ML19275A559: Difference between revisions
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{{#Wiki_filter:, | {{#Wiki_filter:, | ||
PDR w-331 - | PDR w-331 - | ||
NORTH CAROLINA STATE UNIVERSITY AT RALEIGH SCHOOL OF ENGINEERING | NORTH CAROLINA STATE UNIVERSITY AT RALEIGH SCHOOL OF ENGINEERING | ||
.m SEp 2^. Nil .. !6 li DeP4arussi or Nucturn Excissanisc Bos 5636 ZIP 27650 | .m SEp 2^. Nil .. !6 li DeP4arussi or Nucturn Excissanisc Bos 5636 ZIP 27650 | ||
| Line 27: | Line 26: | ||
==Dear Mr. MacDonald:== | ==Dear Mr. MacDonald:== | ||
Enclosed are two copies of our Quality Assurance Plan for Ship-ment of the R-3 Fuel. In the preparation of this docu=ent, the com-ments and suggesticas received frem internal reviews, North Carolina State University Radiatien Prctection Council, and others have been included. | Enclosed are two copies of our Quality Assurance Plan for Ship-ment of the R-3 Fuel. In the preparation of this docu=ent, the com-ments and suggesticas received frem internal reviews, North Carolina State University Radiatien Prctection Council, and others have been included. | ||
If you should require further informatien, please feel free to contact =e, or our Reactor Health Rysicist, Mr. Robert Cross. | If you should require further informatien, please feel free to contact =e, or our Reactor Health Rysicist, Mr. Robert Cross. | ||
Respect #ully subsitted, | Respect #ully subsitted, | ||
| Line 40: | Line 37: | ||
2 ccpies, Quality Assurance Plan for Shipment of R-3 Fuel, ec: J. R. Bohannen, Jr. | 2 ccpies, Quality Assurance Plan for Shipment of R-3 Fuel, ec: J. R. Bohannen, Jr. | ||
R. D. Cross , | R. D. Cross , | ||
W. L. Dunn Institute for Resource Management, Inc. w/encls, liOI 214 | W. L. Dunn Institute for Resource Management, Inc. w/encls, liOI 214 7 9.1 0 0 4 0 S V y .z _;_. n}} | ||
7 9.1 0 0 4 0 S V y .z _;_. n}} | |||
Latest revision as of 18:24, 1 February 2020
| ML19275A559 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold, North Carolina State University |
| Issue date: | 09/17/1979 |
| From: | Saxe R North Carolina State University, RALEIGH, NC |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19275A560 | List: |
| References | |
| NUDOCS 7910040644 | |
| Download: ML19275A559 (1) | |
Similar Documents at Duane Arnold, North Carolina State University | |
|---|---|
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-99-1383, 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 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-99-1327, 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 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 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 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 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 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-99-1126, 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 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-99-0859, 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 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:EDUCATIONAL INSTITUTION TO NRC MONTHYEARML20059D1391990-08-31031 August 1990
[Table view]Forwards Pulstar Annual Rept to NRC for Jul 1989 - June 1990, & Environ Radiation Surveillance Rept for Jul 1989 - Jul 1990 ML20055H9161990-07-24024 July 1990 Forwards Statement of Financial Qualifications,Per 10CFR50.33(f)(3) for Pulstar Reactor Facility ML20055G6441990-07-20020 July 1990 Forwards Rev 5 to Physical Security Plan,Per 900622 Request for Addl Info.Rev Incorporates Subj Matter of Three Commitments.Rev Withheld (Ref 10CFR2.790(d)) ML20055H0831990-07-18018 July 1990 Advises That Amend 9 to SAR Will Be Revised,Per Encl Calculations & Results in Response to Request for Addl Info ML20042E2951990-04-17017 April 1990 Forwards Rev 4 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(d)) ML19332C4051989-11-17017 November 1989 Forwards Kv Mani Current Resume,Transcripts for Degrees, Outlines for Ne 404 & Ne 508 Courses & Radiation Safety Short Courses Taught,In Response to 891106 Request for Qualifications of Reactor Health Physist.Encls Withheld ML19324C3911989-11-0606 November 1989 Requests That Pj Turinsky Be Removed from Publication Mailing List ML19324B5721989-10-20020 October 1989 Requests Addl Time to Respond to Questions on Pulstar SAR Until 891220 ML19327B1981989-10-13013 October 1989 Advises That Kv Mani Meets Tech Spec 6.1.4,despite Failure of American Board of Health Physics Exam.Mani Meets Acceptable Equivalent Statement Per Listed Qualifications. Facility Adequately Staffed ML19325D8271989-10-13013 October 1989 Requests Correction to Mailing List to Reflect Changes in Administration Identified in Amend 8 to License R-120, Figure 6.1-1 of Pulstar Nuclear Reactor Tech Specs ML20247A1821989-08-30030 August 1989 Responds to NRC Re Violations Noted in Insp. Corrective Actions:Personnel Trained by New Health Physics Procedure 30-2 & Permanent Electrical Svc Installed for Sampler by Univ Physical Plant Organization ML20206L7331988-11-21021 November 1988 Responds to NRC Re Violation Noted in Insp Rept 50-297/88-04.Corrective Actions:Radiation Protection Ofc in Process of Updating All Procedures,Including Procedures Associated W/Radiation Surveillance & Effluent Monitoring ML20206M3841988-11-17017 November 1988 Forwards Attachment A,Section 6.7.5.i, Environ Radiation Surveillance Rept for Period 870728-880308, to 1987-88 Tech Specs Annual Rept Dtd 880830.Attachment a Delayed in Printing & Unavailable W/Main Body of Rept ML20150F3391988-07-12012 July 1988 Responds to NRC Re Violations Noted in Insp Rept 50-297/88-03.Corrective Actions:Reactor Safeguards Advisory Group Meetings Will Be Scheduled by Manager of Nuclear Operations ML20236N5671987-11-0606 November 1987 Responds to NRC Re Violation Noted in Insp Rept 50-297/87-03.Corrective Actions:Procedure HP-40-1 Reviewed & Modified to Include Case of Unloading Samples When Reactor Shutdown ML20215A2321987-06-0303 June 1987 Forwards Environ Radiation Monitoring Program at Duane Arnold Energy Ctr,Cedar Rapids,Ia, for Jan-Dec 1986,per Cooperative Agreement NRC-30-83-648.Rept Submitted Late Due to Util Date Change for Info Submittal & Personnel Reasons ML20210A1611987-04-21021 April 1987 Responds to Re Violations Noted in Insp Rept 50-297/87-01 on 870316-18.Corrective Actions:Personnel Advised Not to Irradiate Matl for Transfer Outside Facility Until Procedure Issued & Shipping Form Revised ML20214L4831986-08-29029 August 1986 Forwards Annual Rept for Jul 1985 - June 1986 & Environ Radiation Surveillance Rept for Aug 1985 - Jul 1986 ML20203G3381986-06-12012 June 1986 FOIA Request for Documents Re Reactor & Senior Reactor Operator Licensing Exam Results for Jan 1983 - Dec 1984 ML20138C5601985-10-0808 October 1985 Responds to 850927 Order to Show Cause Re Possession of Highly Enriched U Onsite.Facility Not Licensed to Possess Highly Enriched U as of 850909 Amend to License R-120. Amend 9 Encl ML20134L7411985-08-29029 August 1985 Forwards Pulstar Annual Rept to NRC for Period Jul 1984 - June 1985 & Environ Radiation Surveillance Rept for Period Aug 1984 - Jul 1985 ML20112F0231985-03-20020 March 1985 Forwards Revised Pages 19,20,25,26 & 27 of Rev 1 to Pulstar Emergency Plan,Per NRC 850305 Questions ML20108A4761984-10-15015 October 1984 Forwards Corrected 840726 Request for Tech Spec Changes W/ Minor Editorial Corrections ML20092C5241984-06-15015 June 1984 Requests Delay of Implementation of Pulstar Emergency Plan to Allow Completion of Revised Version of Emergency Plan.Submittal of Revised Plan Expected within 60 Days ML20080H9351984-02-0606 February 1984 Informs That J Thomas Resigned as Chancellor of North Carolina State Univ to Accept Presidency of Univ of Alabama on 810630.New Chancellor Is Br Poulton ML20083J4511984-01-0404 January 1984 Notifies That Tl Brackin Has Been Appointed Acting Reactor Health Physicist for Pulstar Facility.Change in Mailing Address Noted ML20080C0801983-08-16016 August 1983 Notifies That Go Miller Permanently Appointed Nuclear Operations Administrator for Pulstar Facility ML20077H1511983-07-0101 July 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-297/83-01.Corrective Actions:Reactor Health Physicist Assigned Responsibility for Orientation Process ML20085A8031983-05-16016 May 1983 Forwards Rev 3 to Pulstar Reactor Security Plan,Eliminating Control Room Access Keys.Rev Withheld ML20072L6401983-03-29029 March 1983 Forwards Final Survey Re Radiation & Removable Contamination of R-3 Reactor Bay After Biological Shield Demolished.Final Survey Shows Compliance W/Criteria Established by RW Reid to Jl Thomas.Removable Contamination Survey Encl ML20072L6431983-03-16016 March 1983 Forwards Final Survey of R-3 Reactor Bay After Removing R-3 Reactor Biological Shield.Area Above Crane Track Shows No Greater Deviation of Radiological Cleanliness than Area Below Crane.No Swipes on Area Above Crane Necessary ML20064K9881983-01-26026 January 1983 Responds to NRC Re Violations Noted in IE Insp Repts 50-111/82-02 & 50-297/82-01.Justification That Present Procedure Re Stack Monitor Sys Provides Capability of Early Detection of Fuel Clad Failure Submitted ML20064L0061983-01-13013 January 1983 Responds to NRC Re Violation Noted in IE Insp Repts 50-111/82-02 & 50-297/82-02.Justification for Continued Use of Present Stack Gas Monitor Sys Procedures Provided ML20069N8451982-12-0303 December 1982 Advises That Decommissioning Will Take Longer than Anticipated Due to Technical Difficulty of Breaking Up Heavily Reinforced Concrete.Number of Demolition Workers Increased.Work Will Be Complete by 830120 ML20028A8041982-11-0303 November 1982 Forwards Public Version of Emergency Plan ML20069D7521982-09-17017 September 1982 Forwards Section 6.7.5(h),covering Environ Radiation Surveillance Portion of Annual Rept Submitted 820826 ML20063J4451982-08-26026 August 1982 Forwards Pulster Annual Rept to Nrc,Jul 1981-June 1982 ML20054H0841982-05-18018 May 1982 Responds to NRC Re Violations Noted in IE Insp Repts 50-111/82-02 & 50-297/82-01.Corrective actions:820312 Incident Reported & Reactor Safeguards Advisory Group Met 820331.Disputes Item a Re Safeguards Advisory Group ML20040F2771982-02-0404 February 1982 Forwards Section 6.7.5(b) Missing from Annual Rept for Environ Radiation Surveillance Submitted 810827 ML19347E6161981-04-30030 April 1981 Responds to NRC 810306 Ltr Providing Guidance Criteria for Release of Facility to Unrestricted Use.Addendum to Dismantling Plan Encl ML20003E5751981-03-27027 March 1981 Requests Prompt Attention to Univ Submittals Re Dismantling of Reactor.Plans in Progress to Renovate or Demolish Reactor Bldg.Map of Bldg & Surrounding Area Encl ML19350A9401981-03-12012 March 1981 Advises of Two Organizational Changes in Nuclear Engineering Dept.Pj Turinsky Replaces TS Elleman as Dept Head.Rg Cockrell Replaces Jr Bohannon as Director of Nuclear Reactor Program.Requests Appropriate Changes to Mailing Lists ML19341C6421981-02-19019 February 1981 Requests Dismantling of R-3 Reactor & Termination of License R-3 ML20003B1241981-02-0303 February 1981 Forwards Proposed Change to Tech Specs of License R-120 & Univ 791018 Cover Ltr to Ensure Positive Identification Per 810129 Telcon ML20008D8601980-10-10010 October 1980 Forwards Executed Amend 13 to Indemnity Agreement E-7, Changing Description of Location ML19344E6051980-08-27027 August 1980 Forwards Annual Rept,Jul 1979 to Jul 1980. ML19310A4021980-06-0505 June 1980 Forwards Dismantling Plan for R-3,10 Kw Reactor,In Response to NRC Request ML19316B1391980-06-0404 June 1980 Ack Receipt of NRC 800519 Ltr Re Physical Protection Requirements.Physical Security Plan Submitted & Implemented in 1974,achieves Objectives of 10CFR73.67(a),(b),(c),(f) & (G),Therefore New Plan Is Not Necessary ML19211C4541980-01-0404 January 1980 Submits Supporting Info to 791210 Ltr Re Mod to Request for Extension of License R-63.Info Re Area & Stack Monitors, Transfer of SNM from License R-63 & Plan to Dismantle/ Decommission Reactor Encl ML19211D1211980-01-0404 January 1980 Requests Certain Additions to License R-120.Portions Withheld (Ref 10CFR2.790) 1990-08-31 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-99-1214, 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 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 ML20202G9971999-02-0202 February 1999 Forwards Response to Telcon Discussion Between NRC & Licensee,Correcting Typo in Proposed TS Definition 1.26 & Using Definition in Proposed TS 3.1(f) 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 1999-09-09 |
Text
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NORTH CAROLINA STATE UNIVERSITY AT RALEIGH SCHOOL OF ENGINEERING
.m SEp 2^. Nil .. !6 li DeP4arussi or Nucturn Excissanisc Bos 5636 ZIP 27650
.; 17 September 1979
. ~.c Mr. Charles E. MacDonald, Director Nuclear Materials Safety and Safeguards U. S. Nuclear Regulatory Cc-4ssicn Washingten, D. C. 205k5 Ref: Docket No. 50-111 R-63 License Attenticn: Mr. Dick Cdegaarden
Dear Mr. MacDonald:
Enclosed are two copies of our Quality Assurance Plan for Ship-ment of the R-3 Fuel. In the preparation of this docu=ent, the com-ments and suggesticas received frem internal reviews, North Carolina State University Radiatien Prctection Council, and others have been included.
If you should require further informatien, please feel free to contact =e, or our Reactor Health Rysicist, Mr. Robert Cross.
Respect #ully subsitted,
~
$^-
RFS :1pe R. F. Saxe, Acting Head Department of Nuclear Engineering
Enclosures:
2 ccpies, Quality Assurance Plan for Shipment of R-3 Fuel, ec: J. R. Bohannen, Jr.
R. D. Cross ,
W. L. Dunn Institute for Resource Management, Inc. w/encls, liOI 214 7 9.1 0 0 4 0 S V y .z _;_. n
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