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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:OUTGOING CORRESPONDENCE
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
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
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
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)
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
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
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
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
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
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
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
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
ML20195G9581999-06-0909 June 1999
Forwards Amend 227 to License DPR-49 & Safety Evaluation. Amend Revises DAEC TS by Adding New TS 3.7.9, Control Building/Standby Gas Treatment Sys (Cb/Sbgt) Instrument Air Sys
ML20195F2181999-06-0909 June 1999
Forwards Insp Rept 50-331/99-04 on 990414-0525.One Violation of NRC Requirements Identified Involving Inadequate Testing of Standby Liquid Control Sys Valves & Being Treated as non-cited Violation
ML20195D2631999-06-0707 June 1999
Forwards RAI on Third 10 Yr ISI Interval ISI Relief Requests.Addl Info Necessary to Complete Review of Request for Relief NDE-R035 Should Be Provided within 30 Days of Date of Ltr
ML20207G4931999-06-0707 June 1999
Discusses OI Rept 3-1998-023 Conducted by NRC to Determine Whether Quality Control Inspector,Employed by Spec Insp Was Discriminated Against by Being Laid Off at Plant After Raising Safety Concern
ML20207G4281999-06-0707 June 1999
Forwards Synopsis from Investigation Conducted by NRC Office of Investigations to Determine Whether Quality Control Inspector Was Discriminated Against by Being Laid Off at Duane Arnold Energy Center After Raising Safety Concern
ML20207F1431999-06-0303 June 1999
Provides Individual Exam Results for Applicant Who Took 990525 Initial License Retake Exam.Encls Withheld
ML20207B5821999-05-25025 May 1999
Advises That Rept Entitled, Criticality SE of Sf Storage Racks in Duane Arnold Energy Ctr for Max Enrichment Capability, & Holtec Rept HI-971708,dtd Aug 1997,marked Proprietary Will Be Withheld from Public Disclosure
ML20207A7981999-05-20020 May 1999
Informs That During 990319 Telcon Between K Young & M Bielby,Arrangements Were Made for Administration of Licensing Exams at Duane Arnold Energy Center for Week of 990920
ML20206N7491999-05-13013 May 1999
Forwards Safety Evaluation Accepting Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves
ML20206N4531999-05-12012 May 1999
Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created. Reorganization Chart Encl
ML20206G4821999-05-0404 May 1999
Informs That NRC Reviewed Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions & Accepts Resolution for Issue of Thermally Induced Pressurization
ML20206G5271999-05-0404 May 1999
Informs That by ,Ies Utilities,Inc Provided Changes to QA Program in Ufsar,Rev 20 for Daec.Nrc Approval Not Required Prior to Implementation of Proposed Changes
ML20205T6011999-04-23023 April 1999
Forwards Insp Rept 50-331/99-03 on 990303-0413.No Violations Noted.Inadequate Implementation of Mod to a Reactor Water Cleanup Pump Installed Resulted in Insufficient Oil Level & Subsequent Bearing Failure
ML20205G2541999-04-0101 April 1999
Forwards RAI Re GL 95-07, Pressure-Locking & Thermal- Binding of Safety-Related Power-Operated Gate Valves. Response Requested within 30 Days from Date of Ltr
ML20205D5201999-03-31031 March 1999
Requests Addl Info on GL 95-07, Pressure-Locking & Thermal- Binding of Safety-Related Power-Operated Gate Valves, Per Util 960213 Response.Response Should Provide Addl Info as Identified in Encl within 30 Days of Ltr Date
ML20205A6291999-03-26026 March 1999
Informs of NRC Planned Insp Effort Resulting from Duane Arnold Energy Ctr Plant Performance Review for Period 970928-990131.Historical Listing of Plant Issues & Details of Insp Plan for Next 8 Months Encl
ML20204J7341999-03-24024 March 1999
Forwards Insp Rept 50-331/99-01 on 990113-0302.No Violations Noted
ML20204D1831999-03-16016 March 1999
Discusses Review of Revision 20 to Section H of Plant Energy Ctr Emergency Plan
ML20207H9451999-03-11011 March 1999
Discusses Review of Rev 20 to Portions of Plant Emergency Plan.Rev Submitted Per 10CFR50.54(q)
ML20207G0111999-03-0303 March 1999
Discusses GL 96-05 Issued on 960918 & Ies Utilities,Inc Responses ,970317,980513 & 981120 for Duane Arnold Energy Center.Concludes That Licensee Established Acceptable Program to Verify design-basis Capability of MOVs
ML20203F1301999-02-10010 February 1999
Forwards Insp Rept 50-331/98-15 on 981125-990112 & NOV Re Failure to Review & Implement Applicable Procedure Requirements,Due to Sense of Urgency by Quality Control Inspector to Complete Work
ML20203F2541999-02-10010 February 1999
Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function
ML20202G4191999-02-0101 February 1999
Forwards Insp Rept 50-331/99-02 on 990119-21.No Violations Noted.Inspector Concluded That Staff Had Been Effective in Implementing C/As for Items Reviewed
ML20202B3671999-01-26026 January 1999
Forwards Safety Evaluation Addressing Thermo-Lag Related Ampacity Derating Issues & Technical Evaluation of Duane Arnold Energy Ctr Analysis of Ampacity Loads for Fire Barrier Clad Power Cables. Technical Evaluation Rept Encl
ML20202B4231999-01-26026 January 1999
Forwards Safety Evaluation of Request for Approval to Use ASME Code Case N-508-1 in ISI Program for Duane Arnold Energy Ctr.Request Authorized
1999-09-30
[Table view] |
See also: IR 05000331/1992201
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WASHINGTON, D C. 20565
Docket No. 50-331
lowa Electric Light
and Power Company
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E ATTN: Mr. Lee Liu
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V' Chairman of the Board
, :yd and Chief Executive Officer
-.e IE Towers
.. , , i P.O. Box 35)
i $$ Cedar Rapids, IA 52406
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'D *f$ ' Dear Mr. Liu:
SUBJECT: INSPECTION OF THE PROCUREMENT AND COMMERCIAL GRADE DEDICATION
PROGRAMS AT THE DUANE ARN0LD ENERGY CENTER (REPORT NO.
50-331/92-201)
This letter transmits the report of the inspection conducted May 11
through 15, 1992, at Iowa Electric Light and Power (IELP) Company's Duane
Arnold Energy Center (DAEC) by R. Pettis, S. Alexander, L. Camobell, and
S. Magruder of the Nuclear Regulatory Commission's (NRC's) Vendor Inspection
Branch (VIB) and R. Langstaff of NRC Region III. The inspection was related
to activities at the plant site authorized by NRC license DPR-49. At the
conclusion of the inspection, we discussed our findings with Mr. J. Franz,
Vice President, and the other members of your staff identified in Section 5 i
of the enclosed inspection report.
~
The inspection was conducted to review the implementation of IELP's program -
for the procure,ent and dedication o.f commercial grade items (CGIs) used in
safety-related alications at DAEC. The inspection team identified a major
program strer, in that IELP's policy was to purchase safety-related spare
and replacement items from original equipment manufacturers with approved
10 CFR Part 50, Appendix B, quality assurance programs when available, thus
reducing the number of items that need to be purchased commercial grade and
detlicated fcr use in safety-related applications. Another strength identified
was IELP's receipt inspection and testing capabilities for performing material
verification which are perform (d by independent quality control inspectors
qualified to ANS! N45.2.6.
The results of the inspection also indicate that some weaknesses existed
within IELP's program for the dedication of CGIs procured for use in safety-
related applications. These weaknesses contributed to the specific findings
that were identified during the review of dedication files for CGIs installed
or available for installation in safety-related plant systems. Examples of
these findings are that IELP did not fully verify the material of certain
CGIs, did not have provisions to fully assure material traceability and lot
homogeneity when using statistical sampling plans, did not properly classify
9212110153 921208
PDR ADOCK 0S00 1 A
. . -.
-s ,
.
Mr. Lee Liu -2-
certain valve and pump parts when using a generic classification approach, and
did not assure the calibration and control-of certain test equipment used in
the dedication process. It should be noted that the inspection team selected
for review equipment from DAEC's safety-related component list and made no
further attempts to assess individual component contribution to the system's
safety-related function,
lhis was the fourth of a series of five pilot inspections being ccoducted to
evaluate the implementation of licensee- CGI procurement and dedication
programs and to finalize an inspection procedure for future inspections of
this type. The other four inspections also identified certain weaknesses in
licensee CGI deaication programs and their implementation. The first three
inspections classified these weaknesses as deficiencies with the potential for
subsequent enforcement actions by the appropriate NRC regional of fice. - During
this period, the NRC also received significant feedback from several utilities
and from the Nuclear Management and Resources Council questioning the
regulatory basis for the CGI dedication guidance contained in NRC Generic
Letter 91-05 as well as specific interpretations of that guidance by the NRC
inspection teams.
In order for the NRC to properly respond to these concerns and to resolve
major points of contention cencerning the CGI dedication process we will be
holding public meetings with individual utilities and conducting a public
workshop which will address issues concerning-the existing dedication guidance
and specific interpretations of that guidance. Prior to the public workshop,
the proposed ir.spection procedure for future inspections will be issued for
public comment and discussion at the workshop.
In view of these pending actions, the specific observations concerning your
CGI dedication programs and implementation are classified as " findings."
Because of the need for additional discussion of the appropriate guidance for
dedication of CGis, no enforcement action will be taken based on any of the
five pilot inspections. It should be recognized, however, that some of these
findings may require corrective action-based on: (1) their potential impact on
the performance of specific equipment. -or (2) because of noncompliance with
your commitments to specific industry standards or regulatory guides endorsing
such standards. We expect that-you will evaluate the inspection findings in
view of these considerations and take appropriate corrective action as
necessary.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of
this letter and the enclosure will be placed in the NRC's Public Document
Room.
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December 8, 1992
/-
.
Mr. Lee Liu -3-
Should you have any questions concerning this inspection, we will be pleased
to discuss them with you. Thank you for your cooperation in this inspection.
Sincerely,
/
h
Jack W. Roe, Director
Division of Reactor Projects 111, IV, V
Office of Nuclear Reactor Regulation
Enclosure:
Inspection Report 50-331/92-201
cc w/ enclosure: see next page
DISTRIBUTION
Docket files 50-331/ Central Files / RIDS IE:09 CHehl, RI
PDR WHodges, R1 LPDR EMerschoff, Rll
VIB R/F AGibson, Ril DRIS R/F GWright, Rlll
JRoe BBurgess, Rlll WRussell HMiller, Rlli
FMiraglia EGreenman, Rlll ERossi RLangstaff, Rill
LNorrholm LCallan, RIV UPotapovs SCollins, RIV
RPettis RZimmerman SAlexander GGrant, OEDO
LCampbell JZwolinski SMagruder KPerkins, RV
GCwalina RPul si fer RMcIntyre CVanDenburgh, OE ,hb
o SEE PREVIOUS CONCURRENCE 3
OFC :RISl:VIB:DRil :RIS2:VIB:DRIL :RISl:VIB:DRll :RIS2:VIB:DRil : REG 10lFill :REdl\h III g
NAME :RPettis :SAlexander :LCamobell :SMaaruder :RLanastaff :GWrioht ,.
DATE :7/30/92* :7/28/92* :7/20/92* :7/22/92* : ll /h'920tkl :ll/ h /92]pN
OFC :SC:RISl:VIB ,:VIB :NRR : TECH EDITOR :DD:DkbRR :D:BRIL;4R AHNN N ,*,uty
NAME :UPotapovs f :LN;/rholm :R5anders :RZimmermaniel :CTRokWN
DATE :8/05/92* g(:I f/M/92 :WRuTsellM Z Q '
- 8/27/92* :131I /92 :121 2 /92 :W/ \/92a%
0FC :PM:PD3-3: NR :PD:PD3 NRR:AD:R3: iD:DRPW.:NRR
NAME :1RPul si f4r' :dHannon :J7wolinski (fJRoe P
DATE :ll/L /92 : 11M, /92 :11q/92 "h 12]? /92
__ - __ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ - _ - _ _ _ _ _ _ _ _ _ -
, e '+
.
December 8, 1992
Mr. Lee Liu -3-
Should you have any questions concerning this inspection, we will be pleased
to discuss them with you. Thank you for your cooperation in this inspection.
Sincerely,
/ ,
f _-
Jack W. Roe, Director
Division of Reactor Projects III, IV, V
Office of Nuclear Reactor Regulation
Enclosure:
l
Inspection Report 50-331/92-201
cc w/ enclosure: see next page
D_lSTRIBUTICI!
Docket Files 50-331/ Central Files / RIDS IE:09 CHehl, RI
PDR WHodges, RI LPDR EMerschoff, Rll
VIB R/F AGibson, RII DRIS R/F GWright, RIII
JRoe BBurgess, Rill WRussell HMiller, RllI
FMiraglia EGreenman, Rill ERossi RLangstaff, RIII
LNorrholm LCallan, RIV UPotapovs SCollins, RIV
RPettis RZimmerman SAlexander GGrant, OEDO
LCampbell JZwolinski SMagruder KPerkins, RV
GCwalina RPulsifer RMcIntyre CVanDenburgh, OE V,Jk t,
- SEE PREVIOUS CONCURRENCE . 1
c/
L, 6 F @
OFC :RISl:VIB:DRIL :RIS2:VIB:DRIL :RISl:VIB:DRil :RIS2:VIB:DRIL : REG 10A'III :REdliiNIII[p
NAME :RPettis :SAlexander :LCampbell :SMaaruder :RLannstaff :GWriaht . . I
DATE :7/30/92* :7/28/92* :7/20/92* :7/22/92* :
ll/H'92h1J :11/h /92p',5
0FC :SC:RISl:VIB ,:VIBHfd:NRR : TECH EDITOR :DD:D :D;DRil NR TYNd N
NAME :UPotapovs
RR - Q' '
I/: LN/rholm :RSanders :RZimmerman H :CTR5ksh :WRuTselle Z %*
DATE :8/05/92* /) :l f//'f/92 :8/27/92* :ll/l /92 :12] 2 /92
~ : kf/ \ L92"*lO
/3,T y cPR
OFC : PM: PD3-3 :tlRR' :PD:PD3-3.NRR:AD:R3:DR V :D:DRPW.:NRR %
NAME ::RPulsif6f :JHannon :JZwolinski ifJRoe V"
DATE :11/_L/92 :11./q/92 :11q/92 "H 11/f /92
1000$
,
. . _
.' .
.
Mr. Lee Liu -3-
Should you have any questions concerning this inspection, we will be pleased-
to discuss them with you. Thank you for your cooperation in this inspection.
Sincerely,
M
Jack W. Roe, Director
D$ vision of Reactor Projects III, IV, V
Office of Nuclear Reactor Regulation
Enclosure:
Inspection Report 50-331/92-201
cc w/ enclosure: see next page
l
.
- ___ _ _ _ _ _ _ _ _ . _ _ _
j. -
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,-
_4
Mr. Lee Liu
lowa Electric Light and Power Company Duane Arnold Energy Center
Jack Newman, Esquire
Kathleen H. Shea, Esquire
Newman and Holtzinger
1615 L Street, N.W.
Washington, D.C. 20036
Chairman, Linn County
Board of Supervisors
Cedar Rapids, Iowa 52406
lowa Electric Light and Power Company
ATTN: David L. Wilson
Plant Superintendent, Nuclear
3277 DAEC Road
Palo, Iowa 52324
Mr. John F. Franz, Jr.
Vice President, Nuclear
Duane Arnold Energy Center
3277 DAEC Road
Palo, Iowa 52324
Mr Keith Young
Manager, Nuclear Licensing
Duane Arnold Energy Center
3277 DAEC Road
Palo, Iowa 52324
U.S. Nuclear Regulatory Commission -
Resident inspector's Office
Rural Route #1
Palo, Iowa 52324
Regional Administrator, Region Ill
U.S. Nuclear Regulatory Commission
799 Roosevelt Road
Glen Ellyn, Illinois 60137
Mr. Stephen N. Brown -
Utilities Division
Iowa Department of Cammerce
Lucas Office Building, 5th Floor
Des Moines, Iowa 50319
. _ - _ _ _ -
