac)
M)-2069 1834 (ac) 1834 (ac) 14 04 Icxp A naintenarre isolation valve ~
M)-1989 1844 (ac) 1B44 (ac) tem locp B arointenance isolation valve M)-2038 1B34 (ac) 1D13 (de)
M m lamp A drain to torus valve MF1970 1B44 (ac) 1D23 (de) lam Icxp B drain to torus valve M)-2036 1834 (ac) ID13 (de) fem Icxp A drain to recirculation valve M)-1 % 7 . 1B44 (ac) ID23 (de) 14m Icap B drain to recirculation valve M)-2029 1834 (ac) 1B34 (ac)
I4m leat exdursjer A siell intet valve M)-1939 1844 (ac) 1844 (ac)
Idut insat exdanjer B stell intet valve 14m teat exd.orsjer A stell ustlet valve M)-2031 1834 (ac) 1834 (ac)
K)-1941 1844 (ac) 1844 (ac)
Idut imeat exdorvjer B stcll cutlet valve MF2030 1834 (ac) ID13 (de) laut Icx;p A tmat exdussjer Imuss valve M)-1940 1844 (ac), ID23 (de)
I4m loty B lesat exdursjer byguss valve
Paje 5 of Tzel a ! L eincat) tiguigment. Hjulpnent nur (bntrol Ruer niuipnent Descrirtion t&sder _ Division I Division II Division I Division II shanarks .
M"1 leat exdarger A vent valve to-2044A IG34 (ac) 1834 (ac) tem teat exdiarner A vent valve to-2044B 1834 (ac) 1834 (ac)
HR leat exdareer a vent valve to-1949A IB44 (ac) 1844 (ac)
M2 teat exdwger B vent valve to-1949B 1844 (ac) 1B44 (ac) les PP IP-229A stutdwn cooliin valve 60-2011 1834 (ac) 1834 (ac)
HR if IP-2290 slutdwn coolis.; valve to-1912 1844 (ac) IB44 (ac)
M2 PP IP-229C slutdwn molisv) valve PO-2016 1834 (ac) ,
1834 (ac) 14R PP IP-229D stutdwn coolisq valve 60-1920 1844 (ac) 1844 (ac)
MR PP IP-229A suction valve to-2012 1834 (ac) 1834 (ac)
Mut PP IP-229B suction valve to-1913 1844 (ac) IB44 (ac)
Mut PP IP-229C suction vulve M)-2015 1834 (ac) 1834 (ac)-
M54 lY IP-229D six: tion valve 70-1921 1B44 (ac) IB44 (ac)
ME service wter purp IP-22A lA3 (ac) 1D13 (de)
MDt service wter gainp IP-22B 1A4 (ac) 1D23 (de) lent service wter pap IP-22C IA3 (ac) 1D13 (de)
ME service wter pinp IP-22D 1A4 (ac) 1D23 (de) faut lorp u leat exdareer service wter discharge valve to-1947 1844 (ac) ID23 (dc)
ME locp A imat exdiarger service wter discha:Tje valve PO-2046 1834 (ac) 1D13 (de) liigtr-pressure cwlant injection (IUCI) roon coolirg'tmit IV-AC-14A 1834 (ac) 1834 (ac)'
1110I rotn omlire unit IV-AC-14B 1B44 (ac) 1844 (ac)
MR rum moliry asilt IV-AC-Il 1B44 (ac) 1844 (ac) 14D1 run cxx>liry trait IV-AC-12 1834 (ac) 1834 (ac) luut service wter piip rcxn air sayply fhn IV-SP-56A 1836 (ac) 1836 (ac)
Mut service wter psop roon air andy fan IV-SP-568 IB46 (ac) IB46 (ac)
p .
Pm}e 4 of G .
T<dilm I (cc-t int s t ) .
Equipntent n a uipient ther Omtrol Rmer n auirienznt ihsscription Emier Divistor. I Division 11 Division I Division II hunaria ,
C3 service wter pap roon air aqply solenokl valve W-7538A IBM (ac) IBM (ac) l .
Cet service wter pmp suon air agply solenoid valves W-753BB IBM (ac) IBM (ac)
M3 service wter panp roon air surply solernkl valve W-7539A IB M (ac) IBM (ac)
H3 service wter pap rcxis air aqqdy solenoid valve W-75398 IBM (ac) IBM (ac)
M'3 service wter parp roon air mudy soleroLI valve W-7536 IBM (ac) IBM (ac)
Mut service wter psip rcun air su[ ply solenoLI valve W-7537 IBM (ac) IBM (ac)
Intake structure erknin staply finn W-W -50 1891 (ac) IDil (de)
Intake structure rein sugply fan W- W -51 1821 (ac) ID21 (de)
IV441-52A 1821 (ac) 1821 (ac)
Inttke strticture tnit feater W-tal-52C 1821 (ac) 1821 (ac)
Intake structure init feater IV4RI-52E 1821 (ac) 1821 (ac)
Intake structure asilt feater W-441-521 1B01 (ac) 1821 (ac)
Intake stnicture init teater W 4El-528 1891 (ac) 1891 (ac)
Intake structure asilt feater IV4El-52D 1891 (ac) 1891 (ac)
Intake structure tanit leater Iv4Al-52r 1B91 (ac) 1891 (ac)
Intake structure init feater IV-Iti-531 1891 (ac) 1891 (ac)
Intake structure teilt luater Reactor rucirculatiry pop discharge lefpass valve M N 629 IB3M (ac) IB3 M (ac) ID13 (de) ID23 (de) leector ncirculatirn parp discharge trypass valve M)-4630 IB44A (ac) IB44A (ac) 1D13 (de) ID23 (de)
M H 627 IB34A (ac) IB34A (ac) ID13 (de) 1D23 (de)
Reactor recirculatire pmp discharge valve Reector recirculatiro psip diuciarye valve MH628 IB4 R (ac) 1844 (ac) IDl3 (de) 1D23 (de) l l
l L - . - - - - - - - - - - - - - _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
TABIE 2
('
ESSENPIAL ICUIINENT AVAIIABLE EOLIINIE LOSS T DC PNER Icss of Icss of Division II Division I EtIuiptent Description dc Power dc Power Auto depressurization valve SV-4400 SV-4400 Auto depressurization valve SV-4402 SV-4402 Autio depressurization valve SV-4405 SV-4405 Auto depressucization valve SV-4406 SV-4406 Core spray (CS) pmp 1P-211A 1P-211B CS system suction valve m -2100 m -2120 CS system nain isolation valve m-2147 m -2146 CS systen inboard isolation valve m -2117 m-2137 CS systen minimum flow bypass valve m -2104 m -2124
(
i CS system test bypass valve m -2112 m-2132 CS system outboard isolation valve m -2115 m -2135 Water supply pmp IP-ll7A 1P-ll7B Water supply pung 1P-ll7C 1P-ll7D Travelirg screen drive notor 1F-36A 1F-36B Traveling screen wash punp 1P-ll2A 1P-ll2B Screen wash pung nozzle shutoff valve m -2902 m -2903 Screen wash water strainer 1S-85A IS-85B Screen wash water strainer valve m -2910A m-2910B Emergency service water pung 1P-99A 1P-998 Emergency service water puup valve ,
SV-1956A SV-1956B Emergency service water pung valve SV-2080 S"-2081 1 Well water inlet to coolers valve m-2039A m -2039B Wall water return valve m -2077 m ,2078
Table 2 (continued) Paga 2 of 4 Ims of Irss of Division I
(. RIuignent Descriotion Division II de Power dc Power Residual beat removal (RHR) punp 1P-229A 1P-229B RER puup IP-229C 1P-229D RHR reactor head spray isolation valve bO-1900 FO-1901 BHR shutdown cooling isolation valve 30-1908 bO-1909 RHR discharge to waste isolation valve 50 -1936 50 -1937 RHR loop minimun flow bypass valve 30 -2009 bO-1935 RER sample line valve SV-1972 SV-1973 RHR sample line valve SV-2051 SV-2052 High-pressure coolant injection (HPCI) SV-2033 SV-1963 to RHR pressure reduction valve HPCI to RHR pressure reduction valve SV-2034 SV-1964 RHR to reactor core isolation cooling SV-2037 SV-1966 (RCIC) pressure reduction valve RHR contalment stray valve MD-2000 50 -1902 RHR contairment spray regulai.ing valve 50 -2001 50 -1903 RHR discharge to low-pressure coolant 50 -2003 30 -2003 injection (LPCI)
RHR discharge to LPCI BO-1905 to-1905 RER discharge to LPCI 20 -2004 50 -2004 RHR discharge to LPCI PO-1904 50 -1904 RHR test isolation valve 50 -2005 FO-1932 RHR test to torus valve 50 -2006 FO-1933 RHR test to torus valve FO-2007 50-1934 RER cross locp heMer valve 30-2010 Note 1 RER loop maintenance isolation valve 50 -2069 50-1989 l
RHR drain to torus valve 50 -2038 30-1970
Table 2 (continued) Pags 3 of 4 Icss of Ioss of t Division II Division I dc Power dc Power C Ebuipment Description FRR to RCIC isolation valve f0-2036 co-1967 RER heat exdanger inlet valve 20 -2029 BC-1939 RER heat exdarger cutlet valve 30-2031 PC-1941 RHR heat excharger bypass to-2030 bO-1940 RHR heat exchanger vent valve bO-2044A bO-1949A RHR heat exdarger vent valve 20-2044B FO-19498 RHR pmp suction header valve PO-2011 50 -1912 RHR pmp suction header valve 50 -2016 PO-1920 BHR ptmp suction frm torus 50 -2012 PO-1913 RHR pump suction frm torus 30 -2015 50 -1921 BHR service water pmp 1P-22A 1P-22B
' RHR service water pmp 1P-22C 1P-22D RER heat exchanger service water 30 -2046 30-1947 discharge valve HPCI rom cooling unit N-AC-14A IV-AC-148 RER roon ecoling unit IV-AC-12 IV-AC-ll RHR service water pmp roon fan IV-SF-56A IV-SF-56B l RHR service water pmp roon supply valve SV-7538A SV-7538B RHR service water pmp roon supply valve SV-7539A SV-7539B RHR service water pmp roon supply valve SV-7536 SV-7537 Intake structure main supply fan IV-SF-50 IV-SF-51 Intake structure unit heater IV4E-52B IV4E-52A Intake structure unit heater IV-OH-52D IV4E-52C Intake structure unit heater IV4E-52F IV4E-52E Intake structure unit heater IV4E-52H IV4E-523
O e Table 2 (contirmed) Page 4 of 4 Icss of Icss of Division II Division I ac vower O muit aent Description de 90wer Reactor recirculating ptznp discharge m-4629 m -4629 bypass valve Reactor recirculatirq 'ptznp discharge E -4630 m -4630 bypass valve Reactor recirculating ptznp discharge m -4627 m-4627 valve Reactor recirculating pump discharge m -4628 m-4628 valve
Note 1: Valve MO-2010 is keylocked in the cpen Ersition and provides the fiowpath for LPCI systen cperation of either Division 1 or Division 2.
1
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