Letter Sequence Request |
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MONTHYEARNG-92-3961, Forwards Response to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46. Util Commits to Use SQUG Methodology, Per Rev 2 to Generic Implementation Procedure1992-09-21021 September 1992 Forwards Response to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46. Util Commits to Use SQUG Methodology, Per Rev 2 to Generic Implementation Procedure Project stage: Request ML20198E3111992-11-25025 November 1992 Forwards Safety Evaluation Accepting Licensee Response to Suppl 1 to GL-87-02,committing to Entire GIP-2,including Both SQUG Commitments & Implementation Guidance Project stage: Approval ML20129B5831996-10-21021 October 1996 Ack Receipt of 951115 Summary Rept for Resolution of USI A-46.Addl Info Requested.List of Questions Also Encl Project stage: Other ML20135A6951997-02-25025 February 1997 Forwards RAI Re Summary Rept for Resolution of USI A-46, Submitted on 951115 Project stage: RAI ML20212G8211997-10-29029 October 1997 Forwards RAI Re Licensee 951115 Submittal of Summary Rept Re Resolution of USI A-46 for Duane Arnold Energy Ctr. Response Requested within 60 Days of Receipt of Ltr Project stage: RAI ML20199F2651997-11-18018 November 1997 Forwards Request for Addl Info Re Resolution of USI A-46. Encl RAI Revises Questions Contained in NRC . Response Requested within 60 Days Project stage: RAI ML20236X5181998-07-29029 July 1998 Forwards SE on Resolution of USI A-46 Implementation Program at Plant.Staff Determined That Util C/As & Completed Physical Mods for Resolution of Outliers Will Result in Safety Enhancement Beyond Original Licensing Basis Project stage: Approval 1997-10-29
[Table View] |
Forwards Response to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46. Util Commits to Use SQUG Methodology, Per Rev 2 to Generic Implementation ProcedureML20118B079 |
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Site: |
Duane Arnold |
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Issue date: |
09/21/1992 |
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From: |
Franz J IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
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To: |
Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
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References |
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REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, NG-92-3961, NUDOCS 9209290394 |
Download: ML20118B079 (52) |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N5521999-10-21021 October 1999 Forwards Operator Licensing Exam Rept 50-331/99-302(OL) for Tests Administered During Wk of 990920.Six Applicants Passed All Sections of Exam & Were Issued Operating Licenses ML20217H8921999-10-18018 October 1999 Forwards SER Accepting Eight of Licensee Relief Requests, NDE-R001,(Part a & B),NDE-R027,NDE-R028,NDE-R029,NDE-R030, NDE-R032 & NDE-R035,one Request Relief NDE-R036,denied & Relief Request NDE-R034 Unnecessary ML20217F4801999-10-14014 October 1999 Provides Individual Exam Results for Applicants Who Took Sept 1999 Initial License Exam.Informs That Info Considered Proprietary & That Listed Info,Supplements & Exam Rept Will Be Issued Shortly NG-99-1405, Informs That Util Has Completed Addl Review to Ensure That All Related Requirements for Repair/Replacements Have Been Addressed,Per Util Requesting Approval of Several Inservice Insp Relief Request1999-10-0808 October 1999 Informs That Util Has Completed Addl Review to Ensure That All Related Requirements for Repair/Replacements Have Been Addressed,Per Util Requesting Approval of Several Inservice Insp Relief Request NG-99-1383, Forwards Response to NRC 990930 RAI on TS Change Request TSCR-010 Re Excess Flow Check Valve SRs1999-10-0808 October 1999 Forwards Response to NRC 990930 RAI on TS Change Request TSCR-010 Re Excess Flow Check Valve SRs ML20217F7221999-10-0707 October 1999 Forwards Insp Rept 50-331/99-11 on 990820-0930.No Violations Noted ML20212L0411999-10-0505 October 1999 Informs That Privacy Info Identified in Util Re Duane Arnold Energy Center Emergency Telephone Book,Rev 61 Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(a)(6) & Section 103(b) of Atomic Energy Act NG-99-1358, Forwards DAEC plant-specific Response to 990927 RAI Re TS Change Request on Excess Flow Check Valve Surveillance requirements.TSTF-334,included1999-10-0505 October 1999 Forwards DAEC plant-specific Response to 990927 RAI Re TS Change Request on Excess Flow Check Valve Surveillance requirements.TSTF-334,included NG-99-1378, Clarifies TS Change Requests for Revised Safety Limit Min Critical Power Ratio.Approval of 990510 & 0716 Application for Amends to License DPR-49 Requested Prior to Scheduled Start of Cycle 17 & Effective Date No Earlier than 9910221999-10-0404 October 1999 Clarifies TS Change Requests for Revised Safety Limit Min Critical Power Ratio.Approval of 990510 & 0716 Application for Amends to License DPR-49 Requested Prior to Scheduled Start of Cycle 17 & Effective Date No Earlier than 991022 NG-99-1327, Forwards IST Relief Request VR-24 Re Excess Flow Check Valve Test Frequency,Per 10CFR50.55a(a)(3)(i),for NRC Approval1999-10-0404 October 1999 Forwards IST Relief Request VR-24 Re Excess Flow Check Valve Test Frequency,Per 10CFR50.55a(a)(3)(i),for NRC Approval ML20212J8761999-09-30030 September 1999 Forwards RAI Re Util 990412 Request to Revise Duane Arnold Energy Ctr TS SR 3.6.1.3.7 to Allow Representative Sample of Reactor Instrumentation Line EFCV to Be Tested Every 24 Months,Instead of Testing Each EFCV Every 24 Months ML20217A9331999-09-30030 September 1999 Informs That NRC Plan to Conduct Addl Insp by Resident Inspectors Beyond Core Insp Program Over Next 7 Months to Assess Preparation for Implementation of Refuel Outage Activities.Historical Listing of Plant Issues Encl ML20212H2121999-09-27027 September 1999 Forwards Request for Addl Info Re 990412 Licensee Request to Revise DAEC TS SR 3.6.1.3.7 to Allow Representative Sample of Reactor Instrumentation Line EFCV to Be Tested Every 24 Months,Instead of Testing Each EFCV Every 24 Months ML20212H2151999-09-22022 September 1999 Forwards Amend 228 to License DPR-49 & Safety Evaluation. Amend Revises DAEC TS SR 3.4.3.1, Safety/Relief Valves & Safety Valves NG-99-1262, Forwards License Renewal Application for G Thullen,License SOP 30232-2.Thullen Has Completed Requalification Program for Daec.Encls Withheld,Per 10CFR2.790(a)(6)1999-09-20020 September 1999 Forwards License Renewal Application for G Thullen,License SOP 30232-2.Thullen Has Completed Requalification Program for Daec.Encls Withheld,Per 10CFR2.790(a)(6) NG-99-1214, Forwards Voluntary Info Requested in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Re Estimated Number of Operator Licensing Exams & Applicants for Years 2000 Through 20031999-09-15015 September 1999 Forwards Voluntary Info Requested in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Re Estimated Number of Operator Licensing Exams & Applicants for Years 2000 Through 2003 NG-99-1278, Forwards Corrected TS Page 3.3-52 Re TS Change Request TSCR-003,removing Requirements for Hpcis & Rcics Isolation Manual Initiation Instrumentation.Page Indicates Deletion of Condition G as Well as or G from Condition H1999-09-15015 September 1999 Forwards Corrected TS Page 3.3-52 Re TS Change Request TSCR-003,removing Requirements for Hpcis & Rcics Isolation Manual Initiation Instrumentation.Page Indicates Deletion of Condition G as Well as or G from Condition H ML20212A8711999-09-14014 September 1999 Informs That 990716 Application Which Submitted Affidavit & Attachment Re Addl Info Re Cycle Specific SLMCPR for Plant Cycle 17, June 1999,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) NG-99-1249, Requests Exemption from Certain Requirements Applicable to ECCS Evaluation Models Performed IAW App K to 10CFR50 for DAEC1999-09-10010 September 1999 Requests Exemption from Certain Requirements Applicable to ECCS Evaluation Models Performed IAW App K to 10CFR50 for DAEC NG-99-1252, Informs That There Is No Longer Need for Any Waiver Associated with Senior Operator License Application for MR Pettengill Due to Completion of All Five Manipulations1999-09-0909 September 1999 Informs That There Is No Longer Need for Any Waiver Associated with Senior Operator License Application for MR Pettengill Due to Completion of All Five Manipulations NG-99-1192, Forwards marked-up Copies of Affected Tables & Ref Matl Which Supports Changes Re DAEC Reactor Vessel Integrity Database (Rvid),As Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity1999-09-0808 September 1999 Forwards marked-up Copies of Affected Tables & Ref Matl Which Supports Changes Re DAEC Reactor Vessel Integrity Database (Rvid),As Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20211M5621999-09-0202 September 1999 Forwards Insp Rept 50-331/99-08 on 990712-16 & 0810-12.No Violations Noted.Insp Consisted of Review of Source Term Reduction & Integration of ALARA Into Work Planning & Execution,Calibration & Maint NG-99-1216, Requests Waiver to Allow MR Pettengill to Participate in Upcoming Senior Operator Examination on 990920.Util Intends to Ensure That Pettengill Completes All Five Required Manipulations as Soon as Possible1999-09-0101 September 1999 Requests Waiver to Allow MR Pettengill to Participate in Upcoming Senior Operator Examination on 990920.Util Intends to Ensure That Pettengill Completes All Five Required Manipulations as Soon as Possible NG-99-1182, Forwards Certified License Applications IAW Provisions of Examiner Standard (ES)-201 for SA Arebaugh,Sd Bahnsen,Jd Kalamaja,Ja Miell,Bd Musel & MR Pettengill.Encls to Ltr Withheld Per 10CFR2.790(a)(6)1999-08-31031 August 1999 Forwards Certified License Applications IAW Provisions of Examiner Standard (ES)-201 for SA Arebaugh,Sd Bahnsen,Jd Kalamaja,Ja Miell,Bd Musel & MR Pettengill.Encls to Ltr Withheld Per 10CFR2.790(a)(6) ML20211M5811999-08-31031 August 1999 Forwards Proprietary Version of Rev 61 to DAEC Emergency Telephone Book. Proprietary Encl Withheld NG-99-1205, Forwards FFD Rept of Program Performance Info for DAEC During Six Month Period from 990101-06301999-08-30030 August 1999 Forwards FFD Rept of Program Performance Info for DAEC During Six Month Period from 990101-0630 ML20211F7831999-08-26026 August 1999 Forwards Insp Rept 50-331/99-09 on 990708-0819.Violation Re Failure to Log Entry Into TS Limiting Condition for Operation When Power Lost to Drywell Sump Pump Level Switches,Noted & Being Treated as NCV ML20210V1231999-08-17017 August 1999 Forwards Insp Rept 50-331/99-10 on 990802-06.No Violations Noted.Insp Examined Activities Conducted Under Emergency Preparedness Program ML20211A8731999-08-16016 August 1999 Ack Receipt of 990212 & 0402 Ltrs,Which Transmitted Changes Identified as Revs 39 & 40 to DAEC Security Plan,Submitted Under Provisions of 10CFR50.54(p).NRC Review Comments for Subject Plans,Encl NG-99-1146, Forwards Validated Exam Matls for Initial License Exam to Be Administered at Facility,Wk of 990920,IAW Guidelines in NUREG-1021,Rev 8,dtd April 19991999-08-16016 August 1999 Forwards Validated Exam Matls for Initial License Exam to Be Administered at Facility,Wk of 990920,IAW Guidelines in NUREG-1021,Rev 8,dtd April 1999 NG-99-1126, Submits Rept Re Changes in Calculated Peak Cladding Temp for Daec,Iaw 10CFR50.46(a)(3)(ii),guidance in NRC Info Notice 97-015 & Suppl 1.Rept Covers Period from Last Annual Rept Through June 19991999-08-13013 August 1999 Submits Rept Re Changes in Calculated Peak Cladding Temp for Daec,Iaw 10CFR50.46(a)(3)(ii),guidance in NRC Info Notice 97-015 & Suppl 1.Rept Covers Period from Last Annual Rept Through June 1999 NG-99-1050, Informs That Recommendation in BWRVIP-18,incorrectly Interpreted During RFO 15 & 25% of Creviced Welds Examined. All of Inspected Creviced Welds Were Found to Be Acceptable1999-07-28028 July 1999 Informs That Recommendation in BWRVIP-18,incorrectly Interpreted During RFO 15 & 25% of Creviced Welds Examined. All of Inspected Creviced Welds Were Found to Be Acceptable ML20210L8311999-07-27027 July 1999 Forwards Insp Rept 50-331/99-05 on 990601-0701.Violations Noted.Insp Included Assessment & Evaluation of Engineering Support,Design Change & Mod Activities Including 10CFR50.59 Safety Evaluations,Applicability Reviews & C/As ML20210E9781999-07-26026 July 1999 Informs That Info Submitted by Ltr (Nep 99-0067), Ies Utilities,Inc,Will Be Withheld from Public Disclosure, Per 10CFR2.790(a)(6) ML20210E1431999-07-22022 July 1999 Provides Summary of 990715 Meeting with Alliant Utilities & Duane Arnold Energy Ctr Mgt Re Recent Plant Performance Review Issued by NRC for Duane Arnold Energy Ctr.Associated Meeting Summary & Alliant Utilities Meeting Handout Encl NG-99-0993, Submits Amend to Commitment Contained in Util 990623 Response to NRC RAI Re Third ten-year Interval ISI Relief Requests.Licensee Now Commits to Meeting Code Requirement of Asme,Section XI,1989 Edition,Paragragh IWB/IWC-2420(a)1999-07-21021 July 1999 Submits Amend to Commitment Contained in Util 990623 Response to NRC RAI Re Third ten-year Interval ISI Relief Requests.Licensee Now Commits to Meeting Code Requirement of Asme,Section XI,1989 Edition,Paragragh IWB/IWC-2420(a) ML20210B7161999-07-20020 July 1999 Forwards Audit Rept on Y2K Contingency Planning Program at Duane Arnold Energy Center Conducted on 990615-16 as follow-up to NRC GL 98-01 ML20210B5271999-07-16016 July 1999 Forwards Insp Rept 50-331/99-07 on 990526-0707.Two Violations Being Treated as Noncited Violations NG-99-0989, Provides Estimate of Number of Licensing Requests That Will Be Submitted in FY00 & 01,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-16016 July 1999 Provides Estimate of Number of Licensing Requests That Will Be Submitted in FY00 & 01,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20209E8401999-07-13013 July 1999 Discusses Completion of NRC GL 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling & Containment Heat Removal Pumps for Plant NG-99-0990, Forwards License Renewal Applications for Ta Zimmerman SOP 30772 & Ba Westcot SOP 30771.Encls Withheld,Per 10CFR2.7901999-07-13013 July 1999 Forwards License Renewal Applications for Ta Zimmerman SOP 30772 & Ba Westcot SOP 30771.Encls Withheld,Per 10CFR2.790 ML20209G4991999-07-12012 July 1999 Forwards Insp Rept 50-331/98-05 on 990622-24.No Violations Noted ML20207H6741999-07-0606 July 1999 Forwards Operating Licensing Exam Rept 50-331/99-301(OL) on 990525.Staff Administered Written Exam to One Reactor Operator Applicant Previously Demonstrating Unsatisfactory Results During Jul 1998 Exam NG-99-0928, Forwards Response to NRC 980902 Comments Re Design Basis NPSH Analyses as Requested by GL 97-041999-07-0101 July 1999 Forwards Response to NRC 980902 Comments Re Design Basis NPSH Analyses as Requested by GL 97-04 NG-99-0859, Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants,Per GL 98-01.Y2K Readiness Disclosure for Plant Encl1999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants,Per GL 98-01.Y2K Readiness Disclosure for Plant Encl ML20212J4521999-06-25025 June 1999 Discusses Closure of TAC MA1188 Re Response to RAI to GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity NG-99-0880, Informs That Util Commits to Repeating Newly Established Sequence of Component Exams During Successive Insp Intervals for NDE-R035,in Response to NRC Re Inservice Insp Relief Requests1999-06-23023 June 1999 Informs That Util Commits to Repeating Newly Established Sequence of Component Exams During Successive Insp Intervals for NDE-R035,in Response to NRC Re Inservice Insp Relief Requests ML20196F9531999-06-21021 June 1999 Forwards Proprietary Rev 60 to Duane Arnold Energy Center Emergency Telephone Book.Proprietary Info Withheld ML20196A1431999-06-18018 June 1999 Confirms Discussion Between Members of Staffs to Have Meeting on 990715 at Training Ctr at Duane Arnold Energy Ctr to Discuss Results of Plant Performance Review Process ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARNG-99-1383, Forwards Response to NRC 990930 RAI on TS Change Request TSCR-010 Re Excess Flow Check Valve SRs1999-10-0808 October 1999 Forwards Response to NRC 990930 RAI on TS Change Request TSCR-010 Re Excess Flow Check Valve SRs NG-99-1405, Informs That Util Has Completed Addl Review to Ensure That All Related Requirements for Repair/Replacements Have Been Addressed,Per Util Requesting Approval of Several Inservice Insp Relief Request1999-10-0808 October 1999 Informs That Util Has Completed Addl Review to Ensure That All Related Requirements for Repair/Replacements Have Been Addressed,Per Util Requesting Approval of Several Inservice Insp Relief Request NG-99-1358, Forwards DAEC plant-specific Response to 990927 RAI Re TS Change Request on Excess Flow Check Valve Surveillance requirements.TSTF-334,included1999-10-0505 October 1999 Forwards DAEC plant-specific Response to 990927 RAI Re TS Change Request on Excess Flow Check Valve Surveillance requirements.TSTF-334,included NG-99-1327, Forwards IST Relief Request VR-24 Re Excess Flow Check Valve Test Frequency,Per 10CFR50.55a(a)(3)(i),for NRC Approval1999-10-0404 October 1999 Forwards IST Relief Request VR-24 Re Excess Flow Check Valve Test Frequency,Per 10CFR50.55a(a)(3)(i),for NRC Approval NG-99-1378, Clarifies TS Change Requests for Revised Safety Limit Min Critical Power Ratio.Approval of 990510 & 0716 Application for Amends to License DPR-49 Requested Prior to Scheduled Start of Cycle 17 & Effective Date No Earlier than 9910221999-10-0404 October 1999 Clarifies TS Change Requests for Revised Safety Limit Min Critical Power Ratio.Approval of 990510 & 0716 Application for Amends to License DPR-49 Requested Prior to Scheduled Start of Cycle 17 & Effective Date No Earlier than 991022 NG-99-1262, Forwards License Renewal Application for G Thullen,License SOP 30232-2.Thullen Has Completed Requalification Program for Daec.Encls Withheld,Per 10CFR2.790(a)(6)1999-09-20020 September 1999 Forwards License Renewal Application for G Thullen,License SOP 30232-2.Thullen Has Completed Requalification Program for Daec.Encls Withheld,Per 10CFR2.790(a)(6) NG-99-1278, Forwards Corrected TS Page 3.3-52 Re TS Change Request TSCR-003,removing Requirements for Hpcis & Rcics Isolation Manual Initiation Instrumentation.Page Indicates Deletion of Condition G as Well as or G from Condition H1999-09-15015 September 1999 Forwards Corrected TS Page 3.3-52 Re TS Change Request TSCR-003,removing Requirements for Hpcis & Rcics Isolation Manual Initiation Instrumentation.Page Indicates Deletion of Condition G as Well as or G from Condition H NG-99-1214, Forwards Voluntary Info Requested in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Re Estimated Number of Operator Licensing Exams & Applicants for Years 2000 Through 20031999-09-15015 September 1999 Forwards Voluntary Info Requested in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Re Estimated Number of Operator Licensing Exams & Applicants for Years 2000 Through 2003 NG-99-1249, Requests Exemption from Certain Requirements Applicable to ECCS Evaluation Models Performed IAW App K to 10CFR50 for DAEC1999-09-10010 September 1999 Requests Exemption from Certain Requirements Applicable to ECCS Evaluation Models Performed IAW App K to 10CFR50 for DAEC NG-99-1252, Informs That There Is No Longer Need for Any Waiver Associated with Senior Operator License Application for MR Pettengill Due to Completion of All Five Manipulations1999-09-0909 September 1999 Informs That There Is No Longer Need for Any Waiver Associated with Senior Operator License Application for MR Pettengill Due to Completion of All Five Manipulations NG-99-1192, Forwards marked-up Copies of Affected Tables & Ref Matl Which Supports Changes Re DAEC Reactor Vessel Integrity Database (Rvid),As Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity1999-09-0808 September 1999 Forwards marked-up Copies of Affected Tables & Ref Matl Which Supports Changes Re DAEC Reactor Vessel Integrity Database (Rvid),As Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity NG-99-1216, Requests Waiver to Allow MR Pettengill to Participate in Upcoming Senior Operator Examination on 990920.Util Intends to Ensure That Pettengill Completes All Five Required Manipulations as Soon as Possible1999-09-0101 September 1999 Requests Waiver to Allow MR Pettengill to Participate in Upcoming Senior Operator Examination on 990920.Util Intends to Ensure That Pettengill Completes All Five Required Manipulations as Soon as Possible ML20211M5811999-08-31031 August 1999 Forwards Proprietary Version of Rev 61 to DAEC Emergency Telephone Book. Proprietary Encl Withheld NG-99-1182, Forwards Certified License Applications IAW Provisions of Examiner Standard (ES)-201 for SA Arebaugh,Sd Bahnsen,Jd Kalamaja,Ja Miell,Bd Musel & MR Pettengill.Encls to Ltr Withheld Per 10CFR2.790(a)(6)1999-08-31031 August 1999 Forwards Certified License Applications IAW Provisions of Examiner Standard (ES)-201 for SA Arebaugh,Sd Bahnsen,Jd Kalamaja,Ja Miell,Bd Musel & MR Pettengill.Encls to Ltr Withheld Per 10CFR2.790(a)(6) NG-99-1205, Forwards FFD Rept of Program Performance Info for DAEC During Six Month Period from 990101-06301999-08-30030 August 1999 Forwards FFD Rept of Program Performance Info for DAEC During Six Month Period from 990101-0630 NG-99-1146, Forwards Validated Exam Matls for Initial License Exam to Be Administered at Facility,Wk of 990920,IAW Guidelines in NUREG-1021,Rev 8,dtd April 19991999-08-16016 August 1999 Forwards Validated Exam Matls for Initial License Exam to Be Administered at Facility,Wk of 990920,IAW Guidelines in NUREG-1021,Rev 8,dtd April 1999 NG-99-1126, Submits Rept Re Changes in Calculated Peak Cladding Temp for Daec,Iaw 10CFR50.46(a)(3)(ii),guidance in NRC Info Notice 97-015 & Suppl 1.Rept Covers Period from Last Annual Rept Through June 19991999-08-13013 August 1999 Submits Rept Re Changes in Calculated Peak Cladding Temp for Daec,Iaw 10CFR50.46(a)(3)(ii),guidance in NRC Info Notice 97-015 & Suppl 1.Rept Covers Period from Last Annual Rept Through June 1999 NG-99-1050, Informs That Recommendation in BWRVIP-18,incorrectly Interpreted During RFO 15 & 25% of Creviced Welds Examined. All of Inspected Creviced Welds Were Found to Be Acceptable1999-07-28028 July 1999 Informs That Recommendation in BWRVIP-18,incorrectly Interpreted During RFO 15 & 25% of Creviced Welds Examined. All of Inspected Creviced Welds Were Found to Be Acceptable NG-99-0993, Submits Amend to Commitment Contained in Util 990623 Response to NRC RAI Re Third ten-year Interval ISI Relief Requests.Licensee Now Commits to Meeting Code Requirement of Asme,Section XI,1989 Edition,Paragragh IWB/IWC-2420(a)1999-07-21021 July 1999 Submits Amend to Commitment Contained in Util 990623 Response to NRC RAI Re Third ten-year Interval ISI Relief Requests.Licensee Now Commits to Meeting Code Requirement of Asme,Section XI,1989 Edition,Paragragh IWB/IWC-2420(a) NG-99-0989, Provides Estimate of Number of Licensing Requests That Will Be Submitted in FY00 & 01,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-16016 July 1999 Provides Estimate of Number of Licensing Requests That Will Be Submitted in FY00 & 01,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates NG-99-0990, Forwards License Renewal Applications for Ta Zimmerman SOP 30772 & Ba Westcot SOP 30771.Encls Withheld,Per 10CFR2.7901999-07-13013 July 1999 Forwards License Renewal Applications for Ta Zimmerman SOP 30772 & Ba Westcot SOP 30771.Encls Withheld,Per 10CFR2.790 NG-99-0928, Forwards Response to NRC 980902 Comments Re Design Basis NPSH Analyses as Requested by GL 97-041999-07-0101 July 1999 Forwards Response to NRC 980902 Comments Re Design Basis NPSH Analyses as Requested by GL 97-04 NG-99-0859, Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants,Per GL 98-01.Y2K Readiness Disclosure for Plant Encl1999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants,Per GL 98-01.Y2K Readiness Disclosure for Plant Encl NG-99-0880, Informs That Util Commits to Repeating Newly Established Sequence of Component Exams During Successive Insp Intervals for NDE-R035,in Response to NRC Re Inservice Insp Relief Requests1999-06-23023 June 1999 Informs That Util Commits to Repeating Newly Established Sequence of Component Exams During Successive Insp Intervals for NDE-R035,in Response to NRC Re Inservice Insp Relief Requests ML20196F9531999-06-21021 June 1999 Forwards Proprietary Rev 60 to Duane Arnold Energy Center Emergency Telephone Book.Proprietary Info Withheld NG-99-0468, Informs That There Have Been No Changes in Organizational Structure or Ownership from That Previously Submitted in .Ies Util Remains Owner & Operator of Duane Arnold Energy Center1999-06-0303 June 1999 Informs That There Have Been No Changes in Organizational Structure or Ownership from That Previously Submitted in .Ies Util Remains Owner & Operator of Duane Arnold Energy Center NG-99-0625, Informs NRC That SRO License for B Westcot & SRO License SOP 30772 for T Zimmerman Should Be Modified to Require Corrective Lenses for Near & Distant Vision While Performing Licensed Duties.Nrc Forms 396,withheld,per 10CFR2.790(a)(b)1999-05-24024 May 1999 Informs NRC That SRO License for B Westcot & SRO License SOP 30772 for T Zimmerman Should Be Modified to Require Corrective Lenses for Near & Distant Vision While Performing Licensed Duties.Nrc Forms 396,withheld,per 10CFR2.790(a)(b) NG-99-0741, Forwards Remaining Validated Exam Matls for Initial License Exam to Be Administered at Licensee Facility Week of 990524. Exam Matls Should Be Withheld from Public Disclosure Until After Exam Completed1999-05-19019 May 1999 Forwards Remaining Validated Exam Matls for Initial License Exam to Be Administered at Licensee Facility Week of 990524. Exam Matls Should Be Withheld from Public Disclosure Until After Exam Completed NG-99-0700, Forwards License Renewal Applications for SA Brewer OP-30975,EE Harrison SOP-31293 & SD Kottenstette SOP-31294. Encls Withheld Per 10CFR2.790(a)(6)1999-05-17017 May 1999 Forwards License Renewal Applications for SA Brewer OP-30975,EE Harrison SOP-31293 & SD Kottenstette SOP-31294. Encls Withheld Per 10CFR2.790(a)(6) ML20206S7951999-05-11011 May 1999 Informs That Temporary Addendum to DAEC Security Plan Is No Longer Required & Should Be Removed.Addendum Was Transmitted to NRC in 981015 Licensee Ltr NG-99-0664, Forwards Certified Application Re Reactor Operator License Reapplication IAW Provisions of Examiner Standard (ES)-201 for Ma Ruchko.Examination Is Scheduled for 990525.Encl Withheld Per 10CFR2.7901999-05-10010 May 1999 Forwards Certified Application Re Reactor Operator License Reapplication IAW Provisions of Examiner Standard (ES)-201 for Ma Ruchko.Examination Is Scheduled for 990525.Encl Withheld Per 10CFR2.790 NG-99-0636, Forwards Radiological Environ Monitoring Program (REMP) for DAEC for Jan-Dec 1998, IAW TS Section 5.6.2 Reporting Requirements1999-04-29029 April 1999 Forwards Radiological Environ Monitoring Program (REMP) for DAEC for Jan-Dec 1998, IAW TS Section 5.6.2 Reporting Requirements NG-99-0633, Forwards DAEC 1998 Annual Radioactive Matls Release Rept for Jan-Dec 1998. Rept Satisfies Requirements for Annual Radioactive Matl Release Rept,As Stated in Section 5.6.3 of Tech Specs1999-04-29029 April 1999 Forwards DAEC 1998 Annual Radioactive Matls Release Rept for Jan-Dec 1998. Rept Satisfies Requirements for Annual Radioactive Matl Release Rept,As Stated in Section 5.6.3 of Tech Specs NG-99-0622, Forwards Validated Exam Matls for Initial License Exam to Be Administered During Week of 990524,per NUREG-1021.Without Encl1999-04-28028 April 1999 Forwards Validated Exam Matls for Initial License Exam to Be Administered During Week of 990524,per NUREG-1021.Without Encl NG-99-0605, Forwards Response to NRC Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Duane Arnold Energy Center1999-04-28028 April 1999 Forwards Response to NRC Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Duane Arnold Energy Center NG-99-0493, Forwards non-certified Application Re Reactor License Reapplication in Accordance with Provisions of Examiner Std (ES)-201 for Ma Ruchko.Nrc License Exam Scheduled for 990525.Without Encl1999-04-19019 April 1999 Forwards non-certified Application Re Reactor License Reapplication in Accordance with Provisions of Examiner Std (ES)-201 for Ma Ruchko.Nrc License Exam Scheduled for 990525.Without Encl NG-99-0495, Informs NRC That RW Pfeil Did Not Take BWR Generic Fundamentals Exam Section of Written Operator Licensing Exam Administered on 990407.R Pfeil Is No Longer Enrolled in DAEC Operator Licensing Training Program1999-04-19019 April 1999 Informs NRC That RW Pfeil Did Not Take BWR Generic Fundamentals Exam Section of Written Operator Licensing Exam Administered on 990407.R Pfeil Is No Longer Enrolled in DAEC Operator Licensing Training Program NG-99-0529, Forwards Outline of Exam to Be Given Week of 990524 as Requested in Telcon with G Thullen & Requests Exam Matls Be Withheld from Public Disclosure Until After Exam Completed on 9905281999-04-0808 April 1999 Forwards Outline of Exam to Be Given Week of 990524 as Requested in Telcon with G Thullen & Requests Exam Matls Be Withheld from Public Disclosure Until After Exam Completed on 990528 ML20205M2471999-04-0202 April 1999 Transmits Change 40 to DAEC Security Plan,Per Requirements of 10CFR50.54(p).Changes Are Intended to Enhance Capability of Onsite Security Force to Defend Against Design Basis Threat.Plan Withheld,Per 10CFR73.21 NG-99-0491, Requests Relief from Noted Requirements,For Relief Requests MC-R002 Through MC-R006,MC-P001 & NDE-R015,rev 1.Approval Is Requested Prior to Refueling Outage 16,scheduled to Begin on 9910081999-04-0202 April 1999 Requests Relief from Noted Requirements,For Relief Requests MC-R002 Through MC-R006,MC-P001 & NDE-R015,rev 1.Approval Is Requested Prior to Refueling Outage 16,scheduled to Begin on 991008 NG-99-0281, Forwards Decommissioning Funding Rept for Daec,Iaw 10CFR50.75(f)(1).Rept Is Being Submitted by DAEC Joint Owners Ies Utilities,Inc,Central IA Power Cooperative & Corn Belt Cooperative1999-03-31031 March 1999 Forwards Decommissioning Funding Rept for Daec,Iaw 10CFR50.75(f)(1).Rept Is Being Submitted by DAEC Joint Owners Ies Utilities,Inc,Central IA Power Cooperative & Corn Belt Cooperative NG-99-0273, Forwards 1999 DAEC Simulator Certification Rept, Per 10CFR55.45 Every Four Years on Anniversary of Certification. Required Info Contained in Attachments 1-71999-03-24024 March 1999 Forwards 1999 DAEC Simulator Certification Rept, Per 10CFR55.45 Every Four Years on Anniversary of Certification. Required Info Contained in Attachments 1-7 ML20207L8351999-03-10010 March 1999 Forwards Proprietary Rev 59A to Deac Emergency Telephone Book & non-proprietary Rev 20 to Section H of DAEC Emergency Plan, IAW 10CFR50,App E.Proprietary Info Withheld NRC-99-0300, Forwards Rev 15 to Pump & Valve IST Program for Daec1999-03-0101 March 1999 Forwards Rev 15 to Pump & Valve IST Program for Daec NG-99-0302, Forwards Fitness for Duty Program Performance for DAEC During Six Month Period Jul-Dec 1998 in Accordance with 10CFR26.71(d)1999-02-28028 February 1999 Forwards Fitness for Duty Program Performance for DAEC During Six Month Period Jul-Dec 1998 in Accordance with 10CFR26.71(d) ML20203G3041999-02-12012 February 1999 Informs of Rev to Security Plan for DAEC to Improve Flexibility in Deployment of Members of Security Force. Security Plan Change 39,reflecting Changes,Encl.Encl Withheld NG-99-0115, Submits Request for Enforcement Discretion to Tech Spec Surveillance Requirement 3.8.1.7 for Edgs.Listed New Commitment Being Made by Ltr1999-01-21021 January 1999 Submits Request for Enforcement Discretion to Tech Spec Surveillance Requirement 3.8.1.7 for Edgs.Listed New Commitment Being Made by Ltr ML20206S1691999-01-18018 January 1999 Forwards Proprietary Rev 59 to DAEC Emergency Telephone Book. Proprietary Encl Withheld NG-98-2102, Informs That Util Completed Commitment to Assess & Implement Severe Accident Mgt Guidelines at Daec,Based Upon Generic Guidelines Developed by BWROG1998-12-31031 December 1998 Informs That Util Completed Commitment to Assess & Implement Severe Accident Mgt Guidelines at Daec,Based Upon Generic Guidelines Developed by BWROG NG-98-2059, Provides Response to NRC Request for Background Summary of TS Change (TSCR-006), Revise TS 3.6.1.3 Condition E & Add TS for Control Bldg/Standby Gas Treatment (Cb/Sbgt) Instrument Air Sys1998-12-21021 December 1998 Provides Response to NRC Request for Background Summary of TS Change (TSCR-006), Revise TS 3.6.1.3 Condition E & Add TS for Control Bldg/Standby Gas Treatment (Cb/Sbgt) Instrument Air Sys 1999-09-09
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I lima lettric 1.ight arul Pimer Company !
l 4 l Septembe2 21, 1992 HG ~ '/2 - 3 9 61 ii N sHN I. I N AN/, AR iu e ..nem i o Dr. 't h inal. E. Muriey, Di rect or '
Office of Nuclear iteactor Eogulation U. S. IJu e l ea t Regulatory Commiaaion Aitn: Docunmnt Control Desk Mai] St at ion Pl-137 ,
Wabbi nyt on, DC 2 0 % b Sulaj ect : Duano A1nold Energy Center Docket No: 50-331
- Op. License Ho
- DDR-49 Hosponse to Supplement 1 to Gennric I.et ter P7-02 on SQUG Resolution of USI A-46 File: A-18, A-10lb D<Mr Dr. Murley:
On February 19, I 9 87, t.he NRC isouEd Generic Lettml 87-02, aWr i f icat aan of Seismic Adequacy of Mechanical and Elect rical Equipment in Operating Reactors, Unresolved Safety lusuo (USI) A+
46." Thin Generic Letter encouraged utilition to participate in a generic program to lu:mJ ve the seisn.ic verification issues assuciat ed wit h US1 A-4 6. As a result, the Seismic Oucjification Utility Group ( SCtUG) developed the " Generic Implementation Procedure (G1P) for Seismic Ve11fication of Nuclear Plant Equipmenti" On May 22, 1992,_the HRC Staff issued Generic. Letter 87-02, Supplement.1, which t ransmit t ed Supplemental Saf ety Evaluat ion Report No. 2 (SSER-2)' on t he GIP, Revision 2 (corrected on February 14, 1992). Supplement 1 to Generic _ Letter 87-0; requeatn t hat within_120 days, _ Nch _SQUG member utility i
trovide a schedul9 f or implement ing tim GI P. 13y l et t er - da t ed -
Auguat 21, 1992, to James G. Partlow, NRR-NRC, SQUG clarified that the 120 days would expire on September 21, 1992. This let t er respends to the Staf f 's request in Supplement 1 to Gene'lic-Letter 87-02.
EIowa El ect ric Light and Power (IELP) coliuni t s t 'o une the SQU3 met hodology an documented in t he GIP Revision 2 .(corrected February-14, 1992)- to resolve USI A-46 at the Duane Arnold Energy Cent er (DAEC). The GIP, as evaluated by the Staff, permits licenaecs-to deviate trom-the SQUG commitmento embodied in the Commitment sections,-provided the Staff is notified of cubstantial deviations prior to implementation. IELP recognizes that the Staff'a:ponition in SSER-2 "is that if licensees-use other - met hods that deviate from the criteria and proceduren as ll dendribed in SQU.G commitments and in the implementation-guidance L 9209290394 920921' ,
PDR ADOCK'05000331' ,.
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u f. 'im G1P, Pm ;, w2thout p r 101 URC ;tafI al .pl ova) , the tiethod m.r/ m :t m < n 93 t oble tn t.he 0;aff nnd, t het ef, ore, u@ renult in a do /iot i on ft( m t he pt wiaient of" Genatic Lotter 87-02.
IPLP genw al]y till he guided by ot hut cectione of the GIP which oro not- < > .mtm t nw n t a , 1. c . , G.11' itnplementation guldance, which e nprine ;uque st ed nwt hodn for in.plement.tng the applicable ac-an i t:m n t s . (1ELP will nutsty the DEC as soon an practicable, bu t- no lat m t han t he final USI IH t; nummary report, of any
- 1'Jui i * ' un t a pt t gi cumat ic dtva at ionr f rom the guidance port ions -
of the GIP. .iuat i t ient j uns f. t 1 such deviat. ions, ae wel l e s for ot hm , mirer deviationc, will be r et ained on site for MRC 1 L:' ' l e 1
% :b:t ine uei mi c denut ul, IELP will use the Options provided in the GIF- fm anam vative design in structure responue opectra depentling on the building, the Jucation et equipment in the huilding, and equipment CharacteriSLIcJ.
- The l i ceind nu - bam : apectra, approved by the AEC in the Safety Evaluation af t h." Di.Eu (Janu,n y ?3, 3973) will be used and.are Colla i t hal
- Kl t o b* cDi1M rVative desion. 'Ine procedures and critetta which wer e uaed to gener:1te t he licensing-bM ia in-structure r>:p noe Toctra are desetibed in the Attachment to t hi. let t er G4 ven the magnit ude of the effort required tu achieve resolution 01 UDI A-46, final implement 6t ion will be int:egrat ed with i eboduled refuel cmtagea and the seinmic IPEEE response, the
- con pl+:t i on of vhich may be aftected by'the USI A-46 imp i en ent at a t in sta t t ' dat e . A Seinmic Evaluation Report sungna t i ni ng the r e mits of the USI A-46 program at DAEC will be ubmit t ed t o t he ufc by November 21, 1995. However, the schedule foi complet ion of the USI A-46 prtw am may be atfacted by
- cordinat ion wit h t he veinmic IPEEE ' response, the scope and
< chedule f or enmplet ing the necessaly SOUG t raining and by the -
availability of industry resourceu which may be adversely itnpacted by the large number of licenseea implementing this program.
The abovs uchedule cmsumes that we are notified promptly that the acheclule and canalitments stated in this letter are acceptable.
11 such notification is not received by November 20, 1992, we mus t teochedule the USl A-46 completion date to permit coordination with planned refueling outages scheduled for July 1993 and Iebruary 1995.
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Dr. Thet;.ao E . Mu ley Sept ember 31, 19 W _j l I M -- ) 2 ~ 3 9 (t }
l lage 3 This letter in t r ue and aceut at.e t o t he best of n:y knowledge and bA ivi.
10WA ELECTRIC L.ICilT AND POWER COMPM4Y qj
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Corrmianion Exp11 es JFF/SCH/pjv-i At t achment : Description of Licensing 13aais In-Structure Response Spect ra For Uae in Resolving USI A-46 cc: 3. Catron w/att I; . Liu w/o
- L. Root w/o -t R, McGaugby w/o ,
C. Shintki ( t!RC-NRR ) w/att A. Bert Davia (Region IIIi w/att HRC R wident Office w/att
-DCRC w/att-Commi t nRdtt Control Nos. 880428, 920067 .
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Attachment to UG-92-3961 Paqu 1 e i e qL .. m #
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- f ( 31 000 in Ee"OlV[DO U h* 1 /.- 4 6 Th - in ;t t uct ut e :t e J p ;n a o Spvt:a to be uwd by IELP in resolving USI A-40 a: + e <iat i no lict iming-basi: myct1a. The r.poctra were generated noing p r-v mit u e n deacri hd 2 n pet iona 4./.1 and 3.7.2 of the FSAfl.
Ther ;# plt .W l u r e 'l die ;11mMQri Ted hel OU l
The w 2 umir input, ior tho d<.mi on baniD mit t hquake (DBE) f or t he DAliC i sie g r oumi tra 2 on opu ra mth a leak hatizantal ground acceleration :
I
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*! s'. }?g. Tl10 t ij@ra t i ng l uf3 i P ea t't hqudke (OBE) ground motion yet ro m'> ont-haJ! tho DHE cpetIa.
'n at t i t it ;a1 t im hist Oty of the hm inont al groarni motion was D * "l(;j a d l o s.t q l On f l,3 j940 Ej ' ynt. r o , Californid OdIlhquake [QL USe U .i b p i t i la (}W dyn;mit hGilding MSlelL. TllO CalCulalOd TOUpOn30 y ett i a 11 m t he arta ticial tim histoty enveloped t he target seismic de 3 5 'f n g l' CHln d spoet t a . Thir ar t if icial time history was applied t o Oynam1C 'O i umi t W deld U[ the 30 Mni c Jul6901y 1 ULTUClu1OS dnd t h0-time hiat uty 1 ;ponse at each f)cor waa comput ed. In -st ruct ure i e lf;Onut_ qw m t l ot WOT P t }lOn quhel u t ed ! ! :.$t the f1001 time hiGlorieD.
The w p eria ato ronajdered to be conservative denign in-structure !'
t e :p mm spectro n defined in the GIF.
Thoc .fiumic buildilig modelu ?ODO:sted of t hree-dimen tii ona l lumped mass ,
analytimi models. The genera 1ined mass and atiffnese properties were Cd3JU1dlOd ODing COnVOOLiOnal 3CEUctOrd} GOChaniCS mCthOdD.
St.ru ct u ra l damping wag baDOd On the Composite m0 del domping teChniGUG.
Individual d oping coM ticiento langed from 1 to 5 percent such that the ovei J 1 eq u.i va l en t damping waa less than or equal to 5 percent,
, 3nisnu e models for t he t eact or building, control building, intake l at t uct ute, pump houae and turbine bailding are shown in Figures 1 t hr ough 5, re ;pect ively-. CulcuJated model frequencies are tabulated i n TQ b,I ' > } through 5. -
l . . tu --
$ n m , . 4 .b ass Buil Sprillgd butWUOn Llie St.t uct.ure and the f ourdation in t,ne seismic mode!F. Tlm ,o i l splinga modeled the /ettical and tranulational '
at i f ineas M the toandation. The atiffnea propertius of the coil zpringc were based on 2he p ocedure-provided by Ehitman and Richard
(DOOign PloCOdurOJ tur DyLmically Leaded F00ndittions, ' by R. V.
Whi t;Nin and F . E. inchnrd, Jr., J; Soll Mech. and Fod, Div., ASCE, ,
SM7, Naveni n 1967, pp 169-193).
Wpical in-str uct are l esponse spectra f or the reactor building, contial buildin[1, ant ake at ructute, punp house and turbine building are provi&d in Fictures 6 through 10, respectively. These spectra are-OBE. In~ d acrute reaponse spectia fo: the DDE are two times the OBE 3 pe ':t- ra . The in - s t ruc t '.n o responce spectra provided in Figurea 7 through 30 shov a maximum of 2 percent damping. These curves will bei adjualed fOr E perdent ddmping for me in GIF implementetion.
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/>ttachment to IJG-92 3961 T' age 2 Table 1 Reactor Building 11atural Frequencies Mode ik. IJatural Frequency (112) 1; orth Sauth East-West 1 3.5 3,4
$ 4,4 4,4 3 B.3- 8.3- _ _
4 - 13.0 13.9
'i 16,9 16.9 6 .31 .1 21,3 1 23.3 22.7 8 27.8 27,8 9 31.2 29.4 1: h t ough l I 15 50.0 45.5 nl _n=-... -_= ,n _ _ ,= .,-.
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Page 3 Table J l Control Building Natural Frequencies i.
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Mode !k'. Nat.ut al T'i equency (11: )-
Iksi th Sout h East-Went i i,
.1 1.G to 3.2 1.7 to 2.4 1 2 4.0 tc 7.1 3.2 to 5.3 3 25.0 4. 0 t o 6.7 33.3 4 6.7 to 9.3 '
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Table 3 t Intake Structure Natural Frequencies i
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- Mode No. Natural Frequency (lic )
North-South Fact-West 1 8.1 12.8 I
I 2- 21,'7 33,3 I
T 43.5 58.8 i
l I 4 52.6 66.7 J
5 -- 6 6,7 -- 83.3 ,
l 6 83.3 125.0-i 7 100.0 142.9 I l
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. Pump flouso Natural Frequencies
- ,m - w.w =unu = m.c :n.w - ~mm a wz. _ m n: , _ n n m _.,= ,.n n m ,.,u n - n a m - m m n M & !b. Ib t ural Frequency ( Th: )
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Lble S Turbine Building Natural Frequencies e
mnmenan--:t ,sne,rm:==~a=wmmm .-ww:.s,~ ...am:nw;r :rew.m.r;; r=1 wgrv. :symmw.m:nnwcgr.vx.tr ... s2.ts:su.,-
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NOTE: StACH,0 FRAME MaM,ssgf CF JOUTH WALL NOT JHOWN Figure 2 D/tEC Contro] Building .
Mathematical Model
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