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Issue date | Title | Topic | |
---|---|---|---|
ML20217M337 | 20 October 1999 | Forwards Notice of Docketing of License SNM-2506 Amend Application.Notice Has Been Forwarded to Ofc of Fr for Publication | |
ML20217M111 | 19 October 1999 | Forwards 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 Sys | Significance Determination Process |
ML20217C235 | 6 October 1999 | Forwards 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 | |
IR 05000272/1999007 | 28 September 1999 | Forwards 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 | |
ML20212J881 | 28 September 1999 | Forwards 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 Ltr | Emergency Lighting |
ML20212G980 | 23 September 1999 | Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island | |
ML20212D840 | 16 September 1999 | Discusses 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 | |
ML20217H233 | 10 September 1999 | Forwards 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 | |
ML20212B051 | 9 September 1999 | Forwards 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 | |
ML20217H566 | 9 September 1999 | Discusses 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 Encl | Significance Determination Process |
ML20212A924 | 9 September 1999 | Discusses 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 | |
ML20211Q764 | 8 September 1999 | Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant Operator License Applicants During Wk of 000515,in Response to D Westphal | |
ML20211D354 | 24 August 1999 | Discusses GL 95-07 Re Pressure Locking & Thermal Binding of safety-related Power Operated Gate Valves.Forwards SE Re Response to GL 95-07 | |
ML20211C760 | 19 August 1999 | Confirms 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 | |
ML20211B262 | 17 August 1999 | Forwards 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 | |
ML20211C737 | 17 August 1999 | Discusses 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 Actions | Non-Destructive Examination Hydrostatic Probabilistic Risk Assessment Operating Basis Earthquake Earthquake Pressure boundary leak |
ML20210T566 | 12 August 1999 | Forwards 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 Barriers | Safe Shutdown Fire Barrier Exemption Request |
ML20210R702 | 12 August 1999 | Forwards Insp Repts 50-282/99-06 & 50-306/99-06 on 990601- 0720.One NCV Occurred,Consistent with App C of Enforcement Policy | |
ML20210P519 | 11 August 1999 | Discusses 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 | |
ML20209J094 | 15 July 1999 | Forwards SER Finding Rev 7 to Topical Rept NSPNAD-8102, Reload Safety Evaluation Methods for Application to PI Units, Acceptable for Ref in Plant Licensing Actions | Shutdown Margin |
ML20209H836 | 2 July 1999 | Forwards 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 | |
ML20196J968 | 1 July 1999 | Informs 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 | |
ML20209F039 | 30 June 1999 | Forwards 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 Discretion | Enforcement Discretion |
ML20196D550 | 18 June 1999 | Forwards Individual Exam Results for Licensee Applicants Who Took May 1999 Initial License Exam.In Accordance with 10CFR2.790,info Considered, Proprietary. Without Encls | |
ML20196A674 | 17 June 1999 | Refers to 990517-20 Meeting with Util in Welch,Minnesota Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff | Probabilistic Risk Assessment |
ML20207B584 | 26 May 1999 | Forwards SER Concluding That Licensee 990412 Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Reactor Vessel Head Penetrations for part-length CRDMs Will Provide Acceptable Quality & Safety | |
ML20207D064 | 26 May 1999 | Informs of Plans to Conduct Meeting on 990614 in Red Wing,Mn,To Present Planned Changes to NRC Regulatory Processes & Pilot Plant Program for Prairie Island Nuclear Generating Station | |
ML20207B794 | 25 May 1999 | Forwards Insp Repts 50-282/99-05 & 50-306/99-05 on 990426- 30.No Violations Noted.Overall Plant Radiological Controls Effective in Maintaining Reasonable Collective Dose for Work Being Conducted During Unit 1 Refueling Outage | |
ML20207B328 | 24 May 1999 | Informs That in May 1999,Region III Received Rev 20 to Portions of Prairie Island Nuclear Generating Center Emergency Plan.Rev Submitted Under Provisions of 10CFR50.54(q) | |
ML20207A149 | 20 May 1999 | Forwards Request for Addl Info Re Areas of Seismic,Fire,High Winds,Floods & Other External Events for IPEEE Submittals for PINGP Dtd Dec 1996,March 1998 & Dec 1998 | Hot Short Safe Shutdown High winds Earthquake |
ML20206S089 | 13 May 1999 | Informs That on 990505 NRC Staff Held Planning Meeting for Plant to Identify Insp Activities at Facility Over Next 6 to 12 Months | |
ML20206N458 | 13 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 | Enforcement Discretion |
ML20206J210 | 4 May 1999 | Forwards Insp Repts 50-282/99-02 & 50-306/99-02 on 990226-0406.No Violations Noted.During Insp Period,Sf Casks 08 & 09 Successfully Loaded & Cask 08 Transported & Placed in ISFSI | |
ML20206E180 | 29 April 1999 | Forwards Insp Rept 72-0010/99-01 on 990308-0413.No Violations Noted.Purpose of Insp Was to Observe Various Portions of Dry Fuel Cask Loading Program | |
ML20205R484 | 16 April 1999 | Forwards Security Insp Repts 50-282/99-03 & 50-306/99-03 on 990322-26.No Violations Noted.Objective of Insp Effort Was to Determine Whether Activities Authorized by License Were Conducted Safely & IAW NRC Requirements | |
ML20205R179 | 30 March 1999 | Responds to Issue Re Generic Implication of part-length Control Rod Drive Mechanism Housing Leak at Praire Island, Unit 2 & Beaver Valley Power Station,Units 1 & 2 | Non-Destructive Examination Hydrostatic Probabilistic Risk Assessment Operating Basis Earthquake Earthquake Pressure boundary leak |
IR 05000282/1998016 | 30 March 1999 | Discusses Fpfi Repts 50-282/98-16 & 50-306/98-16 on 980810-28.Determined That Violations Occurred Involving MOVs Being Unable to Satisfy post-fire Safe Shutdown Function & Spurious Actuation of Sys Due to Fire Damage | Safe Shutdown |
ML20205B578 | 26 March 1999 | Advises That NSPNAD-8102-P,rev 7, Prairie Island NPP Reload Safety Evaluation Methods for Application to PI Units Submitted in 990129 Application Will Be Withheld from Public Disclosure | |
ML20205G932 | 26 March 1999 | Informs of Planned Insp Effort Resulting from Prairie Island Plant Performance Review for Period 980328-990131.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 6 Months Encl | Safe Shutdown Probabilistic Risk Assessment Systematic Assessment of Licensee Performance |
ML20205C067 | 26 March 1999 | Informs That Exhibit E (CEN-629-P,Rev 03-P, Repair of W Series 44 & 51 Steam Generator Tubes Using Leak Tight Sleeves Will Be Withheld from Public Disclosure,Per Util 990205 Application & C-E Affidavit,Per 10CFR2.7990 | |
ML20205B516 | 26 March 1999 | Discusses Util Re Rept of Corrections to Licensee ECCS Evaluation Models.Attachments 1 & 2 from Were Withheld from Public Disclosure Due to Proprietary Markings from W.Attachments 1 & 2 Will Now Be Placed in PDR | |
ML20204E465 | 18 March 1999 | Forwards Insp Repts 50-282/99-01 & 50-306/99-01 on 990115-0225.No Violations Noted | |
ML20207E040 | 4 March 1999 | Forwards Request for Addl Info Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves, Program at Prairie Island Nuclear Generating Plant | |
ML20203F254 | 10 February 1999 | Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function | |
ML20206U183 | 9 February 1999 | Responds to Encl Ltrs, & 1223 Re Generic Implication of part-length CRDM Housing Leak.Review Under TAC Numbers MA1380 & MA1381 Considered Closed | |
ML20202G210 | 29 January 1999 | Forwards Insp Repts 50-282/98-23 & 50-306/98-23 on 981204- 990114.No Violations Noted.Insp Characterized by Several Unexpected Operational Events,Caused by Equipment Failure, Personnel Errors & Procedure Problems | |
ML20199L442 | 25 January 1999 | Informs That by Encl Ltrs & 981223,NRC Has Responded to WOG Positions Re C/As to Address Generic Aspects of part-length CRD Mechanism Housing Issue That Originated as Result of 980123 Leak at Pings | Non-Destructive Examination Hydrostatic Probabilistic Risk Assessment Operating Basis Earthquake Earthquake Pressure boundary leak |
ML20202J142 | 22 January 1999 | Informs of Completion of Review of NSP Which Proposed Alternative to Surface Exam Requirements of Paragraph N-518.4 of 1968 ASME BPV Code for CRD Mechanism Canopy Seal Welds.Forwards SE Supporting Alternative | Weld Overlay Liquid penetrant |
ML20199F847 | 14 January 1999 | Forwards FEMA Evaluation Rept for 980721-22 Emergency Preparedness Exercise at Prairie Island Nuclear Generating Station | |
ML20206U210 | 23 December 1998 | Provides Staff Response to Re WCAP-15126, Technical Assessment of Part Length CRDM Housing Motor Tube Cracking in WOG Plants.Nrc Agrees That Incremental Core Damage Frequency for Range of Defects Might Be 10.6 Per Ry | Non-Destructive Examination Hydrostatic Probabilistic Risk Assessment Operating Basis Earthquake Earthquake Pressure boundary leak |