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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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Box 355 N Pittsburgfi Pennsylvania 15230-035b
.Date: September 14, 1987 CAW-87-068' m 3
[~VF^ .Dr.sThomas Murley, Director; .. .
0fficeLof Nuclear. Reactor Regulaticn 4 , .U.S... Nuclear Regulatory Commission ~-
7 y
.. Washington,LD.C. ~ 20555
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L APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE l
Subject:
WCAP-11525)(Proprietary) and WCAP-11529 (Non-Proprietary)L
'"Probabilistic. Evaluation of. Reduction In Turbine Valve Test e <
1 Frequency"?
g, Ref: Westinghouse Letter WOG-TVTF-87-013,. J.D.: Campbell of Westinghouse Electric Corporation to M.W. Thomas of Northern States Power Company,
' dated-September 11, 1987; L ,
.e
Dear Dr. Murley:
,. The proprietary information for which withholding is being requested in the enclosed letter.by.Noithern States Power Company is further identified in an affidavit signed'by the' owner of the proprietary information, Westinghouse.
Electric. Corporation. The affidavit , which accompanies this letter, sets forth the basis on which the infomation r<ay be withheld from public disaicsure by
~the Commission's regulations.
The proprietary material 1for which withholding is being required is of the same technical _ type as that proprietary naterial previously submitted as Affidavit AW-80-027
> Accordingly.:this letter authorizes the utilization of the accompanying i: affidavit.by Northern States Power Company.
I
. magnis -
8710200363 87(SlF PDR ADDCK 050002B2 l' PDR
Date: September 14, 1987 CAW-87-068 Correspondence with respect to the proprietary aspects of the application for withMiding or the Westinghouse affidavit should reference this letter, l CAW-87-068, and should be addressed to the undersigned.
l Very truly yours, W
Ro ri A. Wiesemann, Manager l
Re & Legislative Affairs
! Enclosures l cc: E.C. Shomaker, Esq.
l Office of the General Council, NRC (EKF:PROPINF0/PG.22)
I
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.0-IAW-80-27 4
A AFFIDAVIT-
.C0fiMONWEALTH OF . PENNSYLVANIA:
ss COUNTY-OF ALLEGHENY:
Before me, the undersigned authority, personally appeared Robert A.- Wiesemann, who, being. by me duly sworn according to law,
,depos'es and says that he is authorized to. execute this-Affidavit on- '
behalf of Westinghouse Electric' Corporation (" Westinghouse") and that the averments of fact set forth in.this Affidavit are true and correct to the best of his knowledge, information, and belief:
- I-l d./.4 b Robert A. Wiesemann, Manager.
Regulatory and' Legislative Affairs i
Sworn to and subscribed-before this / [ day of _ 1980.
i l
[NotaryPublic / . ..
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AW-80-27 4 (1) I am' Manager, Regulatory and Legislative Affairs, in the Nuclear Technology Division, of Westinghouse Electric Corporation and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public dis-
' closure in connection with nuclear power plant licensing or rule-making proceedings, and am authorized to apply for its withholding on behalf of the Westin: house Water Reactor Divisions.
(2) I am making this Affidavit in conformance with the provisions of 10CFR Section 2.790 of the Commission's. regulations and in con-junction with the Westinghouse application for withholding ac-companying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse Nuclear Energy Systems in designating information as a trade secret, privileged or as confidential commerical or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Ccmmission's regulations, the following is furnished for consideration by the Commission in determining whether the in-formation sought to be withheld from public disclosure should be withneld.
(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.
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AW-80-27 (ii) The information is of a type customarily held in confidence {
.by Westinghouse and not customarily disclosed to the public Westinghouse has a rational basis for determining tne types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence.
The application of that system and the substance of that oyst.em constitutes Westinghouse policy and provides the rational basis required. .
Under that system, information is hels in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential com-petitive advantage, as follows: '
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.)
where prevention of its use by any of Westinghouse's competitors without license from Westinghouse consti-tutes a competitive economic advantage over other j companies.
(b) It consists of supporting data, including test data, i relative to a process (or component, structure, tool, j method, etc.), the application of which data secures a f competitive economic advantage, e.g., by optimization j or improved marketability. ]1 l
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(c) . Its u'se'.by a competitor. would reduce his expenditure o'f re' sources or. improve' his competitive position in the- -l design,. manufacture, shipment, installation, assurance-of quality,- or.. licensing a similar product.
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'( d ) It reveals cost'or price information, production cap-
' acities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.
-(e)
It reveals aspects-of past, present, or future West-inghouse or customer funded development plans and pro-grams of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent pro-tection may be desirable. .
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'(g) 'It .is not the property of Westinghouse, but must be treated as proprietary by Westinghouse according to agreemen.ts'with the owner. -
There.are sound policy reasons.behind.the Westinghouse system which include.the following:
(a') The use of such information by Westinghouse gives Westinghouse a competitive advantage over its com-peti tors . It is, therefore, withheld from disclosure to protect 'the Westinghouse competitive position.
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(b)' ItL is information which .is ' marketable in many. ways.'
r The.-extent to which such information is available to competitors diminishes the Westinghouse ' ability .to Lsell products and services involving"the use'of the in' forma tion'.f
-(c)' use'by our ' competitor would put Westinghouse at a competi.tive disadvantage by reducing his expenditure of resources at our expense.
(d) Each component of proprietary. information pertinent to a particular competitive advantage is potentially
> as valuable as.the total competitive advantage. If, competitors a'cquire components of proprietary.infor-mation, 'any one component' may be the key to the entire
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puzzle, thereby depriving. Westinghouse of a competitive advantage.
.(e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse .in the world' market, and thereby give a market. advantage to the competition -
1 in those countries, i (f) The Westinghouse capacity to invest corporate assets in research and development decends upon the success j in obtaining and maintaining a competitive advantage.
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TheLinformation i.s.-being transmitted to the Commission in confidence and, under the provisions of 10CFR Section 2.790,-
Lit:is;to be received in confidence by the Commission.
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_(i_v). The informatio'n sought ..to be protected is not available .in' Lpuolicisources --to the best of our knowledge and belief.
_( v). The' proprietary information sought to be withheld?in this submittal is-that which is appropriately marked in the attach-
, ment te ilestinghouse Letter No. NS-TMA-2257, Anderson to Miller,'.dc:ed June 16,-.1980 concerning the Westinghouse Equip-4 ment Qualification Program to address Regulatory Guides 1.89 and 1.100. Theiletter and attachment are being submitted to compiete.the_information.provided in WCAP-8587, Supplement 1, which was' requested by the NRC via PBS Standard. Question No.~4,
" Environmental' Qualification of Class 1E Equipment."
This information enables Westinghouse to:
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(a) Develop testiinputs and procedures -to satisfactorily verify the design.of Westinghouse supplied equipment.
(b) Assist its customers to obtain licenses.-
Further, the information has substantial commercial value as follows:
(a) Westinghouse.can sell the use of this information to customers.
4 AW-80-27 (b) Westinghouse uses the information to verify the' design of es 'pment which is sold to customers.
i (c). Westinghouse can sell testing services based upon the experience gained and the test equipment and methods .
J developed. {
Public disclosure of this information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to design, manufacture, verify, and sell electrical equipment for com-mercial power reactors without commensurate expenses. Also, public disclosure of the-information would enable others having the same or similar equipment to use the information to meet NRC requirements for licensing' documentation without i purchasing the right to use the information.
. The development of the equipment described in part by the information is the result of many years of development by Westinghouse and the expenditure of a considerable sum of money.
This could only be duplicated by a competitor if he were to invest similar sums of money and provided he had the appropriate talent available and could somehow obtain the requisite experience.
Further the deponent sayeth not.
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Addresses:
R.G.. Saint-Paul, Director
-Nuclear Safety Westinghouse Nuclear International-Europe 1180 Brussels (internal mail)
~J. Cobian, Manager i Nuclear Safety Westinghouse Nuclear International-Europe Madrid 16, Spain (internal mail)
M.D. Beaumont, Manager- ,
Westinghouse Bethesda-Licensing Operations 4901 Fairmont Avenue
.Bethesda, Maryland 20814
-(or send to-Lori Piplica, WEC 4-12 East) l 1
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Attachment 2 Prairie Island Nuclear Generating Plant
' Supplemental Information for License Amendment Dated September 28, 1987 Turbine Valve Test Frequency Reduction WCAP-ll525 "Probabilistic Evaluation of Reduction in Turbine Valve Test Frequency" CONTAINS PROPRIETARY INFORMATION TO~BE WITHHELD FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFR PART2, SECTION 2.790 i
ATTACHMENT 2 CONTAINS PROPRIETARY INFORMATION TO BE WITHELD FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFR PART.2, SECTION 2.790 ;
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