ML20140E805
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| ML20140E805 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 01/31/1986 |
| From: | Hind J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Leslie Liu IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| References | |
| NUDOCS 8602040085 | |
| Download: ML20140E805 (2) | |
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:NRC TO UTILITY MONTHYEARML20058G2881990-11-0101 November 1990
[Table view]Confirms 901108 Mgt Meeting in Palo,Ia to Discuss Security Issue Re Poor Security Noted in 900910 Insp ML20058C7601990-10-26026 October 1990 Advises That Confirmatory Action Ltr CAL-RIII-90-13 Closed. Facility May Resume Normal Requalification Activities ML20059N6301990-10-10010 October 1990 Forwards Safeguards Insp Rept 50-331/90-19 on 900910. Violations Noted.Notice of Violation Withheld ML20059M4971990-09-24024 September 1990 Confirms 901004 Meeting in Palo,Ia to Discuss Outage Lessons,Engineering Backlog & Staffing Resources ML20059G8921990-09-0505 September 1990 Advises That Written & Operating Exams Scheduled for Wk of 901203.Approved Ref Matl Listed in Encl Should Be Furnished at Least 60 Days Prior to Exam Date in Order for NRC to Meet Schedule ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date ML20056A4981990-08-0101 August 1990 Forwards Master Bwr/Pwr Generic Fundamentals Exam Section W/Answer Key.W/O Encls ML20055J2081990-07-24024 July 1990 Confirms Plans for Mgt Meeting on 900731 in Region III Ofc to Discuss Plant Status & Other Items of Mutual Interest ML20055E1501990-07-0303 July 1990 Confirms Plans of 900705 Mgt Meeting W/Designated Members in Glen Ellyn,Il to Discuss Actions Planned to Improve Reactor Operator Requalification Program ML20059M8851990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248D6361989-09-27027 September 1989 Confirms 891004 Mgt Meeting W/Util in Region III Ofc to Discuss Licensee Actions as Result of GE Introspect Recommendations,Resolution of River Water Silting Problems & Engineering Program Improvements ML20248C5881989-09-25025 September 1989 Forwards Amend 8 to Indemnity Agreement B-68,reflecting Changes to 10CFR140.Util Requested to Submit Signed Amend to Signify Acceptance ML20246D2421989-08-21021 August 1989 Informs That Technical Concerns Expressed by Alleger Not Substantiated & Considered Closed,Per 870901 Allegation. Concerns Expressed Over Job Discrimination Will Remain Open Until Dept of Labor Rules on Matter ML20247D7401989-07-19019 July 1989 Confirms 890718 Discussion Between K Putnam & I Jackiw Re 890912 Mgt Meeting to Discuss Plant Operating Performance, Security Issues,Followup on Previous SALP Weaknesses & Other Issues of Concern ML20247A0611989-05-0404 May 1989 Forwards SER Accepting Util Response to Generic Ltr 83-28, Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing. Technical Evaluation Rept Also Encl ML20246L7591989-03-0606 March 1989 Confirms Plans for 890309 Meeting in Glen Ellyn,Il to Discuss Results of Licensee Safety Sys Functional Insp ML20206K4821988-11-23023 November 1988 Responds to Wc Rothert to AB Davis Re Allegations of Drug Use by Util Employees.Concurs W/Licensee Findings That Allegations Unsubstantiated ML20206G7641988-11-17017 November 1988 Confirms 881121 Meeting in Region III Ofc to Discuss Leakage & Repairs to Msivs,Per 881103 Telcon ML20155F5651988-10-0707 October 1988 Forwards Grading & Answer Sheets for 880921 Generic Fundamentals Pilot Exam.W/O Encls ML20154P7361988-09-28028 September 1988 Requests That Util Initiate Investigation in Order to Fully Analyze Allegation Involving Individuals Working at Plant & to Determine If Allegation Substantiated or Not.Encl Withheld (Ref 10CFR2.790) ML20151Z8481988-08-23023 August 1988 Confirms Arrangements for Written & Oral Exams Scheduled for Wk of 881219,per Telcon.Encl 1, Ref Matl Requirements for Reactor/Senior Reactor Operator Licensing Exam, Will Have to Be Furnished Prior to Exam in Order to Meet Schedule ML20151X5121988-08-19019 August 1988 Advises That Rev 7 to QA Program Description Consistent W/ 10CFR50,App B & Acceptable ML20207F8881988-07-27027 July 1988 Forwards Latest Rev of NRC Manual Chapter 0516, Salp. Region III Will Begin Using New Functional Areas Set Forth in Rev for All SALP Rept Periods Which Extend Beyond 880606 Effective Date of Procedure ML20150B8901988-06-23023 June 1988 Forwards Draft Rev 5 to ES-601, Administration of NRC Requalification Program Evaluations. W/O Encl ML20149G5741988-02-12012 February 1988 Informs of Willingness to Formally Present License Certificates to Newly Licensed Individuals,In Recognition of Accomplishment & Culmination of Rigorous Study & Training Program ML20149G4861988-02-12012 February 1988 Forwards Pilot Requalification Exam Given at Hb Robinson to Aid Util in Generating Questions for Anticipated Testing Later in Yr.Util Encouraged to Review Programs & Manpower Commitments to Accomodate Effort.W/O Encls ML20235F4221987-09-22022 September 1987 Forwards NRR Position Re Entry Into Limiting Condition for Operation Based on Inservice Testing Surveillance Results within Required Action Range.Review of Practices for Performing Inservice Testing Surveillances Recommended ML20235B0901987-09-15015 September 1987 Ack Receipt of 861202 Proposed Amend to Facility Physical Security Plan in Response to Miscellaneous Amends & Search Requirements.Response to Request for Addl Info & Revs Requested within 30 Days of Ltr Receipt ML20239A4471987-09-11011 September 1987 Advises That Arrangements Made for Operator & Senior Operator Licensing Exams for Wk of 871207.Encl Ref Matl Requested within 60 Days Prior to Exam Date ML20238A0651987-08-18018 August 1987 Forwards Exam Rept 50-331/OLS-87-01 of Exams Administered During 870715-16 ML20237J7571987-08-13013 August 1987 Advises That Current Tech Specs Require That All ESF Actuation Logic Relay Contacts Be Tested at Each Refueling Outage,Per 870514 Insp of Util Program to Improve HPCI & RCIC Reliability & 870713 Meeting ML20214U9841987-06-0303 June 1987 Forwards Revised NRC Form 398,personal Qualifications statement-licensee & NRC Form 396,certification of Medical Exam by Facility Licensee.Forms Revised to Reflect Changes to 10CFR55 Effective on 870526.W/o Encls ML20206Q3301987-04-14014 April 1987 Ack Receipt of 870401 Response to Emergency Response Facility Appraisal Rept 50-331/86-20.Proposed Schedule for Completing Corrective Actions for Items 1,4a,4e,4f & 8 Excessive.Requests That Schedules Be Shortened ML20206F6351987-04-10010 April 1987 Requests Listed Approved Ref Matls for Operator/Senior Operator Licensing Exams at Least 60 Days Prior to Written & Oral Exams Scheduled for Wk of 870713.Info Re Administration of Exams & Applicable Rules & Guidance Also Encl ML20212P6791987-03-0909 March 1987 Advises That 870227 Rev 17 to Security Plan Consistent W/ Provisions of 10CFR50.54(p) & Acceptable ML20207Q9521987-03-0505 March 1987 Confirms That Equipment Qualification Insp of Electrical & Instrumentation Equipment Will Be Held on 870413-17.Listed Documents,Including Util Response to Generic Ltr 84-24, Should Be Submitted by 870327 to Facilitate NRC Preparation ML20211H5121987-02-20020 February 1987 Forwards Safeguards Insp Rept 50-331/87-05 on 870126-0204.No Violations Noted ML20211F9781987-02-18018 February 1987 Forwards Safety Insp Rept 50-331/86-19 on 861202-05,09-12, 15-18 & 870112-16 & Notice of Violation ML20211M3481987-02-11011 February 1987 Forwards Safety Insp Rept 50-331/87-02 on 861118-870202.No Noncompliance Noted ML20210F7671987-02-0606 February 1987 Forwards Exam Rept 50-331/OL-86-03 of Exams Administered on 861216-19 ML20210T5961987-02-0606 February 1987 Forwards Insp Rept 50-331/86-20 on 861117-21 of Emergency Response Facilities.No Violations Noted.List of Open Items Identified During Appraisal Encl.Requests Written Response within 45 Days of Ltr Date ML20210A6491987-02-0303 February 1987 Forwards Safety Insp Rept 50-331/87-03 on 870105-09.No Violation Noted ML20212R0641987-01-22022 January 1987 Forwards Exam Rept 50-331/OL-86-02 of Exams Administered on 861216-19 ML20212R6781987-01-21021 January 1987 Ack Receipt of ,Transmitting Rev 6 to Emergency Plan,Effective on 861121.Rev Unacceptable.Resubmittal of Rev 6 Requested,Including Previously Omitted Emergency Action Levels in Table D-2 of Section D ML20207Q6501987-01-16016 January 1987 Extends Invitation to Participate in 870129 Workshop in Chicago,Il on NRC Incident Investigation Program.W/O Stated Encls ML20211Q2741986-12-0909 December 1986 Forwards Safety Insp Rept 50-331/86-15 on 861117-19.No Violations Noted.Exercise Weakness Requires Corrective Action ML20215C3331986-12-0505 December 1986 Informs of NRC 870204-05 Early Emergency Responders Workshop & FEMA 870203 Radiological Emergency Plan Conference in Chicago,Il to Discuss Lessons Learned & Current Problems in Coordination & Integration of Emergency Response Efforts ML20214K8681986-11-21021 November 1986 Forwards Safety Insp Rept 50-331/86-17 on 860916-1117.No Noncompliance Noted ML20215M5441986-10-27027 October 1986 Forwards 860922 Rev to NRC Appraisal Document to Facilitate Planning for Emergency Response Facility Appraisal Scheduled for 861117-21.W/o Encl ML20211F8021986-10-21021 October 1986 Forwards 860922 Rev to NRC Emergency Response Facility Appraisal Document to Facilitate Planning for 861117-21 Emergency Response Facility Appraisal.W/O Encl 1990-09-05 Category:OUTGOING CORRESPONDENCE 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 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 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 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 ML20212H2121999-09-27027 September 1999 Forwards Request for Addl Info Re 990412 Licensee Request to Revise DAEC TS SR 3.6.1.3.7 to Allow Representative Sample of Reactor Instrumentation Line EFCV to Be Tested Every 24 Months,Instead of Testing Each EFCV Every 24 Months ML20212H2151999-09-22022 September 1999 Forwards Amend 228 to License DPR-49 & Safety Evaluation. Amend Revises DAEC TS SR 3.4.3.1, Safety/Relief Valves & Safety Valves ML20212A8711999-09-14014 September 1999 Informs That 990716 Application Which Submitted Affidavit & Attachment Re Addl Info Re Cycle Specific SLMCPR for Plant Cycle 17, June 1999,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20211M5621999-09-0202 September 1999 Forwards Insp Rept 50-331/99-08 on 990712-16 & 0810-12.No Violations Noted.Insp Consisted of Review of Source Term Reduction & Integration of ALARA Into Work Planning & Execution,Calibration & Maint ML20211F7831999-08-26026 August 1999 Forwards Insp Rept 50-331/99-09 on 990708-0819.Violation Re Failure to Log Entry Into TS Limiting Condition for Operation When Power Lost to Drywell Sump Pump Level Switches,Noted & Being Treated as NCV ML20210V1231999-08-17017 August 1999 Forwards Insp Rept 50-331/99-10 on 990802-06.No Violations Noted.Insp Examined Activities Conducted Under Emergency Preparedness Program ML20211A8731999-08-16016 August 1999 Ack Receipt of 990212 & 0402 Ltrs,Which Transmitted Changes Identified as Revs 39 & 40 to DAEC Security Plan,Submitted Under Provisions of 10CFR50.54(p).NRC Review Comments for Subject Plans,Encl ML20210L8311999-07-27027 July 1999 Forwards Insp Rept 50-331/99-05 on 990601-0701.Violations Noted.Insp Included Assessment & Evaluation of Engineering Support,Design Change & Mod Activities Including 10CFR50.59 Safety Evaluations,Applicability Reviews & C/As ML20210E9781999-07-26026 July 1999 Informs That Info Submitted by Ltr (Nep 99-0067), Ies Utilities,Inc,Will Be Withheld from Public Disclosure, Per 10CFR2.790(a)(6) ML20210E1431999-07-22022 July 1999 Provides Summary of 990715 Meeting with Alliant Utilities & Duane Arnold Energy Ctr Mgt Re Recent Plant Performance Review Issued by NRC for Duane Arnold Energy Ctr.Associated Meeting Summary & Alliant Utilities Meeting Handout Encl ML20210B7161999-07-20020 July 1999 Forwards Audit Rept on Y2K Contingency Planning Program at Duane Arnold Energy Center Conducted on 990615-16 as follow-up to NRC GL 98-01 ML20210B5271999-07-16016 July 1999 Forwards Insp Rept 50-331/99-07 on 990526-0707.Two Violations Being Treated as Noncited Violations ML20209E8401999-07-13013 July 1999 Discusses Completion of NRC GL 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling & Containment Heat Removal Pumps for Plant ML20209G4991999-07-12012 July 1999 Forwards Insp Rept 50-331/98-05 on 990622-24.No Violations Noted ML20207H6741999-07-0606 July 1999 Forwards Operating Licensing Exam Rept 50-331/99-301(OL) on 990525.Staff Administered Written Exam to One Reactor Operator Applicant Previously Demonstrating Unsatisfactory Results During Jul 1998 Exam ML20212J4521999-06-25025 June 1999 Discusses Closure of TAC MA1188 Re Response to RAI to GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20196A1431999-06-18018 June 1999 Confirms Discussion Between Members of Staffs to Have Meeting on 990715 at Training Ctr at Duane Arnold Energy Ctr to Discuss Results of Plant Performance Review Process ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195G9581999-06-0909 June 1999 Forwards Amend 227 to License DPR-49 & Safety Evaluation. Amend Revises DAEC TS by Adding New TS 3.7.9, Control Building/Standby Gas Treatment Sys (Cb/Sbgt) Instrument Air Sys ML20195F2181999-06-0909 June 1999 Forwards Insp Rept 50-331/99-04 on 990414-0525.One Violation of NRC Requirements Identified Involving Inadequate Testing of Standby Liquid Control Sys Valves & Being Treated as non-cited Violation ML20207G4281999-06-0707 June 1999 Forwards Synopsis from Investigation Conducted by NRC Office of Investigations to Determine Whether Quality Control Inspector Was Discriminated Against by Being Laid Off at Duane Arnold Energy Center After Raising Safety Concern ML20207G4931999-06-0707 June 1999 Discusses OI Rept 3-1998-023 Conducted by NRC to Determine Whether Quality Control Inspector,Employed by Spec Insp Was Discriminated Against by Being Laid Off at Plant After Raising Safety Concern ML20195D2631999-06-0707 June 1999 Forwards RAI on Third 10 Yr ISI Interval ISI Relief Requests.Addl Info Necessary to Complete Review of Request for Relief NDE-R035 Should Be Provided within 30 Days of Date of Ltr ML20207F1431999-06-0303 June 1999 Provides Individual Exam Results for Applicant Who Took 990525 Initial License Retake Exam.Encls Withheld ML20207B5821999-05-25025 May 1999 Advises That Rept Entitled, Criticality SE of Sf Storage Racks in Duane Arnold Energy Ctr for Max Enrichment Capability, & Holtec Rept HI-971708,dtd Aug 1997,marked Proprietary Will Be Withheld from Public Disclosure ML20207A7981999-05-20020 May 1999 Informs That During 990319 Telcon Between K Young & M Bielby,Arrangements Were Made for Administration of Licensing Exams at Duane Arnold Energy Center for Week of 990920 ML20206N7491999-05-13013 May 1999 Forwards Safety Evaluation Accepting Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20206N4531999-05-12012 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created. Reorganization Chart Encl ML20206G5271999-05-0404 May 1999 Informs That by ,Ies Utilities,Inc Provided Changes to QA Program in Ufsar,Rev 20 for Daec.Nrc Approval Not Required Prior to Implementation of Proposed Changes ML20206G4821999-05-0404 May 1999 Informs That NRC Reviewed Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions & Accepts Resolution for Issue of Thermally Induced Pressurization ML20205T6011999-04-23023 April 1999 Forwards Insp Rept 50-331/99-03 on 990303-0413.No Violations Noted.Inadequate Implementation of Mod to a Reactor Water Cleanup Pump Installed Resulted in Insufficient Oil Level & Subsequent Bearing Failure ML20205G2541999-04-0101 April 1999 Forwards RAI Re GL 95-07, Pressure-Locking & Thermal- Binding of Safety-Related Power-Operated Gate Valves. Response Requested within 30 Days from Date of Ltr ML20205D5201999-03-31031 March 1999 Requests Addl Info on GL 95-07, Pressure-Locking & Thermal- Binding of Safety-Related Power-Operated Gate Valves, Per Util 960213 Response.Response Should Provide Addl Info as Identified in Encl within 30 Days of Ltr Date ML20205A6291999-03-26026 March 1999 Informs of NRC Planned Insp Effort Resulting from Duane Arnold Energy Ctr Plant Performance Review for Period 970928-990131.Historical Listing of Plant Issues & Details of Insp Plan for Next 8 Months Encl ML20204J7341999-03-24024 March 1999 Forwards Insp Rept 50-331/99-01 on 990113-0302.No Violations Noted ML20204D1831999-03-16016 March 1999 Discusses Review of Revision 20 to Section H of Plant Energy Ctr Emergency Plan ML20207H9451999-03-11011 March 1999 Discusses Review of Rev 20 to Portions of Plant Emergency Plan.Rev Submitted Per 10CFR50.54(q) ML20207G0111999-03-0303 March 1999 Discusses GL 96-05 Issued on 960918 & Ies Utilities,Inc Responses ,970317,980513 & 981120 for Duane Arnold Energy Center.Concludes That Licensee Established Acceptable Program to Verify design-basis Capability of MOVs ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20203F1301999-02-10010 February 1999 Forwards Insp Rept 50-331/98-15 on 981125-990112 & NOV Re Failure to Review & Implement Applicable Procedure Requirements,Due to Sense of Urgency by Quality Control Inspector to Complete Work ML20202G4191999-02-0101 February 1999 Forwards Insp Rept 50-331/99-02 on 990119-21.No Violations Noted.Inspector Concluded That Staff Had Been Effective in Implementing C/As for Items Reviewed ML20202B3671999-01-26026 January 1999 Forwards Safety Evaluation Addressing Thermo-Lag Related Ampacity Derating Issues & Technical Evaluation of Duane Arnold Energy Ctr Analysis of Ampacity Loads for Fire Barrier Clad Power Cables. Technical Evaluation Rept Encl ML20202B4231999-01-26026 January 1999 Forwards Safety Evaluation of Request for Approval to Use ASME Code Case N-508-1 in ISI Program for Duane Arnold Energy Ctr.Request Authorized 1999-09-30 |
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Xt; 31 1,56 Docket No. 50-331 Iowa Electric Light and power Company ATTH: Mr. Lee Liu President and Chief Executive Officer IE Towers P. O. Box 351 Cedar Rapids, IA 52406 Gentlemen:
The NRC is in the process of conducting safeguards Regulatory Effectiveness Reviews at ruclear power reactors. I wish to inform you that the Duane Arnold facility has been chosen for such a review scheduled for the week of March 31 through April 4, 1986.
The prime purpose of the review program is to evaluate the overall effective-ness of the Duane Arnold safeguards program and to determine whether existing safeguards regulations yield the level of protection intended by NPC. The team performing the review supports NPC's quality assurance program for safeguards, both as it applies to the Duane Arnold security system and to NPC's regulations. The review will complement, but be independent of, the licensing and inspection functions.
The review at Duane Arnold will be conducted by a tean with representatives from the Division of Safeguards, Region III, and U.S Army Special Forces personnel fron Fort Bragg, North Carolina. The review team will be conprised of two groups. One group will look at the facility's safeguards from the perspective of an insider, while the other will view safeguards from an external adversary's perspective. The resident inspector will participate.
The names and other identification information will be forwarded in another letter.
The review will initiate with an entrance briefing. You may wish to have a representative of your corporate staff present during this briefing, as it will provide an overview of the team's objectives and anticipated activities for the duration of the visit. Any questions that may arise concerning the team's review technioue or other matters, will be addressed at that tine.
For the remainder of the first day, the team would like to have a plant orientation tour with emphasis on safeguards areas and systems, ar.d begin the
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9602040005 060131 I PDR ADOCK 05000331 F pon
Icwa Electric Light and 2 JMt 3 i 1986 Power Company examination of plant vital areas. During the remainder of the onsite assessment, the team will continue reviewing vital areas and components and the entire safeguards program. The last day is reserved for any activities the team has been unable to accomplish and for a briefing of plant and corporate personnel on the preliminary results of the review.
Please provide appropriate plant personnel support for both groups of the team during the scheduled review. The external group will require an escort from the security department who can comunicate with alarm stations. The internal group will need escorts from both security and plant operations. The latter should be individuals familiar with the locations and detailed operation of the engineered safety feature systems and components at Duane Arnold. The team will make every effort to schedule its activities so as to avoid disruption of nonral plant operations. The time that various team members will spend onsite will vary, but generally will range from 4 to 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per day.
If you have any questions regarding the conduct of these regulatory effectiveness reviews which you wish to have answered prior to the team's visit, please contact Robert Dube, Safeguards System Evaluation Section, at (301) 427-4723 or G. M. Christoffer (312) 790-5744 of the Region III staff.
Sincerely, (kh Jack A. Iind, Director
" Division of Padiation Safety and Safeguards cc: D. Mineck, Plant Superintendent Nuclear DCS/RSB(RIDS)
Licensing Fee Managerrent Branch Resident Inspector, RIII Thomas Houvenagle, Iowa State Correrce Consnission bcc: R. F. Burnett, NMSS H. N. Berkow, NRR M. C. Thadani, PM, NRR RIII RIII tile,3i RIIIk eoyd P d 9,, , ,-
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