ML20203G494
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MONTHYEARML20237B0671985-11-25025 November 1985
[Table View]Summary of 851106 Meeting W/Util Re Reliability of Auxiliary Feedwater Sys.List of Attendees & Licensee Viewgraphs Encl Project stage: Meeting ML20138R1801985-12-24024 December 1985 Informs of Addl Areas for Improvement Identified During Retrospective Look at NRR Programs Re Loss of Feedwater Event.Issues Include Emergency Feedwater Sys Requirements & Assessment of Plant Safety Project stage: Other ML20203G4941986-04-24024 April 1986 Forwards Rev 0 to NSPNAD-8606P Prairie Island Units 1 & 2 Auxiliary Feedwater Sys Reliability Study. Evaluation in NUREG-0611 Should Not Be Used in Future Actions Re Auxiliary Feedwater Sys Reliability Project stage: Other NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit1986-11-26026 November 1986 Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit Project stage: Approval ML20209C2151987-01-21021 January 1987 Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) at Prairie Island Units 1 & 2.Util Actively Pursuing Improvements in Sys Reliability & Reducing Sys Challenges Project stage: Approval 1986-11-26 |
| ML20203G494 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/24/1986 |
| From: | Musolf D NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20203G501 | List: |
| References | |
| RTR-NUREG-0611, RTR-NUREG-611 TAC-61519, TAC-61520, NUDOCS 8604290133 | |
| Download: ML20203G494 (2) | |
Similar Documents at Prairie Island | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M3371999-10-20020 October 1999
[Table view]Forwards Notice of Docketing of License SNM-2506 Amend Application.Notice Has Been Forwarded to Ofc of Fr for Publication ML20217M1111999-10-19019 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 ML20217F4331999-10-15015 October 1999 Forwards Rev 39 to Security Plan.Changes Do Not Decrease Effectiveness of Security Plan.Rev Withheld,Per 10CFR73.21 ML20217C2351999-10-0606 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 ML20212J8811999-09-28028 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 IR 05000272/19990071999-09-28028 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 ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island ML20212F5121999-09-20020 September 1999 Forwards Response to NRC , Preparation & Scheduling of Operator Licensing Examinations ML20212D8401999-09-16016 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 ML20217H2331999-09-10010 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 ML20217H5661999-09-0909 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 ML20212A9241999-09-0909 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 ML20212B0511999-09-0909 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 ML20211Q7641999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant Operator License Applicants During Wk of 000515,in Response to D Westphal ML20211N8631999-09-0707 September 1999 Withdraws 970814 Request for Exemption from 10CFR50,App R, Section III.G.2, Fire Protection of Safe Shutdown Capabilities ML20211K5911999-09-0101 September 1999 Informs That Util Reviewed Rvid Data Base,As Requested in NRC .Summary of Proposed Changes & Observed Differences Are Included in Encl Tables ML20211L0211999-09-0101 September 1999 Provides Notification That License Amends 141 & 132 & Associated License Conditions 6 & 7 Have Been Fully Implemented ML20211K5931999-08-31031 August 1999 Forwards License Amend Request for License SNM-2506, Proposing Change to License Conditions 6,7 & 8 & TSs App a of License by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20211Q6041999-08-31031 August 1999 Forwards Rev 19 to USAR for Pingp,Per 10CFR50.71(e).Rev Brings USAR up-to-date as of 990228,though Some Info Is More Recent.Attachment 1 Contains Descriptions & Summaries of SE for Changes,Tests & Experiments,Per 10CFR50.59 ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211D3541999-08-24024 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 ML20211C7601999-08-19019 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 ML20211B8311999-08-19019 August 1999 Forwards Request for Relief 8 Re Limited Exams Associated with Unit 1 Third ten-year Interval Inservice Insp Program. Licensee Requests Relief Due to Impractibility of Obtaining 100% Exam Coverage for Affected Items ML20211B5711999-08-19019 August 1999 Forwards Second 90-day Rept for Implementation of Voltage Based Repair Criteria at Prairie Island Unit 1.Rept Fulfills Requirements of Section 6.b of Attachment 1 to GL 95-05 ML20211C2311999-08-19019 August 1999 Forwards Unit 1 ISI Summary Rept,Interval 3,Period 2 Refueling Outage Dates 990425-0526,Cycle 19 971212-990526. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarizes Results ML20211B0561999-08-18018 August 1999 Provides Addl Info on Proposed Rev to Main Steam Line Break Methodology ,in Response to NRC Staff Request Made in 990416 Telcon.Nuclear Svcs Corp Rept PIO-01-06, Analysis Rept Structural Analyses of Main Steam Check... Encl ML20211B2621999-08-17017 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 ML20211C7371999-08-17017 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 ML20210T5661999-08-12012 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 ML20210R7021999-08-12012 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 ML20210P5191999-08-11011 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 ML20210G5061999-07-30030 July 1999 Responds to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates 05000282/LER-1999-007, Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics1999-07-23023 July 1999 Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics ML20210J4991999-07-22022 July 1999 Forwards Rev 18 to USAR for Pingp,Bringing USAR up-to-date as of 990228,though Some Info More Recent.Safety Evaluation Summaries Also Encl ML20209J0941999-07-15015 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 ML20209H8051999-07-14014 July 1999 Forwards Summary of non-modification Safety Evaluation Number 515 Re Storage of Fuel Inserts,Per Insp Rept 72-0010/99-201 ML20209D4181999-07-0707 July 1999 Informs That Util Has Changed Listed TS Bases Pages Attached for NRC Use.Util Made No New Commitments in Ltr ML20209H8361999-07-0202 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 ML20196J9681999-07-0101 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 ML20209C3951999-07-0101 July 1999 Forwards Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209B7541999-07-0101 July 1999 Final Response to GL 98-01,Suppl 1 Re Y2K Readiness of Computer Sys.Sys Remediated as Required for Plant Operation. Contingency Plans Developed to Mitigate Impact of Y2K-induced Events at Key Rollover Dates ML20196J8941999-06-30030 June 1999 Transmits Util Comments on Draft Regulatory Guide DG-1074, Steam Generator Tube Integrity. Licensee Recommends That NRC Focus on Several Important Listed Areas Considered Principal Concerns & Contentions ML20209F0391999-06-30030 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 ML20209C3011999-06-29029 June 1999 Forwards Annual Rept of Corrections to NSP ECCS Evaluation Models,Iaw 10CFR50.46.Since All Analyses Remain in Compliance,No Reanalysis Is Required or Planned ML20209B5751999-06-24024 June 1999 Submits Revised Relief Request for Limited Examinations Associated with Third 10-yr ISI Examination Plan.Attached Is Unit 1 Relief Request 7,rev 1 Which Addresses Limited Examinations ML20196F3871999-06-23023 June 1999 Forwards Revised Pages 71,72 & 298 of Rev 7 to NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units, Per Discussions with Nrc.Approved Version of Rept Will Be Issued 05000282/LER-1999-006, Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics1999-06-18018 June 1999 Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics ML20196D5501999-06-18018 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 ML20196A6741999-06-17017 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 1999-09-09 Category:INCOMING CORRESPONDENCE MONTHYEARML20217F4331999-10-15015 October 1999
[Table view]Forwards Rev 39 to Security Plan.Changes Do Not Decrease Effectiveness of Security Plan.Rev Withheld,Per 10CFR73.21 ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212F5121999-09-20020 September 1999 Forwards Response to NRC , Preparation & Scheduling of Operator Licensing Examinations ML20211N8631999-09-0707 September 1999 Withdraws 970814 Request for Exemption from 10CFR50,App R, Section III.G.2, Fire Protection of Safe Shutdown Capabilities ML20211K5911999-09-0101 September 1999 Informs That Util Reviewed Rvid Data Base,As Requested in NRC .Summary of Proposed Changes & Observed Differences Are Included in Encl Tables ML20211L0211999-09-0101 September 1999 Provides Notification That License Amends 141 & 132 & Associated License Conditions 6 & 7 Have Been Fully Implemented ML20211Q6041999-08-31031 August 1999 Forwards Rev 19 to USAR for Pingp,Per 10CFR50.71(e).Rev Brings USAR up-to-date as of 990228,though Some Info Is More Recent.Attachment 1 Contains Descriptions & Summaries of SE for Changes,Tests & Experiments,Per 10CFR50.59 ML20211K5931999-08-31031 August 1999 Forwards License Amend Request for License SNM-2506, Proposing Change to License Conditions 6,7 & 8 & TSs App a of License by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211C2311999-08-19019 August 1999 Forwards Unit 1 ISI Summary Rept,Interval 3,Period 2 Refueling Outage Dates 990425-0526,Cycle 19 971212-990526. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarizes Results ML20211B8311999-08-19019 August 1999 Forwards Request for Relief 8 Re Limited Exams Associated with Unit 1 Third ten-year Interval Inservice Insp Program. Licensee Requests Relief Due to Impractibility of Obtaining 100% Exam Coverage for Affected Items ML20211B5711999-08-19019 August 1999 Forwards Second 90-day Rept for Implementation of Voltage Based Repair Criteria at Prairie Island Unit 1.Rept Fulfills Requirements of Section 6.b of Attachment 1 to GL 95-05 ML20211B0561999-08-18018 August 1999 Provides Addl Info on Proposed Rev to Main Steam Line Break Methodology ,in Response to NRC Staff Request Made in 990416 Telcon.Nuclear Svcs Corp Rept PIO-01-06, Analysis Rept Structural Analyses of Main Steam Check... Encl ML20210G5061999-07-30030 July 1999 Responds to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates 05000282/LER-1999-007, Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics1999-07-23023 July 1999 Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics ML20210J4991999-07-22022 July 1999 Forwards Rev 18 to USAR for Pingp,Bringing USAR up-to-date as of 990228,though Some Info More Recent.Safety Evaluation Summaries Also Encl ML20209H8051999-07-14014 July 1999 Forwards Summary of non-modification Safety Evaluation Number 515 Re Storage of Fuel Inserts,Per Insp Rept 72-0010/99-201 ML20209D4181999-07-0707 July 1999 Informs That Util Has Changed Listed TS Bases Pages Attached for NRC Use.Util Made No New Commitments in Ltr ML20209C3951999-07-0101 July 1999 Forwards Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209B7541999-07-0101 July 1999 Final Response to GL 98-01,Suppl 1 Re Y2K Readiness of Computer Sys.Sys Remediated as Required for Plant Operation. Contingency Plans Developed to Mitigate Impact of Y2K-induced Events at Key Rollover Dates ML20196J8941999-06-30030 June 1999 Transmits Util Comments on Draft Regulatory Guide DG-1074, Steam Generator Tube Integrity. Licensee Recommends That NRC Focus on Several Important Listed Areas Considered Principal Concerns & Contentions ML20209C3011999-06-29029 June 1999 Forwards Annual Rept of Corrections to NSP ECCS Evaluation Models,Iaw 10CFR50.46.Since All Analyses Remain in Compliance,No Reanalysis Is Required or Planned ML20209B5751999-06-24024 June 1999 Submits Revised Relief Request for Limited Examinations Associated with Third 10-yr ISI Examination Plan.Attached Is Unit 1 Relief Request 7,rev 1 Which Addresses Limited Examinations ML20196F3871999-06-23023 June 1999 Forwards Revised Pages 71,72 & 298 of Rev 7 to NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units, Per Discussions with Nrc.Approved Version of Rept Will Be Issued 05000282/LER-1999-006, Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics1999-06-18018 June 1999 Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics ML20195G4281999-06-0909 June 1999 Notifies That Amsac/Dss Mods Completed & TS 138/129 Has Been Fully Implemented 05000282/LER-1999-005, Forwards LER 99-005-00 Re Containment Inservice Purge Sys Not Isolated During Heavy Load Movement Over Fuel.Event Has Indicated That Level of Performance Expected by Mgt Has Not Yet Been Achieved1999-06-0707 June 1999 Forwards LER 99-005-00 Re Containment Inservice Purge Sys Not Isolated During Heavy Load Movement Over Fuel.Event Has Indicated That Level of Performance Expected by Mgt Has Not Yet Been Achieved ML20207F4301999-06-0101 June 1999 Forwards 1999 Unit 1 SG Insp Results,Per TS 4.12.E.1. Following Insp 84 Tubes Were Plugged for First Time ML20196L2461999-05-21021 May 1999 Forwards Rev 0 to COLR for Pingp,Unit 1 Cycle 20, IAW TS Section 6.7.A.6 ML20195C6861999-05-21021 May 1999 Forwards Rev 17 to USAR for Prairie Island Nuclear Generating Plant.Attachment 1 Contains Descriptions & Summaries of SEs for Changes,Tests & Experiments Made Under Provisions of 10CFR50.59 During Period Since Last Update ML20206U6781999-05-17017 May 1999 Forwards Revised Emergency Response Plan Implementing Procedures,Including Rev 15 to F3-3,rev 15 to F3-16,rev 14 to F3-22 & Table of Contents ML20206U7131999-05-17017 May 1999 Forwards Revised EOF Emergency Plan Implementing Procedures, Including Table of Contents & Rev 2 to F8-10, Record Keeping in Eof. with Updating Instructions ML20206T2461999-05-17017 May 1999 Forwards Off-Site Radiation Dose Assessment for Jan-Dec 1998, Rev 0 to Annual Radiactive Effluent Rept for 980105- 990103 & Effluent & Waste Disposal Annual Rept Solid Waste & Irradiated Fuel Shipments,Jan-Dec 1998 ML20206R0401999-05-13013 May 1999 Forwards Application for Amends to Licenses DPR-42 & DPR-60, Removing Plant Organization Requirement,Imposed in Amend 141/132 That Plant Manager,Who Has Responsibility for Overall Safe Operation of Plant,Report to Corporate Officer ML20206Q0871999-05-13013 May 1999 Forwards Result of Evaluation Re Ultrasonic Exams of SG Number 22 Performed in Accordance with ASME Boiler & Pressure Vessel Code Section Xi.Procedure Used for Evaluation Contained in WCAP-14166,submitted for Review ML20206F9381999-05-0303 May 1999 Forwards Response to NRC 990304 RAI Re GL 96-05 Program at Pingp.Licensee Commitments Are Identified in Encl as Statements in Italics ML20206J3851999-05-0303 May 1999 Forwards 1998 Annual Radiological Environmental Monitoring Rept 05000282/LER-1999-004, Forwards LER 99-004-00 Re Discovery of Inadequate Sp That Demonstrates Operability of SFP Special Ventilation Sys.Two New NRC Commitments Are Contained in Corrective Action Section of Rept in Bold Italics1999-05-0303 May 1999 Forwards LER 99-004-00 Re Discovery of Inadequate Sp That Demonstrates Operability of SFP Special Ventilation Sys.Two New NRC Commitments Are Contained in Corrective Action Section of Rept in Bold Italics ML20206E1761999-04-28028 April 1999 Forwards Revised TS Pages for Amends 144 & 135 to Licenses DPR-42 & DPR-60,respectively,to Update Controlled Manual or File ML20205S3221999-04-20020 April 1999 Forwards Application for Amends to Licenses DPR-42 & DPR-60, Changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements of TS 5.1 ML20205P9891999-04-12012 April 1999 Requests Approval for Proposed Alternatives to Liquid Penetrant Requirements of N-518.4 of 1968 ASME Boiler & Pressure Vessel Code.Results of Analysis & Summary of Tests Performed & Tests Results Are Encl ML20205Q0191999-04-12012 April 1999 Forwards Application for Amend to License DPR-42 & DPR-60, Relocating Shutdown Margin Requirements from TS to COLR 05000282/LER-1998-010, Forwards LER 98-010-01 Re Discovery That 32 App R Related MOVs Are Susceptible to Physical Damage by Fire Induced Hot Shorts.Rept Provides Addl Details on Current Plans for Completing C/As Committed to in Original LER1999-04-0808 April 1999 Forwards LER 98-010-01 Re Discovery That 32 App R Related MOVs Are Susceptible to Physical Damage by Fire Induced Hot Shorts.Rept Provides Addl Details on Current Plans for Completing C/As Committed to in Original LER ML20205P9221999-04-0101 April 1999 Submits Relief Request 8,rev 0 Which Addresses Limited Exams Associated with Unit 2 Third ten-year Interval Inservice Insp Program.Util Requests Relief Per 10CFR50.55a(q)(5)(iii) Due to Impracticality of Obtaining 100% Exam Coverage ML20205E8371999-03-31031 March 1999 Submits Four Copies of Rev 38 to Prairie Island Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Security Plan.Encl Withheld,Per 10CFR73.21 ML20196K7831999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Monticello & Prairie Island Nuclear Generating Plants,Per Requirements of 10CFR50.75(f)(1) ML20205Q5051999-03-30030 March 1999 Forwards Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327- 981229. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarized Results ML20205H5731999-03-29029 March 1999 Submits Required 1998 Actual & 1999 Projected Cash Flow Statements for Monticello Nuclear Generating Plant & PINGP, Units 1 & 2.Encl Contains Proprietary Info.Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20205C6561999-03-26026 March 1999 Submits Semiannual Update on Project Plans for USAR Review Project & Conversion to ITS ML20204H3371999-03-19019 March 1999 Forwards Application for Amend to Licenses DPR-42 & DPR-60, Removing Dates of Two NRC SERs & Correcting Date of One SER Listed in Section 2.C.4, Fire Protection 1999-09-07 Category:UTILITY TO NRC MONTHYEARML20065D5821990-09-19019 September 1990
[Table view]Forwards Rev 25 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20059L3431990-09-13013 September 1990 Forwards Application for Amends to Licenses DPR-42 & DPR-60, Revising Tech Spec Section 6.7.A.6.b ML20064A6411990-09-0606 September 1990 Amends 900724 Certification for Financial Assurance for Decommissioning Plant,Per Reg Guide 1.159.Util Intends to Seek Rate Relief by Pursuing Rehearing & Appeal of Rate Order by Initiating New Rate Proceeding ML20059E8671990-09-0606 September 1990 Forwards Rev 24 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20028G8401990-08-29029 August 1990 Forwards Effluent & Waste Disposal Semiannual Rept for Jan- June 1990 & Revised Effluent & Waste Disposal Semiannual Rept for Second Half of 1989,which Includes Previously Omitted Fourth Quarter Analyses Results of Sr-89 & Sr-90 ML20058Q4021990-08-0202 August 1990 Informs NRC of Potentially Generic Problem Experienced W/Westinghouse DB-50 Reactor Trip Breaker.Info Being Provided Due to Potential Generic Implications of Deficiencies in Westinghouse Torquing Procedues ML20056A3371990-07-31031 July 1990 Forwards Rev 2 to, ASME Code Section XI Inservice Insp & Testing Program,Second 10-Yr Insp Interval of Operation ML20055J4441990-07-26026 July 1990 Submits Supplemental Info to Violations Noted in Insp Repts 50-282/89-26 & 50-306/89-26.Training of Supervisory Personnel Not Completed Until 900719 Due to Time Constraints Encountered During Feb 1990 Unit 1 Refueling Outage ML20055G3981990-06-28028 June 1990 Forwards Annual Rept of Changes,Tests & Experiments for 1989 & Rev 8 to Updated SAR for Prairie Island Nuclear Generating Plant ML20043F7341990-06-11011 June 1990 Responds to NRC 900420 Ltr Re Violations Noted in Insp Repts 50-282/90-04 & 50-306/90-04.Corrective Actions:Operations Procedure D61 Will Be Revised to More Clearly Identify Requirements for Logging Openings ML20043D5681990-06-0505 June 1990 Rev 23 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043C7731990-05-25025 May 1990 Informs That on 900425,yard Fire Hydrant Hose House 7 Declared out-of-svc Due to Const in Area,Per Tech Spec 3.14.F.2.Const in Area Will Prevent Return to Svc of Hydrant Hose House 7 Until Approx 900630 ML20043A4451990-05-0909 May 1990 Responds to NRC 900319 Ltr Re Violations Noted in Insp Repts 50-282/89-29 & 50-306/89-29.Corrective Actions:Changes Will Be Made to Review & Approval Process for Work Packages ML20043A4531990-05-0202 May 1990 Responds to NRC 900319 Ltr Re Violations Noted in Insp Repts 50-282/89-29 & 50-306/89-29.Corrective Actions:Incoming Workers Will Be Specifically Trained in Fire Prevention Practices & Permanent Workers Will Be Reminded at Meetings ML20042F8681990-04-30030 April 1990 Submits Supplemental Info on Response Time Testing of Instrumentation,In Response to Concerns Raised in Insp Repts 50-282/88-12 & 50-306/88-12.No Addl Changes to Current Response Time Testing Program Necessary ML20042E8081990-04-27027 April 1990 Forwards Radiation Environ Monitoring Program Rept 1989. ML20012E4261990-03-28028 March 1990 Forwards Inservice Insp-Exam Summary 900103-0219 Refueling Outage 13,Insp Period 2,Second Interval. Exam Plan Focused on Pressure Retaining Components & Supports of RCS & Associated Sys,Fsar Augmented Exams & Eddy Current Exam ML20012D9131990-03-22022 March 1990 Forwards Rev 0 to Core Operating Limits Rept Unit 1 - Cycle 14 & Rev 0 to Core Operating Limits Rept Unit 2 - Cycle 13. ML20012E0091990-03-21021 March 1990 Forwards Completed Questionnaire in Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. ML20006G1931990-02-26026 February 1990 Forwards Rev 22 to Security Plan & Advises That Changes Do Not Decrease Effectiveness of Plant Security Plan & May Be Implemented W/O Prior NRC Review & Approval.Rev Withheld (Ref 10CFR73.21) ML20012A3131990-02-26026 February 1990 Forwards Rev 0 to Effluent Semiannual Rept,Jul-Dec 1989, Supplemental Info, Amend to Effluent & Waste Disposal Semiannual Rept for First Half of 1989 & Rev 11 to Odcm. Analyses for Sr-89 & Sr-90 Will Be Included in Next Rept ML20006F8631990-02-22022 February 1990 Provides Steam Generator Tube Plugging & Sleeving Info,Per Tech Spec 4.12.E.1.Following Recent Inservice insp,15 Tubes Plugged for First Time & 37 Tubes W/New Indications Sleeved ML20042E1871990-02-19019 February 1990 Forwards Response to NRC 900118 Ltr Re Violations Noted in Insp Repts 50-282/89-30 & 50-306/89-30.Response Withheld (Ref 10CFR73) ML20006E8031990-02-16016 February 1990 Forwards Request for Relief from Schedule Requirements of NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor/Darling Valves. ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20006B9291990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Procedure Will Be Developed to Periodically Inspect Emergency Intake Crib Located in River ML20006B9041990-01-29029 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Boron Concentration Will Be Calculated W/Provisions for One Shuffle Alteration ML20006B9951990-01-0303 January 1990 Suppls Response to Violations Noted in Insp Repts 50-282/89-14 & 50-306/89-15 Re Containment Airlock Local Leak Rate Testing.Corrective Actions:Changes to Local Leak Rate Testing Procedures Approved on 891229 ML20005E4881989-12-28028 December 1989 Responds to Generic Ltr 89-10 Re motor-operated Valve Testing & Surveillance.Listed Actions Will Be Performed in Order to Meet Recommendations of Generic Ltr ML20011D6941989-12-15015 December 1989 Forwards Addendum 1 to Sacm Diesel Generator Qualification Rept & Diesel Generator Set Qualification Rept. ML19351A5281989-12-13013 December 1989 Forwards Supplemental Response to NRC Bulletin 88-009, Thimble Tube Thinning in Westinghouse Reactors. Thimble Tube Insp Program Will Be Formalized by 901231 ML20005G4861989-12-11011 December 1989 Updates Response to Insp Repts 50-282/86-07 & 50-306/86-07 Provided by 860819 Ltr.Listed Actions Taken as Result of Task Force Evaluation,Inlcluding Implementation of Work Control Process for Substation Maint ML19332F3621989-12-0101 December 1989 Responds to Generic Ltr 89-21 Re Implementation Status of USI Requirements at Facilities.Pra to Address USI A-17, Sys Interactions in Nuclear Power Plants Will Be Completed in Feb 1993 ML19332E9371989-12-0101 December 1989 Forwards Executed Amend 9 to Indemnity Agreement B-60, Reflecting Changes to 10CFR140 ML20006E3301989-11-20020 November 1989 Forwards Fee in Amount of $25,000,in Response to 891019 Notice of Violation & Civil Penalty Re Commercial Grade Procurement,Per Insp Repts 50-282/88-201 & 50-306/88-201. Responses to Violations Also Encl ML19332D1761989-11-17017 November 1989 Forwards Application for Amends to Licenses DPR-42 & DPR-60, Deleting cycle-specific Core Operating Limits from Tech Specs & Creating New Core Operating Limits Rept,Per Generic Ltr 88-16 ML19332C8341989-11-13013 November 1989 Responds to NRC 891012 Ltr Re Violations Noted in Insp Repts 50-282/89-23 & 50-306/89-23.Corrective Actions:Procedure Changes Implemented to Require Placement of Yellow Tags on Fire Detection Panel Bypass Switches in Bypass Position ML19324C4031989-11-0606 November 1989 Responds to NRC Bulletin 88-010,Suppl 1, Nonconforming Molded-Case Circuit Breakers. Supply Breaker to Unit 2 Feedwater Isolation Valve Replaced W/Qualified & Traceable Replacement Circuit Breaker ML19332B6131989-11-0606 November 1989 Forwards Rev 4 to Safeguards Contingency Plan & Implementing Procedures,Per Generic Ltr 89-07.Rev Withheld ML19324B3321989-10-13013 October 1989 Submits Supplemental Info in Response to Violations Noted in Insp Repts 50-282/88-16 & 50-306/88-16.Corrective Actions: Air Test Connections Will Be Added to Allow Pressurization of Containment Spray Piping Between Stated Motor Valves ML20246L5061989-08-31031 August 1989 Responds to Generic Ltr 89-12, Operator Licensing Exams ML20246K2361989-08-28028 August 1989 Forwards, Effluent & Waste Disposal Semiannual Rept for Jan-June 1989, Revised Repts for 1988,1987 & 1985 & Revised Offsite Dose Calculation Manual ML20246L3771989-08-23023 August 1989 Forwards Supplemental Response to NRC Re Violations Noted in Insp Repts 50-282/88-16 & 50-306/88-16. in Future,Outboard Check Valves Will Be Tested W/Upstream Vent & Motor Valves MV-32103 & 32105 Repositioned ML20245L1911989-08-14014 August 1989 Submits Supplemental Info Re NRC Audit of Westinghouse Median Signal Select Signal Validation.Operability of Median Signal Select Function Will Be Demonstrated by Verifying That Failed Channel Not Selected for Use in Level Control ML19332C8431989-08-11011 August 1989 Responds to NRC 890713 Ltr Re Violations Noted in Insp Repts 50-282/89-18 & 50-306/89-18.Corrective Actions:All Personnel Involved in Event Counseled on Importance of Following Procedures & Work Requests as Written ML20246F4341989-08-11011 August 1989 Forwards Comments on SALP 8 Repts 50-282/89-01 & 50-306/89-01 Per 890629 Request.Addl Room Adjacent to Emergency Offsite Facility Ctr Classroom to Be Designated ML20247Q8181989-07-31031 July 1989 Provides Supplemental Info in Response to 890612 Request Re NRC Bulletin 79-14, Consideration of Torsional Moments (Tms) Piping Mods. Future Mods Will Reflect Tms Where Calculations of Stresses Due to Occasional Loads Performed ML20247H9111989-07-24024 July 1989 Forwards Response to Generic Ltr 89-08, Erosion/Corrosion- Induced Pipe Wall Thinning. Administrative Procedure, Defining Erosion/Corrosion Monitoring Activities,Issued on 890220 & NUMARC Recommendations Adopted ML19332F3501989-07-20020 July 1989 Responds to NRC 890620 Ltr Re Violations Noted in Insp Repts 50-282/89-17 & 50-306/89-17.Corrective Actions:New Monthly Sampling Procedures Prepared Which Will Require Monthly Independent Samples Be Taken from Fuel Oil Storage Tank ML20247D1851989-07-12012 July 1989 Provides Addl Info Re Molded Case Circuit Breaker Replacement,Per Insp Repts 50-282/88-201 & 50-306/88-201. Util Has Concluded That Replacement Breakers from Bud Ferguson Co Suitable for safety-related Purposes 1990-09-06 |
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Northem States Power Company 414 Niconet Mall ,
Minnespohs. Minnesota 55401 Telephone (612) 330-5500 April 24, 1986 Director Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NOS- 50-282 LICENSE NOS. DPR-42 50-306 DPR-60 Auxiliary Feedwater System Reliability Study On November 6, 1986 representatives of Northern States Power Company met with the NRC Staff to discuss the reliability of the auxiliary feedwater system at the Prairie Island Nuclear Generating Plant. At this meeting we presented the NRC Staff with information related to the design of the auxilia-ry feedwater system at Prairie Island and discussed plans for a reliability study to be performed to determine if the Prairie Island design is deficient in any way. This analy-sis has now been completed. The purpose of this letter is to transmit the analysis for the information of the NRC Staff.
On the basis of an analysis presented in NUREG-0611, " Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents in Westinghouse-Designed Operating Plants," January, 1980, Prairie Island appeared to have a lower than average auxiliary feedwater system reliability.
This six-year old report has been used by members of the NRC Staff in public discussions of planned regulatory actions to improve auxiliary feedwater system reliability in the wake of the June, 1982 Davis-Besse event. The analysis presented in NUREG-0611 does not include improvements made in the Prairie Island auxiliary feedwater system in response to NUREG-0737.
An noted in the attached report, " Prairie Island Units 1 and 2 Auxiliary Feedwater System Reliability Study," NSPNAD-86906P, April, 1986, an analysis of the reliability of the Prairie Island auxiliary feedwater system which incluoes modifications made subsequent to NUREG-0611 shows a system reliability that compares very favorably with other facili-ties and lies well within the NRC's range of acceptability.
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Northem States Power Company Director of NRR April 24, 1986 Page 2 As part of this analysis Northern States Power Company sought to determine if there were any changes in system design, maintenance, or operation which could significantly improve system reliability. A number of such changes were identified. These are described in Section 5.5 of the !
attached report. These recommendations are currently being I reviewed by the plant technical staff for implementation. .
Completion of these modifications could significantly in-prove the already high reliability of the Prairie Island design. We will inform the NRC Prairie Island licensing project manager, Mr Dominic Dilanni, of our specific plans and schedule for implementing changes.
We request that the evaluation presented in NUREG-0611 not be used by the NRC Staff in future actions related to Prairie Island auxiliary feedwater system reliability and that the attached analysis be made available to the Staff for their consideration.
Please contact us if you have any questions related to our reliability study .or if additional information is required to resolve this matter.
D&w. -
David Musolf Manager Nuclear Support Services c: NRR Project Manager, NRC Resident Inspector, NRC Regional Administratcr. Region III, NRC G Charnoff Attachment
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