Semantic search

Jump to navigation Jump to search
 Issue dateTitleTopic
ML20217N55221 October 1999Forwards 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
ML20217M33720 October 1999Forwards Notice of Docketing of License SNM-2506 Amend Application.Notice Has Been Forwarded to Ofc of Fr for Publication
ML20217M11119 October 1999Forwards Insp Repts 50-282/99-14 & 50-306/99-14 on 990920- 22.One Violation Noted & Being Treated as Ncv.Insp Focused on Testing & Maint of Heat Exchangers in High Risk SysSignificance Determination Process
ML20217H89218 October 1999Forwards 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
ML20217F48014 October 1999Provides 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
ML20217F7227 October 1999Forwards Insp Rept 50-331/99-11 on 990820-0930.No Violations NotedPower change
ML20217C2356 October 1999Forwards Insp Repts 50-282/99-12 & 50-306/99-12 on 990823-0917.No Violations Noted.Insp Consisted of Selected Exam of Procedures & Representative Records,Observation of Activities & Interviews with Personnel
ML20212L0415 October 1999Informs 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
ML20217A93330 September 1999Informs 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
ML20212J87630 September 1999Forwards 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
IR 05000272/199900728 September 1999Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified
ML20212J88128 September 1999Forwards Preliminary Accident Sequence Precurson Analysis of Operational Event That Occurred at Plant,Unit 1 on 990105, for Review & Comment.Comment Requested within 30 Days of Receipt of LtrEmergency Lighting
ML20212H21227 September 1999Forwards 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 MonthsIncorporated by reference
ML20212G98023 September 1999Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island
ML20212H21522 September 1999Forwards Amend 228 to License DPR-49 & Safety Evaluation. Amend Revises DAEC TS SR 3.4.3.1, Safety/Relief Valves & Safety Valves
ML20212D84016 September 1999Discusses 990902 Telcon Between D Wesphal & R Bailey Re Administeration of Retake Exam at Prairie Island During Wk of 991206.NRC May Make Exam Validation Visit to Facility During Wk of 991116
ML20212A87114 September 1999Informs 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)
ML20217H23310 September 1999Forwards Security Insp Repts 50-282/99-10 & 50-306/99-10 on 990809-12.Two Findings,Each of Low Risk Significance Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy
ML20217H5669 September 1999Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils EnclSignificance Determination Process
ML20212A9249 September 1999Discusses Plans Made During 990902 Telephone Conversation to Inspect Licensed Operator Requalification Program at Prairie Island During Weeks of 991101 & 991108.Requests That Written Exams & Operating Tests Be Submitted by 991022
ML20212B0519 September 1999Forwards Insp Repts 50-282/99-11 & 50-306/99-11 on 990816-20.One Issue of Low Safety Significance Was Identified & Being Treated as Ncb
ML20211Q7648 September 1999Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant Operator License Applicants During Wk of 000515,in Response to D Westphal
ML20211M5622 September 1999Forwards 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
ML20211F78326 August 1999Forwards 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 NCVDownpower
ML20211D35424 August 1999Discusses GL 95-07 Re Pressure Locking & Thermal Binding of safety-related Power Operated Gate Valves.Forwards SE Re Response to GL 95-07
ML20211C76019 August 1999Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program
ML20210V12317 August 1999Forwards Insp Rept 50-331/99-10 on 990802-06.No Violations Noted.Insp Examined Activities Conducted Under Emergency Preparedness Program
ML20211B26217 August 1999Forwards Insp Repts 50-282/99-09 & 50-306/99-09 on 990719-22.No Violations Noted.Insp Included Review & Evaluation of Current Emergency Preparedness Performance Indicators
ML20211C73717 August 1999Discusses Closure of Staff Review Re Generic Implication of Part Length Control Rod Drive Mechanism Housing Leak on 980123.Enclosed NRC 980811 & 1223 Ltrs Responded to WOG Positions Re Corrective ActionsNon-Destructive Examination
Hydrostatic
Probabilistic Risk Assessment
Operating Basis Earthquake
Earthquake
Pressure boundary leak
ML20211A87316 August 1999Ack 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
ML20210R70212 August 1999Forwards Insp Repts 50-282/99-06 & 50-306/99-06 on 990601- 0720.One NCV Occurred,Consistent with App C of Enforcement Policy
ML20210T56612 August 1999Forwards RAI Re & Suppl ,which Requested Exemptions from TSs of Section III.G.2 of 10CFR50 App R,To Extent That Specifies Separation of Certain Redundant Safe Shutdown Circuits with fire-related BarriersSafe Shutdown
Fire Barrier
Exemption Request
ML20210P51911 August 1999Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & NSP Responses for PINGP & 951117. Staff Reviewed Info in Rvid & Released Info as Rvid Version 2.Requests Submittal of Comments Re Revised Rvid by 990901
ML20210L83127 July 1999Forwards 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/AsTemporary Modification
ML20210E97826 July 1999Informs That Info Submitted by Ltr (Nep 99-0067), Ies Utilities,Inc,Will Be Withheld from Public Disclosure, Per 10CFR2.790(a)(6)
ML20210E14322 July 1999Provides 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 EnclTemporary Modification
Systematic Assessment of Licensee Performance
ML20210B71620 July 1999Forwards Audit Rept on Y2K Contingency Planning Program at Duane Arnold Energy Center Conducted on 990615-16 as follow-up to NRC GL 98-01
ML20210B52716 July 1999Forwards Insp Rept 50-331/99-07 on 990526-0707.Two Violations Being Treated as Noncited Violations
ML20209J09415 July 1999Forwards SER Finding Rev 7 to Topical Rept NSPNAD-8102, Reload Safety Evaluation Methods for Application to PI Units, Acceptable for Ref in Plant Licensing ActionsShutdown Margin
ML20209E84013 July 1999Discusses Completion of NRC GL 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling & Containment Heat Removal Pumps for Plant
ML20209G49912 July 1999Forwards Insp Rept 50-331/98-05 on 990622-24.No Violations NotedNondestructive Examination
ML20207H6746 July 1999Forwards 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
ML20209H8362 July 1999Forwards Operator Licensing Exam Repts 50-282/99-301(OL) & 50-306/99-301(OL) for Tests Administered During Week of 990517-21.Two Applicants Passed All Sections of Exam & Issued Reactor Operator Licenses to Operate Pings
ML20196J9681 July 1999Informs That in Sept 1998,Region III Received Rev 20 to Portions of Util Emergency Plan Under 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of Licensee Emergency Plan,No NRC Approval Required
ML20209F03930 June 1999Forwards Insp Repts 50-282/99-04 & 50-306/99-04 on 990407-0531.Violation Noted.Notice of Violation or Civil Penalty Will Not Be Issued,Based on NRC Listed Decision to Exercise DiscretionEnforcement Discretion
ML20212J45225 June 1999Discusses Closure of TAC MA1188 Re Response to RAI to GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity
ML20196A14318 June 1999Confirms 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
ML20196D55018 June 1999Forwards Individual Exam Results for Licensee Applicants Who Took May 1999 Initial License Exam.In Accordance with 10CFR2.790,info Considered, Proprietary. Without Encls
ML20212J05417 June 1999Responds 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 FirstWeld Overlay
ML20196A67417 June 1999Refers to 990517-20 Meeting with Util in Welch,Minnesota Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA StaffProbabilistic Risk Assessment