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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 05000331/1998007
Text
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.
,
May 12,1998
Mr. John F. Franz, Jr.
Vice President, Nuclear
IES Utilities, Inc.
200 First Street SE
P. O. Box 351
Cedar Rapids, IA 52406-0351
SUBJECT: DUANE ARNOLD RADIATION PROTECTION INSPECTION REPORT
50-331/98007(DRS) AND NOTICE OF VIOLATION
Dear Mr. Franz:
On May 4,1998, the NRC completed an inspection at your Duane Amold Energy Center. The
enclosed report presents the results of this inspection.
The inspection was an examination of activities conducted under your license as they relate to
radiation safety and to compliance with the Commission's rules and regulations and with the
conditions of your license. The inspection consisted of a selective examination of procedures
and representative records, observations, and interviews with personnel. Specifically, the
inspection focussed on radiological planning and controls for refueling outage work and a
review of previous inspection issues. On May 1,1998, the NRC also received and reviewed
additionalinformation conceming post accident sampling and analysis of the containment
atmosphere.
Six violations of NRC requirements were identified during this inspection. One violation
concemed the failure to perform an adequate survey to identify potential radiological hazards
incident to the April 4,1998, low pressure core injection system full flow testing. Two violations
were identified conceming the posting of a high radiation area in the torus and lapses in post ;
accident sampling system training for three chemistry technicians. Three additional violations
concemed the failure of your staff to adequately adhere to radiation protection procedures and
work controls. We are concemed that the latter three violations are similar to previous
violations documented by the NRC concoming personnel adherence to radiological work ,
controls, indicating continuing lapses in your staff's attention to radiation protection
requirements and in communications. We are also concemed that NRC-identifMKl post accident
sampling system training problems were not thoroughly evaluated by your staff, which resulted
in a violation of NRC requirements.
'
During the inspection, we also observed weaknesses in the planning and control of diving
evolutions in the torus, which resulted in two of the violations described above. Based on these
observations, we concluded that your staff had not fully evaluated NRC generic
communications and recommendations addressing diving evolutions near underwater radiation
sources. We also observed weaknesses in management oversight of the torus diving which
appeared to contribute to the violations associated with this evolution. Weaknesses in
management oversight also appeared to contribute to problems identified concerning the post
9eosanoo64 9eosta
PDR ADOCK 05000331
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_ - ------- _ - _ _ _ __,
s' ,
.
! J. Franz, Jr. 2
l
accident sampling system. For example, chemistry management was unaware of lapses in
technician training on the system. Further, we identified that your staff's actions to address
post accident sampling system problems concerning atmosphere iodine sampling were not
timely.
Notwithstanding the violations and associated problems, we did recognize some strengths in
radiation protection performance. Specifically, your staff maintained effective oversight of
outage dose performance to ensure that work progress was consistent with dose goals. In
addition, the radiation protection staff's review of shielding installation and removal was
thorough and addressed lessons learned from previous outage performance.
The violations are cited in the enclosed Notice of Violation (Notice), and the circumstances
surrounding them are described in detail in the enclosed report. Please note that you are ,
required to respond to this letter and should follow the instructions specified in the enclosed
Notice when preparing your response. The NRC will use your response, in part, to determine
whether further enforcement action is necessary to ensure compliance with regulatory
requirements.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its
enclosures, and your response to this letter will be placed in the NRC Public Document Room.
We will gladly discuss any questions you have concerning this inspection.
Sincerely, l
Original Signed by John A. Grobe
John A. Grobe, Director
Division of Reactor Safety
Docket No. 50-331 !'
License No. DPR-49
l
1
Enclosures: 1. Notice of Violation
2. Inspection Report 50-331/98007(DRS)
cc w/encis: L. Root, President and
Chief Operating Officer
G. Van Middlesworth,
Plant Manager
U . E. Peveler, Manager,
Regulatory Performance
Chairperson, Iowa Utilities Board j
N
DOCUMENT NAME: G:\DRS\DUA98007.DRS (SEE PREVIOUS CONCURRENCE)
t c.~. . .. o, u. *>e, nup.i. m e,. w c cm -%ui .n.a.,n.nv ,. r . cm .na .=,. v . % em
OFFICE Rlli l Rlli l Rlli Rill mf)( ;
NAME SOrth:Jp W GShear < RLanskbury 4 JGrobb K"
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i
DATE 05/ /98 05/ /98 05/ /98 05/\T98 \
OFFICIAL RECORD COPY \
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- - - _ - _ _ _ _ _ _- - - _ _ _ _ - _ - _ _ _ _ - _ _ - _ _ -
- -
l. l
J. Franz, Jr. 2
accident sampling system. For example, chemistry management was unaware of lapses in
technician training on the system. Further, we identified that your staff's actions to address
post accident sampling system problems conceming atmosphere iodine sampling were not
!
timely.
!
However, we did recognize some strengths in radiation protection performance. Your staff !
maintained effective oversight of outage dose performance to ensure that work progress was
consistent with dose goals. In addition, the radiation protection staff's review of shielding
installation and removal was thorough and addressed lessons learned from previous outage i
l
performance.
>
i
The violations are cited in the enclosed Notice of Violation (Notice), and the circumstances
surrounding them are described in detail in the enclosed report. Please note that you are
required to respond to this letter and should follow the Instructions specified in the enclosed
Notice when preparing your response. The NRC will use your response, in part, to determine
whether further enforcement action is necessary to ensure compliance with regulatory
requirements,
in accordance with 10 CFR 2.790 of the NRC's Rules of Practice," a copy of this letter, its
enclosures, and your response to this letter will be placed in the NRC Public Document Room.
!
We will gladly discuss any questions you have concerning this inspection. !
Sincerely,
l
John A. Grobe, Director l
Division of Reactor Safety
Docket No. 50-331
i License No. DPR49
,
Enclosures: 1. Notice of Violation
2. Inspection Report 50-331/98007(DRS)
<
cc w/encis: L. Root, President and
, Chief Operating Officer
! G. Van Middlesworth,
i Plant Manager
l K. E. Peveler, Manager,
!
Regulatory Performance
Chairperson, Iowa Utilities Board
DOCUMENT NAME: G:\DRS\DUA98007.DRS:
1. .. ., ~ . - c.. - . _ _ . . ~ . - v . ~
OFFICE Rll! [6 Rlli ggp lE Rlli l A) Rlli l
NAME SOrth:Jp 6G k - GShear 6t,5 RLarf4)urygA @ JGrobe
DATE 05/ll/98 05//i/98 05/c/98 05/ /98
OFFICIAL RECORD COPY
- - -. - _ _ _ - _ _ _ _ . _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ - - - _ - _ _ _ . _ _ _ - _ - _ - _ _ _ _ -
g. ',,
D'
'
.
,~ J. Franz, Jr. 3
Distribution:
Project Mgr., NRR w/encls
A. Beach w/encls
J. Caldwell w/encls
B. Clayton w/encls
SRI Duane Arnold w/encls
DRP w/encls
TSS w/encls
DRS w/encls
Rlll PRR w/encls
PUBLIC IE-01 w/encls
Docket File w/encls
GREENS
LEO (E-Mail)
DOCDESK (E-Mail)
)
~()OOO2
