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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
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Docket No. 50-331 Iowa Electric Light and Power Company ATTN: Mr. Lee Liu Chairman of the Board and Chief Executive Officer IE Towers P. O. Box 351 Cedar Rapids, IA 52406 Dear Mr. Liut SUBJECT OPERATOR AND SENIOR OPERATOR LICENSING EXAMINATIONS In a telephone conversation between Mr.-F. VanEtten, Training Supervisor, and Mr. H. Bielby, Principal Examinor, arrangements wern-made for the administration of licensing excminations at'the Duane Arnold Energy Center..
The written and operating examinations are scheduled for the week of June 7, 1993.
In order for us to meet this schedule, it will be necessary for the facility to furnish the approved reference material-listed in Enclosure 1, " Reference Material Requirements for Reactor / Senior.
Reactor Operator Licensing Examinations" at least 60 days prior to the examination date. Any substandard or incomplete material or delay in receiving approved properly bound and indexed referenco material may_ result in a delay in administering the examinations. Mr. F. VanEtten has been advised of our reference material requirements, the number of reference material sets that are required, and the examiners' names and addresses where each' set is to be mailed.
The facility management is responsible for providing adequate space and accommodations in order-to-properly _ conduct the written examinations. Enclosure 2, " Requirements for Administration of Written. Examinations," describes our_ requirements for conducting _
these examinations. Mr. F. VanEtten has also been-informed of these requirements.
Enclosure 3'contains the Rules and Guidelines that will bo in effect during the administration of the written examination. The facility management is responsible for ensuring that all applicants are aware of these rules.
080000:
9302100010 930203 PDR- ADDCK 05000331' I V PDR
- A
Iowa Electric Light and Power 2 IIO 'O 6G3 Company
, The facility staff review of the written examination will be conducted in accordance with requirements specified in Enclosure 4, " Requirements for Facility Review of Written Examinations." Mr. . VanEtten has been informed of these requirements.
To better document simulator examinations, the Chief Examiner ;
will have the facility simulator operator record predetermined !
plant conditions (i.e., plant pressure, temperature, preasurizar !
level, etc.), for each simulator scenario. The applicants will !
be responsible for providing this information with any appeal of a simulator operating examination. Therefore, the facility !
training staff should retain the simulator examination scenario information until all applicants who took the examinations have either passed the operating examination, accepted the denial of their license, or filed an appeal.
Preliminary reactor operator and senior reactor operator license applications should be submitted at least 30 days before the first examination dates so that we will be able to review the training and experience of the candidates, process the medical certifications, and prepare final examiner assignments after applicant eligibility has been determined. If the applications are not received at least 30 days before the examination dates, it is likely that a postponement will be necessary. Final signed applications certifying that all training has been completed shall be submitted at least 14 days before the first examination date. However, if processing of a license application is not completed in time to make a determination of applicant eligibility, the candidate shall not be permitted to sit for the examination. Therefore, it is recommended that license applications be provided as soon as possible to ensure an appropriate level of review.
This request is covered by Office of Management and Budget (OMB) clearance Number 3150-0101 which expires May 31,-1995. This estimated average burden is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response, including gathering, copying and mailing the required material. Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reducing this burden, to the Information and-Records Management Branch, MNBB-7714, Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555; and to the Paperwork Reduction Project (3150-0101), Office of Information and Regulatory Affairs, NEOB-3019, Office of Management'and Budget, Washington, D.C. 20503.
~ ,_ -._ _ _ - . _ . . _ _ _ _ _ _ _ _ . _ _ . . . _ _ _ . ._ . . _ _ _ _ _ - - _ _ . .._
Iowa Electric Light and Power 3 FEB - 31993 Company Thank you for your consideration in this matter. If you have any questions regarding the examination procedures and requirements, please contact R. Doornbos, Chief Examiner at (708) 790-5601.
Sincerely, original signed by !! ark A. Ring Mark A. Ring, Chief operations Branch
Enclosures:
- 1. Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations
- 2. Requirements for Administration of Written Examinations
- 3. NRC Rules and Guidelines For Written Examinations
- 4. Requirements for Facility Review of Written Examinations cc w/ enclosures:
D. Wilson, Plant Superintendent - Nuclear K. Young, Manager, Nuclear Licensing DCD/DCB (RIDS)
OC/LFDCB Resident Inspector, RIII Stephen Brown, Iowa Dept.
of Commerce S. L. Swalls, Plant Training Manager cc w/o enclosures:
R. M. Pulsifer, Project Manager, NRR R. M. Gallo, Branch Chief, OLB R. D. Lanksbury, Section Chief,-DRP R RIII R 1I{@6 lby/cg Jord n ng 02/j /93 G2/$/.03 02fp/93
t ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS
- 2. Existing learning objectives, Job Performance Measures and lesson plans (including training manuals, plant orientation manual, system descriptions, reactor theory, thermodynamics, ;
etc.)
A copy of the facility Job and Task Analysis (JTA), ,
specifying the knowledges and abilities required of an I operator at the facility. Each particular Knowledge and/or !
ability will include an importance rating correlating it to ensuring the health and the safety of the public. If a JTA is not furnished, the Knowledgou and Abilities catalog for :
Nuclear Power Plant Operators, HUREG-1122 (1123) will be ;
used to establish content validity for the examination.
All Job Performance Measures (JPMs) used to ascertain the computence of the operators in performing tasks within the control room complex and, as identified in the facility JTAs, outside of the control room, i.e., local operations.
Training materiala should include all substantive written material uaed for preparing applicants for initial RO and SRO licensing. The written material should includo learning objectives and the details presented during lectures, rather than outlines. Training materials should be idontified by plant and unit, bound, and indexed. FAILURE TO PROVIDE COMPLETE, PROPERLY BOUND AND INDEXED PLANT REFERENCE MATERIAL MAY RESULT IN Tilt RETURN OF THE MATERIAL TO TiiE PERSON WHO IS THE HIGHEST LEVEL OF CORPORATE MANAGEMENT WHO IS RESPONSIBLE FOR PLANT OPERATIONS (E.G., VICE PRESIDENT OF NUCLEAR OF NUCLEAR OPERATIONS). ACCOMPANYING THE MATERIAL WILL BE A COVER LETTER EXPLAINING THE DEFICIENCIES IN THE REFERENCE MATERIAL AND Tile FACT TIIAT THIS WAS THE REASON THE EXAMINATIONS WERE CANCELLED OR POSTPONED. Training materials which include the following should be provided.
- System descriptions including descriptions of all operationally relevant flow paths, components, controls and instrumentation. System training material should draw parallels to the actual procedures used for operating the applicable system.
- Complete and operationally useful descriptions of all safety-system interactions and, where available, BOP system interactions under emergency and abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment
- failure.
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- Enclosure 1 (Cont'd) j r
- Training material used to clarify and strengthen understanding of emergency operating procedures.
- 2. Complete Procedure Index (including surveillance procedures, etc.)
- 3. All administritive procedures (as applicable to reactor
! operation or safety)
J e 4. All integrated plant procedures (normal or general operating procedures)
- 5. All omergency procedures (crorgency instructions, abnormal or special procedures)
- 6. Standing orders (important orders that are safety-related and may supersede the regular procedures) ,
- 7. Surveillance procedures (procedures that are run frequently, i.e., weekly or that can be run on the simulator) 8.
Fuel-handling and core-loading procedures, (initial core-loading procedure, when appropriate)
- 9. All annunciator / alarm procedures
, 10. Radiation protection manual (radiation control manual or procedures)
Emergency plan implementing procedures 11.
- 12. Technical Specifications (and interpretations, if available) '
for all units for which licenses are sought.
- 13. System operating procedures
- 14. Piping and instrumentation diagrams, electrical single-line diagrams, or flow diagrams
- 15. Technical Data Book, and/or plant curve information as used by operators and facility precautions, limitations, and set points (PLS) for the facility
- 16. Questions and answers specific to the facility training ,
program which may be used in the written or operating examinations (voluntary by-facility licensee)
- 17. The following on the plant reference simulation facility
- a. List of all preprogrammed initial conditions
a Enclosure 1 (Cont'd)
- b. List of all preset malfunctions with a clear identification number. The list should include cause and effect information. Specifically, for each malfunction a concise description of the expected result, or range of results, that will occur upon implementation should be provided. Additionally, an indication of which annunciators are to be initially expected should be given.
< c. A description of simuistor failure capabilities for valves, breakers, indicators and alarms
- d. Where the capability exists, nn explanation of the ability to vary the severity of a particular mealfunction shall be provided, i.e., ability to vary t's size of a given LOCA or steam leak, or the ability tb cause a slow failure of a component such as a feed pump, turbine generator or major valve (e.g., dr.ifting
< shut of a main feedwater control valve)
- c. An identification of modeling conditions / prob 1cmo that '
may impact the exaraination
- f. Identification of any'known performance test discrepancies not yet corrected
- g. Identification of differences between the simulator and the reference plant's control room
- h. Copies of facility generated scenarios that expose the applicants to situations of degraded pressure control (PWR), degraded heat removal capability (PWR' and BWR) and containment challenges (PWR and BWR) may be provided (voluntary by licensee)
- 1. Simulator instructors manual (voluntary by licansee)
- j. Description of the scenarios used for the training class (voluntary by licensee)
- 18. Additional material. required by the examiners to develop examinations that meet the requirements of these Standards and the regulations.
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Enclosure 1 (Cont'd) 1 4 The above reference material shall be approved, final issues and I
- uhall be ao marked. If a plant has not finalized some of the 4
material, the chief Examiner shall verify with the facility that the most complete, up-to-date material is available and that l agreement has been reached with the licensee for limiting changes 4 before the adelnistretion of the examination. All procedures and retcrence matorial shall be bound with appropriate indices or tables of contents so that they can be used efficinntly. Failure
- to provide complete, properly bound and indexed plant reference material could result in cancellation or rescheduling of the
{ examinations.
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e EHCLQSPRE 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. A singlo room shall be provided for administration of the written examination. The location of this room and supporting restroom facilities shall be such as to provent contact with all other facility and/or contractor personnel during the written examination. If necessary, the facility should make arrangement for the use of a suitable room at a loca'. school, motel, or other building. Obtaining this room is 'no responsibility of the licensee.
- 2. M' aimum spacing is required to ensure examination integrity ts determined by the Chief Examinor. Minimum spacing should be one applicant por table, with a three-foot space between tables.
- 3. Suitable arrangements shall be mado by the facility if the applicants are to have lunch, coffee or other refreshments.
Those arrangements shall comply with 7. tom 1 above and shall be reviewed by the examiner and/or proctor.
- 4. Applicants may bring pens, pencils, calculatora or slido rules into the examination room. Only black ink or dark pencils should be used for writing answers to questions.
- 5. The licensee shall have one not of steam tables available for each applicant. The examinor shall distribute the steam tables to the applicants if necessary. No wallfcharts,_
models, and/or other training materials shall be present in the examination room. No other equipment or reference material chall be allowed unless provided by the anaminor.
- 6. The facility staff shall be provided with a copy of the written examination and answer key after the last candidato han handed in his written examination. The facility staff shall have five working days to provide formal written comments with supporting documentation regarding written examination questions and answers to the Chief Examinor.
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ENCLOSURE _2 PROCEDURES FOR T!!E ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. Check identification badges.
- 2. Paar out examinatione and all handouts. Remind applicants not to review examination until instructed to do so.
READ THE FOLLOWING INSTRUCTItNS VERDATIM:
During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination. This must be done af ter ycu complete the examination. ,
READ Tile FOLLOWING INSTRUCTIONS:
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- 1. Restroom trips are to be limited and only one applicant at a time may leave. You must avoid all contacts with anyone outside the examinatiore room to avoid even the appearance or possibility of cheating.
- 2. Use black ink or dark pencil 2nly to facilitate legible reproductions.
- 3. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer )
sheet.
- 4. Mark your answers on the answer sheet provided. USE ONLY TiiE PAPER PROVIDED AND DO NOT WRITE ON TiiE BACK SIDE OF Tile PAGE.
- 5. The point value for each question in indicated in (brackets) after the question.
- 6. Partial credit uhy be given on matching questions. Partial credit will NOT be given on multiple choice questions.
- 7. If the intent of a question is unclear, ask questions of the exeminer only.
- 8. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets.- In addition, turn in all scrap paper.
Enclosure 3 (Cont'd)
- 9. To pass the examination, you must achieve a grade of 80% or greater.
- 10. There is a. time limit of four (4) hours for completion of ,
the examination.
- 11. Wh6.. you are dono and have turned in your examination, leave the examination area (DEFINE THE AREA). If you are found in this area while the examination is still in progress, your license may be denied or revoked.
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ENCLOSURE 4 REQUIREMENTS FOR FACILITY REVIEW OF WRITTEN EXAMINATIONS
- 1. At the option of the Section. Chief,.the facility may review-the written examination up to two weeks prior to its administration. .This review may take place at the facility or in the Regional office. The Chief Examiner will coordinate the details of the review with the facility. hn-NRC examiner will always be present during the'reviewe
, Whenever this option:of examination review is utilized,' the facility reviewers will sign the attached statement prior to-
'being allowed access to the examination. The examination or- i written notes-will_HQT,be retained by the. facility.
In adaition, the. facility staff reviewers will sign the agreement:after the written examination has been-administered.
- 2. Regardless of whether the above e).taination review option is-exercised, immediately following .the administration of the written examination, the facility ritaff shall be .provided a copy of the examination and:the answer key. The copy of the written examination shall include. pen and ink changes made to questions during the examination. administration.
If the facility did not review the examination: prior to its administration, they will have five (5). working days from the day'of the written examination to' submit formal comments. If-the' facility reviewed the examination prior to its administration, any additional. comments must be given tx) .
- an examiner prior to his/her leaving the site at the end-.of I
the week of the written examination administration. 'Ir
( either case,.the comments willLbe addressedLto the i_
responsible Regional Office by'the highest onsite level of-corporate management for plant. operations,Le.g..,,Vice.
-President 1for Nuclear Operations. A. copy of the' submittal will be' forwarded tx) the-Chief' Examiner, as appropriate.
Comments not isubmitted within the required' time : frame Lwill:
be considered for. inclusion in the grading' process on a l
case-by case basis by the RegionalcOffice Section_ Chief.-
! Should the comment submittal deadline not be met,Ja long delay in-grading'the~ examinations ~may occur.
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REQUIREMENTS FOR FACILITY REVIEW-OF WRITTEN EXAMINATION (Cont'd) . .
b 3. -The following format should be adhered-to-for submittal of' j specific comments:
- a. Listing of NRC Question,; answer.and reference
- - b. Facility comment / recommendation- J
- c. Reference (to support facility' comment) i No change to the examination will be made without-
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submittal'ofEa reference to support-the facilityL comment. Any_' supporting documentatio.tthat1was-
! not previouslyLsupplied-should-be provided..
- 2..- -Comments made without_a concise facility? +
1 recommendation'will not be addressed.
'4 . A two-hour post examination review may be--held at the discretion of-the Chief Examiner.- If this review is held,-
r the. facility staff should'be informed that only written -i comments that are properly supported <will be; considered'irn ;
the grading of the= examination.
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EXAMINATION SECURITY AGREEMENT
- 1. Pre-Examination I acknowledge that I have acquired specialized knowledge concerning the referenc d examination (s) as of the date of my signature and agree that I.will not knowingly divulge any information concerning the_ examination (s) to any unauthorized persons.-- I understand-that i am not-to participate in any, instruction. involving those applicants, operators or senior operators scheduled to be administered the referenced examination (s) from this date until completion.of examination administration. I further understand that violation of'the conditions of this .
agreement may result in cancellation of the. examination (s)_
and/or enforcement action against myself or the facility' licensee by-whom I am employed or represent.
- 2. post-Examination I did not,-to the best of my! knowledge, divulge any information concerning the referenced examination (s) :ta) any 1 unauthorized _ persons. I did'not participate in providing any instruction to those' applicants,-operators andLsenior operators who were administered the : referenced examination (s) from the date that I entered into this security agreement until the completion of examination administration.
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EXAMINATION SECURITY AGREEMENT Facility -
Examination Dates N/A if not applicable.
Initial Exam Dates - / /' to / /
Requal Exam Dates -
/ / to /, / _
Signature below indicates compliance with the appropriate pre- or post-examination agreement statement.
t PRE-EXAMINATION SIGNATURE & DATE POST-EXAMINATION INITIAL REQUALIFICATION SIGN & DATE 4D shWE O
ese
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