ML19331A809
ML19331A809 | |
Person / Time | |
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Site: | Prairie Island, Midland |
Issue date: | 12/01/1975 |
From: | Gove P ECIMPCA, MINNESOTA, STATE OF |
To: | Boyd R Office of Nuclear Reactor Regulation |
Shared Package | |
ML19331A807 | List: |
References | |
NUDOCS 8007230838 | |
Download: ML19331A809 (2) | |
Similar Documents at Prairie Island, Midland | |
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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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20211L0211999-09-0101 September 1999 Provides Notification That License Amends 141 & 132 & Associated License Conditions 6 & 7 Have Been Fully Implemented 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 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 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 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 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 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 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 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 ML20205Q0191999-04-12012 April 1999 Forwards Application for Amend to License DPR-42 & DPR-60, Relocating Shutdown Margin Requirements from TS to COLR 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 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:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC MONTHYEARML20235W8101987-09-24024 September 1987
[Table view]Requests NRC Submittal of Written Statement Giving Formal Approval of Proposed Fuel Rod Consolidation Pilot Project at Plant.Recent Info Indicates That Util Will Be Allowed to Perform 10CFR50.59 self-review.Assurances Re Safety Needed ML20237H8721987-08-10010 August 1987 Requests Encl Public Hearing Testimony & Criticality Concerns Re Util Fuel Rod Consolidation Project Be Added to Docket ML20236D5231987-07-27027 July 1987 Requests Relocation of NRC 870814 Meeting W/Northern States Power Co to Discuss Rod Consolidation.Meeting Should Be Held in St Paul,Mn Instead of Bethesda,Md to Facilitate Participation of State & Local Officials ML20210S9971986-10-0202 October 1986 Requests Change in Facility Svc List Address to Ref Address. Related Correspondence ML20107J7281984-11-29029 November 1984 FOIA Request for Documents Re Shipment of Spent Nuclear Fuel from Facility & D Musolf to NMSS ML20211E3271984-10-0101 October 1984 FOIA Request for All Documentation,Including Notes,Ltrs, Memoranda,Computer Printouts & Data Compilations Re Board Notification 84-149 Concerning Investigation Repts on Comanche Peak ML20101U5541984-06-15015 June 1984 FOIA Request for All Agency Records Generated in Connection W/Dg Eisenhut 840524 Request for Addl Info Re Structural Adequacy of Plant Diesel Generator Bldg ML20112E4681984-05-22022 May 1984 FOIA Request for Documents Re Meetings Between Members of Nrr,J Kane,H Singh,F Rinaldi & Others Re Resolution of Diesel Generator Bldg & Implementation of Recommendations or Conclusions from Brookhaven 831021 Rept ML20084K8631984-05-11011 May 1984 Forwards Intervenor B Stamiris Second Supplemental Proposed Finding & Conclusions of Law Re QA & Mgt Attitude Issues & cross-reference to Previously Filed Proposed Findings of Fact & Conclusions of Law ML20084Q3491984-05-10010 May 1984 Requests That J Keppler Respond to Listed Issues Re Evaluation of Facility Completion.Caseload Forecast Panel Evaluation of Plant,Taking Into Account Issues Discussed, Also Requested ML20084L6261984-05-10010 May 1984 Questions J Keppler Statement That Util Projected Schedule for Finishing Unit 2 by Dec 1986 Attainable & No Caseload Forecast Panel Evaluation Planned.Objective Caseload Forecast Panel Evaluation Requested ML20112D2991984-05-0202 May 1984 FOIA Request for Documents Re Insp of Auxiliary Bldg ML20090K6941984-05-0202 May 1984 Expresses Belief That Intervenors Govt Accountability Project,Lone Tree Council & M Sinclair Represent Small Minority of Community Persons Not Wanting Plants Completed & Operating.Majority of People in Favor of Facility Operation ML20084N3611984-05-0101 May 1984 Presents Differing View from M Sinclair Re Safety Concerns. Closing of Plant Would Result in 5,000 Lost Jobs & Create far-reaching Economic Hardship Throughout Community ML20084M6381984-04-30030 April 1984 Contends That Intervenors Govt Accountability Project,Lone Tree Council,B Stamaris & M Sinclair Do Not Represent Midland County Community,As Intervenors Claim ML20084K6471984-04-30030 April 1984 Contends That Govt Accountability Project,Lone Tree Council, M Sinclair & Representatives of B Stamiris Do Not Represent Majority of Midland County Population ML20084K3711984-04-30030 April 1984 Contends That Govt Accountability Project,Lone Tree Council, M Sinclair & Representative of B Stamiris Do Not Represent Majority of Midland County Population ML20090K7121984-04-30030 April 1984 Expresses Belief That Govt Accountability Project,Lone Tree Council,M Sinclair & Representatives of B Stamaris Do Not Represent Majority of Midland,Mi as Claimed ML20090K7211984-04-30030 April 1984 Expresses Belief That Intervenors Govt Accountability Project,Lone Tree Council,M Sinclair & B Stamaris Represent Minority of Community Persons Not Wanting Plants Completed & Operating.Majority in Favor of Operation ML20100F5011984-03-0606 March 1984 Supplemental FOIA Request for Four Categories of Documents, Including Trip Repts to Region III or Facility & Vaugh Index ML20087P0531984-01-30030 January 1984 Discusses Encl Newspaper Article Re QA Problems at Facility. Increase in Number of Inspectors at Plant Requested ML20080T6271984-01-17017 January 1984 Appeals Denial of FOIA Request for T Novak Notes Generated by or During Visit to Glen Ellyn,Il to Discuss Ofc of Special Cases Findings Re Facilities from Sept 1982 to Dec 1983 ML20084S1421984-01-0909 January 1984 FOIA Request for Documents Re Executive Notice 83-69 on Facilities ML20083N2151984-01-0909 January 1984 FOIA Request for Documents Generated by Kane or Singh for Evaluation of BNL Rept Re Diesel Generator Bldg at Facility ML20079Q6931983-12-30030 December 1983 Requests Cessation of Radioactive Matls Discharge Into Tittabawassee River.Synergistic Effect W/Radioactivity Increases Cancer Possibility ML20082N9291983-12-0505 December 1983 Forwards Stamiris Exhibit 140,consisting of Applicant Responses to Stamiris Interrogatories 14,28,31 & 19(a). Applicant Two Sets of Supplementary Responses Should Be Filed W/Aslb.Svc List Encl ML20086Q4011983-11-26026 November 1983 FOIA Request for Agency Records & Info Generated in Connection W/Or as Result of T Novak Visit to Region III Ofc to Discuss Ofc of Special Cases Findings on Facilities from Sept 1982 - Dec 1983 ML20086Q2611983-11-26026 November 1983 FOIA Request for Documents Re 831025 Meeting Between Util & NRC Concerning Mgt Audit & Associated 10CFR2.206 Request ML20080B2781983-11-26026 November 1983 FOIA Request for Records Generated in Connection W/Ta Rehm to Bp Garde Re Midland Caseload Forecast Panel ML20078R5091983-10-31031 October 1983 Commends Util Efforts to Develop Employee Assistance Program to Deal W/Employee Substance Abuse Problems.Pressure Should Be Placed on Remaining Contractors & Subcontractors to Develop Similar Programs ML20080S7061983-10-13013 October 1983 Expresses Concern Re Discrepancies in Const Completion Schedule.Public Meeting Warranted in Light of Varying Completion Dates ML20086J3781983-09-28028 September 1983 FOIA Request for IE 800103 Rept Re Review of Matl False Statement at Facilities,Associated & Supporting Records to Rept & Repts Prepared in Response ML20080J5801983-08-19019 August 1983 Requests Answer to Question Raised During 830811 Public Meeting by B Stamiris Re NRR Review of Const Completion Plan & Individuals Consulted.Appointment of Independent Geotechnical Consultant to Review Work Suggested ML20078K9431983-08-10010 August 1983 FOIA Request for Documents Re Degradation of Fuel Assemblies While in Spent Fuel Storage Pools in Us Nuclear Power Plants ML20078K8791983-08-10010 August 1983 Appeals Denial of FOIA Request for Documents Re Caseload Forecast Panel 830419 Meeting on Plant Const.Denial Effectively Denied Bulk of Documents Requested ML20077J4501983-08-0808 August 1983 Requests Names of Review Team Members,Methodology & Plans for Public Participation Re Review of R Landsman Concerns Over Structural Adequacy of Diesel Generator Bldg ML20078G9471983-08-0808 August 1983 FOIA Request for All Records on re-review of Structural Adequacy of Diesel Generator Bldg Subsequent to May Testimony of R Landsman in ASLB Proceedings ML20078K1741983-08-0505 August 1983 FOIA Request for Documents Submitted by Util for Consideration of Candidate Companies or Methodologies to Perform Const Implementation Overview of Const Completion Plan ML20082G3931983-08-0505 August 1983 FOIA Request for Records on 830615 Briefing of Commissioners Re Facilities ML20078K8921983-07-11011 July 1983 FOIA Request for Documents Re Caseload Forecast Panel 830419 Meeting on Plant Const ML20077F3151983-06-22022 June 1983 Forwards Govt Accountability Project (Gap) Rept of Gap Investigation Into Region V/Nrr Effort on Former Bechtel Employee Allegations Re Welding Practices ML20071P8951983-06-0101 June 1983 Requests Info Re Total Number of Wells & Amount of Electricity Required to Operate Wells for Dewatering ML20024B0931983-05-31031 May 1983 Ack Receipt of Response Re Independent Audit of Facility. Truly Independent Audit Should Include Full Scope Overview of Completed Const Done by Third Party Rather than Util ML20076B0961983-05-16016 May 1983 FOIA Request for Matls Re Release of Draft Insp Rept to Util from Region III Dealing W/Startup Test Program for Facilities ML20023C5171983-04-21021 April 1983 Requests Assurance of Independent Agent to Perform Facility Audits,Per NRC 830419 Reinsp Order ML20069L1531983-04-19019 April 1983 Responds to Informal Discovery Questions Re Insp Repts, Deviation Repts,Attachment 10 Repts & Return Options in QA Sys.Containment Chipping Incident Was First Identified as Noncompliance by Region III During Oct-Nov Team Insp ML20090F1921983-04-18018 April 1983 Discusses Subcontractor Employee Concerns Re Unqualified Personnel at Plant Site in Jobs of Critical Importance to Safety,Poor Installation & Lack of Worker Qualification on Zack Design.Investigation Requested ML20024D7271983-04-0505 April 1983 FOIA Request for Documents Re Incineration of Radioactive Matls by Dow Chemical Co at Facilities ML20072S6431983-03-30030 March 1983 Supports Halting of Nuclear Legacy & Opposes Plant Opening Until Permanant Nuclear Waste Storage Method Devised ML20072M3921983-03-29029 March 1983 Requests to Make Limited Appearance Statement at 830329 OL Hearing 1987-09-24 |
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j M!nnesota Po!!ution Control Agency
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December 1, 1975 P' I
Mr. R.S. Boyd, Acting Director Division of Reactor Licensing
, U.S. Nuclear Regulatory Commission j Washington, D.C. 20555 RE: Prairie Island Nuclear Generating Plant (Docket Nos.
50-292 and 50-306, License Nos. DPR-42 and DPR-60)
Dear Mr. Boyd:
1
. The Minnesota Pollution Control Agency, an intervenor
} in the ongoing licensing hearing for the Prairie Island Nuclear Generating Plant, has received a copy of an Unusual Event Report -
from the Licensee dated November 14, 1975.
t l The Report indicates that the release rate of long-lived J
halogens and particulates, when averaged over a three-month period and extrapolated at the same release rate for one year, was greater than two times the Design Objective contained in Technical Specificati,on 3.9.2.b. Our review of Technical Speci-fication 3.9.B.l.a indicates that in such circumstances the Licensee is required to identify the cause for such excessive release rates, and to define and initiate a program to reduce the rates. In spite of the rather specific language of that i section, the Licensee has failed to make an adequate identifica-i tion of the causes and to develop a program to reduce the excessive
! releases.
It has long been the position of the Minnesota Pollution
- Control Agency, in this proceeding as well as in the Monticello l .
licensing proceeding and the Appendix I rulemaking hearing, that i
routine releases of radioactive plants can and should be signi-
'ficantly reduced. In this instance, the Agency has the following specific concerns:
- 1. Further explanation of the cause of this excessive rel' ease of halogens and particulates is required. The only explanation given by the company is that " abnormal amounts of I-131 and Co-58 were released from Unit 1 Containment" as a result of " required purging to permit maintenance." It is of concern to the Agency that routine maintenance would cause the release of excessive amounts of radioactive gaseous materials.
If extra purging is necessary due to steam leaks in the containment or other causes, this should be fully investigated.
1935 West County Road 32. Roseville. Minnesoto 55113 D
.80 o n a ggy' al Offices Duluth / Brcinerd ,. s ne /__ _.,_, Falls / Marshcli/ Rochester / Rose Fergus d
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I Mr. R.S.*Boyd, Acting Director ~
page 2
- 2. Information should be prcvided as to the extent to which esterials released during raintenance purges are treated e in the plant's gaseous emission treatment system. If such releases are not treated, explanation and justification should be provided.
- 3. Technical Specifications 3.9.B.l.a and 6.7.3.2 require written Unusual Event Reports to be submitted "within 30 days."
} Submission of such a report on November 14 identifying excessive release rates from May 11, 1975, through August 10, 1975, does l
! not seen timely, i
t j 4. The Minnesota Pollution Control Agency does not believe
! that, merely because chere is scce delay in the ultimate imple-l-
y mentation of Appendix I, the Licensee should be allowed to violate the provisions of its existing Technical Specifications i, with imounit":.
The Minnesota Pollution Control Acencv rec.uests that the i ?!uclear Regulator 1 Ccrnission pa2e irrediate and neaningful action to insure that the concerns expressed above are addressed.
l I I Sin,er 'ly e j f -
-Cfd,L t . ter L. Gove l Executive Director cc: Jay Silberg, Esq.
O. Gregory Lewis, Esq.
L.O. Mayer 4
e
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