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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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gd t UNITED STATES 3* ., j NUCLEAR REGULATORY COMMISSION WASWNGTON, D.C. 20555-0001 g
%, .... f Scientech, Inc. E 2kO Attn: Roger J. Mattson 11821 Parklawn Drive Rockville, MD 20852
Dear Mr. Mattson:
Subject:
Contract No. NRC-04-91-068, Task Order No.15 Entitled,
" Individual Plant Examination (IPE) Reviews, Internal Events - Back-End Only (Duane Arnold)
This confirms the verbal authorization provided to Pat Love of Scientech, Inc.
on April 16, 1993, to commence work under the subject task order with a temporary ceiling of $3,500.00.
In accordance with Section G.9 entitled, " Task Order Procedures" of the subject contract, this letter definitizes Task Order No.15. The effort shall be performed in accordance with the enclosed Statement of Work.
Task Order No.15 shall be in effect from April 16, 1993 through April 15, 1994, with a total cost ceiling of $14,992.23 which is inclusive of the
$3,500.00 temporary ceiling authorized on April 16, 1993. The amount of
$13,647.00 represents the total estimated reimbursable costs, the amount of
$117.00 represents the facilities capital cost of money, and the amount of
$1,228.23 represents the fixed fee.
The obligated amount of this task order is $14,992.23.
Accounting Data for Task Order No. 15 is as follows:
APPN No.: 31X0200.360 B&R No.: 36019202300 FIN No.: L1933 OBLIGATED AMOUNT: $14,992.23 RES IDENTIFIER: RES-C93-095 The following individuals are considered to be essential to the successful performance of work hereunder: James Meyer and Mohsen Khatib-Rahbar.
The contractor agrees that such personnel shall not be removed from the effort under the task order without compliance with Contract Clause H.1, Key Personnel. .
Issuance of this task order does not amend any terms or conditions of the subject contract.
9308250290 PDR CONTR 930525 l' "f '
NRC-04-91-068 PDR .
NRC-04-91-068 "
Task Order No. 15 Page 2 ,
Your contacts during the course of this task order are:
Technical Matters: John Flack Project Officer (301) 492-3979 Contractual Matters: Edna Knox-Davin i Contract Administrator (301) 492-4731 Please indicate your acceptance of this Task Order No.15 by having an ;
official,' authorized to bind your organization, execute three copies of this document in the space provided and return two copies to the Contract i Administrator. you should retain the third copy for your records. l If you have any questions regarding this matter, please contact Edna Knox-Davin, Contract Administrator, on (301) 492-4731.
Sincerely, FaM o Mattia, Contracting Officer Contract Administration Branch No. 2
. Division of Contracts and Property Management Office of Administration
Enclosure:
As stated ACCEPTED: y NAME:
James F. - yer TITLE.
M nager, Safety Analysis Group DATE: 5/28/93 4
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- [j ENCLOSURE 1 Contract NRC-04-91-068 Scientech STATEMENT OF WORK Task Order - 15 TITLE: Individual Plant Examination (IPE) Reviews, Internal Events Back-End Only (Duane Arnold)
DOCKET NUMBER: 50-331 ,
1 NRC PROJECT MANAGER: John H. Flack, RES (301-492-3979)
NRC TEAM LEADER FOR DUANE ARNOLD: Ed Chow, RES (301-492-3984)
TECHNICAL MONITOR: John H. Flack, RES (301-492-3979)
PERIOD OF PERFORMANCE: April 16 1993 to April 15, 1994 BACKGROUND On November 23, 1988, the NRC issued Generic Letter 88-20, " Individual Plant Examination," which stated that licensees of existing plants should perform a systematic examination (IPE) to identify any plant-specific vulnerabilities to' severe accidents, and to report the results to the Commission. The purpose of the IPE is to have each utility (1) develop an overall appreciation of severe accident behavior; (2) understand the most likely severe accident sequences at its plant; (3) gain a quantitative understanding of the overall probability of core damage and radioactive material releases; and (4) reduce the overall probability of core damage and radioactive releases by modifying procedures and hardware to prevent or mitigate severe accidents. All IPE submittals will be reviewed by the NRC Staff to determine if licensees met the intent of Generic Letter 88-20.
OBJECTIVE The purpose of this contract is to solicit contractor support in order to i enhance the NRC review of licensees' IPE submittals. This contract / includes the examination and evaluation of the Duane Arnold IPE submittal, jpecifically with regard to the "back-end" analysis. The contractor review will be of limited scope and consist of a " submittal only" review. The " submittal only" ,
review and gathering of associated insights will help the NRC staff determine whether the licensee's IPE process met the intent of Generic letter 88-20, or whether a more detailed review is warranted.
By identifying the IPE's strengths and weaknesses, extracting important insights and findings, and providing a comparison to staff reviewed and accepted PSAs (e.g. NUREG-ll50, PSAs identified in NUREG-1335 Appendix B), it is expected that the NRC will be in a better position to expeditiously evaluate the licensee's IPE process. To provide support under this contract, the contractor will search for obvious errors, omissions and inconsistencies in the IPE submittal as described in the work requirements listed below.
WORK REQUIREMENTS AND SCHEDULE The contractor will perform a " submittal only" review of the Duane Arnold "back-end" IPE analysis. [The review is to include only the Level II analysis. Review of Level III (consequence analysis) is beyond the scope of this contract.) The contractor shall provide the qualified specialists and the necessary facilities, materials, and services to carry out such a review.
The contractor will utilize NRC review guidance documents for detail and reference as well as other interim guidance provided by the NRC Technical Monitor. The contractor is not expected to make a plant / site visit in order to perform this review.
Subtask 1. Review and Identification of IPE Insichts Perform a back-end " submittal only" review of each IPE submittal and identify important IPE insights by completing the NRC IPE Data Summary Sheets. (The sheets identify the information that will be entered into the IPE insights and findings data base.) During the review, focus on the areas described below under " Work Requirement." The contractor will note any: (1) inconsistencies between methodology employed in the IPE submittals and other PSA studies, (2) ,
inconsistencies between the submittal's IPE findings a' ' findings stemming from other PSAs (See NUREG-1335, Appendix B). The conu actor will respond explicitly to each work requirement by noting important review findings including any IPE strengths and weaknesses. The contractor will also list under each listed work requirement, any questions (back to the licensee) associated with the lack of appropriate information or need for further clarification. , 4 Work Reoufrement 1.1. Egrform a General Review of the Licensee's IPE Back- '
End Analytic Process:
Check the following:
l.1.1 The IPE submittal is essentially complete with respect to the level of detail requested in NUREG-1335.
1.1.2 IPE employed methodology is clearly described and justified for ;
selection. Approach is consistent with Generic letter 88-20
- Appendix 1. i 1.1.3 The IPE employed a viable process to confirm that the containment '
and containment systems represent the as-built, as-operated plant.
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1.1.4 IPE back-end had been appropriately peer-reviewed to help assure the analytic techniques were correctly applied.
Work Recuirement 1.2. Review of the containmens analysis / characterization.
Check the following:
1.2.1 The IPE analysis appropriately treated front-end and back-end dependencies, i.e., plant damage states considered reactor system / containment system availability, system mission times, inventory depletion, dual usage (spray vs. injection).
1.2.2 Classes of sequences with significant probability (those that meet the G.L. 88-20/NUREG-1335 screening criteria) were evaluated further using simplistic, but realistic, containment event trees.
1.2.3 The focus of the IPE's containment analysis was on failure modes and timing. Containment failure modes are consistent with those identified in Table 2.2 of NUREG-1335.
1.2.4 The IPE process assessed and identified contributors to containment isolation failure.
1.2.5 System / human response were integrated with the phenomenological aspects of accident progression into the containment event trees.
Allowances for recovery actions were made to allow for accident management actions.
1.2.6 The IPE submittal appropriately documented radionuclide release characterization for accident sequences exceeding the Generic Letter 88-20 (or NUREG-1335) screening criteria.
Work Recuirement 1.3. Review the cuantitative nature of the accident prooression and containment performance analysis.
Check the following: ,
1.3.1 The licensee employed a reasonable process to understand and quantify severe accident progression. The process lead to a determination of important conditional containment failure probabilities, and conrid;r;d ph:r.cmenological uncertainties, either qualitative or quantitative.
l 1.3.2 Dominant contributors to containment failure are consistent with insights from other PSAs of similar design. .
1.3.3 The IPE appropriately characterized containment performance for each of the CET end-states by assessing containment loading -
(either calculated or referenced). '
1.3.4 The containment analysis considered the impact of severe accident environments on equipment behavior.
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Work Reauirement 1.4. Review the IPE aooroach to reducina the probability of l core damaae or fission product release. l
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Check the following:
I.4.1 The IPE analysis appears to support the licensee's definition of i vulnerability, and that the definition provides a means by which the identification of potential vulnerabilities (as so defined) :
and plant modifications (or safety enhancements) is made possible. ,
1.4.2 The identification of plant improvements and proposed modifications are reasonably expected to enhance plant safety. .
Work Reauirement 1.5. Review Licensee's Response to Containment Performance ;
Jmprovement Recommenda_tjons.
Check that the licensee appropriately responded to recommendations stemming from the Containment Performance Improvement (CPI) Program, i.e., that the i i
licensee's assessment, findings, conclusions and actions (as appropriate) considered the following as a function of containment type: l BWRs (MARK I,II,III) o Harden vent o Alternative water supply for drywell spray / vessel injection ,
o Enhanced reactor pressure vessel depressurization system l reliability l 0 Implementation of Revision 4 of the BWR Owners Group EPGs I o Improved hydrogen igniter power supply (Mark-III) I
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Additional for BWR (MARK III) o Evaluation of vulnerability to interrupted power supply to hydrogen igniters and need for improvement PWR Ice Condenser Containments .
o Evaluation of vulnerability to interrupted power supply to hydrogen igniters and need for improvement PWR Dry Containments o Evaluation of containment and equipment vulnerabilities to hydrogen combustion (local and global) and need for improvement. This would include consideration of gaseous pathways between the cavity and the upper containment volume to confirm adequate communication to promote natural ~
circulation and recombination of combustible gases in the reactor cavity.
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t Work Reouirement 2.0 Comqlete data sheets.
- Complete the NRC data summary sheets and note any lack of information as appropriate.
Subtask 2. Preoare Technical Evaluation Reoort Prepare a report with the outline provided below.
I. Introduction Provide a brief overview of the IPE review, the scope and depth as appropriate. Place emphasis on review areas identified as being important and rationale for importance, i.e., found to be important in ,
other PSAs of similar design. Discuss any important or unique plant characteristics. Note plants with similar features and any important ,
insights stemming from other relevant PSA studies.
II. Contractor Review Findings Explicitly address each work requirement element listed under subtask I,
" Review and Identification of IPE Insights." Discuss any strength or weakness so identified and significance with respect to the overall IPE effort. Identify any additional information (in the form of questions back to the licensee) which would be important to the review effort. i Indicate why the information is important for closure. ,
III. Overall Evaluation and Conclusion Summarize the " submittal only" review conclusions based on the ;
information submitted and significance of IPE strengths and weaknesses.
IV. IPE Evaluation and Data Summary Sheets f I
Attach the IPE Data Summary Sheets. l
, i REPORT REQUIREMENTS l
Technical Reports The contractor will submit to the NRC technical monitor four copies of the Technical Evaluation Report (TER) six weeks after the initiation of -this task order. Copies will include one hard copy and one 3.5" computer diskette i version (Wordperfect 5.1 or other IBM PC compatible software acceptable to the - '
NRC IPE Team Leader). The TER shall summarize all findings, results, and If conclusions in the areas examined in the format described under Task 2.
the contractor finds that the licensee's IPE is obviously deficient ~ in any of ' j the areas examined, the technical monitor should be notified in advance. '
Deficient or weak areas should be clearly documented in the technical evaluation report. In addition, if the contractor finds that there are 5 l I
specific areas that need additional in-depth review, the Team Leader should be notified of the areas, and provided with the rationale for subsequent review.
The contractor shall meet with the NRC staff after submittal of the TER to present and discuss its findings, results, and conclusions.
The NRC staff shall review the TER submittal, prepare questions for the licensee, and submit a package for the licensee's response within two to three weeks after the contractor's presentation. The licensee is given at least 60 days to respond to NRC's questions. Upon receipt of the licensee responses, the NRC staff will review the responses against the TER within one to two months after the receipt of the responses to determine the need for further clarification. If further clarification is required, the contractor shall provide NRC with their response.
The contractor should allow for one day of effort to provide NRC with quick-turn-around reviews of licensee's comments or responses to the TER and/or questions.
BUSINESS LETTER REPORT The contractor shall provide monthly progress reports in accordance with the requirements of the basic contract.
HEETINGS AND TRAVEL
'One, one person trip to NRC Headquarters to present and discuss review .
findings and conclusions.
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NRC FURNISHED MATERIAL Licensee's IPE submittal.
TECHNICAL DIRECTION i
The NRC Project Manager is: !
John H. Flack Severe Accident Issues Branch i Division of Safety Issue Resolution U.S. NRC, Mail Stop NL/S 324 Washington, D.C. 20555 Telephone No. (301) FTS-492-3979
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