NG-87-1881, Responds to Generic Ltr 87-06 Requiring List of All Pressure Isolation Valves W/Description of Periodic Testing Requirements & Operational Limits for Each Valve.Applicable Valves Listed.Testing Requirements Described
From kanterella
Jump to navigation
Jump to search
| ML20215C248 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 06/11/1987 |
| From: | Mcgaughy R IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation |
| References | |
| GL-87-06, GL-87-6, NG-87-1881, NUDOCS 8706180042 | |
| Download: ML20215C248 (3) | |
Similar Documents at Duane Arnold | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N5521999-10-21021 October 1999
[Table view]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 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
[Table view]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 Category:UTILITY TO NRC MONTHYEARNG-90-2226, Forwards Proposed Operator Licensing Exam Schedule for FY91- FY94 in Response to Generic Ltr 90-071990-09-17017 September 1990
[Table view]Forwards Proposed Operator Licensing Exam Schedule for FY91- FY94 in Response to Generic Ltr 90-07 NG-90-2088, Forwards Summary of Root Cause & Corrective Action Plan Re Operator Requalification Training Program,Per NRC 900713 Confirmatory Action Ltr CAL-RIII-90-131990-08-25025 August 1990 Forwards Summary of Root Cause & Corrective Action Plan Re Operator Requalification Training Program,Per NRC 900713 Confirmatory Action Ltr CAL-RIII-90-13 ML1124202601990-08-17017 August 1990 Forwards Summary of Changes Omitted from 900814 Transmittal of Emergency Plan NG-90-1894, Forwards Licensed Operator Requalification Exams & Evaluations for Accelerated Remedial & Enhanced Training1990-08-0101 August 1990 Forwards Licensed Operator Requalification Exams & Evaluations for Accelerated Remedial & Enhanced Training ML1122122061990-07-27027 July 1990 Forwards Exams & Evaluations for Licensed Operator Requalification Documentation of Remedial & Enhanced Training.Both Types of Training Conducted in Segments of 30 H & 20 H.Encl Withheld ML1122122001990-07-20020 July 1990 Forwards Licensed Operator Requalification Documentation of Remedial & Enhanced Training,Per 900713 Confirmatory Action Ltr.Encl Withheld ML20043H2471990-06-18018 June 1990 Forwards Description of Security Plan Change SPC-24, Evaluation of Change W/Respect to 10CFR50.54(p),security Plan & Security Plan Addendum Re Intake Structure Mods.Encl Withheld (Ref 10CFR73.21) ML20042E6381990-04-20020 April 1990 Forwards Environ Radiological Monitoring Program for Duane Arnold Energy Ctr,Annual Rept - Part I Summary & Interpretation,Jan-Dec 1989. ML20011F7961990-02-28028 February 1990 Forwards Rev 23 to Plant Security Plan & Contingency Plan, Incorporating Numerous Editorial Changes & Upgrades made-to- Date on Perimeter Barrier Surrounding Plant Protected Area. Rev Withheld (Ref 10CFR73.21) ML20006D9781990-02-0909 February 1990 Responds to Notice of Violation & Proposed Imposition of Civil Penalty Transmitted in NRC 900110 Ltr.Corrective Actions:Secondary Containment Operability Test Revised to Require Securing Main Plant Exhaust Sys During Test ML20006B9551990-01-26026 January 1990 Responds to NRC 891227 Ltr Re Violations & Proposed Imposition of Civil Penalty.Corrective Actions:Fourteen Improperly Insulated Splices Repaired Per Facility Environ Qualification Program ML20005G0321989-12-19019 December 1989 Forwards Security Plan Change 22,per Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs. ML19324C3921989-11-0606 November 1989 Responds to Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs. Vital Equipment Identified Using Station Blackout Safe Shutdown Equipment List NG-89-2589, Forwards Proposed Operator Licensing Exam Schedule Format Estimating Number of Candidates to Be Examined & Dates for Scheduled Requalification Exams1989-08-29029 August 1989 Forwards Proposed Operator Licensing Exam Schedule Format Estimating Number of Candidates to Be Examined & Dates for Scheduled Requalification Exams ML20245K8201989-06-30030 June 1989 Forwards Security Plan Change 21,addressing Concerns Noted in Insp Rept 50-331/89-08.Change Withheld (Ref 10CFR73.21) ML20247A1491989-05-15015 May 1989 Forwards Response to Violations Noted in Insp Rept 50-331/89-08 Per Unresolved Item in Insp Rept 50-331/85-07 Re Security Plan.Response Withheld ML20245E9731989-04-26026 April 1989 Forwards 1988 Annual Radiological Environ Operating Rept for Plant ML20246D9401989-04-21021 April 1989 Forwards Public Version of Rev 2C to Emergency Telephone Book NG-88-3744, Responds to Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Corrective Actions:Util Has Taken Steps to Preclude Future Installation of Unqualified Butt Splices in Circuits,Per 10CFR50.491988-11-21021 November 1988 Responds to Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Corrective Actions:Util Has Taken Steps to Preclude Future Installation of Unqualified Butt Splices in Circuits,Per 10CFR50.49 NG-88-3593, Requests Approval to Defer Insp of Piping Susceptible to IGSCC Until Cycle 10/11 Due to Welds in RWCU Not Previously Examined,Per Generic Ltr 88-011988-10-21021 October 1988 Requests Approval to Defer Insp of Piping Susceptible to IGSCC Until Cycle 10/11 Due to Welds in RWCU Not Previously Examined,Per Generic Ltr 88-01 NG-88-2390, Forwards NPDES Monthly Operating Repts for Apr 1985,Jan-Aug 1987 & Jan-Feb 19881988-10-0606 October 1988 Forwards NPDES Monthly Operating Repts for Apr 1985,Jan-Aug 1987 & Jan-Feb 1988 NG-88-3187, Responds to NRC Bulletin 88-007, Power Oscillations in Bwrs. Evaluation Consisted of Review of Operating Procedures,Licensed Operator Training Program & Neutron Monitoring Hardware1988-09-19019 September 1988 Responds to NRC Bulletin 88-007, Power Oscillations in Bwrs. Evaluation Consisted of Review of Operating Procedures,Licensed Operator Training Program & Neutron Monitoring Hardware ML19318G2431988-09-0909 September 1988 Submits Licensee Schedule of Best Estimates for Operator Licensing Exams & Requalification Exams for FY89-92 Per Generic Ltr 88-13 ML20154J3371988-08-30030 August 1988 Forwards Security Plan Changes 19 & 16A.Changes Withheld (Ref 10CFR73.21) ML20207H2711988-08-17017 August 1988 Forwards Response to Concerns Noted in Insp Rept 50-331/88-15.Response Withheld (Ref 10CFR2.790 & 73.21) ML20151U8831988-04-22022 April 1988 Forwards Parts 1 & 2 to Environ Radiological Monitoring Program Annual Rept for 1987 ML20147F1541988-02-24024 February 1988 Forwards Response to Violations Noted in Insp Rept 50-331/88-02.Response Withheld (Ref 10CFR2.790 & 73.21) ML20196G4391988-02-24024 February 1988 Forwards Response to Insp Rept 50-331/88-02.Encl Withheld (Ref 10CFR2.790 & 73.21) ML20237D8771987-12-17017 December 1987 Forwards Addl Info on 861202 Proposed Security Plan Change Re Generic Ltr 87-08, Miscellaneous Amends & Search Requirements, Per 870915 Request.Encl Withheld ML20236H5691987-10-26026 October 1987 Forwards Security Plan Change 18 to Security Plan.Change Does Not Decrease Safeguards Effectiveness of Security Plan. Change Withheld (Ref 10CFR73.21) ML20234B0151987-09-15015 September 1987 Forwards Monthly Operating Rept for Aug 1987 & Revised Monthly Operating Repts for May,June & Jul 1987 NG-87-1918, Forwards Exemption Request Re Combustible Foam Matl in Drywell Liner Expansion Gap.Per Exemption request,3 H Fire Barrier Unnecessary to Ensure That One Train of Safe Shutdown Equipment Free of Fire Damage.Fee Paid1987-08-25025 August 1987 Forwards Exemption Request Re Combustible Foam Matl in Drywell Liner Expansion Gap.Per Exemption request,3 H Fire Barrier Unnecessary to Ensure That One Train of Safe Shutdown Equipment Free of Fire Damage.Fee Paid ML20238A0321987-08-25025 August 1987 Forwards Radioactive Effluent Releases Semiannual Rept for Jan-June 1987, Per Radiological Tech Specs NG-87-3176, Responds to Violations Noted in Insp Rept 50-331/87-16. Corrective Actions:Fire Watch Reestablished in Accordance W/Procedure & Contract Personnel Will Meet W/Fire Marshall Before Commencing W/Hot Work Activities1987-08-21021 August 1987 Responds to Violations Noted in Insp Rept 50-331/87-16. Corrective Actions:Fire Watch Reestablished in Accordance W/Procedure & Contract Personnel Will Meet W/Fire Marshall Before Commencing W/Hot Work Activities ML20236K5691987-07-28028 July 1987 Forwards App B to Analyses for Gamma-Emitting Isotopes of Samples W/Elevated Gross Beta Activity Resulting from Chernobyl Nuclear Plant Accident (Ussr) on 860826. Addendum Consists of Samples Collected on 860515 & 22 NG-87-1881, Responds to Generic Ltr 87-06 Requiring List of All Pressure Isolation Valves W/Description of Periodic Testing Requirements & Operational Limits for Each Valve.Applicable Valves Listed.Testing Requirements Described1987-06-11011 June 1987 Responds to Generic Ltr 87-06 Requiring List of All Pressure Isolation Valves W/Description of Periodic Testing Requirements & Operational Limits for Each Valve.Applicable Valves Listed.Testing Requirements Described NG-87-1090, Responds to Emergency Response Facility Appraisal Rept 50-331/86-20 Open Items.Corrective Actions:Procedure for Generating Offsite Dose Projections for Unmonitored Releases Will Be Developed for Midas Dose Projection Sys1987-04-0101 April 1987 Responds to Emergency Response Facility Appraisal Rept 50-331/86-20 Open Items.Corrective Actions:Procedure for Generating Offsite Dose Projections for Unmonitored Releases Will Be Developed for Midas Dose Projection Sys NG-87-1015, Responds to Violations Noted in Insp Rept 50-331/86-19 on 861202-870116.Corrective Actions:Maint Procedure MD-017 Revised to Require That Maint Engineering Be Notified of Measuring & Test Equipment Found to Be out-of-calibr1987-03-20020 March 1987 Responds to Violations Noted in Insp Rept 50-331/86-19 on 861202-870116.Corrective Actions:Maint Procedure MD-017 Revised to Require That Maint Engineering Be Notified of Measuring & Test Equipment Found to Be out-of-calibr NG-87-0830, Notifies of Annual Emergency Planning Exercise on 871027. Exercise Will Be During Normal Working Hours & Will Involve Full County Participation.State of IA Will Not Be Participating1987-03-0505 March 1987 Notifies of Annual Emergency Planning Exercise on 871027. Exercise Will Be During Normal Working Hours & Will Involve Full County Participation.State of IA Will Not Be Participating ML20212J5031987-02-27027 February 1987 Forwards Change 17 to Physical Security Plan.Entire Plan Resubmitted Due to Binding Procedure,However,No Changes Involve Guard Training & Qualification Program.Change Withheld (Ref 10CFR73.21) NG-86-4544, Forwards Scotch Brand Tapes Maint Procedure GMP-ELEC-008, Installation Instructions, Rev 0 to QUAL-M345-00, Preliminary Equipment Qualification Record for 3 M Tapes & QUAL-A602-00, Qualification of Splices ..1986-12-19019 December 1986 Forwards Scotch Brand Tapes Maint Procedure GMP-ELEC-008, Installation Instructions, Rev 0 to QUAL-M345-00, Preliminary Equipment Qualification Record for 3 M Tapes & QUAL-A602-00, Qualification of Splices .. ML20215C1841986-12-0505 December 1986 Forwards Changes 12-15 to Security Plan & Guard Training & Qualification Plan.Changes Withheld (Ref 10CFR73.21) ML20214V3511986-12-0202 December 1986 Forwards Changes to Personnel Search Requirements of Security Plan,In Response to Amends to 10CFR50 & 73.Approval Requested.Fee Paid.Security Plan Changes Withheld (Ref 10CFR73.21) ML20214F4031986-11-0707 November 1986 Forwards Response to Safeguards Inadequacies Noted During Regulatory Effectiveness Review Conducted from 860331-0404. Encl Withheld (Ref 10CFR73.21) NG-86-3988, Responds to IE Bulletin 86-003.Facility Does Not Have air-operated Min Flow Bypass Valves in ECCS Min Flow Bypass Lines or Min Flow Bypass Valve Configuration or Logic1986-10-30030 October 1986 Responds to IE Bulletin 86-003.Facility Does Not Have air-operated Min Flow Bypass Valves in ECCS Min Flow Bypass Lines or Min Flow Bypass Valve Configuration or Logic NG-86-3044, Suppls 860528 Response to IE Bulletin 85-003,Item E Re motor-operated Valve Common Mode Failures During Plant Transients.Max Expected Differential Pressures During Opening & Closing of Valves Provided1986-10-0101 October 1986 Suppls 860528 Response to IE Bulletin 85-003,Item E Re motor-operated Valve Common Mode Failures During Plant Transients.Max Expected Differential Pressures During Opening & Closing of Valves Provided ML20210A9341986-09-15015 September 1986 Forwards Monthly Operating Rept for Aug 1986 & Revised Page 1 for Monthly Operating Repts for June & Jul 1986.Page Revised Due to Mathematical Errors NG-86-2722, Forwards State of IA NPDES Permit 57-00-1-04,per 830425 Agreement to Submit Permit Changes Based on License Amend 84 Re Water Quality Requirements.Cooling Tower Maint Chemicals, Containing Zinc or Chromium,Not Used by Util1986-08-22022 August 1986 Forwards State of IA NPDES Permit 57-00-1-04,per 830425 Agreement to Submit Permit Changes Based on License Amend 84 Re Water Quality Requirements.Cooling Tower Maint Chemicals, Containing Zinc or Chromium,Not Used by Util ML20214K6151986-08-15015 August 1986 Forwards Monthly Operating Rept for Jul 1986 & Revised Page 1 to Monthly Operating Rept for June 1986 ML20209B2461986-08-0606 August 1986 Responds to Request for Info Concerning Allegation Re Contract Supervisor Failing to Meet Criteria for Continued Unescorted Access to Vital Areas.Unescorted Access Terminated Due to Conviction of Felony 1990-09-17 |
Text
_ _ _ - _ _ _ _ _ .
a ,
Iowa Electric Light and Ihwer Company June 11,1987 NG-87-1881 Mr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation Attn: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555 l
Subj ect: Duane Arnold Energy Center Docket No: 50-331 !
Op. License No: OPR-49~
Periodic Testing of Leak Tight Integrity of 1
Pressure Isolation Valves (Generic Letter 87-06)
Reference:
- 1) letter from D. Vassallo (NRC) to L. Liu (Iowa Electric) dated September 26, 1983
- 2) Letter from R. McGaughy (Iowa Electric) to T. Murley (NRC), NG-87-1629, dated May 1,1987 File: A-10lb, A-105, A-107a, E-11
Dear Mr. Murley:
Generic Letter 87-06 requires that licensees submit a list of all pressure isolation valves with a description of the periodic testing requirements and operational limits for each of the valves to assure the integrity of the reactor coolant pressure boundary. The purpose of this letter is to provide the information requested in Generic Letter 87-06.
The Duane Arnold Energy Center (DAEC) currently has ten valves classified 4 as pressure isolation valves, as defined in Generic Letter 87-06. They are motor operated valves M0-2117, M0-2137, M0-1905, M0-2003, M0-1908 and M0-1909, and check v alves V-19-0149, V-20-0082, -V-21-072, and V-21-073.
Reference 1 required the DAEC to test the listed valves periodically in accordance with the Inservice Testing (IST) Program, which is based on the ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWV. This requirement has remained in the DAEC IST Program through the current revision, submitted with Reference 2. Complete descriptions of the functions, testing requirements, and the operational limits associated with each of these valves are given in the following paragraphs.
8706180042 DR 870611 ADOCK 05000331 PDR i
General Q[ lice
- In Iks 33I
- Cedar linpids, foun 3240G
- 319/39n4411 . (Q(e b
f i r
Mr. Thomas E. Murley
'NG-87-1881 June 11,1987 Page Two l
MO-2117 and M0-2137 are 8 inch motor operated gate valves which function as the outboard pressure isolation valves for the A and B Core Spray system injection lines. The valves are cycled quarterly or during cold shutdown, and are subjected to a hydrostatic seat leakage test during each refueling outage at a nominal differential pressure of 1000 psid. The allowable seat leakage rate is 4 gallons per minute (gpm). M0-2117 and M0-2137 are normally closed and are electrically interlocked such that they cannot be opened unless reactor pressure is less than 450 psig or the associated upstream isolation valves are closed.
V-21-072 and V-21-073 are 8 inch swing check valves that are located downstream of M0-2117 and M0-2137. They function as the inboard pressure isolation valves for the A and B Core Spray systen injection lines. The valves are verified to properly open and close, and are subjected to a hydrostatic seat leakage test at a nominal differential pressure of 1000 psid during each refueling outage. The allowable seat leakage rate is 4 gpm. There are no operational limits associated with these valves. )
M0-1908 and M0-1909 are 18 inch motor operated gate valves. They function as the inboard and outboard pressure isolation valves for the Residual Heat Renoval (RHR) systen pump suction line fran the B Reactor Recirculation loop.
The valves are normally closed and are opened only when the RHR system is being used in the shutdown cooling mode. M0-1908 and M0-1909 are cycled during cold shutdown, and are subjected to a hydrostatic seat leakage test at a nominal differential pressure of 1000 psid each refueling outage. The allowable seat leakage rate is 5 gpm. These valves are electrically interlocked such that they cannot be opened unless reactor pressure is less than 135 psig.
M0-2003 and M0-1905 are 20 inch motor operated gate valves which function as the outboard pressure isolation valves for the A and B Low Pressure Coolant l Injection (LPCI) lines. The valves are normally closed and are required to open I when the RHR system is used in the LPCI mode. M0-2003 and MD-1905 are cycled quarterly or during cold shutdown, and are subjected to a hydrostatic seat leakage test at a nominal differential pressure of 1000 psid during each ref ueling outage. The allowable seat leakage rate is 5 gpm. These valves are electrically interlocked such that they cannot be opened unless reactor pressure is less than 450 psig or the associated upstrean isolation valves are closed.
V-19-0149 and V-20-0082 are 20 inch swing check valves that are located downstream of M0-2003 and M0-1905. They function as the inboard pressure isolation valves for the A and B LPCI lines in the RHR system. V-19-0149 and V-20-0082 are verified to properly open and close, and are subjected to a hydrostatic seat leakage test at a nominal differential pressure of 1000 psid during each refueling outage. The allowable seat leakage rate is 5 gpm. There are no operational limits associated with these valves.
I i
c .. , .
- Mr. Thomas ' E. M' urley NG-87-1881 i June 11, 1987 j
Page Three Please note that~ Reference ~1 required similar testing of two additional motor operated valves (M0-1900 and M0-1901) in the RHR. system which then. .
functioned as the inboard and outboard isolation' valves for the RHR system head spray line. .However, during the Cycle 8/9 refueling outage, the Head Spray Mode of..the RHR system was . permanently disabled and. the head spray-line was blank fl anged . The valves were closed, retired in place, and electrical power was j removed from the associated motor controllers. Subsequently, M0-1900 and M0-1901 i
were removed from the IST- Program.
Should you have any questions regarding this' letter, please contact this.~ j office.
Very truly yours,
%% C Richard W. McGaughy ,
Vice-President,. Production - !
RWM/NKP/gj*
cc: N. Peterson L. Liu '
A. Cappucci (NRC-NRR)
L. Root NRC Resident Office A. Bert Davis (NRC-Region III Office)
Commitment Control 870052