Letter Sequence Other |
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MONTHYEARML20072L4311983-03-17017 March 1983 Authorizes Utilization of Encl Affidavit AW-77-47 in Support of Northern States Power Request to Withhold Proprietary Info Per 10CFR2.790 Project stage: Other ML20072L4141983-03-22022 March 1983 Forwards Proprietary Info Presented at 830223 Meeting W/Nrc in Bethesda,Md Re Fuel Assembly Failure.Info Withheld (Ref 10CFR2.790) Project stage: Meeting ML20076J2431983-06-0707 June 1983 Forwards Safety & Licensing Portion of Westinghouse Apr 1982 Rept,Providing Addl Info Re Fuel Assembly Failure Effect on Insertion of Control Rods or Core Cooling Geometry Project stage: Other 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 Project stage: Request 1983-03-22
[Table View] |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M3371999-10-20020 October 1999 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
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F4331999-10-15015 October 1999 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
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20151K6201988-03-25025 March 1988 Requests That Proprietary WCAP-11787, Prairie Island Units 1 & 2 Evaluation for Tube Vibration Induced Fatigue, Be Withheld from Public Disclosure (Ref 10CFR2.790(b)(1)) ML20235Y4451987-09-14014 September 1987 Authorizes Withholding of Proprietary WCAP-11525, Probabilistic Evaluation of Reduction in Turbine Valve Test Frequency, Per Encl Affidavit AW-80-027 (Ref 10CFR2.790) ML20215G4951987-04-0707 April 1987 Requests Withholding of Vol 2 to WCAP-10924, Westinghouse Large-Break LOCA Best Estimate Methodology:Application to Two-Loop PWRs Equipped W/Upper Plenum..., Per 10CFR9.5(4). Rept Will Be Separately Submitted Under 10CFR2.790 NRC-87-3216, Forwards Proprietary Vol 2 to WCAP-10924, Westinghouse Large-Break LOCA Best-Estimate Methodology:Application to Two-Loop PWRs Equipped W/Upper Plenum Injection, to Support Early 1988 Facility Startup.Rept Withheld (Ref 10CFR9.5(4))1987-04-0707 April 1987 Forwards Proprietary Vol 2 to WCAP-10924, Westinghouse Large-Break LOCA Best-Estimate Methodology:Application to Two-Loop PWRs Equipped W/Upper Plenum Injection, to Support Early 1988 Facility Startup.Rept Withheld (Ref 10CFR9.5(4)) ML20215F5271986-09-10010 September 1986 Requests Withholding of Proprietary Slide Presentation Entitled, Nrc/Northern States Power/Westinghouse Joint Technical Exchange:Shape Memory Alloy Sleeving (Ref 10CFR2.790).Affidavit Encl ML20214P8301986-08-0505 August 1986 Requests Rev 1 to WCAP 10929, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis... & Rev 1 to WCAP 10931, Toughness Criteria..., Be Withheld (Ref 10CFR2.790) ML20154L4771986-02-25025 February 1986 Requests That Proprietary Prairie Island Unit 1 Reactor Vessel Upper Internals Replacement Safety Evaluation Be Withheld (Ref 10CFR2.790).Affidavit Encl ML20136H9031985-11-14014 November 1985 Requests Withholding Proprietary Info Re Best Estimate LOCA Methodology as Applied to PWRs W/Upper Plenum Injection from Public Disclosure Per 10CFR2.790.Supporting Affidavit Encl ML20198F3561985-09-27027 September 1985 Requests That Proprietary WCAP-10929, Technical Bases for Eliminating Large Primary Loop Pipe Rupture... & WCAP-10931, Toughness Criteria... Be Withheld from Public Disclosure Per 10CFR2.790 ML20126A2651985-03-0707 March 1985 Requests That Proprietary WCAP-10756, Prairie Island Units 1 & 2 Steam Generator Sleeving Rept (Mechanical Sleeves), Be Withheld from Public Disclosure (Ref 10CFR2.790). Affidavit Encl ML20106J5371984-09-18018 September 1984 Requests Proprietary WCAP-10639, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Prairie Island Unit 1, Be Withheld Per 10CFR2.790.Affidavit Encl ML20072L4311983-03-17017 March 1983 Authorizes Utilization of Encl Affidavit AW-77-47 in Support of Northern States Power Request to Withhold Proprietary Info Per 10CFR2.790 ML20070C9801982-12-0909 December 1982 Forwards Summary of NRC Review of Exxon Nuclear Co Thermal Hydraulic Methodology for Mixed Cores in Pwrs.Encl Toprod Sensitivity & Thermal Margin Studies Submitted on 820618 & 29,respectively,remain Valid.Comments Requested ML1116511951980-04-11011 April 1980 Forwards Proprietary & Nonproprietary Versions of Structural Analysis of RCS for Postulated LOCA, Preliminary Issue.Applications for Withholding Encl. Proprietary Version Withheld (Ref 10CFR2.790) ML19262B5721979-12-19019 December 1979 Forwards Westinghouse Evaluation of 791002 Tube Rupture Event.Concurs W/Util Recommendations in LER 79-027/01T-0 Re Operation of Turbine Driven Auxiliary Feed Pump & Steam Supply Valve from Faulted Steam Generator ML19263C4091979-02-12012 February 1979 Forwards Rept XN-NF-78-44,Generic Analysis of Control Rod Ejection Transient for Pwrs. 1988-03-25
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Westinghouse Water Reactor sue: ear reennetegy civis:an Electric Corporation Olvisions eu sss Ptsourgn Pennsylvania 15230 CAW-83-20 d
March 17, 1983 Dr. Cecil O. Dxxnas, Clief Standard 4?a*4em & Special Projects Brandi Division of Licensing U. S. Nuclear Regulatory h4==iews phil14na milding 7920 Norfolk Avenue Bethesda, Maryland 20014 APPLICATICN ER WIIHBOEDIN3 PROPRILTARY INERMATICN FBCM PUBLIC DISCEDSURE
REFERENCE:
Northern States Power Ccznpany letter to C. O. Oxznas, dated March,1983
Dear Dr. Oxznas:
Tie proprietary material for which withM1 ding is being requested by'He Northern States Power Canpany is further 4danti#ied in an affidavit signed by the owner of the proprietary information, Westinghouse Electric Corporation. Die proprietary material for which withholding is being requested is of the same tachnical type as that proprietary material previously sulznitted with application for withM1 ding AW-77-47. The affidavit AW-77-47 sulznitted to justify the previous material is equally applicable to this material.
It is resgtfully requested that the information which is proprietary to Westinghouse and which is further identified in the affidavit be withheld fran public disclosure in accordance with 10CFR Section 2.790 of the Catmission's
, regulations.
Accordingly, this letter authorizes the utilization of the a >, - +sying affidavit in support of the Northern States Power Canpany.
Cou.es@rdence with respect to the proprietary aspects of the application for withholding or the West 2nghouse affidavit should reference this letter, CAW-83-20, and should be addressed to the undersigned.
Very truly yours, 8303310287 830322 PDR ADOCK 05000282 P PDR M M[
Robert A. Wiesenann, Manager Regulatory & Legislative Affairs
! cc: E. C. Shanaker, Esq.
Office of the Executive Legal Director, NBC
, WKSTiliCliOUSE Pii0fRIETr'P.Y Clil5_1 A!!-77-47 AFFIDAVIT -
CO:C:0::WEALTil 0F PEi!!!SYLVAilIA:
ss
'COUi:TY OF ALLEGHEtiY:
!!cfore me, the undersigned authority, personally appea' red Robert A. Wiesemann, who being duly sworn according to law, daposes and says that he is authorized to e.xecute this Affidavit on behalf of Westinghouse Electric Corporation (" .2stinghouse")
and, that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:
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Robert A. Wiesemar.n, itanager Licensing Programs I
Suorn to and subscribed before pe this 27 day ,
of [ buy'5.'1,197.7.
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}IESTI!!GHOUEEPROPRIEII.R7Cl. ASS 2
, AW-77-47 Tile NATUPE OF Tile C0".PETITIO:: If! THE NUCLE /.R BUSli:ESS Westinghouse's ' principal competitors in the nuclear steam supply business are Babcock & Wilcox, Combustion Engineering, and General Electric. The principal U. S. competitors in the nuclear fuel fabrication business are Babcocli & Wilcox, Combustien Engineering, Exxon, and General Eltetric.
With the exception of General Electric, these competitors are new entries in the business with substiantially smaller investmants in technology.
Westinghouse also has competition from foreign fabricators. This com-petition can drastically affect our ability to obtain contracts in the international market. Specific competitors include ASEA-ATO:4 (Sweden),
Kraftwerk AEG (Germany), Framateme (France), S"FL (Great Britain) Enusa (Spain) Hitsubishi (Japan), and Fabricazione flucleari (Italy).
Both the nuclear steam supply and the nuclear fuel fabrication businesses involve high technology, and competition is on the basis of that high technology rather than on price. Only if competition centinues based on technology will Westinghouse be able to recover its substantial invest-ments in technology and product development.
- EFFECT OF RELEASE OF INFORMATION ON WESTIMGHOUSE C0f4PETITIVE p0SITION If, as a matter of general practice, cost or price information or infor-mation about the basis on which Westinghouse makes its business judge-ments were made publicly available, it would have the general effect of altering the nature of comoetition from a technology base to a price .
base. This would change the entire complexion of the business and drive it toward a low investment-low technology development business. Under
. such circumstances, those in the business with heavy unrecovered invest-ments in technology such as Westinghouse would have difficulty competing successfully with those who have made relatively small investments since 2
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WESTIf!CI;CU5d PP.uPRIETAP.Y Cf. ASS 2
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A* !- 77-,*. 7 business would tend to go to the lowest c,ualified idder. The general public would also suffer in that they would be dcreived of the benefits
'of technoicgical developments that would most li::. i. far exceed any short-term benefits derived .frca lower prices. Lil.riise, a general practice of making publicly available information .btained from invest-ments in. technology would enabic competitors to beaefit without having to maka commensurate investments. This would stif'.a the incentive for further investments in technology and drive the busir. ass to price-based competition instead of competition on the ba:is,of te'chnology with the scme end results as in the case of disclosura Of cost or price infor-mation. . .
WHAT WESTII!GHOUSE SEEKS TO PP.0TECT Westinghouse seeks to protect its abili'ty to recev2r its investcents in: *
(1) Basic data resulting from research and development.
(2) Analytical methcds and models.
(3) Details of our, designs including margins, tolerances, etc.
(4) The knowledge of what data to present and how to pr:sent the data to satisfy NP.C licensing requirements. NOTE: In the current licensing environment, die cacability to obtain ,
licensing approval has bece=a very important in the market-place.
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WijsTI-:5:0"CE P"092IETAin' Ct.'.CS 2 .
A'<.'- 7."- 4 7 The above identified information is of considerable ccmmercial advantage
.to the competitors of "estinghouse to the extent that it climinates the need for similar investments in technology.
REl.ATIO::S!!IP OF I :FOR:*.'sTIO:: 50"3HT TO BE WITHHELD Fr.C". FUPLIC DISCLOSURE TO WHAT IS SOUGHT TO BE PROTECTED INFORMATI0 ! SOUGHT TO CE UITPHEl.D, r
The information sought to be withheld in this report includes conclusions regarding thermal, physt:al, ch:mical' and mechanical properties of fual and core component matericls based upon Mastingh:use experimental data and an extensive literature survey and data reduction progrca. The report also contains Uestinghouse material specifications. The release of this information would result in the following competitor benefits:
POTENTIAL ADVA:lTAGES TO COMPETITORS
- 1. It would allow cc:rpetitors to verify their material property
. design values by mare reference to the Westinghouse Report without having to expend the time, . resources and funding otherwise necessary.
- 2. For. the materials listed in the report, the data presented would enable competitors to determine to a close approximation some of the final heat treatments , processes, densities, etc. , used by ,
Westinghouse.
- 3. Knowledge of the materials properties presented, or the implied .
specifications may permit competitors to either relax their material specifications or reduca design margins, either of which circum-stances could lead to sales advantagas detrimental to the Westinghouse
' :t :c positica.
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WESTINGi!OUSE Pr.0PP.IETAP.Y f.L/iSS ?
Ai!-77-47 ITNESTMEiii BY WESTINGHOUSE Ill WHAT IS SOUGHT TO BE Pfl0TECTED It is estimated 'that four to five man-years of engineering and one mar.-
year of technician effert, amounting to approximately $500,000 was expended to perform the literature survey, obtain Westinghouse experi-
- mental data,' perform detailed analysis of selected data and to derive acceptable design equations and valu2s.
Competitors could obtain the equivalent information, Nith difficulty, by investing a similar sum of money and provided ,they had the appropriate resources available and the requisite experience.
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-P0TENTIAL HARM TO HESTIt:GHOUSE We believe there is a likelihood of substantial harm to the competitive position of Westinghouse if the information sought to be withheld is publicly disclosed, which could result in a loss of revenue to desting-house of approximately $10,500,000 in potential first-core and $7,000,000
-in potential reload fuel business.
Further the deponent sayeth not.
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